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NUREG/CR-5281 BNL-NUREG-52180 Value/Impact Analyses of Accident Preventive and Mitigative Options for Spent Fuel Pools Prepared by J.H. Jo, P.F. Rose, S.D. Unwin, V.L. Sailor, K.R. Perkins, A.G. Tingle. Brookhaven National Laboratory Prepared for U.S. Nuclear Regulatory Commission

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Page 1: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

NUREG/CR-5281BNL-NUREG-52180

Value/Impact Analyses ofAccident Preventive andMitigative Options forSpent Fuel Pools

Prepared by J.H. Jo, P.F. Rose, S.D. Unwin, V.L. Sailor,K.R. Perkins, A.G. Tingle.

Brookhaven National Laboratory

Prepared forU.S. Nuclear RegulatoryCommission

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NUREG/CR-5281BNL-NUREG-52180R4, 9H

Value/Impact Analyses ofAccident Preventive andMitigative Options forSpent Fuel Pools

Manuscript Completed: January 1989Date Published: March 1989

Prepared byJ.H. Jo, P.F. Rose, S.D. Unwin, V.L. Sailor,K.R. Perkins, A.G. Tingle

Brookhaven National LaboratoryUpton, NY 11973

Prepared forDivision of Safety Issue ResolutionOffice of Nuclear Regulatory ResearchU.S. Nuclear Regulatory CommissionWashington, DC 20555NRC FIN A3963

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ABSTRACT

A series of value/Impact studies were performed for accident preventiveand mitigative options intended to reduce the risks posed by the storage ofspent fuel at nuclear power plants in spent fuel storage pools. Optionsstudied Included limited low-density reracking of spent fuel, installation ofwater sprays above the spent fuel pool, and the installation of redundantcooling and/or makeup systems. The results of these studies indicated thatthe measures were in general not likely to be cost effective. The reason forthis is due to both the low likelihood of a spent fuel pool accident thatcould result in a significant radiological release and the high cost of pro-posed modifications. These insights are largely contingent upon compliancewith guidelines developed for licensees to assure the safe handling of heavyloads in the vicinity of spent fuel pools thus reducing the likelihood of thestructural failure of the pool and rapid loss of water inventory due to a caskdrop event.

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EXECUTIVE SUMMARY

S.1 Introduction

In light of the possibility of a Zircaloy fire in a spent fuel pool,

Generic Safety Issue 82, "Beyond Design Basis Accidents in Spent Fuel Pools,"was assigned a MEDIUM priority in November 1983.

In a previous study undertaken at Brookhaven National Laboratory (BNL) 1

the radiological risks posed by the storage of spent reactor fuel at commer-

cial reactor sites in the United States was characterized through evaluationof the likelihood and the consequences of identified scenarios involving loss

of integrity in spent fuel pools. In the current study various optionsintended to reduce the risk posed by nuclear power plant spent fuel pools have

been assessed within a value/impact methodological framework. These 6ptions

included both accident preventive and mitigative measures as discussed below.

Limited low-density reracking of spent fuel is a mitigative option whichis intended to reduce radiological releases through obviating the onset of

self-sustaining clad oxidation in the event of loss of pool water inventory.An assessment of the cost impact of this option was made including the costs

for the provision of the additional storage space required due to earlierexhaustion of pool capacity. These included pool, drywell, vault, cask, andsilo facilities.

The NRC Standard Review plant (SRP) requires, as a minimum, redundantcooling systems as well as redundant coolant makeup systems for the spent fuelpool. To assess the risk control efficacy of these requirements and the

potential for further risk-reduction in plants complying with the SRP, a pre-liminary evaluation of the risk impact of assuming system redundancy above the

minimum currently required was undertaken. Additionally, for older plantswith comparable SRP requirements, the risk-reduction potential of backfits wasalso assessed. Based upon a spectrum of assumed plant configurations, thefinancial impact of such modifications were also estimated.

Several methods that might serve to mitigate the consequences of "beyond-design-basis accidents" in commercial nuclear power plant spent fuel storagepools were proposed and evaluated to identify which mitigating measures, ifany, appear to merit more detailed analyses.

S.2 Spent Fuel Pool Inventory Reduction Options

The potential risk reduction value and the cost impact of storage pool

system modifications and of alternative onsite spent fuel storage strategieswere assessed.

Structural failure that could result in rapid and complete draining of

water from the pool are predominantly caused by two typfs of initiators, i.e.,

seismic events and a cask drop on the spent fuel pool. The probability of asevere seismic event has been recently re-evaluated 2 and data from this more

recent document has been used in this study.

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The limited low density storage option is one in which fuel dischargedfrom the reactor within the last two years is stored in a low-density configu-ration. Calculations indicate that it reduces the likelihood of fire initia-tion following loss of pool inventory, by increasing air circulationcapability, by a factor of five. 3 In order to obtain insight into thepotential cost-effectiveness of the limited low-density reracking option, avalue-impact assessment was performed fotlowing guidelines in the Handbook forValue-Impact Assessment (NUREG/CR-3568).

Attributes considered included public health occupational exposure, off-site and onsite costs, and cost of industry implementation and operation. Theassociated incremental costs to the industry include the replacement of high-density storage racks with low-density racks, and the cost of increased drystorage requirements due to the consequent decrease in pool capacity.

A summary of the results is presented in Table S.1. It indicates thatthe costs outweigh the potential benefits due to both the low probability ofthe accidents under consideration and the high cost of proposed modifications.

S.3 Improvement of Pool Make-up Reliability

The risk-control efficacy of the Standard Review Plan (SRP) requirementsupon pool make-up capability was characterized within a value/impact frame-work. The approach taken was one of evaluating first the risk-reductionprofile of requirements exceeding those of the SRP. For older plants withcomparable _SRP requirements, -the risk-reduction potential for similarrequirements was also assessed.

The cost/benefit characteristics of adding these improvements to thespent fuel pool cooling systems is summarized in Table S.2. Only the Instal-lation of an additional cooling pump to System C (Old Existing Plant with BothCooling Pumps Required 30% of Time) appears to have non-negligible economicrisk impact. The generalized representation of the Standard Review Planrequirements indicate that additional requirements would not result incost/beneficial improvements.

S.4 Water Spray System

Several accident mitigative measures such as water spray systems,building ventilation gas treatment systems, and covering fuel debris withsolid materials were considered and evaluated to identify which mitigativemeasures, if any, appear to merit further analyses. Only the installation ofa water spray above the spent fuel pool was studied within the value/impactframework due to its potentially significant risk-reduction properties. Inthe event of loss of pool water inventory, and subsequently, fuel damage dueto the generation of fission product decay heat, the pool sprays would servethe function of decontaminating the radiological release. However, a scopingvalue-impact assessment indicates that the addition of a water spray system isnot cost effective.

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Table S.1 Summary of Industry-Wide Value-Impact Analysis ofthe Inventory Reduction Option

Attributes Best Estimate Evaluation ($1983)*

Public Health 4.00 x 107

Offsite/Onsite Property 6.96 x 106

Industry Implementationand Operation -1.38 x 109

Net Benefit ($) -1.33 x 10O

Benefit ($)/Cost ($) Ratio 0.035

Ratio of Public Dose Reduc-tion per Million DollarsCost (Person-rem/$10 6 ) 29.0

Cost of Implementation perAverted Person-rem($/Person-rem) 3.45x10 '

*Based on 1988-dollars, the Best Estimate Net Benefit, Benefit/

Cost Ratio, Public Dose Reduction per Million Dollars Cost andCost per Averted Person-rem would be -1.47x10 9 Dollars, 0.032,26.4 Person-rem and 3.79x10 4 Dollar/Person-rem, respectively.Cost escalation during 1983-1988 was assu•;;d to be 9.8%.

Table S.2 Value-Impact for Generic Improvements to the Spent Fuel Pool Cooling System*

Improvement Expected Averted Uenefit/

System Description Improvement Cost (1983$) Cost (1983$) Cast Ratio

A. Minimum SRP 1. Additional pump 50,000 None 0.0

2. Additional train 1.0E6 645 to 6640 'C0.01

B. Minimum SRP 1. Additional pump 5.OOO None 0.0RequirementWith Credit 2. Additional train L.0E6 27 to 330 0.0for FireSystem

C. Old Existing 1. Additional pump 50,000 2500 to 30.400 .05 to 0.61Plant WithBoth Cooling 2. Additional train L.OES 3160 to 38,550 .003 to 0.04Pumps Required30% of Time

0. Old Existing 1. Additional pump 50.000 125 to 1500 .0025 to 0.03Plant WithCredit for Fire 2. Additional train 1.0E6 159 to 1940 (.002System

"Quantification reflects a single spent fuel pool.

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S.5 Summary and Discussion

Generic analyses of various potential modifications to nuclear powerplant spent fuel pools have been performed. Cast within the framework ofvalue/impact analysis methodology, the risk-reduction value and the costimpact of these modifications were evaluated and compared. These were asfollows:

I. The limited low-density reracking of recently discharged fuel to de-crease the likelihood of the initiation of self-sustaining clad oxida-tion in the event of loss of pool water inventory.

2. The addition of a full capacity pump in one pool coolant makeup trainto increase pool cooling reliability.

3. The addition of a completely independent pool coolant makeup train.4. The installation of pool sprays to attenuate fission product releases

in the event of fuel degradation.

Value/impact assessments were performed. A $1000/per person-rem avertedconversion factor was utilized to convert dose-reduction measures into a mone-tary measure in the best estimate calculations. None of the risk-reductionmeasures were assessed to have a value/impact ratio greater than 1.

Executive Summary References

1. V.L. Sailor et al., "Severe Accidents in Spent Fuel Pools in Support ofGeneric Safety Issue 82," NUREG/CR-4982 (July 1987).

2. P.G. Prassinos et al., "Seismic Failure and Cask Drop Analysis of theSpent Fuel Pools at Two Representative Nuclear Power Plants," NUREG/CR-5176 (January 1989).

3. A.S. BenJamin et al., "Spent. Fuel Heatup Following Loss of Water DuringStorage,* NUREG/CR-0649 (March 1979).

4. S.W. Heaberlin et al., "A Handbook for Value-Impact Assessment," NUREG/CR-3568 (December 1983).

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TABLE OF CONTENTS

Page

ABSTRACT ............................................................... iiiEXECUTIVE SUMMARY. ................................... vLIST OF TABLES ................... ............................. xiACKNOWLEDGEMENTS... ..................... ............... x i i

1. INTRODUCTION ...................... 1

1.1 Risk of Accidents in Spent Fuel Pools......................... 2

2. RISK REDUCTION MEASURES ........ ...................... ... .. 5

3. SPENT FUEL POOL INVENTORY REDUCTION ................................ 7

3.1 Introduction .................................................. 73.2 Development of Value/Impact Quantification.................... 7

3.2.1 Accident Sequence Frequencies ......... .... .... ;........ 83.2.2 Public Health and Offsite Property Damage............ 83.2.3 Occupational Exposure (Accidental) ........... . ..... *.. 93.2.4 Onsite Property Damage .......... . ..................... 93.2.5 Industry Implementation................................ 10

3.2.5.1 Spent Fuel Storage Requirements............... 103.2.5.2 Cost Estimate .................... 12

3.3 Value-Impact Assessment............ . .......................... 143.3.1 Assumption and Checklist for Identification of

Affected Attributes .................................... 143.3.2 Value/Impact Comparison................................ 143.3.3 Sensitivity Studies ..................................... 15

4. IMPROVEMENTS OF POOL MAKE-UP RELIABILITY ........................... 31

4.1 Introduction .................................................. 314.2 Quantification ................................................ 31

4.3 Results and Conclusions of Value-Impact Study ................. 34

5. ACCIDENT MITIGATIVE OPTIONS .................... ................ 37

5.1 It out o . .. ... . .... .. . .. .. .. . ... . . 37

5.2 Definition of Accident Sequences .............................. 375.2.1 Accident Sequence "Al," A Complete Loss of Pool

Water Inventory Followed by a Zircaloy Fire ............ 385.2.2 Accident Sequence "A2,u A Complete Loss of Pool

Water Inventory Followed by Clad Failures but NotZi rcaloy Fi re .......................................... 38

5.3 Definitions of Mitigative Measures............................ 395.3.1 Mitigative Measure "M1," Covering Fuel Debris With

Solid Materials................ ... .................... 395.3.2 Mitigative Measure "M2," Water Spray Systems........... 395.3.3 Mitigative Measure "M3," Building Ventilation Gas

Treatment System.................., ..................... 39

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5.4 Discussion of the Efficacies of Mitigative Measures for TwoAccident Sequences .................... ........... ........... 405.4.1 Zircaloy Fires (Al): Mitigative Options ............... 405.4.2 Clad Failure Without Zircaloy Fire (A2): MitigativeOptions ................................................ 41

5.5 Value-Impact Assessment of a Post-Accident Spray System ....... 415.5.1 Characterization of Post-Accident Spray Systems ........ 415.5.2 Quantification ......................................... 42

5.6 AnDlDisCUSO. .................................. ......... 43

6. SUMMARY AND DISCUSSION ................. ............ , 47

7. REFERENCES ...................................... 49

APPENDIX A ................... . . ... . .. .......................... 51

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LIST OF TABLES

Table Page

3.1 Estimated Risks From Spent Fuel Pool Fires ..................... 173.2 Offslte Consequence Calculations ............................... 183.3 Onslte Property Damage Costs per Accident ($) .................. 193.4 Nuclear Power Plant Spent Fuel Storage Data .................... 203.5 Storage Options ................................................ 24

3.6 Incremental Storage Costs Associated with Limited Low-DensityRacking in the Primary Pool (1983 Dollars) ..................... 24

3.7 Checklist for Identification of Affected Attributes ............ 253.8 Summary of Parameters Affecting Attributes for the Spent

Fuel Pool Inventory Reduction Option ........................... 263.9 Summary of Industry Wide Value-Impact Analysis of the

Inventory Reduction Option ..................................... 28

3.10 Value-Impact Sensitivity Analysis of the Inventory ReductionOption ......................................................... 29

4.1 Failure Frequency for Generic Spent Fuel Pool Cooling andMakeup SstS esstem .s 0...... a 0 0.. a.........aa..........................a.*.... 0 0 00 0 35

4.2 Value-Impact for Generic Improvements to the Spent Fuel PoolCooling System........o ............................. ........... 36

5.1 Offsite Property Damage and Health Costs per Accident .......... 445.2 Summary of Industry-Wide Value-Impact Analysis of the Post-

Accident Spray System ......... ......... ............. 45

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ACKNOWLEDGEMENTS

This work was performed for the Reactor and Plant Safety Issues Branch ofthe Division of Safety Issue Resolution, NRC/RES. The authors would like tothank Mr. E. Throm of the NRC for his technical guidance and the many helpfulsuggestions he provided throughout this study.

The authors also wish to thank Ms. S. Flippen and Ms. C. Conrad for theirexcellent typing of this report.

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1. INTRODUCTION

The Reactor Safety Study (RSS, WASH-1400) concluded that risks associatedwith spent fuel storage were extremely small In comparison with severe acci-dents involving the reactor core. Since publication of the RSS, however, var-ious factors have provided a basis for reexamination of the risks associatedwith the storage of spent fuel. First, the storage of spent fuel rather thanits shipment for reprocessing or disposal is resulting in larger spent fuelpool inventories than anticipated in WASH-1400. Second, the accommodation ofthese larger inventories can involve the high-density racking of fuel assem-blies and, third, various theoretical models have identified the possibilityof a Zircaloy fire propagating from recently discharged assemblies to lowerpower assemblies in the event of a loss of pool water inventory. In the lightof such factors, Generic Safety Issue 82, nBeyond Design Basis Accidents inSpent Fuel Pools" was assigned a MEDIUM priority in November, 1983.

In a previous study undertaken at Brookhaven National Laboratory (BNL)1current information and models regarding the likelihood and the consequencesof pool drainage scenarios were adopted to generate a risk profile of thestorage of spent fuel. In this study various options intended to reduce therisk posed by nuclear power plant spent fuel pools have been considered withina value/impact methodological framework. These options included both accidentpreventive and mitigative measures.

Limited low-density reracking of spent fuel, a risk reduction optionwhich involves maintenance of recently discharged fuel batches (i.e., dis-charged within the last two years) in a low-density configuration, is a miti-gative option which is intended to reduce radiological releases through obvi-ating the onset of self-sustaining clad oxidation in the event of-loss of poolwater inventory. An assessment of the cost impact of this option was madeincluding the costs for the provision of the additional storage space requireddue to.earlier exhaustion of pool capacity. These included pool, drywell,vault, cask, and silo facilities.

Of the accident mitigative options considered, one option was studiedwithin the value impact framework due to its potentially significant risk-reduction properties. This involved the installation of a water spray abovethe spent fuel pool. In the event of loss of pool water inventory, and subse-quently, fuel damage due to the generation of fission product decay heat, thepool sprays would serve the function of decontaminating the radiological re-lease.

The NRC Standard Review plant (SRP) provides guidance and defines theacceptance criteria for spent fuel cooling systems and is used by the NRCstaff to determine whether a specific design complies with the Commission'sRules and Regulations. The SRP requires, as a minimum, redundant cooling sys-tems as well as redundant coolant makeup systems for the spent fuel pool. Toassess the risk control efficacy of these requirements and the potential forfurther risk-reduction in plants complying with the SRP, a preliminary evalua-tion of the risk impact of assuming system redundancy above the minimum cur-rently required was undertaken. Such requirements affect risk through influ-encing the expected frequency with which loss of water inventory accidentsoccur in the spent fuel pool. Additionally, for older plants with comparableSRP requirements, the risk-reduction potential of backfits was also assessed.

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Based upon a spectrum of assumed plant configurations, the financial impact ofsuch modifications were also estimated.

1.1 Risk of Accidents in Spent Fuel Pools

With the U.S. moratorium on spent fuel reprocessing, spent fuel storagedemands are being increased. To accommodate this growing need, existing stor-age pools are being expanded with the use of high-density storage of fuel.Furthermore, various dry storage options are being developed and used for ex-tended storage.

To characterize the safety profile of spent fuel pool facilities, a rangeof postulated accident sequences was considered, and predictions of the prob-ability of occurrence of these accidents and the resulting consequences weremade in NUREG/CR-4982.' This work was performed under the auspices of theU.S. Nuclear Regulatory Commission in support of their technical analysis re-lated to Generic Safety Issue 82, "Beyond Design Basis Accidents in Spent FuelPool s."

The objective of the current report is to identify and to assess thoseadditions or modifications to spent fuel pools that have the potential toreduce the risk associated with the storage of spent fuel in the spent fuelstorage pool. The methodological framework of value/impact analysis isadopted in which the risk reduction value, and the cost impact of a givenplant benefit are evaluated, .and cast into a numerical framework that permitsthe direct comparison of benefitwith cost.

Attention is focused upon those accident sequences that were assessed inReference I to dominate the risk posed by spent fuel storage. Considerationof those measures that reduce the likelihood of, or the consequences of theaccident sequences assessed to be risk dominant is an approach that permitsinvestigations to be directed towards the plant backfits with the greatestpotential risk reduction effect.

The risk dominant sequences fall into two categories. The first categoryinvolves structural failure of the spent fuel pool due to a seismic event andthe consequent rapid loss of pool water inventory. The probability of such asevere seismic event has been discussed in NUREG/CR-4982, and has been re-cently re-evaluated. 2 Data from this more recent document has been used inthe present study.

The generation of fission product decay heat raises the temperature ofthe uncovered fuel assemblies to the point where self-sustaining Zircaloycladding oxidation is initiated in the most recently discharged assembliesand, possibly propagation of the cladding fire to neighboring assembliesensues. The concomitant radiological releases result in health and economicconsequences both onsite and offsite.

The second category of risk dominant accident sequences differ from thosejust described only with respect to the initiating event. Here the structuralintegrity of the-pool is compromised through the impact of a heavy object(i.e., the dropping of a storage cask) upon the pool wall rather than througha seismic event. The probability of a cask dropping in the spent fuel pool is

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given in NUREG/CR-4982 conditional upon a probability of 0.1 for structuralfailure. The present study uses a conditional probability of 1.0 as discussedin Reference 2.

Standard improvements in operator training, heavy load procedures, andequipment as outlined in NUREG-0612 3 are part of the resolution for GenericIssue A-36 and have been assessed to significantly reduce the likelihood ofthe accidental dropping of heavy loads, thus reducing the risk associated withthe cask drop sequence significantly. The risk-reduction multiplicativefactor associated with this resolution has been estimated to be 0.0011 foraffected sequences and has been incorporated in the present study.

The phenomenological progression of the cask-drop accident from the pointof pool drainage is identical to that associated with the seismic sequencecategory.

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2. RISK REDUCTION MEASURES

Given the diversity of plant-specific design and construction of spentfuel pools, the applicability of any generic analysis of risk-reduction mea-sures is limited both with respect to the characterization of risk impact, andto the cost of implementation for any one plant. As with any generic assess-ment, therefore, the current analyses are intended only to provide a broadevaluation of the value/impact attributes of a given plant modification. Inthe event that more detailed analyses are found to be merited, such evalua-tions may need to be carried out on a plant specific basis.

In general, risk-reduction options may be classified into one of two cat-egories reflecting the fashion in which the plant modification affects risk.A preventive option is one intended to reduce the frequency of conditions po-tentially conducive to the release of fission products from the fuel assem-blies. The course of events leading to such conditions is defined as an acci-dent sequence. Hence, an option intended to reduce the likelihood of the lossof pool integrity subsequent to a seismic event, or to reduce the unavailabil-ity of the pool cooling systems is classified as a preventive option. A miti-gative option is one intended to reduce the magnitude of the consequences thatwould result from a selected set of accident sequences. This objective isgenerally achieved through reduction of the environmental radiological releaseassociated with each of the affected sequences.

Given the occurrence of an accident sequence initiator (seismic event,load drop, loss of pool cooling, etc.), there exists the potential to arrestthe progression of the accident at various stages of its development. Forexample, in the event of loss of pool cooling and the gradual boil-off of poolwater inventory, measures taken to increase the reliability of inventory make-up will have direct impact upon the risk profile of such a sequence. Such ameasure, characterized as accident preventive, is addressed in this report.

Given a loss of pool coolant inventory and the uncovery of spent fuelassemblies, measures taken to reduce the likelihood of the subsequent initia-tion of self-sustaining clad oxidation will also impact upon the risk profileof pool coolant-loss accidents. Such a measure, involving the reracking ofin-pool fuel into lower density configurations in order to promote air coolingsubsequent to .water loss is assessed in the current report. Whether thismeasure be characterized as accident preventive or accident mitigative isdependent upon whether the initiation of clad oxidation is viewed as part ofthe accident sequence itself, or as part of the consequence scenario. Fordefiniteness, the former viewpoint will be adopted such that the low-densityfuel reracking measure is viewed as an accident preventive option.

Finally, given loss of water inventory, fuel uncovery and the onset ofclad degradation, measures may be taken to minimize the subsequent release ofradiological fission products. Such measures characterized as accident miti-gative, actuation of installed pool sprays and the installation of filteringsystems, are assessed in the current report.

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3. SPENT FUEL POOL INVENTORY REDUCTION

3.1 Introduction

In NUREG/CR-4982 1 the radiological risks posed by the storage of spentreactor fuel at commercial reactor sites in the United States was character-ized through evaluation of the likelihood and the consequences of Identifiedscenarios involving loss of integrity in spent fuel pools. This section ad-dresses the potential risk reduction value and the cost impact of storage poolsystem modifications and of alternative onsite spent fuel storage strategies,.

A series of storage concepts were considered. The limited low densitystorage option is one in which fuel discharged from the reactor within thelast two years is stored in a low-density configuration. The associated in-cremental costs to the utility include the replacement of high-density storageracks with low-density racks, and the cost of increased dry storage require-ments due to the consequent decrease in pool capacity.

The risk-reduction basis for low-density racking of fuel is the promo-tion of air cooling in the event of loss of water inventory of the pool. Thenew high-density fuel storage racks restrict air flow and render recently dis-charged fuel (one to two years) susceptible to self-sustaining oxidation inthe event of pool drainage. The older style fuel baskets with large inletholes (3 inch diameter or more per assembly) allow less impeded air circula-tion. If all recently discharged fuel (less than two years) is kept in lowdensity fuel baskets and they are separated from the wall and the older fuelby a one foot gap then the likelihood of the initiation of self-sustainingoxidation would be significantly reduced compared to the high density storageconfiguration. 4 Calculations with the SFUEL Code indicate that for plantswhich use a high density storage rack configuration a factor of five reductionin the likelihood of fire initiation (given loss of pool inventory) can beachieved by improved air circulation capability." This reduction factor isbased upon the time period following discharge for which SFUEL predicted suf-ficient decay heat to initiate clad fire.

In order to obtain insight into the potential cost-effectiveness of thelimited low-density reracking option, a value-impact assessment was performedfollowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568).s

3.2 Development of Value/Impact Quantification

The principal components of any value-impact assessment are the attri-butes (costs and benefits) that are used to characterize the consequences ofthe action proposed in Section 3.1. The attributes described represent thefactors that are affected by this proposed plant modification. Each attributemeasures the change from the existing condition due to implementation of theoption.

Comparisons of the benefit and cost in our value/impact analysis werecarried out in 1983 dollars throughout this report, since many of the avail-able data were expressed in 1983 dollars. , Our results are not sensitive tothe reference year since both costs and benefits were computed on the samecost index. Furthermore, the cost escalation between 1983 and 1988 was only

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9.8% (Reference 17). Our final results (Tables 3.9 and 5.2), however, includedata expressed in 1988 dollars.

3.2.1 Accident Sequence Frequencies

Because of the strong and reinforced concrete structure of LWR spent fuelstorage pools, designed to Category I seismic criteria, initiating events thatwould lead to structural failure are extremely unlikely. However, a structur-al failure that results in rapid and complete draining of water from the poolcould have significant consequences. The study presented in NUREG/CR-4982concludes that the risk dominant sequences fall into two main categories.

The first category involves structural failure of the spent fuel pool dueto a seismic event and the consequent rapid loss of pool water inventory. Thsprobability of such a severe seismic event has been recently re-evaluated.Data from. the more recent document has been used in the present study (seeTable 3.1).

The second category of risk involves the compromise of the structuralintegrity of the pool through the impact of a heavy object (i.e., the droppingof a storage cask) upon the pool. The frequency of a cask drop onto a spentfuel pool is given in NUREG/CR-4982. The conditional frequency of structuralfailure of the pool is assumed to be 0.1 in Reference 1. The present studyuses a conditional probability of 1.0 based upon the more recent analysesreported in Reference 2. The assumed frequencies of the accident sequencesconsidered in the current analyses are summarized in Table 3.1. Sensitivityto these assumptions is discussed in Section 3.3.3.

3.2.2 Public Health and Offsite Property Damage

The health and economic consequences of spent fuel pool accidents werecalculated using the MELCOR Accident Consequence Code System (MACCS) Version1.4. MACCS is a new consequence code developed at Sandia National Labora-tories (SNL) and is intended to replace the older CRAC2. The code models aredescribed in NUREG-1150 (Appendix 0).6 The principal differences from CRAC2are that MACCS uses a multipuff atmospheric dispersion model and has a new.radiological health effects model described in NUREG/CR-4214. 7

Two radiological source terms were utilized to reflect a range of. releaseassumptions. The worst case assumes an accident that results in a Zircaloyfire that propagates throughout the entire spent fuel inventory in the pool,and that the accident occurs 30 days after the reactor was shut down for dis-charge of the last fuel batch. The best estimate assumes an accident that re-sults in a Zircaloy fire that involves only the last fuel batch to be dis-charged, and that the accident occurs 90 days after the reactor was shutdown. The source inventory was based on the Millstone I reactor as.discussedin NUREG/CR-4982.1 The release fractions were also based upon Reference 1.These are 100% of the noble gases, halogens, and alkali metals, a negligiblerelease of lanthanides and actinides, 0.2% of the alkali earths and assortedreleases of other isotopes from the fuel and cladding. The source was assumedto be released in one puff with a uniform particle size distribution and a de-position velocity of 0.01 m/s.

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The Zion site was used to represent worst case conditions with respect topopulation density. Hence Zion data was combined with high source term as-sumptions to characterize 'worst case' consequences. MACCS sorts meteorologi-cal data into 29 categories (or bins) depending on rain, stability and windspeed. Four random samples from each bin are taken. This assures thatweather sequences which can produce serious consequences are aaequately repre-sented (NUREG/CR-2239)..e The population data for Zion were supplied by theNRC for 16 angular and 20 radial Intervals out to 500 miles. Within 50 milesthe population density is 860 people per square mile. The data also includedthe site-specific wind rose. The land fraction for intervals near Zion wereobtained from the Zion FSAR and for large distances from a national map. Foreach grid element the appropriate state average land use and economic datacurrent in 1980 was used.

For the best estimate calculations the Zion meteorology, and Illinoisstate average land use and economic data were employed in conjunction with a95% land fraction uniform population density of 340 people per square mile(average of all U.S. nuclear power plant sites). Hence, this site data wasemployed in conjunction with the best estimate source term to evaluate best-estimate consequences. No planned evacuation was modeled since this has asmall effect on the total cost and dose impact. However, people were assumedto be engaged in normal activities which provides some protection from thecloud shine, ground and inhalation dose pathways. Also people were relocatedat one day if their projected ground shine dose in 7 days would exceed 25rems. An additional dose limit over 30 years was set to 25 rems.

With this information the offsite costs and public dose impact were com-puted. The offsite costs include emergency actions, decontamination, inter-diction, food disposal, and loss of use of farmland and residential areas.These costs do not include costs associated with health effects (see Table3.2).

3.2.3 Occupational Exposure (Accidental)

Exposures for a major spent fuel pool accident were assumed to be similarto those associated with the TMI-2 accident. For this accident the eslimatedoccupational radiation dose from cleanup was less than 4,580 man-rem. Thisexposure is small compared to the potential offsite dose impact and more re-fined quantification appears to be unwarranted.

3.2.4 Onsite Property Damage

Economic risks from light water reactor (LWR) operation are dominated byonsite losses resulting from replacement power costs. 9 Severe accident risksalso have significant contributions from plant monetary losses (i.e., repairand refurbishment) and plant decontamination.

The risk-dominant accident sequence as identified in Reference 1 involve:(1) failure of the pool due to seismic or load drop events resulting in a com-plete loss of water inventory, (2) Zircaloy fire initiation and propagationthrough the spent fuel assemblies stored in the pool, and (3) loss of contain-ment integrity as the spent fuel pool building is breached. The consequencesof these scenarios are expected to be similar to the Category II accident asdefined in Reference 9, i.e., 50% clad melting and contamination. For this

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case clepnup and decontamination costs are estimated to be approximately. $165million. Outage times (5 to 7 years) are estimated from EPRI-NP-3380. Thecosts for replacement of the spent fuel pool ($46 million for a 400 MT pool)and costs of permanent disposal of the damaged fuel ($26 million) are alsoestimated from EPRI-NP-3380.

The cost of replacement power can be approximated by

C - (0.13 * R + 0.12)106 $/MW year

where R is the fraction of replacement energy by oil fired or noneconomicalpower purchases for a given NERC (National Electric Reliability Council)region. This formula includes credit for the avoided variable fuel cycle costof the shutdown reactor. For this study R = 0.41 was used as a best estimate(national average) and R - 0.9 was used for the worst case. 5 A plant capacityfactor of 65% is factored into the above equation and a 1,000 MW generic plantwas assumed.

The onsite costs are calculated from

U (Cc + Cr + Crp) e-rti-- 2 (1 - e-r(tf'ti))(1 - e~rm)m r2

where U = present (1983) value of onsite property damage,Cc = cleanup and decontamination cost,Cr = repair, replacement of spent fuel pool, and disposal of damaged

fuel cost,Crp - replacement power cost,tf = years remaining till end of reactor life, taken as 29.8,ti = year plant starts operating -- 0.0,

-r = discount rate (10%), andm = years plant is out of service.

The values of U must be multiplied by the accident frequency and numberof plants. U reflects the expected loss due to an accident. When U is multi-plied by the accident frequency the result is the expected loss over a reactorlife discounted to 1983 dollars. Table 3.3 summarizes these calculations.

3.2.5 Industry Implementation

3.2.5.1 Spent fuel storage requirements

It has been assessed1 that the risks of self-sustaining cladding oxida-tion for bundles in high density racks is confined to those that have beendischarged from the core within the last two years. For plants with a reload-ing period of less than two years, the fuel with the greater likelihood ofcladding oxidation initiation and propagation would be associated thereforewith the last two reload batches. For plants with a reload period of twoyears or more, the higher-risk fuel would be confined to the last reloadbatch. Where two plants share a spent fuel pool and each has a reloadingperiod of less than two years, the assumption of staggered reloading emplacesthe last three reload batches entering the pool in the higher-risk category.Limited low-density reracking of spent fuel is a risk-reduction option that

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Involves maintenance of recently discharged fuel batches (i.e., dischargedwithin the last two years) in a low-density configuration. This is a mitiga-tive option in that, subsequent to an accident sequence leading to loss ofcooling to the fuel, implementation of the option is intended to reduce radio-logical releases through obviating the onset of self-sustaining clad oxida-tion. Adopting the high density configuration as a base case, the degree ofrisk-reduction achieved through a limited low density racking option can beinvestigated.

The cost impact of this option involves, first, the cost associated withthe installation of low density racks and, second, the incremental cost asso-ciated with altered additional storage requirements resulting from earlierexhaustion of the spent fuel pool capacity. To evaluate the latter cost, thetime at which additional storage will be required and the degree of that stor-age must first be evaluated both in the base case and in the case for whichlimited low density racking is assumed. The costs associated with fulfullingthese requirements must then be estimated.

Available spent fuel and fuel pool data have been collated for all U.S.operating PWR and BWR plants. Spent fuel management schemes have been devel-oped for the low density racking option and of evaluating the modified storagerequirements. The results are presented in Table 3.4, "Nuclear Power PlantSpent Fuel Storage Data.*

Data needed for completion of this collation was assembled with the aidof the DOE document "Spent Fuel Storage Requirements 1987," DOE/RL-87-11(Sept. 1987).11 This document provides spent fuel storage inventories andcapacities and utility estimates of future discharges from U.S. commercialnuclear reactors through the year 2005. Historical data through 1986 arepresented, and projected discharge through the end of each reactor life areestimated.

Information relative to the low density storage option are reflected inColumns 12-15 of Table 3.4.

fn estimating the storage capacity decrement of the storage pools, it wasassumed that the fuel bundle packing area densities for PWR and BWR high den-sity racks exceed the low density rack densities by factors of 4 and 3 respec-tively. These ratios were based on the inter-bundle spacing for high and lowdensity racks. For PWRs, the bundle center to center spacing ranges from 10.5to 13 inches for high density racks while for the low density racks the rangeis 18 to 22 inches, giving area ratios ranging from 2 to 4.4. For BWRs, thesesizes are 6.5-8 inches for high density racks and 10-13 inches for low densityracks, yielding area ratios of 1.5-4. A sample of spent fuel pool capacityexpansion amendments 1 2 requested by licensees indicated that the average ratioof modified capacity to the initial capacity was about 3.5 for PWRs and 3.0for BWRs. For many PWRs, however, the appropriate ratio was approximately 4and, therefore,, this value was assumed as the generic scaling factor.

Based on the pool storage capacity decrement due to conversion to lowdensity configurations, the year in which the current pool storage space willbecome full (Column 13) and the additional storage space required to the end-*of-life of the plants (Column 14) were adjusted relative to the base case.

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The plants were classified into four groups based upon the year in whichthe additional storage space will be required. In the majority of the plants(denoted as X in Column 15), conversion to the low density option would resultin a storage capacity that would not accommodate the current spent fuel poolinventory. In these plants, construction of additional storage space wouldneed to begin concurrently with conversion to low density racking and, in cer-tain cases, this additional space would need to be in a low density configura-tion to accommodate recent fuel discharges. Several plants, denoted Y inColumn 15, have sufficient capacity to accommuodate the low density rackingrequirements presently but this space may be exhausted in a time-frame shorterthan that associated with construction of additional storage space.

In estimating the design, construction and licensing time for additionalstorage, the lead time estimates of Reference 10 were used.

Plants denoted Z in Column 15 would have no immediate need for additionalstorage in the low density racking option. Based upon the lead time estimatesof Reference 10, the year in which construction procedures would need to beinitiated is given in Column 15. One plant, denoted U, currently hassufficient storage space to .the end-of-life even allowing for low densitystorage of the full core reserve and the last 2 reload batches.

It is reiterated that the approach adopted here to evaluate the modifiedstorage requirements, given implementation of the limited' low density rackingoption, is based upon a generic assessment of the relative packing densitiesof high and low density racks. No plant'specific variation in this ratio, norfactors associated with pool-specific geometries have been accounted for inthe assessment. Further, *-the projected storage requirements are based uponthe current maximum storage capacities provided in Reference 11. Offsitetransshipments of fuel and onsite transfers were not accounted for unless thespent fuel pools are connected by some means as indicated in Table 3.4. Theseprojecti~ons are anticipated to be sensitive to adjustment of the approximatedpool capacities in Reference 11 and to transshipment assumptions.

3.2.5.2 Cost estimate

Cost estimate for replacing high-density storage racks with low-densityracks for recently discharged fuel have been evaluated. Also the cost forrequired additional spent fuel storage capacity based on the storage require*-ment in Table 3.4 have been evaluated. for four dry-storage concepts and foradditional wet-pool storage. The cost estimates were broken down into twoassumptions:

1. Wait until capacity is required.2. Provide for required capacity now.

Various societal discount rates, were selected (0, 5 and 10%) to show thesensitivity to the discount rate for future or delayed actions.

Costing data presented in EPRI NP-3380 provided the basis for the evalua-tion. This data were parameterized to facilitate calculations and involved:

1. Capital Costs.2. Operation and Maintenance Costs (O&M).3. Implementation time for design, licensing and construction (allowing

for overlap).

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The storage options selected for this study are shown in Table 3.5.

Reracking costs have been discussed in EPRI NP-3380 which involve con-struction and installation of high-density racks to replace low-densityracks. This data pertained to three reracking options: low-density racks toborated stainless steel racks, low density to stainless steel racks and stain-less steel to borated stainless steel racks.

The cost of conversion from high- to low-density racks per assembly spacewas approximated to be equal to the cost of the reracking options consideredin the EPRI report. (Each cost per assembly was approximately equal for thethree options considered.) Since these reracking costs were ultimatelyassessed to be typically one to two orders of magnitude less than the incre-mental cost of additional storage, this approximation did not introduce sig-ni ficant inaccuracies.

Operational and maintenance costs are incurred when the auxiliary storagecapacity is put into operation. From then on these costs will be constant onan annual basis for the remaining life of the reactor. These costs have beenestimated with the aid of EPRI NP-3380.

Table 3.6 summarizes the results of the cost assessments performed. Fordiscount rates of 0%, 5% and 10%, the table displays the incremental cost ofspent fuel storage to the end of plant use given conversion to limited low-density in-pool storage. The discounts are applied assuming that constructionis Initiated when required. Zero discount is equivalent to the assumptionthat construction Is initiated immediately for each plant. The costs areaveraged over LWR units and are provided in 1983 dollars. Data are providedfor the five storage options outlined in Table 3.5. Unit-averaged costs areprovided for each.

Additional statistics generated in the evaluation of the net incrementalcosts associated with the limited low-density storage of spent fuel are pre-sented in Appendix A. They may be consulted for confirmation of the summaryfigure provided in Table 3.6. All costs are quoted in 1983 dollars. Thetables contain the following information.

Table Al: The incremental cost of additional storage associated withlimited low-density in-pool storage under 'build now' and'build when needed' (10% discount rate) assumptions.

Tables A2-A6: Cost of additional storage assuming high-density and assuminglimited low-density in-pool storage. Storage-type options:pool (Table 4), drywell (Table 5), vault- (Table 6), cask(Table 7) and silo (Table 8). Evaluated at 0%, 5% and 10%discount rates.

Tables A2a-A6a: Assuming high-density in-pool storage, these tables provide abreakdown of additional storage costs into construction, andoperation and maintenance components for each option.

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Tables A2b-A6b: Assuming limited low-density in-pool storage, these tablesprovide a breakdown of additional storage costs into con-struction, and operation and maintenance costs for eachopt i on.

3.3 Value-Impact Assessment

3.3.1 Assumptions and Checklist for Identification of Affected Attributes

. Table 3.7 summarizes the affected attributes of this study while Table3.8 summarizes the quantification of the affected parameters. Following Ref-erence 1, the mechanism for risk-reduction by the limited low-density rerack-ing option is the reduction of the conditional probability of the initiationof self-sustaining Zircaloy clad oxidation given loss of pool water inven-tory. Hence an 80% (see Reference 1) reduction in sequence frequency isapplied uniformly both to the seismic and the cask-drop categories ofsequences to model the risk-reduction value of the option. It should be notedthat an additional, potential risk-reduction mechanism associated with low-density racking is a mitigative nature and involves reduction of the potentialradiological source term, given fuel degradation. Such an effect could bemodeled in the 'worst case' conditions where participation of older fuel dis-charge in the clad fire is assumed. Since 80% sequence frequency reductionremoves most of the risk (i.e., 80%) associated with the sequences, and Table3.9 reveals that the cost impact of this option significantly outweighs itsvalue, then the modeling of additional accident mitigative values of theoption would not alter the cost/benefit insights.

3.3.2 Value/Impact Comparison

Table 3.9 presents a summary of the value-impact analysis. For the in-dustrial cost of implementation, the best estimate uses the costs associatedwith the wet pool storage option while the high estimate utilized dry caskstorage costs. Monetary attributes in Table 3.9 were expressed in 1983 dol-lars as well as 1988 dollars to account for the escalation of costs in thisperiod. The cost escalation between 1983-1988 was assumed to be 9.8% (Refer-ence 17).

The results indicate that the costs outweigh the benefits due primarilyto the low probability of the accidents under consideration. An importantfactor is the probability of pool failure due to heavy load drops. Table 3.9.is predicated upon compliance with the guidelines which were developed forlicensees to assure the safe handling of heavy loads.

These recommended guidelines include general rules for all facilities toreduce the potential for uncontrolled movement of a load or a load drop, suchas by calling for: definition of safe load paths; development of load hand-ling procedures, periodic inspection and testing of the crane; qualifications,training and specified conduct of the crane operator; and use of guidelines onrigging.

If these guidelines are not part of the standard operating procedures fora facility then plant-specific human reliability analyses may be warranted tocharacterize the value/impact properties of the current option.

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3.3.3 Sensitivity Studies

The results presented in Table 3.9 are based on assumptions listed inTable 3.8. In Table 3.9 best estimate/worst case evaluations are presented.However, other parameters might be varied to investigate the sensitivity ofthese parameters to the final results. Those parameters include:

1. Pool Failure Probability,2. Discount Rate,3. Monetary Conversion of Health Effects,4. Plant Site Economics,5. Meteorology, and6. Industrial Implementation.

The sensitivity of the value-impact assessment to variations in each ofthese parameters is examined below and* the results are summarized in Table

3.10.

1. Pool Failure Probability

There is a large uncertainty in the risks associated with the structuralfailure of the spent fuel pool. It is significantly dependent upon the magni-tude of the probability of pool failure due to seismic events and the proba-bility of a cask drop induced pool failure. Since the risk-reduction impactof low-density reracking is effected through reduction in the frequency of allpool drainage sequences by a multiplicative factor, then any fractional in-crease in the assumed frequencies of the sequences is reflected by the samefactorial increase in the risk-reduction value of reracking. For example, ifthe base frequency of pool drainage sequences is increased by a factor of 100,then the risk-reduction value of reracking is increased by a factor of 100also. Hence, in the high risk-reduction estimate case (Zion demography andhigh source term), increasing the assumed frequency of pool drainage sequencesby an order of magnitude results in a benefit/cost ratio of 3.5.

2. Discount Rate

The baseline assumption for the discount rate was 10%. The effect ofchanging the discount rate can be seen by using a 5% rate. The affectedattributes are offsite and onsite property costs as well as industrialimplementation. Public dose reduction is not affected since it Is notdiscounted in accordance with the guidelines of Reference 5. The impact of achange in discount rate is relatively small. The best estimate net benefitwould remain somewhat the same since both benefits and costs increase. Thebest estimate benefit/cost ratio decreases to 0.028 from 0.035.

3. Monetary Conversion of Health Effects

A major difficulty in the net-benefit method is the evaluation of healtheffects in monetary units. The sensitivity of this particular analysis tothat evaluation can be demonstrated by substituting values of $500 and $2,000per person-rem averted instead of $1,000 per person-rem. The ratio estimates(public dose reduction/$10 6 cost) are not affected by these variations. Re-vised best estimates of the net-benefit are $-1.35E9 and $-1.29E9 for $500 and

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$2,000 conversion respectively relative to the net-benefit of $-1.33E9 associ-ated with the $1,000 conversion factor.

4. Plant-Site Economics

The baseline calculations adopted the economic factors of the surroundingarea of the Zion plant site as a best estimate. However, the economic valueof land at the Zion site is somewhat higher than that of the U.S. average.The impact of the economics of the area surrounding the plant site was as-sessed by recalculating the offsite consequence attributes using the economyof West Virginia as input to the MACCS code. 6 The economy of the WestVirginia site is considered to be much below the national average. The re-sults indicated that site economics do not impact the cost benefit ratio sig-nificantly since it may be seen from Table 3.9 that dollar-converted healtheffects exceed economic risk by an order of magnitude.

5. Meteorology

The baseline calculations employed Zion weather conditions. Several ad-ditional severe accident calculations indicated that varying weather modelscaused only a small change in the public health/offsite consequences.

6. Industrial Implementation

The incremental costs associated with spent fuel storage constructioncosts and overhead/maintenance is known quite accurately as indicated inReference 10. Therefore, the sensitivity to industrial implementation was notinvestigated.

Table 3.10 displays the results of the sensitivity studies. It can beseen that the net benefit is quite sensitive to 4he spent fuel pool failureprobability and to a lesser degree sensitive to the monetary conversion ofhealth effects. The net benefits are less sensitive to discount rate, econom-ics, and meteorology of the plant site.

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Table 3.1 Estimated Risks From Spent Fuel Pool Fires

ProbabilityEvent PWR Plant BWR Plant

Structural Failure of Pool Resultingfrom Seismic Events 1.8E-6/Ry* 6.7E-6/Ry

Probability of a Cask Drop Causedby Human Error 3.1E-4/Ry 3.1E-4/Ry

Reduction in Failure Rate for CaskDrop Implementing Generic Issue A-36 1.OE-3 1.OE-3

Conditional Probability of PoolStructural Failure Given a Cask Drop 1.0 1.0

Conditional Probability of a CladFire Given a Pool Structural Failure** 1.0 0.25

Frequency of Spent Fuel Pool Firefrom Seismic Initiator 1.8E-6/Ry 1.68E-6/Ry

Frequency of Spent Fuel Pool Firefrom a Cask Drop Initiator 3.IE-7/Ry 7.75E-8/Ry

*Ry = Reactor year.**NUREG/CR-4982, p. 75.

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Table 3.2 Offsite Consequence Calculations

OffsitePublic Property

Health Dose DamageCase Characterization Source Term* Population (person-rem) ($1983)

1 Average Case Last fuel discharged 340 persons/ 7.97x10 6 3.41x10 9

90 days after dis- mile 2

charge

2 Worst Case Entire pool inventory Zion population 2.56x10 7 2.62x101 °30 days after dis- (roughly 860charge persons/mile2)

*From NUREG/CR-4982.0O

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Table 3.3 Onsite Property Damage Costs Per Accident ($)

Item Best Estimate Worst Case

Cleanup andDecontamination 1.65E8 1.65E8

Repair 7.2E7 7.2E7

Replacement Power 8.67E8 1.66E9

Total Number ofOperating YearsRemaining 29.8 years 29.8 years

Number of YearsPlant is Out ofService 5 years 7 years

Expected DollarLoss 8.24E9 1.29E10

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PLANT NAME

TABLE 3.4 Nuclear Power Plant Spent Fuel Storage Dota(&)

CURRENT RACK CONF MODIFIED CONF(c)TYPE STARTUP SHUTDOWN FULL RE- FUEL INV. W. FILLUP ADD. ST--- UA FILLUP ADD. U--

YEAR YEAR CORE LOAD CYCLE 1986 CAP. YEAR RACE REQ. CAP. YEAR RACE REQ.(d) (.) (e) (MON.) (e) (b) (.) (1) (e) (9) (e) (h) (M) (e) (9)

CLASSI-FICATION

(I)

ARK NUCLEAR I P 1974 2008ARK NUCLEAR 2 P 1980 2012BEAVER VALLEY I P 1976 2016BEAVER VALLEY 2 P 1987 2028BELLEFONTE I P 1992(f) 2028BELLEFONTE 2 P 1996(J) 2030BIG ROCK I B 1965 2001

A BRAIDWOOD I P 1987 2026A BRAIDWOOD 2 P 1988 2027B BROWNS FERRY 1 B 1974 2014B BROWNS FERRY 2 B 1976 2014BROWNS FERRY 3 B 1977 2017BRUNSWICK 1 B 1977 2010

P (u)BRUNSWICK 2 a 1976 2010

P (u)A BYRON I P 1985" 2024A BYRON 2 P 1987 2026

CALLAWAY 1 p 1984 2024B CALVERT CLF1 P 1975 2014B CALVERT CLF 2 P 1977 2018

CATAWBA 1 P 1986 2026r• CATAWBA 2 P 1988 20280 CLINTON 1 B 1987(,i) 2027

B COMANCHE PK 1 P 1989 2030B COMANCHE PK 2 p 1989 2030A COOK I p 1976 2009A COOK 2 p 1978. 2009

COOPER STN B 1974 2008CRYSTAL RVR 3 P 1977 2018DAVIS-BESSE 1 P 1978 2017DIABLO CANYON 1 P 1985 2025DIABLO CANYON 2 P 1988 2025DRESDEN 1 B 1980 1984DRESDEN 2 B 1970 2008DRESDEN 3 B 1971 2008DUANE ARNOLD B 1975 2010ENRICO FERMI 2 B 1987(J) 2025FARLEY I P 1977 2012FARLEY 2 P 1981 2012FITZPATRICK B 1975 2016FORT CALHOUN P 1973 2808FT ST VRAIN a 1979 207GINNA P 1970 200GRAND GULF 1 B 1985 2022HADDAM NECK P 1968 2007HARRIS I P 1987(J) 2028

B (v)B HATCH 1 a 1974 209B HATCH 2 B 1979 2012

HOPE CREEK B 1987(j) 2026HUMBOLDT BAY B 1983 1978-

177 60 18 448 988 1998 377177 68 18 288 988 1999 85s167 69 18 283 833 1998 853167 73 18 0 1088 2009 8s8206 84 18 0 1058 209 1900205 84 18 0 1065 2011 190084 20 12 188 441 1995 95193 64 19 0 lo5o 199 3827193 84 18 0 (a) (n) (.)784 228 20 1328 3471 2602 3226784 228 20 1192 3471 (.) (.)784 228 20 1004 3471 201 2441580 188 18 840 1883 1990 2401

0 160 18050 188 18 750 1839 1991 2281

0 144 144193 88 18 0 1050 1994 3827193 88 18 0 (m) (n) (m)193 84 18 84 1340 2005 1129217 96 24 618 830 1992 2213217 96 24 432 1000 (n) (m)193 72 16 84 2816 2026 0193 72 16 0 2816 2028 0824 172 18 0 2672 2008 2672193 80 12 0 1895 2016 2087193 GO 12 0 1687 (n) (m)193 80 18 646 2270 1998 1241193 88 Is 424 (m) () (.)548 118 12 648 2388 197 1238177 72 24 302 1167 2006 482177 60 18 197 735 1996 2490193 86 24 51 1324 2011 617193 86 24 0 1324 2011 517464 0 - 683" 720 0724 168 18 168 3637 1998 1015724 158 18 1468 3537 200 693388- 128 18 698 2860 1999 998764 276 20 0 2306 1997 6365167 68 18 410 1407 2008 298157 88 18 268 1407 2008 140680 180 18 1012 2864 1997 2248133 46 18 834 729 1994 413

1482 240 24 0 604121 32 12 470 1016 200 21980 268 18 284 3124 1998 4392157 52 18 694 1168 1997 319167 52 18 0 3361 2026 0

0 - 0 2057(w) - -650 198 18 1107 3181 200 2874680 198 18 745 2845 (n) (m)764 232 18 0 3976 207 2820184 a - 390 488 - 0

8(8120) (k)50 136) 1989419(138 (k)650(146) 2000554 5168) 2000654 1IGO 202381 40 1992294 2521 1998(m) 1990

5574(684) 1998(0) 1998

2659(468) 19961051(376) (k)

1s07 (376) (k)

264(284)(m) (k)830(289) 19981264(292)(. M~

2183 144) 20212188 144) 20231984(344) 20002788(198) 2010(m) 2010

1602(266) 1991(W) 1991

1902 C232) 1993941 72) 1999375(120) 1988

1089(85) 2001069 (86) 20"6

2905(816 19922905 316 19941638 2568 19911201 652 1990999 188 19979991138 1999

2134 ,38 1991459 90 WIc

240824 64 1994

2062 636 1992858 104 1990

3039(104 2028

4850(588) 1998(W) 1998

3946(464) 201

7379731287129824042404

1754383

(0)4594Cm)33633163

3033

4413(a)

16322789(C,)226210

32826861

(04)2"9(,,)1702

6482860

772772

1647132616106469

7086482988683

41154846310

4050(C)

8748

xY

x2 C1998)z(1998)

Y z(1998)

z(19)x

Z(1998)

2(200)YY

Z C(1989)2(1996)

X Z 201)z(2001)CLOSED

Y2(1990)

YY

Z (1993)Z(1995)Y

xX 2 (1990)

YY

U

Z 1992)Z(1992)z(1997)

CLOSED -

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PLANT NAME

TABLE 8.4 Nuclear Power Plant Spent Fuel Storage Dmta(a)(cont'd)

CURRENT RACK CONF MODIFIED CONF(c)TYPE STARTUP SHUTDOWN FULL RE- FUEL INV. UXM. FILLUP ADD. ST- 1- FILLUP ADD. 3TD;

YEAR YEAR CORE LOAD CYCLE 1986 CAP. YEAR RACE REQ. CAP. YEAR RACE REQ.(d) (e) (e),(MON.) (a) (b) (e) (f) (e)(g) (e) (h) (f) (e)(g)----------- ------ ---------------------------------------- -------------------

INDIAN Pt 1INDIAN PT 2INDIAN PT 3KEWAUNEELACROSSE

B LASALLE CTY IB LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEMC-UIRE 1MCCUIRE 2MILLSTONE 1MILLSTONE 2MILLSTONE 3MONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE 1A OCONEE 2

r• OCONEE 3OYSTER CRK 1PALISADESPALO VERDE 1PALO VERDE 2PALO VERDE 3PEACHBOTTOM 2PEACHBOTTOM 3PERRY 1PILORIM 1

A POINT BEACH 1A POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 2B qUAD CITIES 1B QUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR.BEND 1SALEM 1SALEM 2

E SAN ONOFRE 1E SAN ONOFRE 2E SAN ONOFRE 3

SEABROOK 1A SEQUOYAH 1A SEQUOYAH 2

SHOREHAMSOUTH TEXAS 1SOUTH TEXAS 2

P 1982 1980P* 1974 2006P 1978 2015P 1974 2014B 1989 2002B 1982 2022B 1984 2023B 1986 2024B 1990 2029P 1972 2008P 1981 2021P 1984 2023B 1970 2010P 1976 2015P 1986 2025B 1971 2007B 1989 20059 1987 2028P 1978 2018P 1990 2020P 1973 2013P 1974 2013P 1974 2014B 1989 2004P 1971 2011P 1986 2024P 1986 2026P 1987 2028B 1974 20098B 1974 2008B 1987 2026B 1972 20098P 1970 2007P 1972 20098P 1973 20098P 1974 2008B 1973 2007B 1973 2007P 1975 20098P(u) 1971 2007B 1986 2025P 1977 2016P 1981 2020P 1988 1999P 1983 2012P 1984 2013P 1987(j) 2031P 1981 2021P 1982 2022B 1988(j) 2027P 1987 2027P 1989 2028

120 a -193 68 18193 78 18121 87 12

72 24 12784 220 18764 220 18764 224 18784 220 18217 73 18193 72 15193 72 15580 198 24217 68 18193 84 18484 120 18582 184 24784 278 24157 65 18157 85 18177 80 16177 60 18177 80 18680 128 18204 68 24241 85 18241 95 18241 85 18784 228 18764 220 18748 224 18589 192 24121 32 12121 32 12121 40 12121 40 12724 160 18724 .16 18177 69 18157 48 16824 192 18193 80 18193 84 18157 52 24217 109 24217 109 24193 64 16193 80 18193 80 185680 184 18193 52 12193 52 12

18 758464 980292 1817389 963261 440132 2098

0 20400 2040

793 1478219 1463186 1463

1536 2184474 11120 1836

428 22871444 2778

0 4049294 1737235 0590 1312381 0529 825

1392 2600545 7980 13290 13290 1329

1462 88141496 3819

0 40201320 2320446 1502408 (in)388 1386415 (in)

1393 36571428 3897287 1080270 5440 3172

344 1170174 1170148 218147 800147 800

0 1238212 1381"136 (m)0 26850 19890 1989

- 01994 4932004 5361999 5791992 2051990 9824

at 4098 "I(n) (in)

1998 42361996 6322005 9652006 9891987 24801997 8232016 S412004 3551998 8842011 19711999 1886

(n) (m)1989 2102

(n) (mn)1991 10211994 9121988 8a82005 11172006 11212007 1121-1997 18121997 15892009 25481993 16121995 849

(n) (m)1993 1142

(n) (m)2005 50S

(n) (m)2004 2261990 8882007 24521997 10072001 11681995 2382

20098 12811995 2806

(n) (in)2006 28352023 2582024 258

572(186) (k)81 (162) 1994741( 74) 1993344( 48) 197840(880) (k)(m) (k)

1144 448 19881180 440 19911038 146 19871081 144 19971031 144 19981792 198" (k844 165)

1332 188 20071757 240 19982408 184 19903497 278 20071152(195 1992

(m) 1992

465 120)20998 256 1989594 88) (k)819 170) 1998819 170) 1997819 170) 1999

2902 468) 19912939 440) 19913124 44 200831936 192 19881214 96)1990

(m) 19901026(120) 1988

S9)?4(480) 2002

(m) 2002686(138) 199226 (98) (k)

2404 (394) 2001690(16S) 19898885188) 1992

1008 270) 1989m 1989

1989852(128) 2000061(240) 1989(m) 1989

1949(388) 20001867(104) 20171867(104) 2018

ge1992801301

11144(n)

49925116107013971421287212911045

835125225332451

(m)2641

(m)13811424103916271881163127242489844418961137

(i)1502

(m)1463

(m)640956

3220148718878172

16483400

(m)3371

670570

CLASSI-FICATION

(i)

CLOSEDX

Z(1990)z (1989)X

XY

Xz(1993)Z (1994)

XX

z(2003)Z (1994)YZ (2003)

YYXXX

YX

X

XX

X

Z (2992)z(1993)Z (1994)

YY

Z (1999)

YY

z (199)Z (1998)

Y

z(1997)YYYYY

Z (1998)YY

Z (199)Z (2013)Z (2014)

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TABLE 8.4 Nuclear Power Plant Spent Fuel Storage Date(m)(contbd)

PLANT NAME

ST LUCIE 1ST LUCIE 2SUMMER 1

A SURRY 1A SURRY 2a SusquEHANNA 1B SUSQUEHANNA 2

THREE MILE ISLTROJAN

E TURKEY PT 3E TURKEY PT 4B VOGTLE 1B VOOTLE 2

VT YANKEE 1WASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK 1YANKEE-ROWE 1

A ZION IA ZION 2

TYPE STARTUP SHUTDOWNYEAR YEAR

(d)

PPPPP

PPPPP

B

PPPPP

1978 2010198l 28231984 20241972 20121978 20131985 28221986 20241974 208"1976 20111972 20071973 28071987 20271988 20261972 20121984 20231985 202419s8(i) 20261999(J) 20271986 20261961 2001973 2001974 2088

FULLCORE(0)

217217167167167764764177193167167193193388784217193193193

78193193

RE- FUELLOAD CYCLE() (ON.)

7672686363

232232

7348464884684

132156'soasBe76as7272

18181818181018181218181818181218181618181818

INV.1980(C)

444164112488386488324284379424446

0a

132212892

00

52341674603

CURRENT RACK CONF1W. FILLUP ADD. SW-CAP. YEAR RAGE REQ.(b) (e) (f) - ( a) (a) -

7281078127810441764 (y)284028401401 (x)140814046381117(x)1117(x)287026581388

1294(m)

1348721

2079(W)

1987

28812012

(n)2800

(n)280628042802

(n)200

199919982082001(n)

280819991995(n)

11821128781

97la')

7288Cm)76373384(0)

2496(0)

401811432891

(on)867

1296(o)

MODIFIED CONF (c)UWW. FILLUP ADD. STU=CAP. YEAR RACE REQ.

(e) (h) (f) (e) (9)

272(162) (k) 1638644(144) 1992 1668888(138) 1999 1189

2331(159) 2006 674(a) 2005 (in)

4268(898) 1995 868()1995 i)1148 1997 513

112:0 (96) 1998 61184(144) 1995 G81

( 17) 1996 (a)1478 (22) 2009 3251

(a) 2099 (i)2342(284) 1993 15982034(312) 1994 4642838(176) 1997 1871514(248) 1994 3411(in 1994 (10)884(162) 1999 1313493 78) 1998 284

1431 (218) 1988 1943(in) 1988 (m)

CLASSI-FICATION

(1)

xy()

Z(1995Z 2001Z 2001Z 1991Z 1991Z(1993Z 1994Z 1991Z 1991Z 1998Z 1998Z 1989Z 19907 19937 1990Z 1990Z (199

Yxx

ABE

d0

1i

INDICATES COMMON POOL SHARED BY TO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS REQUIRING CASK TRANSFERs CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

UTILITY DATA AS OF 12/31/1986 (Reference DOE/RL-87-11)PROJECTED MAXIMUM CAPACITY USING CURRENTLY LICENSED TECHNOLOGY(| .e. HIGH DENSITY RERACKING)BASED ON THE CONVERSION OF POOLS TO LOW DENSITY RACKS FOR THE FUEL LESS THAN 2 YEARS OLD.P-PWR BSBWR, GuHTGRUNIT fN NUMBER OF ASSEMBLIESYEAR WHEN THE STORAGE SPACE RUNS OUT AT THE PLANT SITE. FULL CORE RESERVE(FCR) ASSUMED.ADDITIONAL STORAGE REQUIRED TO THE END-OF-LIFE OF THE PLANTS. FCR ASSUMED.NUMBERS IN () INDICATE LOW DENSITY RACKS NEEDED TO ACCOMODATE FUEL LESS THAN 2 YEARS OLD.CLASSIFICATION OF PLANTS ACCORDING TO ADDITIONAL STORAGE NEED (AS OF 1988).

X PLANTS WHICH CURRENTLY NEED ADDITIONAL STORAGE SPACE WHEN POOLS ARE CONVERTED TO LOW DENSITY.Y PLANTS WHICH CURRENTLY HAVE SPACE BUT WHOSE SPACE WILL RUN OUT BEFORE CONSTRUCTION OF ADDITIONAL SPACE

WHEN POOLS ARE CONVERTED TO LOW DENSITY RACKS (CONSTRUCTION TIME BASED ON THE CASK OPTION.)Z PLANTS WHICH CURRENTLY HAVE SUFFICIENT SPACE BUT EVENTUALLY NEED CONSTRUCTION OF ADDITIONAL SPACE

WH POOLS ARE CONVERTED TO LOW DENSITY RACKS( MES IN ) INDICATE THE YEARWHEN CONSTRUCTION OF ADDITIONAL STORAGE SPACE SHOULD BEGIN - BASED ON THE CASKSTORAGE METHOD.)

U PLANTS WHICH HAVE SUFFICIENT SPACE UNTIL END-OF-LIFE OF THE PLANT.STARTUP DATE BASED ON PROJECTED YEAR OF FIRST DISCHARGE.NEED ADDITIONAL STORAGE SPACE AS OF 1996.INCLUDED IN UNIT ISAME AS UNIT 1NO SPACE IN THE POOL FOR FCR+FUEL LESS THAN 2 YEARS OLD WHEN CONVERTED TO LOW-DENSITY CONFIGURATION.

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TABLE 3.4 Nuclear Power Plant Spent Fuel Storage Data(a) (cont'd)

(u) SOME ROBINSON 2 PWR FUEL IS STORED AT THE BRUNSWICK (BWR) REACTOR SITE.)IN 1986, HARRIS 1 IDENTIFIED SPACE FOR THE FUTURE STORAGE OF BWR FUEL. (HARRIS 2 IS A PWR.)

w CAN BE CONVERTED TO PWR STORAGE IF NECESSARY.(x) THIS NUMBER IS NOT EXPLICITLY GIVEN BY THE UTILITY. MAXIMUM CAPACITY WAS DERIVED FROM.UTILITY'S STATEMENT REGARDING THE TIME WHEN THE STORAGE SPACE RUNS OUT.

(y) INCLUDES STORAGE CAPACITY OF DRY STORAGE INSTALLATION (ISFSI).

N%

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Table 3.5 Storage Options

Number Storage Option Special Condition

1 Wet-Pool

2 Drywell

3 Vault Fuel is Canned

4 Cask 10 MTU Cask

5 Silo

Table 3.6 Incremental Storage Costs Associated With Limited Low-DensityRacking in the Primary Pool (1983 Dollars)

STORAGE PER UNIT ALL PLANTS

OPTION 0UP 5%' 10% 0%" 5% 10%

POOL 2.17+7 1.67+7 1.28+7 2.34+9 1.80+9 1.38+9

DRYWELL 9.13+6 8.24+6 6.85+6 9.86+8 8.90+8 7.40+8

VAULT 2.07+7 1.67+7 1.28+7 2.24+9 1.80+9 1.38+9

CASK 1.20+7 1.22+7 1.05+7 1.30+9 1.32+9 1.13+9

SILO 1.56+7 1.22+7 9.35+6 1.68+9 1.32+9 1.01+9

*Zero % discount ratecapacity is built now

corresponds to the case where additional storage16

Notes: 1. These costs include the cost of in-pool reracking and theincremental costs associated with the change in additionalstorage requirements resulting from the decrease in primarypool capacity.

2. Assuming the extra storage capacity is built when required,two discount rates are applied.

24

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Table 3.7 Checklist for Identification of Affected Attributes

ATTRIBUTE QUANTIFIED UNAFFECTED

1. Public Health X

2. Occupational Exp. X(Accidental)

3. Occupational Exp.(Routine) X

4. Offsite Costs X

5. Onslte Costs X

6. Regulatory Efficiency X

7. Improvement in Knowledge X

8. Industry Implementation& Operation X

9. NRC Development X(a)

10. NRC Implementation X(a)

11. NRC Operation x (a)

(a)Based on DOE/RL-87-11 (Reference 11) virtuv.lly all plants will requireadditional at-reactor spent fuel storage. NRC costs for at-reactorstorage licensing actions are not affected by this alternative.

25

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Table 3.8 Summary of Parameters Affecting Attributes for the Spent Fuel Pool Inventory Reduction Option

Factors AffectingAttributes Attributes Description Quantification References

Public Health A. Pool Failure Probability Seismic Structural Failure Table 3.1Dose Reduction High - PWR 1.8 x IOr'lRy Ref. 2* BUR 1.68 x 1lo-

Low g 0Failure due to Cask Drop

High - PIJR 3.1 x 10-7 lRy Ref. 2- B•R 7.76 x 10-a

Low - 0Others . 0

B. Number of Pools Involved PWR 69 DOE/RL-87-11BWR 39

C. Average Remaining Life- PI4R 29.8 DOE/RL-87-11Time of Plant BWR 27.9

0m D. Radioactive Inventory Worst Case Total Inventory 30 days NUREG/CR-4982Release After Discharge

Best Estimate Last Fuel Discharge90 Days After Discharge

E. M4eteorology Zion

F. Population Worst Case Zion (860 people/sq. mi.)U.S. Average 340 people/sq. mi.

G. Risk Reduction 80% Sequence Frequency 801 NUREG/CR-4982Reduction

Reduction of Considered to be insig-Occupational nificant compared toExposure Public Health Impact-- Accidental

Reduction of No significant changeOccupational expectedExposure-- Routine

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Table 3.8 Summary of Parameters Affecting Attributes for the Spent Fuel Pool Inventory Reduction Option (Cont'd)

Factors AffectingAttributes Attributes Description Quantification References

Offsite Property A, B, C. 0, E, F, G Same as those of Public Health

DamageEcomony ZionDiscount Rate 10%

Onsite Property Decontamination, Refur- 5 years NUREOCR-3568

Damage bishment and Replace- EPRI MP-3380

ement Power Time.Discount Rate 10%

Reg. Efficiency Unaffected

Improvement in UnaffectedKnowledge

Industry Imple- Additional Storage High (Pool Option) DOE/RL-87-11

mentation and Option and Reracking Low (Drywell Option) EPRI NP-3365

Operation Cost.Discount Rate 10%

NRC Development Unaffected/Implementation/Operation

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Table 3.9 Summary of Industry -Wide Value-Impact Analysis of the InventoryReduction Optionta)

Dose Reduction (Person-Rem) Evaluation ($1983)Best High (b Best High (b)

Attributes Estimate Estimateb) Estimate Estimate

Public Health 4.00 x 104 1.28 x 105 4.00 x 107 1.28 x 10O

Occupational Exposure/Accidental - 0 - 0 -0 - 0/Routine - 0 - 0 - -0

Offsite Property 1.42 x 106 2.22 x 106

Onsite Property 5.54 x 106 4.25 x 107

Regulatory Efficiency Unaffected

Improvement in Knowledge Unaffected

Industry Implementationand Operation -1.38 x 109 -1.13 x 109

NRC Development, Imple-mentation and Operation Unaffected

Net Benefit ($) -1.33 x 10 9(c)-9. 5 7 x 108

Benefit ($)/Cost ($) Ratio 0. 0 3 5 (c) 0.15

Ratio of Public Dose Reduc-tion per Million DollarsCost (Person-rein/$10 6) 2 9 . 0 (c) 113.0

Cost of Implementation perAverted Person-rem($/Person-rem) 3 . 4 541 0a(c) 8.83x10 4

(a)Based upon a U.S. pool population of 108.(b)High estimate is based on the 'Worst Case' source term release and Zion

site population (see Table 3.2).(c)Based on 1988 dollars, the Best Estimate Net Benefit, Benefit/Cost Ratio,

Public Dose Reduction per Million Dollars Cost and Cost per Averted Person-rem would be -1.47x10 Dollars, 0.032, 26.4 Person-rem and 3.79x10" Dollar/Person-rem, respectively. Cost escalation during 1983-1988 was assumed tobe 9.8% (Reference 17).

28

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Table 3.10 Value-Impact Sensitivity Analysis of the Inventory Reduction Option

Public DoseNet Reduction/ Benefit/

Parameter New Value Benefit $ Million $ Cost

Baseline Best Estimate -1.33E9 29.0 .035

Pool Failure Probability Factor of 100 Increase 3.32E9 2900 3.5

Discount Rate 5% -1.75E9 22.2 .028

Monetary Evaluation ofHealth Effects $500/person-rem -1.35E9 No Change .020

$2000/person-rem -1.29E9 No Change .063

Economics of the PlantSite W. Virginia -1.34E9 24.5 .029

29

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4. IMPROVEMENT OF POOL MAKE-UP RELIABILITY

4.1 Introduction,

In the current section, the risk-control efficacy of Standard ReviewPlan (SRP) requirements upon pool make-up capability is characterized within avalue/impact framework. The approach taken is one of evaluating first therisk-reduction profile of requirements exceeding those of the SRP. Second forolder plants comparable to the SRP requirements, the risk-reduction potentialfor similar requirements is also assessed.

The methods used to provide cooling for the removal of decay heat fromstored assemblies in a spent fuel pool vary from plant to plant. Spent fuelassemblies are cooled and covered with water during all storage conditions.

If circulation of the pool cooling water is disrupted, e.g., due to sta-tion blackout, pump failure, pipe rupture, etc., the water temperature of thepool would steadily increase until boiling occurred.

Thermal -hydraulic analyses of the consequences of partial or completeloss of pool cooling capability are a routine part of the safety analysisreports required for licensing. Generally, these analyses address severalscenarios ranging from likely to extremely unlikely conditions. Even underpessimistic assumptions the water level in the pool would drop only a fewinches per hour. Thus, there 'is considerable time available to restore normalcooling or to implement one of several alternative backup options for cooling.

The NRC Standard Review Plan13 provides guidance and defines the accep-tance criteria for spent fuel pool cooling systems and is used by the NRCstaff to determine whether a specific design' complies with the Commission'sRules and Regulations.

The SRP requires conformance with General Design Criteria 2, 4, 5, 44,45, 46, 61 and 63 along with several specific criteria relating to operatingtemperatures and structural classification. Although these requirements arevery general the SRP requlires, as a minimum, redundant cooling systems as wellas redundant makeup systems. Thus, four failures must occur before the spentfuel pool can be uncovered. A station blackout could cause these multiplefailures, but the likelihood of recovering from a station blackout before thespent fuel is uncovered (at least 24 hours) is extremely high.

4.2 Quantification

Four *generic" fuel pool cooling and makeup systems have been examined toillustrate the possible range of failure frequencies for these systems. Thefailure estimates are also "generic" in nature and may tend to overestimatethe actual failure rates. A detailed systems analysis of a specific coolingsystem (including recovery actions) is likely to result in a somewhat lowerfailure' rate considering the time frame (days) for recovery. The four repre-sentative systems are outlined below.

31

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System A - Minimum cooling and makeup system required by the SRP: 13 One fullcapacity cooling train with redundant activecomponents (i.e., re-dundant valves and pumps). One Category I makeup system and onebackup pump or system (not required to be Category I) which can bealigned to a Category .1 water supply.

System B - Minimum cooling and makeup system with credit for makeup from firesystem (Note that some plants may identify the fire system as thebackup in System A).

System C -Typical older system comparable to current SRP requirements: Onecooling train with backup active components (but backup componentsare required to supplement cooling about 30% of time"1 ); One safetygrade makeup train and one non-safety grade makeup system.

.System D - Typical older system (System C) with third makeup train available(e.g., fire system).

Simplified failure estimates are listed in Table 4.1 for these four rep-resentative systems. Note that systems A and B are not intended to representactual systems. Rather, they are representative of the minimum requirementsin the current SRP. Systems C and D are based on a previous analysis' andrepresent older plants.

The failure rates and system failure frequencies are based on failurerate data from the Reactor Safety Study'1 with methods similar to the Priori-tization Study. 15 Specifically:

° An 0.1 per reactor year frequency for the initiating event is based onthe Reactor Safety Study estimates for failure of one spent fuel poolcooling train.

° The conditional failure probability of 0.05 (for the second train ofType A and B) represents a relatively high commnon mode failure proba-bility given previously in the Prioritization Study. s

° The conditional failure probability of 0.3 (for the second train ofType C and 0) represents the assumption that both cooling pumps arenecessary 30% of the time. Thus a failure of one pump represents afailure of the system.

° Train 1 of the makeup system is assumed to be independent of the cool-ing system and is assigned a low common cause contribution. Note thatthe likelihood of the prolonged (greater than 24 hours) station black-out event is assumed to. be low (<10-6 per reactor year). Otherwisestation blackout could provide a common cause failure of all pumps.

a Train 2 of the makeup system is assumed to have a high common causecontribution (-5%) since it is likely to have several active compo-nents in common with the first train of makeup.

32

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*The 5% conditional failure probability of the fire system is arbitraryand can only be construed as engineering Judgement. The likelihood ofsuccessful cooling with the fire system after all else has failed willdepend greatly-upon plant specific equipment and emergency procedures.

The failure frequencies for these four systems range from 2.2 x 10-5 to1.9 X 10-7 per year. Although a loss of cooling and subsequent heat n~ is avery slow event (several days), previous analyses by Benjamin et al. haveshown that after the fuel is uncovered, the remaining water would block aircirculation and clad overheating would occur even for fuel which had beencooled for 1 year. However, because of the lack of air circulation within thespent fuel holders, the oxidation reaction would be oxygen starved and cladmelting would not occur. Thus, catastrophic failure of the spent fuel wouldnot be expected. Consequence estimates have been obtained previously for thistype of accident (see page 65 of liVREG/CR-4982, Cases 3 and 4). Only the.noble gases were released in significant quantities. The consequences werefound to be minimal (about 4 person-rem). Thus the offsite health conse-quences of this type of accident are expected to be minimal. However, theeconomic consequences of such an accident appear to be important. Since thereactor could not operate until the spent fuel pool was available, the cost ofthe replacement power, until the spent fuel pool building was decontaminatedand the equipment was repaired, could be considerable. It is estimated thatrepairs and decontamination would take from one. month to a year depending uponthe degree of fuel damage and contamination. Replacement power was calculatedbased. on a 1,000 t4W generic plant and a 65% capacity factor.5 The onsitecost would then range. from 16 to 195 million dollars conditional upon a spentfuel pool accident. Integrated over the life of the plant (taken to be 29.2years, the industry average remaining plant lifetime), the expected costassociated with gradual coolant loss sequences could be as high. as $125,000per plant (assuming failure rate frequencies for a plant with system C: seeTable 4.1).

In calculating the expected averted costs-associated with improved make-up systems, the product of the resultant accident sequence frequency reductionand the onsite costs associated with the accident, discounted at 10% over theremaining plant lifetime is evaluated.

Two alternative systems for improvement of the fuel pool cooling systemhave been assessed as potentially cost-beneficial for the four system types:

" Alternative 1 is simply another full capacity pump and associatedvalves to eliminate the need for running the cooling system without abackup pump (System C). The cost estimate for this alternative is$50,000 (1983) based upon References 16 and 17.

" Alternative 2 is a completely independent makeup train.- We assumethis system to be similar to the primary spent fuel pool supply train.The hardware requirements include a Category I water storage tank(200,000 gallon capacity), pumps, controls and piping. The cost ofthe independent makeup train plus overhead and maintenance costs wereestimated with the aid of References 16 and 17. The cost is estimatedat $106' (1983).

33

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4.3 Results and Conclusions of Value-Impact Study

The cost/benefit characteristics of adding either of these improvementsto the four generic spent fuel pool cooling systems is summarized in Table4.2 where a discount rate of 10% is assumed. Only improvements to one coolingsystem (Type C) appears to have non-negligible economic. risk impact. Thegeneralized representation of the Standard Review Plan requirements indicatethat additional requirements would not result in cost/beneficial improvements.Although the assessment was based on the 1983 dollars, minor variations ofequipment costs due to inflation between 1983 and 1988 do not significantlyalter the conclusions of this study.

For those older plants (Type C) which operite the spent fuel pool coolingsystem without a backup, these preliminary evaluations indicate that the addi-tion of a full capacity pump or a redundant makeup train is not a cost-benefi-cial measure (see Table 4.2). However, the estimated cost of a full capacitypump is approaching the range of averted cost. Thus such an improvement maybe justifiable on a plant-specific basis.

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Table 4.1 Failure Frequency for Generic Spent Fuel Pool Cooling and Makeup Systems*

Total FailureFailure Rates Per Demand Frequency

Coolinq System up SZstem Per SystemSystem Type Description Train 1* Train 2 Train I1 Train 2 Fire System Year

A. Minimum SRPRequirement 0.1 0.05 0.015 0.05 3.8 x 10-6

B. Minimum SRPRequi rementWith Credit forFire System 0.1 0.05 0.015 0.05 0.05 1.9 x 10-7

L" C. Old ExistingPlant with BothCooling PumpsRequired 30% ofTfmett 0.1 0.3 0.015 0.05 2.2 x 10-

0. Old ExistingPlant With

0

Credit for FireSystem 0.1 0.3 0.015 0.05 0.05 1.1 x 10"6

* Reference 1.•*Ugnits of failure per system year.

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Table 4.2 Value-Impact for Generic Improvements to the Spent Fuel Pool Cooling System*

Improvement Expected Averted Benefit/System Description Improvement Cost (1983$) Cost (1983$) Cost Ratio

A. Minimum SRP 1. Additional pump 50,000 None 0.0

2. Additional train L.0E6 545 to 6640 "0.01

8. Minimum SRP 1. Additional pump 50,000 None 0.0RequirementWith Credit 2. Additional train 1.0E6 27 to 330 0.0for FireSystem

C. Old Existing 1. Additional pump 50,000 2500 to 30.400 .05 to 0.61Plant WithBoth Cooling 2. Additional train 1.0E6 3160 to 38,550 .003 to 0.04Pumps Required30% of Time

D. Old Existing 1. Additional pump 50,000 125 to 1500 .0025 to 0.03Plant WithCredit for Fire 2. Additional train 1.0E6 159 to 1940 <.002System

*Quantification reflects a single spent fuel pool.

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5. ACCIDENT MITIGATIVE OPTIONS

5.1 Introduction

This section discusses several proposed methods that might serve to miti-gate the consequences of "beyond-design-basis accidents" in commercial nuclearpower plant spent fuel storage pools. Two hypothetical accident sequences,defined In Section 5.2, have been considered. The efficacy of three mitigat-ing systems is evaluated for each of the two accident sequences. The objec-tive of these preliminary evaluations is to identify which mitigating mea-sures, if any, appear to merit more detailed analyses. A value-impact assess-ment for one of the mitigative measures is performed in Section 5.5.

It must be noted that the designs and structural details of spent fuelpools are plant specific. Also, the current inventories of spent fuel varygreatly from plant to plant. Therefore, the evaluations that follow will notapply equally to all plants. In the event that more detailed analyses arefound to be merited, such evaluations will need to be carried out on a plant-specific basis.

5.2 Definition of Accident Sequences

Generic Safety Issue 82, "Beyond Design Basis Accidents in Spent FuelPools," was the subject of a recent risk assessment' limited specifically toaccident sequences resulting in complete or partial loss of water inventory ofa spent fuel pool. Initiating events for such sequences included:

- structural failure of pool due to seismic events, missiles or caskdrop;

- water inventory boil-off resulting from prolonged loss of cooling watercirculation capability; and

- partial drain down of pool due to pneumatic seal failure.

Accident sequences that were analyzed in Reference 1 ranged from cata-strophic cases which involved Zircaloy fires to less severe situations inwhich damage was limited to multiple cladding failures.

For purposes of this report, two sequence types have been selected torepresent a bounding case with respect to the source terms involved. Lesssevere cases, such as partial loss of water inventory and loss of coolingcapability are not discussed, since the source terms released to the environ-ment from these sequences are relatively small and thus the associated riskreduction potential is bounded by those discussed here. The less severeaccident sequences are also relatively low frequency. For both the sequencesconsidered, it is assumed that radiation levels severely limit or precludehuman access to the spent fuel pool area. Also, it should be noted that mostof the accident sequences are postulated to occur simultaneously with otherplant disruptive events due to common initiating causes such as seismicevents. The sequences are characterized In the following sections. Forconvenience, the accident sequences have been denoted by the symbols "Al" andKA2." 1

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5.2.1 Accident Sequence "Al," A Complete Loss of Pool Water Inventory Fol-lowed by a Zircaloy Fire

The accident sequence, "Al," reflects an upper bound scenario with re-spect to potential radiological releases. It is based on the followingassumptions:

- structural failure of the pool results in a complete loss of waterinventory;

- the age and storage configuration of the spent fuel meet the criteriafor ignition of a Zircaloy fire (see Reference 1, pp. 49-62);

- the Zircaloy fire propagates through all of the spent fuel assembliesstored in the pool;

- a major fraction of the U02 fuel pellets are oxidized to U30s and relo-cate as a bed of rubble on the bottom of the drained pool; and

- the containment integrity of the building covering the spent fuel poolis breached.*

The fire is assumed to burn and propagate through the spent fuel inven-tory for a period of approximately eight hours, producing localized maximumtemperatures in the range of 15000C as each fuel batch successively ignitesand the cladding Is consumed (see Reference 18 for the temperature-time pro-files for several typical cases).

Theoretical analyses and expertimental data that relate to an Al typesequence are very limited, and, in particular, no studies have been made whichcan be readily adapted to characterize the bed of debris resulting from aspent fuel Zircaloy fire. As far as a source term for sequence Al is con-cerned, the release data obtained from the Chernobyl accident, i.e., the frac-tional releases that occurred after the initial burst release, are possiblypertinent. Such data are summarize in Section 6 of Reference 19. The Cher-nobyl fractional releases of specific isotopes c•iffer somewhat from the esti-mates made in Reference 1, Table 4.2, pg. 69. In particular, the cesiumrelease fractions were an order of magnitude smaller in the Chernobyl case.For purposes of bounding the risk reduction potential of mitigative optionsdiscussed in Section 5.3, the release fractions estimated in Reference 1 andutilized in Section 3 of the current document will be adopted, pending furtherinvestigation of the relevance of the Chernobyl data. The sourceterm isobtained by convolution of the fractional releases with the. radionuclideinventory as a function of decay time (tonnes of fuel in each dischargebatch).

5.2.2 Accident Sequence "A2," A Complete Loss of Pool Water Inventory Fol-lowed by Clad Failures but Not Zircaloy Fire

The accident "A2" sequence, is based on the following set of assumptions:

- complete loss of water inventory due to structural failure of the pool;

*Spent fuel pools are normally housed in "secondary containment" areas (as,e.g., in BWRs), or in auxiliary buildings that provide only limited containment capability; however, even limited containment, when intact, can greatlyattenuate the source term. The sequence Al assumes that the building roofhas collapsed as a result of the intense heat of the Zircaloy fire, and vigorous convection carries the plume into the atmosphere.

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-conditions for the ignition of a Zircaloy fire are not satisfied (seeReference 1, Tables 3.1 through 3.5);

- the containment integrity of the building is intact;- pool structural damage is such that water inventory cannot be restored

before extensive clad failures; and- all assemblies with decay times of 5 years or less subsequently suffer

100% failures of the clad pressure envelope.

The fractional releases of selected radionuclides from the fuel (gap re-leases) are assumed to be as follows:

Noble gases: 1.00Cesium isotopes: 0.05

5.3 Definitions of Mitigative Measures

Several measures have been proposed which might effectively mitigate theconsequences or interrupt the progress of beyond-design-basis accidents inspent fuel pools (e.g., see Reference 1, Section 6). Design criteria for suchsystems depend on the particular accident sequence against which protection issought. Design details would be plant specific as appropriate for the partic-ular pool configuration. Not all measures would be applicable to all spent

fuel pools.

5.3.1 Mitigative Measure "Ml," Covering Fuel Debris With Solid Materials

Mitigative measure, "Ml,* applies only to accident sequence Al, i.e., acatastrophic accident in which the stored fuel inventory has been reduced to abed of hot rubble. It consists of the a contingency plan to dump massiveamounts of various solid materials into the drained pool to cover the rubble

to a depth of several feet. It is assumed that the solid materials are notstockpiled onsite, but could be obtained in a timely manner on an ad hocbasis, the materials being commonly available in all parts of the country.The types of material or potential value include sand, clay, dolomite, boroncompounds, lead, etc. "Ml" would consist of a generic contingency plan that:

- specifies the types and quantities of materials that would be used;- conceptual studies on how the materials could be emplaced; and- analyses on attenuation of radioactive releases and gamma-ray shielding

efficacy.

5.3.2 Mitigative Measure "M2," Water Spray Systems

Mitigative system, "M2,* consists of a water spray system located abovethe pool, having sufficient- capacity to block or mitigate a given accidentsequence.

5.3.3 Mitigative Measure "M3," Building Ventilation Gas Treatment System

Mitigative system, "M3," consists of a building ventilation/filter systemdesigned to reduce the concentration of airborne radioactivity beforedischarge to the environment.

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5.4 Discussion of the Efficacies of Mitigative Measures for Two AccidentSequences

This section presents qualitative evaluations of the mitigation measuresfor the different accident sequences. The objective is to identify whichmeasures, if any, appear to merit more detailed, quantitative analysis.

5.4.1 Zircaloy Fires (Al): Mitigative Options

Al/Mi: An Al sequence initiated by a beyond-design-basis seismic eventimplies serious damage in other sections of the nuclear plant, as well asmajor disruption of emergency services in the surrounding region. Given acatastrophic Zircaloy fire, the M1 measure would attenuate prolonged radioac-tive releases from the bed of rubble, but it appears dubious that the measurescould be implemented soon enough to prevent a major release to the environmentduring the first few hours of the sequence.

The question to be evaluated here, is whether it would be cost effectiveto develop a generic contingency plan as a cooperative effort among all licen-sees, and, if so, hgw much development effort would be merited? The contin-gency plan would be concerned with an extremely low frequency, but high con-sequence event.

The results at Chernobyl can be used as a rough gauge of the efficacy ofthis measure, when carried out on a strictly ad hoc basis with apparently noadvanced planning. It is reasonable to assume-t-hat a generic M1 plan could beprepared that, if ever needed, could be more effective than the Chernobyl ex-perience, i.e., be implemented sooner and provide higher attenuation of radio-active releases.

It is our evaluation that M1 merits a small effort, perhaps a few man-months of study to determine whether a more intensive planning effort would becost effective.

Al/M2: A seismic Category I safety-grade water spray system drawing on aCategory I reservoir of water could be effective in mitigating the conse-quences of a Zircaloy fire in a spent fuel pool that has lost its water inven-tory. Such a system built to meet seismic safety standards would have a veryhigh probability of surviving a seismic event. It would also act as a standbyfor an accident initiated by a shipping cask drop resulting in structuralfailure of the pool. A value/impact analysis for a spray system is describedin Section 5.5.

In situations where spray actuation is retarded relative to fire initia-tion, there is the possibility that oxidation could be aggravated by the watersource. Consideration of this scenario is beyond the scope of the currentanalysis.

Al/M3: No building ventilation system could cope with an Al accidentsequence.

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5.4.2 Clad Failure Without Zircaloy Fire (A2): Mitigative Options

A2/Ml: In the event of a structural failure which allows the pool waterinventory to drain, recovery from the accident would present difficult prob-lems even though no Zircaloy fire occurred. Radiation levels above the poolwould be extremely high, preventing human entry. Structural repairs whichwould allow the pool to be refilled with water would be difficult, is not im-possible. Therefore, an M1 type measure might prove necessary for recovery.The cost effectiveness of developing a contingency plan faces the same uncer-tainties as described earlier for Al/Mi. It is our evaluation that a modesteffort appears merited and could be included in the scope of the Al/Mi study.

A2/M2: (See AI/M2. The same evaluation applies here).

A2/M3: In an A2 sequence, in which the building integrity is notbreached, an M3 building ventilation and gas treatment system could reduce thedischarge of airborne particulate radioactivity. To be effective, the systemwould have to be qualified to survive the A2 initiating event, and have ade-quate capacity to handle extremely large volumes of air. Removal of noblegases from the circulating air would require heroic measures - a system ofcryogenic filters (e.g., liquid nitrogen cooled zeolite beds), that could bepurged into high pressure cylinders at frequent- intervals, and, of course, alarge supply of liquid nitrogen would be necessary. Investment in an effec-tive M3 system to cope with an extremely low frequency A2 accident sequencewould not appear to be reasonable.

5.5 Value-Impact Assessment of a Post-Accident Spray System

5.5.1 Characterization of Post-Accident Spray Systems

Post-accident spray systems were discussed in Section 5.4 as a potential-ly significant mitigative measure for spent fuel accidents. A scoping value-impact assessment has been performed in this section to provide some insightinto the potential cost-effectiveness of introducing spray systems. Thisassessment is a rough approximation (order of magnitude) of a cost and benefitcomparison and generally follows the guidelines outlined for "First Approxima-tion of Benefits and Costs" in NUREG/CR-3568. 5

It should be emphasized that this assessment is scoping in nature due tothe many assumptions involved and large uncertainties in data, especially withrespect to the estimation of seismic accident sequence frequencies, and decon-tamination factors assumed for spray systems. The benefit estimate has thepotential to be increased significantly through modification of assumptionswith regard to cask drop frequencies.

The principal risk reduction effect of spray systems is achieved by de-contaminating radiological releases thus permitting greater retention of fis-sion products in the pool and the pool building. Results of analyses ofsevere reactor accidents (Draft NUREG/CR-4551, Vol. 1, in support of DraftNUREG-1150) 2 ° indicate that containment spray systems can be significantlyeffective in reducing source terms and severity of consequences of nuclearreactor accidents.

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In this assessment, it was assumed that the major benefit of spraysystems derives from reduction in the offsite consequences. In NUREG/CR-3673;it was estimated that occupational exposure would be small compared to theoffsite impact of a radiological accident. The incremental contribution torisk reduction through mitigation of the accident would then be a much smallerand second order effect. ' Decontamination and Replacement Power Costs wouldalso be assumed to be minimally influenced by the use of a spray system.

5.5.2 Quantification

The effectiveness of a spray system is measured by the DecontaminationFactor (DF - The amount of release of the radioactive species to the environ-ment without spray divided by the amount of release with spray). Decontamina-tion factors for a fuel pool spray system are difficult to estimate withoutdetailed calculations. A DF for containment spray systems (for major reactoraccidents) was assigned a best estimate of 45 across radionuclide groups inthe NUREG-1150 analysis of the Surry plant. 2 0 That factor will be assumed forthe current calculations. From Table 5.1 it may be seen that a Df of 45 hasthe effect of reducing offsite consequences to a small fraction of their ori-ginal levels. In practical terms, therefore, a DF of 45 provides an upperbound upon the value/impact ratio relative to spray effectiveness.

In Reference 1, seismic initiators and cask drop accidents wereidentified as potentially dominant contributors to the risk for spent fuelpool accidents. Contributions from other sequences were assessed to berelatively small due both to lower initiator frequencies and lesserradiological releases. For purposes. of the current scoping analysis, anaccident sequence frequency was assumed corresponding to data presented inTable 3.1.

Preliminary construction and industry maintenance costs were based uponReferences 16 and 17. Assumed hardware requirements included a Category Iwater storage tank (200,000 gallon capacity) and a spray system includingpumps, spray nozzles, and associated hardware. Total costs (industry wide:108 pools) were estimated at $1.1E+8 (1983$).

The offsite consequences were calculated using the 14ACCS code. 6s The Zionplant was selected as a reference plant since detailed population and landdata were available. Two calculations were performed varying source terms andpopulation density. The population density of 340 persons/sqt. mile used inthe "Average Case" is a U.S. average figure. The average source termdeveloped in NUREG/CR-4982 was utilized here. The "Norst Case" represents thecombined effect of the worst-case source term developed in NUREG/CR-4982 and ahigh population density (860 persons/square mile: Zion population). The Zioneconomic data and Zion meteorology were used for both calculations. The off-site property damage in MACCS is given in 1980 dollars and has been escalatedto 1983 dollars. Table 5.1 summarizes these calculations..

Results of the value/impact analysis are shown in Table 5.Z. The tableindicates a first estimate of industry-wide potential benefit of $4.2E+7 basedpurely upon the dollar conversion of radiological dose to the population, anda potential cost of $1.1E+8. The expected averted offsite economic impact isestimated to be $6.77E+6. These figures are based upon the average caserelease/population assumptions, and a 10% discount rate for monetary costs.

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For the worst case release/population, the expected dose reduction benefitover plant lifetime (with $1000/person-rem conversion) is $1.18E+8 and theeconomic impact reduction is $5.20E+7.

5.6 Conclusions

Inspection of Table 5.2 reveals that for best estimate calculations, theinstallation of pool sprays is not a cost-effective measure. High estimatesof risk-reduction (high source term and Zion demography) can be seen to resultin marginally cost-effective comparisons for this option. As a genericindustry-wide analysis based upon the U.S. population of plant sites,however,utilization of Zion site demography for consequence evaluation results in anoverly conservative estimate of risk-reduction properties of a given plantmodification. Use of Zion demography in the 'high estimate' calculations isintended only to provide insights into the potential site-specific risk reduc-tion achievement of a given backfit. In-plant, pool-specific evaluations ofrisk-reduction would need to be performed, however, to reach conclusions re-garding the cost-effectiveness of any modification on a plant-specific basis.As with the fuel reracking measure discussed in Section 3, the dominant sensi-tivity factors in the cost-benefit evaluation are the frequencies of the poolfailure sequences. A given percentage increase in the assumed freqdency ofall sequences leading to structural failure of the pool would result in anequal percentage increase in the risk-reduction value of the pool spray op-tion. Current assumptions regarding the frequencies of the seismic and heavyload, drop sequences are based upon the sequence analyses of Reference 1 andthe updated seismic and load drop fragilities reported in Reference 2. Thecurrent study may easily be used to reflect alternative assumptions regardingsequence frequencies through straightforward numerical scaling adjustments ofthe results generated.

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6. SUMMARY AND DISCUSSION

Generic analyses of various potential modifications to nuclear powerplant spent fuel pools have been performed. Cast within the framework ofvalue/impact analysis methodology, the risk-reduction value and the costimpact of these modifications were evaluated and compared. The analysesfocused upon the risk-dominant accident sequences Identified in Reference 1.Both accident preventive and accident mitigative risk-reduction options wereassessed. These were as follows:

1. The limited low-density reracking of recently discharged fuel to de-crease the likelihood of the initiation of self-sustaining clad oxi-dation in the event of loss of pool water inventory.

2. The addition of a full capacity pump in one pool coolant makeup trainto increase pool cooling reliability.

3. The addition of a completely independent pool coolant makeup train.4. The installation of pool sprays to attenuate fission product releases

in the event of fuel degradation.

Best-estimate calculations of the following value/impact attributes wereperformed: Public dose, offsite economic impact, onsite economic impact andindustry implementation and operation costs. Other attributes identified,such as occupational exposure and regulatory efficiency improvement were con-sidered either to be negligible contributors to the value/impact balance orunaffected within the scope of the current project. A $1000/per person-remaverted conversion factor was utilized to convert dose-reduction measures intoa monetary measure in the best estimate calculations. None of the risk-reduction measures were'assessed to have a value/impact ratio greater than 1.

A series of sensitivity calculations were performed in which variousparameter inputs and modeling assumptions were varied. Factors varied in-cluded source term magnitude, site demography economics and meteorology, acci-dent sequence frequencies, cost discount rate, ,•se/dollar conversion and thecost of implementation to industry. The only factors with significant influ-ence upon the balance of value against impact was found to be the frequenciesof the sequences that involve structural failure of the pool due to seismicevents and heavy load drop events. The aggregate frequency of all suchsequences is found to behave as a simple multiplier in evaluation of therisk-reduction value of the low-density reracking and the spray installationoptions. Hence to increase this aggregate frequency by a factor of 10, say,is to increase the risk-reduction value of each of these two plant modifica-tions by a factor of 10 also. In the case of low-density reracking, thisaggregate frequency would need to be increased by two orders of magnitude toenter the cost-effective domain while, for spray installation, increase by asingle order of magnitude would increase the value/impact ratio above 1. Itshould be noted that even then, to draw inferences regarding the cost-effectiveness of a pool modification on a plant-specific basis would requireplant-specific analyses.

Given this sensitivity to the sequence frequencies, it is important toidentify the factors and assumptions that influence these frequencies. Theseinclude seismic hazard magnitudes and pool fragilities. Reference 2 provided

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the basis for the current quantification. Additional important assumptionsrelate to the effect of implementing the resolution of Generic Issue A-36 inthe handling of heavy loads in the vicinity of the pool. These assumptionsare summarized in Table 3.1 and are based upon discussions in Reference 1.

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7. REFERENCES

1. V.L. Sailor et al., "Severe Accidents in Spent Fuel Pools in Support ofGeneric Safety Issue 82," NUREG/CR-4982 (July 1987).

2. P.G. Prassinos et al., "Seismic Failure and Cask Drop Analysis of theSpent Fuel Pools at Two Representative Nuclear Power Plants," NUREG/CR-5176 (January 1989).

3. H. George, "Control of Heavy Loads at Nuclear Power Plants," NUREG-0612(July 1980).

4. A.S. Benjamin et al., "Spent Fuel Heatup Following Loss of Water DuringStorage," NUREG/CR-0649 (March 1979).

5. S.W. Heaberlin et al., "A Handbook .for Value-Impact Assessment," NUREG/CR-3568 (December 1983).

6. U.S. Nuclear Regulatory Commission, "Reactor Risk Reference Document,"NOREG-1150, Appendix 0, Vol. 3, Draft for Comment (February 1987).

7. J.S. Evans et al., "Health Effects Model for Nuclear Power Plant Conse-quence Analysis," NUREG/CR-4214 (1985).

8. D.C. Aldrich et al., "Technical Guideline for Siting Criteria Develop-ment," NUREG/CR-2239 (1982).

9. R.P. Burke et al., "Economic Risks of Nuclear Power Reactor Accidents,"NUREG/CR-3673 (April 1984).

10. J.S. McCartney and R.B. Cairns, "Cost. Comparisons for On-Site Spent-FuelStorage Options," EPRI NP-3380 (May 1984).

11. DOE Richland Operations Office, "Spent Fuel Storage Requirements 1987,"DOE/RL-87-11, UC-85 (September 1987).

12. P. Bleimeis et al., "Review and Evaluation of Spent Fuel Pool Expansion*Potential Hazards Consideration," SAI-84-221, WA (July 1983).

13. U.S. Nuclear Regulatory Commission, Standard Review Plan, "9.1.3 SpentFuel Pool Cooling and Cleanup System," NUREG/CR-0800 (July 1981).

14. U.S. Nuclear Regulatory Commission, "Reactor Safety Study: An Assessmentof Accident Risks in U.S. Commercial Nuclear Power Plants," NUREG-75/104,WASH-1400 (October 1975).

.15. U.S. Nuclear Regulatory Commission, "A Prioritization of Generic SafetyIssues," pp. 3.82-1 through 6 (December 1983).

16. United Engineers and Constructors, Inc., "Capital Cost: PressurizedWater Reactor Plant," NUREG-0241 (June 1977).

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17. R.S. Means Co. Inc., Building Construction Cost Data, 1988, 46th AnnualEdition, Kingston, MA (1987).

18. N.A. Piscano et al., "The Potential for Propagation of a Self SustainingZirconium Oxidation Following Loss of Water in a Spent Storage Pool,"Draft Report (January 1984) PDR Accession No. 8505090480.

19. U.S. Nuclear Regulatory Commission, "Report on the Accident at the Cher-nobyl Nuclear Power Station," NUREG-1250 (January 1987).

20. A.S. Benjamin et al., "Evaluation of Severe Accident Risks and the Poten-tial for Risk Reduction: Surry Power Station, Unit 1," Draft Report,NUREG/CR-4551 (February 1987) PDR Accession No. 8703170262; M. L. Ernst,et al., "Reactor Risk Reference Document," Draft Report, NUREG-1150 (February1987) PDR Accession No. 8703100040 (Vol. 1), 8703170207 (Vol. 2), and8703180080 (Vol. 3).

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APPENDIX A

Additional statistics associated with Limited Low-Density Storage of

Spent Fuel.

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TABLE Al. COST TO PROVIDE THE ADDITIONAL STORAGE CAPACITY TO COMPENSATEFOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS STORAGE OPTIONS(1983 DOLLARS)

----------------------------------------------------------------------------------------------------------------

l I .. .LOWDEN BUILT NOW IBUIL T WHENNEEDED( 10%DISCOUN T RATE)PLANT NAME TYPE SHUTHUDO0- -I RACKS .............................................................. ...

YEAR NEEDED POOL DRYWELL _VAULT .. .CASK I SIO I POOL .DRYWELL .VAULT I SILO

AABB

AA

u'

B

B

AA

ARK NUCLEAR 1ARK NUCLEAR 2BEAVER VALLEY 1BEAVER VALLEY 2BELLEFONTE 1BELLEFONTE 2BIG ROCK IBRAIDWOOD 1BRAIDWOOD 2BROW"S FERRY 1BROWNS FERRY 2BROWNS FERRY 3BRUNSWICK 1

BRUNSWICK 2

BYRON 1BYRON 2CALLAWAY 1CALVERT CLF 1CALVERT CLF 2CATAWBA 1CATAWBA 2CLINTON ICOUN"CHE PK 1COMANCHE PK 2COOK 1COOK 2COOPER STHCRYSTAL RVR 8DAVIS-BESSE 1DIABLO CANYON 1DIABLO CANYON 2DRESDEN 1DRESDEN 2DRESDEN 3DUANE ARNOLDENRICO FERMI 2FARLEY 1FARLEY 2FITZPATRICKFORT CALHOUNFT ST VRAINGINNAGRAND GULF IHADDAM NECKHARRIS 1

200820122016202862028203020012028620272014201420172010

2010

202420282024201420162026292820262027203020302009200920082018201720262026198420082008201020262012201220152008200720082022200720286

12013813814818816840

262(a)684(a)468378

376

264(a)168192(a)144144344198(a)268(a)232

721208686

316316286552138138280

98

24084

164104

1.88.72.39.73.46873.64.74.02+74.02.78.87.83.74,7

9.06+81.08.71.19.71.23+71.64+71.64+78.3*363.11.7

1.94.72.$6-72.60+7

2.89.74.08+74.08.71.62.86.08+7

1.26.71.43.71.43+71.61+72.24+72.24+74.33+.2.38.7

1.70.72.00.72.00+72.13+72.77.72.77.72.49+84.62.7

2.32.72.46572.87.71.02.71.23.71.03+77.26863.17.7

1.06571.14.71.38+76.06+67.09.88.00+82.16-82.48+7

1.94+72.13.72.69+79.68+81.63+71.28.73.638+4.31+7

1.36+71.63+71. 97*77.11.81.20+71.00+72.13.83.94.7

1.99.7 1.34.7 3.04,7 1.98.7 2.14.72 * 55.7 1.01.7 2.24.7 1 * 26.7 1.68.7 8.89.8 0.016 1.17.7 9.04.8 8.48.6

2.66+71.47.7

1.80+7

1.01+77.14+8

7.29.8

2.24+71.67+7

1.63.7

1.28-71.00+7

1.01.7

1.07.7

1.14+7

1.28*71.21.7

1.66.7

6.70+88.89.8

7.83+6

2.28+71.34+7

1.64.7

9.63+81.03+7

1.18+7

9.49+69.16.6

1.09+7

3.72+7 3.17.7 6.19,7 2.3657 4.6657

3.51.7 1.48.7 3.3657 1.69+7 2.49.72.47+7 1.20+7 3.22*7 2.88+7 2.0657

3.10+7 3.00.7 3.73+7

1.60.7 8.09+6 1.69+72.11.7 1.38.7 2.6657

4.78.7 2.73+7

1.17.7 1.16872.61.7 1.89.7

1.62,71.64.71.93.77.12.81.08.79.02.63.10.63.10+7

6.62+76.28.72. 38*73.38.7

1.9+.71.87.78.88+61.33+7

3.16+73.09.71.92.78.74.7

1.96-71.94.79. 72.62.68.7

2.46+72.38.71.46.72.36+7

2.06*61.73887.89+84.61.8

1.13+69.89+54.09.62.81.+

1.48+81.28.67.68.66.62+8

1.16.81.01.65.87.64.92.8

1.28.61.09.85.89.84.02+8

3.18.7 1.88.7 4.42+7 2.76+7 3.12+7 2.30*7 1.44.7 3.02+7 2.80.7 2.14.7

9.69.61.39.73.88+71.18.71.18.7

1.42.71.42+71.87.73.80.72.10.72.10.72.61.71.39+7

1.38.72.78.71.82.7.4.76+6"

5.23+80.61+61.24.76.73+66.73+8

6.10.63.63.86.29.81.3a978.47+66.50868.36.83.94.0

1.78a81.31.76.08+64.75+6

1.10.71.39.73.26871.48+71.48.7

1.28+76.89.81.29.73.79+71.78.71.09.71.84+78.09,8

3.33.63.29+71.04.74.76+5

7.62.80.91+81.90.79.83*89.883*0

8.04.63.75.67.83.62.20+71.17.76.18.61.03+74.64+8

9.68961.82.76.91.64.76+5

9.42.81.24+72.09.71.21.71.21.7

1.17+77.74+61.29+72.40+71.66871.*20,71.41.78.6386

6.88+82.26+71.08.74.76+6

8.86.66.79.83.38.73.28.63.28+8

1.32.71.11.71.76.72.89.71.10+79.18.81.79.71.88+7

1.07.71.92.71.76574.7656

4.33+63.12+61.98.71.77+61.77.6

6.79.84.12+66.98+61.69+74.96+83.63+88.38+88.90.8

3.27+61.14.76.88.84.76+6

7.84.85.62.63.49+73.08.83.08.6

1.01.78.83+81.22-73.61.78.67+66.99+61.81.71. 19.7

6.42.62.44*71.17+74.7658

6.66+85.87+6

3.78+72.31-62.31.6

6.98+84.42+88.19.62.98078.14.84.02.61.19.77.64+8

3.23861.*88.77.62+64.7656

6.11-64.40.82.33.72.43.82.43+8

8.21.66.70.89.93.62.47+76.98+86.00.61.20-79.87+6

4.63+81.72.79.62.84.76+6

Page 67: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Al. COST TO PROVIDE THE ADDITIONAL STORAGE CAPACITY TO COMPENSATEFOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS STORAGE OPTIONS(1983 DOLLARS) (Cont'd)

--- ----------------------------------------------------------------------------------- ----- --------------LOW DENI BUILT NOW BUILT WHEN NEEDED(... DISCOUNT RATE)

PLANT NAME TYPE SHUTDOWH RACKS I ....-...........--- ---------------I -.. .

.... N iEEDED DRYOEL L V I .... . ..CASK I SZLO POOL RY1 ELLI VAULT ICASK SILO

--------- ---- I----- ----- I ---- IL ----- I- --- I----- -m----- I------- -- T --------

B HATCH 1B HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT 1INDIAN PT 2INDIAN PT SKEWAUNEELACROSSE

8 LASALLE CTY 1B LASALLE CTY 2LIMERICK 1LIMERICK 2MAINE YANKEEMCGUIRE 1MCGUIRE 2MILLSTONE 1

•n MILLSTONE 2MILLSTONE 8MONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA IA NORTH ANNA 2A OCONEE 2A OCONEE 2

OCONEE 3OYSTER CRK 1PALISADESPALO VERDE 1PALO VERDE 2PALO VERDE 8PEACHBOTTOM 2PEACHBOTTOM 8PERRY 1PILGRIM 1

A POINT BEACH IA POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 2B QUAD CITIES 1B QUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR BEND 1SALEM 1SALEM 2

208920122626197619862006201520142022202228282024202926682821202320102016262520072887

20262618202020132013201420042011202420252026200882008

26262618

2820

2614266420112624

2887

2008

200720252088

2026

22688

8e8(a)464

136152

7448

686

446148

144144196158168240184276195(a)186(a)120258

88170170170456844044819296

(a)120(a) •486(a)138

396884166188

1.8387 1.11+7 2.49+7 1.68.7

2.46,7 1.12+7 2.49.7 1.31.7

1.79.7 9.72+6

1,84.7 7.71+8

6.21+8 1.2067 9.31.6

4.4686 8.63.6 8.27.8

2.52+72.87+71.29471.14.72.73+.

2.84.72.95.72.09+73.19.73.19.73.31.63.24.72.78+71.41271.40+71.51+73.9127

2.17.7

1.80.71.18.71.17.63.66+78.66.73.66.72.19.71.88.72.60.71.17471.45.7

9.7?6"1.19.75.85.61.30867.67.6

1.33+71.38679.77+61.22.71.25.72.82.61.14.71.22.72.68,63.85+66.77+81.68.7

1.01#7

9.08+64.19.63.39+81.37+71.37+78.87.86.65681.84-74.73.65.08+8

2.16.72.67.71.27.72.66+62.89.7

3.17+7S. 18.72.18+72.76+72.02+76.11+62.86+72.73+73.59.65.82.61.27+74.34+7

8.83-7

2.68.78.*41.67.17763.11.73.12,73.01271.97.71.98.7

2.28+71.02.71.34.7

1.49.71.88+77.66+86.77+68.78*8

1.53.71. 52.71.36.71.49.71.48.74.84+61.46.71.81+71.22.62.906.8.07+62.74.7

2.44.7

1.12875.114.65.85*81.58.71.68.71.68.71.30.71.28.71.25.78.14,88.54*8

1.89.72.17#71.15.74.09+81.4387

2.23.72.24+71.80372.06.72.09,73.21.62.88.72.15.76.84+67.01.69.77+82.79+7

1.72.7

1.39.78.43+64.87.82.32+72.82.72.32+71.52.71.49+71.89,7

1.09.7

1.95+71.86.71.18.71.68.71.47.6

2.76+72.19+72.64+71.26.71.15.73.06+62.91+75.20.87.68.61.58+73.14.62.41+7

1.14+7

1.65+71.51.76.70+51.48.71.86+71.24+71.72+71.62+78.48.81.64.71.47.7

1.03.77.87+85.07+86.21+81.1657

1.66871.27,71.28.78.47.88.01+8-3.60.

1.34.72.82.62.68+66.33+61.74.61.35.7

7.81.6

8.80+88.0B8+1.79.67.6*857.03866.45+68.48.68.09+63.86.67.23+68.97*8

1.99.71.48079.18.08.90+68.27#6

3.17.72.68.72.31.71.26+71.*18.71.87.62.61+7

4.84+84.83+89.04.62.90*88.89.7

1.19.7

1.77.71.85.74.088.1.56071.37.71.25.71.66.71.52+78.54+81.34.712.33.7

1.47.71.08.78.29.65.18.82.14.7

2.83.72.82+71.73.79.365-t8.65.69.06+51.91.73.76.62.55+85.68482.29.8

1287.7

1.34.76.97.63.69+6

1.01+79.24+61.22.71.14.76503.89.33869.87*6

8.78*6

6.17.8

1.49.71.12277 • 84.87.8•685.27.6

2.20+71.96.71.71+79.20+88.56861 • 68*61.93.73.79.83.48+67.54.62.29.82.12.7

6.95+6

1.19.78. 6082.82+81.10.71 •01*79.25.81.20*71.15674.96+8

2.88+6

1.1.+77.79.86.42482.62.71.77.7

2.12,7 7.81+6 1.85+7

7.69+6 4.20+8 7.87+8

9.63+8 1.25.7 2.87.7

6.06*6 7.18.6 3.89+8

9.80.6 1.89.7 1.46.7

2.14+8 3.17.6 2.49.6

2.78+75.20.62.45.73.33.78.49+7

8.18+686.616.5.59.69.81.81.39.71.57+7

1.87.71.28.72.82.73.16573.58.7

9.78.69.23+81.18,71.86571.88.7

1.73.79.00+81.63.72.30+72.82+7

2.03+77.77.87.42.82.a9+72.19.7

8.09.86.36261.39+71.20+7

1.41.71.07.77.15.62. 80*72.44.7

9.45.68.49.85.43862.86.71.80÷7

Page 68: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Al. COST TO PROVIDE THE ADDITIONAL STORAGE CAPACITY TO COMPENSATEFOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS STORAGE OPTIONS(1983 DOLLARS) (cont'd)

----------------- ---------------------- w------------------------------------ m------- --

. ..LOW DeNl' WIBUILT NOW I BUILT WHEN NEEDED(lOS DISCOUNT RATE)PLANT NIME TPE I . R . ------- ------- --------- -------- - --- - - ----

YEA NEEDED ~ POOL IDRYWELL VUTI CASK 0 SIL POOL J DRYWELL jVUL CASW I SILO

E SAN ONOFRE IE SAN ONOFRE 2E SAN ONOFRE 3

SEABROOK 1A SEQUOYAH IA SEQUOYAN 2

SHOREHAMSOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE 1ST LUCIE 2SUMMER 1

A SURRY IA SUtRY 2B SUSQUEHANNA IB SUSQUEHANNA 2

THREE MILE ISLE TROJAN

TURKEY PT 3E TURKEY PT 4B VOOTLT 1B VOOTLE 2

VT YANKEE 1WASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK IYANKEE-ROWS 1

A ZION 1A ZION 2

TOTAL

PPPPPPBPPPPPPPBB

1PPPPPPBBPPPPPP

1999281228132031282120222027202728828281020232024201220132022202420820112007

202726828201220232024202628272026200120082008

270

(2)

240(a)38810410416214413"169(a)98"

(a)146

98144(a)262(a)284312178240(a)15276

216(a)

3.2657 1.37*7 3.73,7 2.76+7 2.63.7 2.91+7 1.65.7 3.86+7 3.10+7 2.46.7

3.00.075.38.7

2.48071.42+71.42.76.86-63.68+73.27+71.68.7

4.07+7

2.18-71.488-71.66+7

6.22#71.42.71.66573.63.7

6.82.7

3.7.*72.08073.04.7

1.31.72.37.7

9.11+86.66+66 • 55.87.07+81 . 12.71.12.76.19.0

1.88+7

4.78.688.61+89.33.8

2. i0.7

16.80.08.24.61.41.72.44+7

1.29.72.61+81.25.7

3.00.76.8+67

2.02.71*38.71.36.71.83.72.53+72.68+71.01.7

4.06.7

9.19+61.38+71.99.7

6.19.7

1. 38.71.96573.19.76.62.7

2.92.74.84.84.02.7

1.440.73.39+7

1.04+79.79+09.69+82.16+71.23.71.43.76.56+6

2.49.7

4.*88.89.34.01.46+7

3.02*7

8.86*69.97.61.83.73.47*7

1.67+71.28.62.38+7

2.21.73.49.7

1.61+71.24.71.22.79.*3561.93+71.97+71.06.7

2.73.7

1.07.71.24+71.68-7

S. 26#7

1.26.71.38.72.37&73.64.7

2.18.77.4.6+2.83.7

9.67,63.80.7

8.01.81.71+61.060.2.66.82.06+71.07.74.79+8

1.93.7

1.10.77.66+81.12.7

1.40.7

1.21.71.07.7I.38.72.61+7

1.13.72.04.72.84*7

6.36+62.21+7

4.23861.06.81.00.82.32+89.60866.13.62.21.6

1.16+7

4.11+83.62+66.76÷88

8.01+6

6.41+88.46+87.18.01.62.7

6.6.868.04.61.76.7

1.08.73.98.7

7.79*61.60+81.408+7.08.61.88,79.65.83.42,6

2.44.7

8.7".88.20+81.56*7

1.73.7

9.64.61.32.71.40,73.29+7

1.08+71.02.73.48+7

7.81.84.16.7

6.87.01.21+81 . 14.66.16+81.37.77.17.62.49+0

2.06+7

4.43.64.41+87.78+.

1.60+7

6.68*69.856.1.03+72.81.7

7.98.66.00+62.84.7

7.74.62.70+7

6.87.61.29.81.22.84.36.81.39+77.28.62.90+.

1.67.7

4.95*88.16.6

1.18.7

7.68.89.46081.03.72.24.7

7.93.88.08.82.40.7

------------------------------------------------------------------ ~-e2.34.9 9.88.8 2.24.9 1.30.9 1.68.9 1.38.9 7.40+8 1.38.9 1.13.9 1.01+9

A. INDICATES COMMON POOL SHARED BY TWO REACTORS t CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEB INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEE INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULLCORE RESERVE

(a) INCLUDED IN UNIT I

Page 69: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A2. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - POOL STORAGE OPTION(19983 DOLLARS).

LOW DEN BEFORE CONVERSION AFTERPLANT HAVE TYPE RACKS -------------- RERACKING --

iNEEDED OX G 11% Ie'x II --I - - - I - -- - --- I- - - - -I- - - -

CONVERSION I INCREMMTAL COST-I--------------

5A I if" I -ex - ' 5% 1 0

AAB

A

B"

AA

ARK NUCLEAR 1ARK NUCLEAR 2BEAVER VALLEY 1BEAVER VALLEY 2BELLEFONTE 1BELLEFONTE 2BIG ROCK 1BRAIDWOOD 1BRAIDWOOD 2BROWNS FERRY 1BROWNS FERRY 2BROWNS FERRY 8BRUNSWICK 1

BRUNSWICK 2

BYRON IBYRON 2CALLAWAY 1CALVERT CLF 1CALVERT CLF 2CATAWBA 1CATAWBA 2CLINTON 1COMANCHE PK 1COMANCHE PK 2COOK 1COOK 2COOPER SICRYSTAL RVR 8DAVIS-BESSE 1DIABLO CANYON 1DIABLO CANYON 2DRESDEN 1DRESDEN 2DRESDEN 3DUANE ARNOLDENRICO FERMI 2FARLEY 1FARLEY 2FITZPATRICKFORT CALHOUNFT ST VRAINOINNAGRAND GULF 1HADDAM NECKHARRIS I

136188140188188

46262(a)684(a)468878

378

284(a)18l192(1)144144344198(,)256(a)232

72120

9585

318818258552138136980

24084

588104104

7.27*77.60.79.09+78.40.71.11-81.11.65.91.71.99.8

8.27.7

8.68,79.48.7

9.0.+7

1.99.8

9.83.71.19.8

91.96.0

9.93+*71.093.8

7.92.7

7.04.77.4.+71.37+87.72.77.72476.96,08.82.76.38+*77.04.71.43+86.91.75.46878.75.77.04*70.00+05.91.71.28.288.82.70.0&080.080+1

3.49.73.07*73.92.72.00.72.55-72.32.73.18-.77.81,7

2.94.7

5.4a.7

5.02.7

8. 88*7

2.71+78.04*7

0.00+02.69+7

1.87.7

3.48.7

3.25.72.290*78.07+71.73.7

.73.+7

3.03+*72.3.*72.95.75.24,71.88.71.59.78.69.73.78.7

2.49+74.61.78.18.7

1.77.71.34.71.88-75.85.88.72.8B.65+681.77.78.51.7

1.18,.7

1.19.78.48+7

3.06+7

4.24.*7

8.68,83.44.7

0.00+00.00+007.73+83.83+8

1.61.7

1.69+77.41+68.02.74.82.64.82+8

1.42.71.14.71.81.72.29.76.19+84.88.61.71.72.12+7

1.18+71.92.71. 57.7

5.42+55.54.+8.21,58.47+57.84.57.84.68.68.*41.0936

1 32.+89.02- 6

7.69.5

7.52+51.* 7.68

7.13.67. 16.5

8.42+55.94.58.96858.78+5

1 . 12.6

4.9+.53.84*55.48+53.89+53.89.5

a. 12.56.12.56.30561.08.68.13+58. 13.57.3&.58 • 19.5

2.82+51.04.84.19.54.75+5

9.098.*79.83.*71.25#81.20+81.56081.50986.59.972.35+8

1.01.8

1.10981.09.8

1.07.8

2.35.8

1.31.81.438.

5.46*76.23.71.22.81.35.8

1.16.28

7.95,78.40.71.768*8.e8+78.88.7

8.18.77.72.78.88.71.*89,.8

7.95,7

1.12.88.40.7

7.27.71.49.88.40+7

5.70875'72+77.67.73. 88*74.79*74.33+7

8.98.71.11.8

4.18-7

4.982+78.89.78.61,7

1.17,8

5.01.78.28.7

8.•39.67.35+63.92.72.98.7

8.19.7

4.24.73.28.79.78.72.37+72.37.7

4.52,73.97.74.93+*70.5+.73.49.73.07.75.80976.67.7

3.83,78.80.75.88.7

4.03.73.74.74.89.71.49.71.83.71.61*72.40878.69#*7

1.87.7

2.38*74.59.7

4.53+*7

7.28+7

2.29.75.4487

1.41+81.14.61.49+77.46.8

2.43.72.•39+78.35+77.21.67.21.6

2.8.#72.19.7399.75.07+71.65.71.34.73.42.73.98.7

2.14.73.73873.27,7

1.88.72.39+78.48.73.84.74.02.74.92*7

.87.863.74+7

1.99.7

2.55.71.47.7

3.72+7

3.61.72.47.7

6.$2.75.28.72.38.73.88+7

3.18.7

9.59.61.39.73.88.71.18.71.18.7

1.42.71.42.71.87+73.89+72.10672.10.72.61+71.39.7

1.38.72.78+71.82.7

2.34.72.71.73.21.71.95.72.30672.99.78.08+68.58.7

1.85.7

1.87.71.81.7

1.67.7

8.4867

2.37.72.31-.7

8.79+87.94.81.46.71.17.7

2.82.7

1.04.71.09978.78,78.79.68.79M8

1.65+.71.40+72.03.*78.42.71.76.71.54.72.18.71.84.7

1.88+72.39.71.92.7

2.32.72.45.72.87.71.02.*71.28.71.03.77.28+63.17.7

8.09+8

1.29+71.21.7

1.65.7

8. 1#7

1. S0+72.11-7

2.05#61.7376

7.89*84.51.6

2.89.7

8.86868.79+63.88.73.28.63.28,6

1.82.71.11.71.75.72.89.71.16.79.18.61.79.71.89.7

1.07.71.92.71.75.7

Page 70: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A2. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - POOL STORAGE OPTION(1983 DOLLARS)(cont*d)

I LOW DEN BEFORE CONVERSIO I AFTER CONVERSION INCREMENTAL COSTPLANT NAME TYPE I RACKS ---I -- -- -- RERACKINGI- m --- !------ .... I .... w ---

NEEDED IOE. ED... I ...... . .6. lo.x ox a lox

B HATCH IB HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT 1INDIAN PT 2INDIAN PT 3KEWAUNEELACROSSE

B LASALLE CTY 1B LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEMCGUIRE 1MCGUIRE 2MILLSTONE 1

c,• MILLSTONE 2MILLSTONE 3MONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE IA OCONEE 2

OCONEE aOYSTER CRi IPALISADESPALO VERDE 1PALO VERDE 2PALO VERDE 3PEACHBOTTOM 2PEACHBOTTOM aPERRY 1PILGRIM I

A POINT BEACH 1A POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 2B QUAD CITIES 1B QUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR BEND 1SALEM 1SALEM 2

688(a)484

1t8162

7448

889(a)448440148144144198168168240184276196(a)16(a)120268

6817917017046544044819298(a)

120(a)4"8(,,)138

384189188

7.27*7 2.98+7 1.28.7 1.14+6 8.99,7 4.24+7 2.13+7 1.83.7 1.40.7

9.22+6 1.21.8 3.89+7 1.40+7 2.48.7 1.40.79.78.79.0.0"9.0.007.27.77.04,77.96+78.82*72.19.8

1.36581.41.87.27.78.66578.88+71.02+88.83+76.69+76.23+78.69+77.96+71.12.8

2.49.7 7.19+4

8.83+72.81.73.17.74.07.71.69.8

6.38.74.72*73.49+72.60+72.43.78.37+73.84+71.23,71.85*73.27*71.78.74.21.7

2.14.78.14.81.37,72.62+78.69+7

2.66+71.94+71.7757

8.11.67.48+84.44.71.69+72.62+68.91.81.77.74. *861.78-7

6.01+68.77.62.84.68.68841.2748

8.93*68.73+66.26.68.42.66.42+64.06+68.13+67.46564.89.63.80+66.71.68.91-6

8.73+79.84+79.31.77.96+72.16+8

1.83+81.70789.31+71.17+81.29.81.06+81. 18.89.28+78.69+77.96+79.40+71.6-98

6.71.74.69,74.68.76.68+71.98,8

8.23.77.28.76.61#74.51+74.34,76.48*78.80+72.49*72.97.74.91.72.40977.28.7

4.63.72.41.72.62+74.09+70.82+7

6.22+74.04.74.26+7

2.01+71.84.74.43+74.64+78.98+81.46.73.23.78.93+84.98.7

1. 62-72.87+71.39.71.14+72.73.6

2.84.72.95+72.09+73.19.73.19.79.31+83.24+72.76.71.41.71.40.71.61.73.91.7

1.94.72.36+71.44.72.60-72.70*6

2.96.7

2.86572.67*72.07*71.97.71.30+83.22.71.24.71.16.71.87+78.94.63.18.7

9.72.8

7.71+.

1.96#71.68.71.18+71.68-71.47.8

2.76.72.19"72.64.71.28+71.16-73.06552.91+76.20687.68.81.68+73.14.82.41.7

1.14.7

1.66.71.61.76.70+61.48.71.36571.24.71.72.71.62+78.48+81.64-71.47.7

2.07.7

3.89+8

2.03+77.77.87.42+.2.68972.19+7

1.31.8 7.47+7 4.84.7 8.91.6 1.6128 8.9097 6.90+7 2.17+1 1.61.7

1.64.88.82*79.78*79.36*79.38.79.38.77.64*77.64.78.98+77.96*77.27+7

6.68*73.68876.97.72.64*72.61+72.39+73.26.73.26572.13.74.24.73.68+7

3.28.72.09.74.08#74.98+7

7.89.88.91.81.6597

6.6+842.43.71.94.7

6.42.66.11.62.70+66.74+68.74+60.74+69.02.58.73.68.93.63.97+63.64.6

1.22.87.96*79.86+71.29.81.29.81.29.89.14.78.83#71.14.89.68.78.88.7

7.10.76.18+78.01.74.93+74.70.74.47.76.22.76.06+73.33#76.78.76.21.7

4.78*73.64.74.11.72.26572.06+71.87.73.22+73.12.71.13.74.93.73.38+7

1.8+.71.18.71.17.8

2.68*972.19.7

2.46,71.17.71.45.7

1.86571.63.78.79+62.*3872.28+72. 16#72.06871.80971.29,71.68.71.69.7

8.68.7 4.31.7 2.48.7

5.69.7 1.70+7 8.68.6

4.31.6 1.62.8 8.44+7 4.48+7 2.12+7 2.17.7

9.21+5 6.6887 2.19.7 8.8658 7.89+8 5.78+8

6.48+78.40+79.16.79.49.7

9.86+7

1.92.76.08+72.36573.91+73.38*7

7.12.83.27.78.85+61.79,71.28.7

8.19.64.98.67.61+67.11.67.4656

8. 18.78.88.71.16-81.27,81.33.8

4.62+76.73.73.65,78. 92.78.19.7

2.68.74.01+71.36.74.41.73.40+7

2.71876.20882.45+73.33+73.49,7

2.66.77.1.801.38873.68.72.90.7

Page 71: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A2. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - POOL STORAGE OPTION(1983 DOLLARS)(cont•d)

--- -- - -- --- --- -- --- -- ----------- - --- - ------------------------------ - ---------- m - -----

PLANT NAIMETYPE RACKS---------

-OI DEN.]- I BEFCONVERSION AFTER CONVERSION I INCREMENTAL COST

-IFwr(ine---------------------IKRCAMI----------------

---- kex I 5% 1 ox Iex I 5% '1 loxm•

E SAN ONOFRE 1E SAN ONOFRE 2E SAN ONOFRE 8

SEABROOK 1A SEQUOYAH 1A SEqUOYAH 2

SHOREHAMSOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE 1ST LUCIE 2SUMMER 1

A SURRY 1A SURRY 2B SUSQUEHANNA 11 SUSQUIEHANNA 2

cin THREE MILE ISL"-J TROJAN

E TURKEY PT 3E TURKEY PT 4B VOCTLE 1B VOCTLE 2

VT YANKEE IWASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK 1YANKEE-ROWE 1

A ZION 1A ZION 2

TOTAL

PPPPPPBPPPPPPP

ipPPPP

PBPPPP

276

128

240(a)s88104164162144136159(a)896(a)14896

144(a)252(a)264312178240(a)15278

218(.)

8.77.7 3.7?.7 2.0897

1 • 11-81.6688

6.46.75.46+71.02.89.74.78.18.74.65.7

1.49.8

5.00676.14.76.68.7

1.33+8

7.59*71.23.89.26471.610+8

8.4+.75.66.7

2.54.?6.66.?

2.860+77.81.67.25*66.37.73.20+72.08+71.11+7

6.18+7

1.82+72.16+7

2.19.7

8.47.7

3.67+74.46+72.65074.82+7

2.11+72.28.74.23.7

8.85+63.2647

7.79.61.17+61.08.64.44+71.26,76.84+62.87*6

2.0867

5.93+66.84.*67.64.868.85.8

1.065+7

1.34+71.89+77.61.81.8067

5.88+81.68.72.23+7

9.54+6

6.74+61.11.08

7.38.8-6.51.6

6.46+65.82.66.26.56.65.57.63.5

1.31.86

6.54.54.37,56.3996

1.11.6

6.39.56.986.1.68.*6

6.77.51.86.59.54,5

9.92+7 6.8657 4.90+7 3.25+7 3.25.7

1.41#82.09+8

1.23+88.82.76.82.71.108+1.32.81.14.88.14+7

1.88+8

7.04.77.60.77.27.7

1.84+8

8.86.71.39.81.27+82.065+8

1.20+87.64*71.16.8

4.25.71.09+8

3.95.71.20#71.14.76.78.75.91.73.94.72.01+7

7.89+7

3.25+73.21+73.86+7

6.02+7

4.48+76.80474.88.78.5647

4.16.74.8.+77.23+7

1.88.78.89+?

1.61.7

2.12.84.66.73.21.71.80676.98.8

3.8067

1 • 69+71.48.71 . 94+7

2.34.7

2.49*?2.89.?2.06.74.31+7

1.66+73.1.+?4.97+7

S.M*76.38.7

2.46+71.42.71.42+78.85.83.53.73.27+71.8867

4.67+7

2.10471.40+71.8567

5.22+7

1.42.71.85+73.63#75.62*7

3.70+72.06673.64+7

1.77+74.48*7

1.42.74.94-84.73.64.85.62.78+71.93+79.6886

2.84.7

1.70.71.16+71.64.7

2.88.7

1.47.71.46.?2.25*73.83.7

2.066?2.32+73.1-,7

2.91+7

9.87.6

8.01.61.71.,81.6"2.05+62.68.71.7.+74.79.8

1.93.7

1.10-77.65+61.12.7

1.46.7

1.21+71.67.71.38.72.61.7

1.13.72.04+72.84+7

--------------------------------- m -------------- m-m-m ---- m --- M ------ m --------------------- m-8.51.9 3.27.9 1.52+9 8.5•67 16.78+9 5.01+9 2.84+9 2.34+9 1.8649 1.38.9

ABE

INDICATES COMMON POOL SHARED BY TWO REACTORSs CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFERt CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1

Page 72: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A2.. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - POOL OPTION(1983 DOLLARS)

---------------------------------------------------------------------------------- m ------------- m ----------- -m ------ADD. YEAR

SIHUTDOVI STORAGE WHEN CONS.PLANT NAME YEAR REQ'D ADD'L TIME

(ASSEM- STOR. (MON.)BLIES) NEEDED------- ------ -- -- ------- ---... ..-

COST-I- SCONSTRUCTION I 0s

- --------- -- - ---- ----- -I TOTAL

6% 11 x I I a I11o,;T I 5fix 8 I l ox I

ARK NUCLEAR 1ARK NUCLEAR 2BEAVER VALLEY 1BEAVER VALLEY 2BELLEFONTE 1BELLEFONTE 2BIG ROCK 1

A BRAIDWOOD 1A BRAIDWOOD 2B. BROWHS FERRY 1B BROWNS FERRY 2

BROWIS FERRY 3BRUNSWICK 1

BRUNSWICK 2

A BYRON 1A BYRON 2

cn CALLAWAY 1cO a CALVERT CLF 1

B CALVERT CLF 2CATAWBA 1CATAWBA 2CLINTON 1

B COMANCHE PK 1B COMANCHE PK 2A COOK 1A COOK 2

COOPER STNCRYSTAL RVR 3DAVIS-BESSE 1DIABLO CANYON 1DIABLO CANYON 2DRESDEN 1DRESDEN 2DRESDEN 8DUANE ARNOLDENRICO FERMI 2FARLEY 1FARLEY 2FITZPATRICKFORT CALHOUNFT ST VRAINGINNAGRAND GULF 1HADDAM NECKHARRIS I

208201220162028262820d201228620272814201420172618

2810

2024228620242014201620262028202720302030.2009200200820182017202520251984206820082010202620122012201620082007280020222072028

377665883858

19001000

"827(a)

3228

24124012281

3827(a)

11292213

(a)0a

26722067

(a)1241

(a)1238432

2490517517

01016893g98

5356298140

2248413

2194392

3190

1998199919982009209201119851900

2082

1998

1991

1994

200S1992

2025282620882016

1998

1997200199520112011

1os8200019981997200820"19971994

20"199819972028

6868so68536368

72

59

6767

68

72

6762

8

05764

68

6858

584

68

68so58645858585868

8258so

4.66*74.66574.65.74.66575.60*76.00.76.69#74.65578.68.7

5.11.7

4.74,74.72*7

4.62+7

8.6687

4.90+76.69+7

0.00.00.w+04.82+76.64+7

6.08+1

4.55,74.66578.70.74.66+74.56+7

4.66+74.66+74.66576.93,74.6657

4.81.74.66+7

4.66+76.48.74.66570.00+0

2.42.72.09.72.42.71 . 28,71.67.71.43.72.64.74.64+7

2.02.7

1.97.73.98+7

8.13,7

5.00+7

1.60+73.60.7

0.00.06.0670

1.57,7

1.67+71.23.7

2.44+7

2. N8.71.66.73.73*71 • 16.71 . 16.7

2.19.71 • 99.72.09+73.•0.71.48.71 . 36572.83872.6687

1.99.72.88.72.3+70.900

1.32+79.91.81.32.78.82+64 . 70+83.88+61.45.72.48.7

8.38*0

8.63+82.42.7

2.16,7

6.02.62.37+7

0.+00.9.0".6.38+82.77.6

1.21+7

1 * 20,76.6"•2.18+73.18.83.18+8

1.09+79.01.69.91+61.68.76.09.04.20.81.21+71.68.7

9.01.61.31.71.20+70.0+6

2.72.72.96.74.68578.86576.47+76.47*71.38.71.18+8

3.16.7

3.82*74.74,7

4.3887

1.13.8

4.73.70.32.7

0.60.00.00.66.11.74.49,7

2.88.7

2.49+72.49.77.62*78.17.78.17.7

2.27+71.01+72.49+78.36.71.38.79.87.84.14.72.49.7

1.38÷78. 79*72.27.7G.0+6

9.7658

7.19.89.79-88.08868.41.83.07+7

9.24.8

1.07.72.10*7

1 . 89+7

3.38.7

1.03-72.44.7

0.00.0

1.02.76.44*8

1.04.7

9.61.86.44.82.34.76.72*86.72+4

8.42+88.39+88.62*82.24.73.76+82.37+81.38,7

6.92+81.10.7

8.84.80.00.0

4.47.68.6+8*6.69+81.63.82.02.82.82-61.67.88.16581.03*7

2 .93.8

3.38.6

1.94.7

1.*24,7

2.58+61.07+7

0.080.2.38.8

4.04.8

3.88+81.81.88.92.8

1.18-8I • 16.81 • 16.83.*33.62.43983.20+67.48088.• 1+668• 3,54.97+86.16.8

1.95.88.08+83.87.80.0-.0

7.27.77.5W+79.08.78.40*71.11.81 . 11.86.91.71.99+80.00+08.27+70.60.08.68.79.48.70.00.09.00+70.00.01.99•80.+00.9.63,71419.81.19-80.0".0.00.00.00#09.93.71.+8.80.00.07.92*70.00+07.04,77.94.71.37+87.72*77.72.70.00.06.82.78.36.77.04*71.43+86.91.76.48*78.76+77.84+70."00,6.91+71 . 23+8

8.02+0.00+0

3.49.73.07.78.92-72.00,72.66.72.32.73.18.77.61.7

2.94.7

3.04*76.48.7

6.02.7

*8.88.7

2.71.76.84.7

0.00+.0.00.02.69.71.87.7

3.48+7

3.26+72.20*76.07*71.73.71.73#7

3.03.72.83*72.95676.24+71.88-71.69+73.69*78.78+7

2.49.74.51.78.18.7

1.77,71.34.71.88.76.5*386.72.86.66+81.77+73.61*7

1.13,7

1.19-73.48.7

3.0+.7

4.24.7

8.68+83.44.7

0.00.00.0"7.73+83.83+8

1.6197

7.41-88.02.74.32.84.32+8

1.42.71.14+71.31.72.29.78.19+64.8+81.71.72.12.7

1.10+71.92.71.67.7

Page 73: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Aft. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - POOL OPTION(1983 DOLLARS) (con'd)

e----------------------------------------------- -- ------ ------ m - - m ------- m--w ------ ----------

ADD. YEARSHUTDOWN STORAGE WHEN I

PLANT NAME YEAR REQ'D ADD'L I(ASSEM- STOR.BLIES) NEEDED

-- - - - -- -e--------------

CONS. ITIME

(MON.-)I

COST*- - --- - - --ltli ell I---------ee e---- q--eee-ee~

CONSTRUCTION.% ... 10 OSM I TOTALn •ilillil I I liiliM ...... iilii ........

-I 5%-,- I lox I - -.- -,- I lo-. xww

e---------~e~eeeee

B HATCH 1B HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT IINDIAN PT 2INDIAN PT 8KEWAUNEELACROSSE

B LASALLE CTY 1B LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEUCGUIRE 1MCOUIRE 2MILLSTONE 1

t MILLSTONE 2MILLSTONE 8MONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA IA NORTH ANNA 2A OCONEE 1A OCONEE 2

OCONEE 3OYSTER CRK 1PALISADESPALO VERDE 1PALO VERDE 2PALO VERDE 3PEACHBOTTOM 2PEACHOOTTOM 8PERRY 1PILGRIM 1

A POINT BEACH IA POINT BEACH 2A PRAIRIE ISL IA PRAIRIE ISL 2B QUAD CITIES 2B QUAD CITIES 2

RANCHO SECO IROBINSON 2RYR BEND 1SALEM 1SALEM 2

202220281978

20082014

200220222023202420292008202120282010201520252007200520282018202020132018201420042611202420252026200820082028206820672009200826082007200720082007202526182020

2874(,)2820

00

493588679205

9824(a)

40984236832g96989

2480828641355884

19711868

(m)

21021

912885

1117112111211812168926481512

849(a)

1142(a)508(a)228

245210071163

2000

2007

1994

199919921990

1995199819982005200$1997

20182004199820111999

1999

19911994198820062008200719971997200919931995

1993

2005

2e641990200719972001

B5

58

8858565876

6181585757575856585868

84

5756585757575858575858

58

58

5856575758

4.99.7 2.17,? 9.88.6

4.9687 1.54.7 5.04+8

2.29#7 7.88+6

4.80+7 9.40+8

4.654?4.55.74.*55.7?4.* 55.79.02+7

5.89.75.42*74.56*74.74*74.77*?4.72.74.55,74.55,74.65+74.55.74.65+74.56.75.87.7

2.86.?1.68.72.09.72.94+78.41.7

83.09+72.81+72.42+71.82.71.55.73.74.72.83079. 10.1.83+72.42+71.18.72.80+7

1.60.78.16.89.91.61.93*74.63+7

1.72*71.38.7

1.32.75.82+85.838.3.10O+71.20+71.98+68.15.81.82.73.18.81.23.7

2.72+72.49+73.40+72.27.71.29+8

8.11.78.72+72.72+73.81.74.09+75.46.74.08+72.04.78.80+82.04#73.46.75.51.7

1.17.70.78+81.08+71. 18.74.53,?

2.88,72.11.71.07.78.82+68.82+82.86871.34.73.22+62.22.88.54+68.00.81.81+7

2.90.8 7.27+70.0&0.

2.16+8 9.76.78.00+00.0m.

5.41+. 7.27+71.99+8 7.04+78.75+6 7.95.75.91+8 8.82.71.97.7 2.19.8

0.0&08.35.6 1.35.88.38+8 1.41.84.47+6 7.27.72.29+8 8.55.72.156+ 8. 6?71.44+7 1.02+84.89+8 8.83.75.62+5 6.69+77.62.5 5.23+78.78+8 8.59+71.20+8 7.95.75.26+8 1.12.8

0.00*01.51+7 1.31+8

0.00+01.01.7 1.04+84.88+6 8.82.71.25.7 9.76+72.48+8 9.8+,72.25+6 9.88.72.05+6 9.38.73.88+8 7.04+73.88+8 7.04+71.84.8 8.98+78.85+8 7.95.74.92+8 7.27.7

0.00.08.77.8 8.0887

[email protected]+6 6.00+7

0.*0+09.71+5 6.48+79.38.8 8.40+72.00+8 9.10+75.34+8 9.40+73.84+8 9.85.7

2.98+7

2.49#7

.88.372.31*78.17.74.07.71.09.8

5.36.*74.72.73.49+72.50+72.43.78.87.78.84.71.23.71.85.73.27.71.7.+74.21.7

7.47+7

5.56.?3.60875.97072.84.72.51.72.39+73.25+78.25+72.13+74.24+73.66.7

4.81.7

1.70+7

1.92.75.06872.35.78.91.73.3867

1.28+7

7.19+8

2.14+78.14.61.87.72.92#78.60+7

2.58+71.94.71.77.78.11.87.48.84.44.71.69+72.52+88.91+81.76+74.88.81.76+7

4.84.7

8.26.72.09+74.08+78.38+687.80.88.91.81.*59+71.59.75.68+62.48+71.94.7

2.46.7

8.0+88

7.12+68.27+78.85+81.79+71.28+7

5.91.7 4.41.7 8.3837 7.14.7 3.08.7

4.89.74. 5574.55+74.78.?4.79,74.79.74.55+74.55,74.82+74.56+74.55+7

3.27#72.88473.57+71.84.71.6.+71.48+72.30+72.83071.36.72.4.+72.54+7

2.29+71.00+72.83.75.88.6

.*85+84.86+81.20+71.20.74.04+81.78671.46+7

5.01.72.27.75.21.74.58+74.69,74.59+72.49+72.49.74.14.73.40.72.72.7

2.23+71.02+72.40.79.98.69.50+69.05+89.51+69.51+67.72+61.44+71.12+7

4.62+7 2.84.7

4.55+7 1.58+7

1.78+7 8.46+7 1.47.7

5.06+8 4.58+6 1.44+6

4.55+?

4.77.74.80.75.06+7

1.63+73.24+71.48+72.43+72.08.7

8.15+82.34+74.865+1.28+78.99+8

9.07+a8.99+74.33+74.80+74.86+7

2.88+61.82.78.71+61.48+71.28+7

Page 74: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

- i..,, ',,..

TABLE A2*. COST FOR ADDITIONAL SPENT FUEL. STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - POOL OPTION(1983 DOLLARS) (cont'd)

----------------------------------------------------------------------------------------------------------------------ADD. YEAR

SHUTDOWN STORAGE WNHE I CONS.PLANT NAME YEAR REQ'D ADD'L I TIME

(ASSEM- STOR. I (MON.)BLIES) NEEDED

COST-----------------.---------------- -------------

CONSTRUCTION I 08M TOTAL-- - - -- - -- - -- -- - - -- - - - - - -i-- -m- -- - - - -

1 56 1 le~i I oi I 6x I I8 ; I 01G I5 IlOS------------ ---------------E SAN ONOFRE 1E SAN ONOFRE 2E SAN ONOFRE 3

SEABROOK 1A SEQUOYAH 1A SEQUOYAN 2

SHOREHAMSOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE 1ST LUCIE 2SUMMER 1

A SURRY 1A SURRY 2B SUSQUEHANNA 1B SUSQUEHANNA 2

THREE MILE ISLoý TROJAN

E TURKEY PT 3E TURKEY PT 4B VOGTLE 1B VOGTLE 2

VT YANKEE 2WASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK 1YANKEE-ROWE 1

A ZION 1A ZION 2

TOTAL

1999201220132031202120222027202720282010202328242012201820222024

1 2•082011200720072027202820122023202420262027202620012"082008

2882

12612880

(a)2835

268268

11821126

76197

(a)7288

75373884(a)

2495(a)

1088401811432891

361296

(a)

1996 63 6.62.7 3.13.7 1.79+7 1.1657 6.70.6 2.92+6

20081996

28"0202320241987

2001

2012

20"

2002042"02

206

199919982006201

2"819991995

s968

67565667565668

89

686668

67

s6816768

686869

6.50977.04*7

4.86.74.65+74.66+74.72+74.84+74.66+74.66+7

7.41+7

4.56*74.66+74.66+7

8.81+7

4.65+74.365..74.624717.66+7

4.66+74.66+76.12.7

1.69+73.92+7

1.68+71.47*58.18+83.74+71.93.71.36571.11.7

8.23.7

1.48.71.63?71.88.7

2.16+7

2.09.7.68-7

2.93.7

1.36.72.89.72.8657

4.760#2.24.7

6.42.61.01+89.16+63.600.78.36-74 0.8664.29882.87.6

1.47.7

6.09.86.16+67.46+8

7.39+6

9.91.61.28.76.28+61.27.7

4.20+89.91+61.6897

6.03.78.66.7

6.16579.07.69.07+86.46576.10,73.86370.0800

7.47+7

4.65361.69.71.13+7

6.65.7

2.96+7

4.88+77.91.7

3.86+74.63.63.43#7

1.04.72.63.7

1.02.71.14+61.09.62.63.71.27.77.26+80.00.0

1.95.7

1.37+64.71.83.88.8

1.32.7

9.76+61.88.79.25.61.80+7

7.66*81.93.81.3887

2.16+69.69.6

2.37.81.69*61.44.61.44+73.66881.84.60.06*0

6.589.

4.39+61.49+61.40.6

3.08~6

3.6+8-6.04.62.23+66.32#6

1.68.68.686.6.98+8

8.77+70.080.0.00+01.11+81.68.80.00.01.00.86.48+76.48671.02+89.74,78.18.74.66+7

1.49+80.00+06.00+76.14+75.68.70.0+001.33.80.00+07.65071.23+89.20.71.50+80.00.08.40+76.00+78.66*70.0010

8 .61+9

3.70+7 2.08+7

2.64+78.66+7

2.*6077.61+67.26+88.37+73.20+72.08.71.11.7

5.18.7

1.62+72.10+72.19+7

3.47+7

3.07.74.48.72.68-074.82+7

2.11.72.28+74.23#7

8.86+83.20+7

7.79+81 • 17.61.10864.44+71.20.7

2.87+6

2.08+7

S .653.7.68488.86.+

1.6.67

1.34.71.88+77.61.81.80.7

6.88.81.08872.23+7

-- - - - - - - - - - - - - - - - - - - - - - - - - - - - m--m -----n mwe -- - --

4.73.9 2.14.9 1.10.9 3.78.9 1.13.9 4.18.0 3.27+9 1.62+9

ABE

INDICATES COMMON POOL SHARED BY TWO REACTORS, CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY WE FULL CORE RESERVEINDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS REQUIRING CASK TRANSFERs CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT I

Page 75: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A2b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION-POOL OPTION(1903 DOLLARS)

---------------------------------------------- ----------- - - -------------------------- -

ADD. YEAR C OS TISHUTDOWN ISTORAGEI WHEN ICONS. - ----------

PLANT NAME YEAR REQ"D ADD'L TIME CONSTRUCTION -o 0 8M - TOTAL(ASSEM- STOR. (MON.)------------ - - - - ------ ------- - -BLIES) NEEDED 0% I5 10% ex 56% lox% e% 6x lox%

ARK N0CLEAR 1 208 737 (b) 58 4.55#7 3.57.7 2.83.7 4.53+7 2.21.7 1.20-7 9.08.7 5.78*7 4.03.7ARK NUCLEAR 2 2012 973 1989 56 4.58.7 8.42*7 2.59#7 5.25.7 2.30.7 1.15.7 9.8837 5.72.7 3.74,7BEAVER VALLEY 1 2018 1267 (b) 59 5.11+7 4.00.7 3.17+7 7.37+7 3.07.7 1.52.7 1.25+8 7.07+7 4.89.7BEAVER VALLEY 2 2028 1298 2000 59 5.12+7 2.2387 1.01.7 8.8897 1.a5+7 4.78.6 1.20.0 3.88.7 1.49.7BELLEFONTE 1 2028 2404 2000 866 .3857 2.77.7 1.28+7 8.87+7 2.01.7 6.70.6 1.60.8 4.78+7 1.03.7BELLEFONTE 2 2030 2404 2002 66 8.35.7 2.51*7 1.04*7 8.87.7 1.827' 4.71.6 1.50.8 4.33.7 1.51.7BIG ROCK 1 2001 175 1992 58 4.55.7 2.94+7 1.93+7 2.04+7 1.04+7 5.54.6 6.59.7 3.98*7 2.48.7

A BRAIDWOOD 1 2026 4383 1998 77 8.90.7 8.33.7 4.57.7 1.48,8 4.78.7 2.01+7 2.35+8 1.11.0 6.5087A BRAIDWOOD 2 2027 (a) 1990B BROWNS FERRY 1 2014 4594 1999 62 5.55.7 2.87+7 1.83.7 4.58*7 1.49.7 5.38.6 1.01.8 4.16+7 1.87+7B BROWNS FERRY 2 2014 (a) 1998

BROWNS FERRY 3 2017 3363 1995 59 5.16.7 2.87+7 1.84+7 5.06+7 1.95+7 7.44+6 1.10.8 4.82.7 2.88.7BRUNSWICK 1 2010 3153 (b) 59 5.09+7 3.99*7 3.18+7 5.78.7 2.70+7 1.43.7 1.09.8 8.89+7 4.59.7

BRUNSWICK 2 2010 3033 (b) 68 5.04.7 3.95+7 3.1387 5.68.7 2.8687 1.40.7 1.07.8 8.81.7 4.53+7

A BYRON 1 2024 4413 (b) 77 8.87.7 6.4987 4.9087 1.46+8 5.25.7 2.43.7 2.35.8 1.17.0 7.23.7A BYRON 2 2026 (a) (b)

O• CALLAWAY 1 2024 1833 1998 61 5.33.7 2.62+7 1.54.7 7.74.7 2.19*7 7.48+8 1.31.8 5.01.7 2.29+7-' B CALVERT CLF 1 2014 2789 (b) 86 6.30*7 4.81.7 3.73+7 8.01.7 3.47.7 1.75.7 1.43.8 8.28.7 5.48,7

B CALVERT CLF 2 2018 (a) MCATAWBA 1 2025 226 2021 68 4.55.7 7.13.8 1.22.8 9.87.8 1.26,8 1.92+5 5.48.7 8.39.6 1.41.6CATAWBA 2 2026 210 2023 68 4.55.7 8.47.6 1,01.8 6.80,8 8.77+5 1.25.5 5.23.7 7.35.8 1.14.6CLINTON 1 2027 3260 2000 59 5.12.7 2.23.7 1.01.7 7.12.7 1.89+7 4.82.6 1.22.8 3.92.7 1.49.7

B COMANCHEPK 1 2030 2881 2010 08 8.99*7 1.87.7 6.3.8• 6.55+7 1.09.7 2.13+8 1.35.8 2.98.7 7.486#B COMANCHE PK 2 2030 (a) 2010A COOK 1 2009 2009 1991 83 6.73.7 3.89+7 2.68*7 5.2687 2.31#7 1.12.7 1.10.8 6.19.7 3.80.7A COOK 2 2009 (a) 1991

COOPER STN 2008 1702 1993 58 4.56.7 2.80.7 1.78.7 3.40.7 1.44+7 8.65.6 7.95.7 4.24+7 2.43.7CRYSTAL RVR 3 2016 048 1999 58 4.6557 2.09.7 9.91.6 3.85+7 1.17.7 3.98,8 8.40+7 3.26#7 1.39+7DAVIS-BESSE 1 2017 2850 1998 69 7.57+7 5.70.7 4.35.7 9.9987 4.08+7 2.00+7 1.78+8 9.78+7 8.35+7DIABLO CANYON 1 2025 772 2006 68 4.55.7 1.48.7 6.09.6 4.31+7 8.92+6 2.1226 8.8867 2.37.7 7.21,8DIABLO CANYON 2 2026 772 2008 56 4.55+7 1.48.7 5.09+8 4.31.7 8.92.6 2.1226 8.8867 2.37.7 7.21.8DRESDEN 1 1984DRESDEN 2 2008 1847 1992 56 4.55.7 2.94*7 1.93.7 3.83+7 1.58+7 7.52+6 8.18+7 4.52+7 2.68.7DRESDEN 3 2006 1325 1994 56 4.55.7 2.6867 1.80.7 3.17.7 1.31.7 5.85+8 7.72.7 3.97+7 2.19.7DUANE ARNOLD 2010 1610 1991 68 4.55,7 3.08+7 2.12.7 4.3147 1.85.7 8.84.6 8.8687 4.93+7 3.00.7ENRICO FERMI 2 2026 8459 1990 87 6.77.7 4.81+7 3.4897 1.1208 3.74.7 1.59.7 1.80.8 8.55.7 5.07+7FARLEY 1 2012 708 1997 58 4.55.7 2.30.7 1.20.7 3.40.7 1.19.7 4.64.8 7.95+7 3.49.7 1.85.7FARLEY 2 2012 548 1999 56 4.55.7 2.09.7 9.91.8 2.95+7 9.76+6 3.60+6 7.50+7 3.07*7 1.34.7FITZPATRICK 2015 2966 1991 58 5.02.7 3.40.7 2.34.7 6.17.7 2.40.7 1.08.7 1.12+8 5.80.7 3.42.7FORT CALHOUN 2008 683 (b) 56 4.55.7 3.57.7 2.83+7 3.85+7 2.00.7 1.1237 8.40.7 6.57+7 3.96+7FT ST VRAIN 2007GINNA 2008 411 1994 58 4.55+7 2.8667 1.80+7 2.72.7 1.17.7 5.41.8 7.27.7 3.83.7 2.14.7GRAND GULF 1 2022 6484 1992 84 5.96.7 3.04.7 2.53.7 8.97+7 2.98+7 1.20.7 1.49.8 8.80.7 3.73+7HADDAM NECK 2007 631 1990 58 4.55.7 3.24.7 2.34+7 3.85+7 1.82.7 9.33+6 8.40+7 5.06.7 3.27+7HARRIS 1 2028 a 2026 0 0.00.0 0.00.0 0.00+0 0.00,0 0.00,0 0.00,0

Page 76: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A2b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION-POOL OPTION(1983 DOLLARS) (cont'd)

-------------------------------------------------------------------------------------------------------- - ---- - - -

PLANT NAME

o HATCH 1* HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT 1INDIAN PT 2INDIAN PT 3KEWAUNEELACROSSE

6 LASALLE CTY 1B LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEMCGUIRE 1ACGUIRE 2MILLSTONE 1

o• MILLSTONE 2~~ MILLSTONE 3

MONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE 1A OCONEE 2

OCONEEOYSTER CRK 1PALISADESPALO VERDE IPALO VERDE 2PALO VERDE 3PEACHBOTTOM 2PEACHBOTTOM 3PERRY 1PILGRIM 1

A POINT BEACH 1A POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 2B QUA CITIES 1

CITIES 2RANCHO SECO 1ROBINSON 2RVR SEND ISALEM ISALEM 2

2009201220281976198020820152014200228222023202420292008202120232010201620262007200620282018202020132013201420428112824202620282008200820286200820072087200820082"07200720082007202620182020

4060 1998 61 6.37.7 2.86,7 1.68.7 3.82.7 1.39.7 6.74-8 8.99.7 4.24+7 2.13.7

SI 2001 00 6.28+7 2.19+7 9.86" 8.85.7 1.81*7 4.46+8 1.21+8 3.80*7 1.46+7

901992801

11144(a)

49926118107013971421287212911046

836126226332451

(a)2841

(a)1381142410391827163116312724246934441898

1137(a)

1602

(a)

640958322014871687

(b)199419931987

1988

1991198719971998

420019981990200719921992

1989(b)

19981997199819911991200319881990199019881988200220021992

(b)260119891992

6867686879

63646860680

68

68

68

6757

69

68

57

6768695860

6869

81

4.80.74 . 78.74 665574 . 66578.02.7

6.765.76. 80.74.66.76.21.76.22.74.94.74 . 97+74.08+`74.66+7

4.66574 . 80.76.70+7

3.81.72.79.72.280+73.62.76.81.7

4.43+73.92+73.62.72.08372.61+73.87*73.89.71.61.72.19.73.24+71.49.74.32+7

2.86.71.68.71'.78.72.91*74.2867

3.48.72.70.72.91.71.37.71.26.73.08*74 .69374.93+061.09.72.34.74.87.62.84.7

4.08+7

3.23.72.67+*72.86571.62271.38.71.28672.29.72.22.77.72.62.83.*72.41.7

4.13.76.08+74.78+73.40.71. 36*.8

1.06.81.12.84.78.76.47.76.77+76.62+*76.84.*7

4.42+72.04+73.40+74.68078.30+7

8.17.7

8.99.+73.40•76.28*277.81.77.62.77.62+74.23+74.07.76.18.74.63+73.99+7

2.10.71.80.71 . 78.71.94.76.03,7

3.80+73.8+.72.39.71.88.71 . 83+72 . 69.72.91.78.91+67.76.81.67.79.7.+62.98+7

3.61+7

1.76.72.42.72.16.72.06.7

1.90.71.83+71.37.72.21,71.88.7

1.17.77.38+87.686+1.18+72.38.7

1.78.71.34.71.34.78.38+66.88+61.37+71.46.72.06+83.12.88.8.662.08+61.24.7

8.73+79.84.79.31.77.964,72.16-+87 9.781.83+81.70.89.31.71.17.81.20+81.05.81.18.89.28.76.69`*77.96+79.4+4.712.0.8

6.71.74.69*7

4.68*76.68+7

1.08+8

8.23*77.28*76.01.74.61+7

4.34.76 • 48.78.*80.72.40*72.97+74.91*72.40.77.28+7

4.03.72.41.72.62.74.09.76.62+7

6.22.74.04.74.26#72.01.71.84.74.43.74.64,70.98.81.40+73.23*76.93.864.08.7

6.97#7 6.29.7 1.84.7 1.61.8 8.90.7 6.90.7

6.20.74.56574.69.76.24+76.26+*76.26+74.91.74.76.76.19.74.66+74.09+7

4.07*73.40+73.69*72.78+72.66572.62*73.32+73.22.71.98.73.67+73.33+7

1.63.79.783+81.28*77.39.88.87+86.08+69.32.88.97+82.66*61.20.79.67+6

1.22.87.96579.86671.29.81.29.81. 29.89.14*78.83+71.14+89.08878. 88.7

7.18+76.16+7.01.*7

4.93.74 . 70.74.47.75.22+76.05.73.33+76.78.7

6.21.7

4.78.73.64.74.11+72.26.72.05+71.87.73.22.73.12271.13.74.03.73.38.7

6.02.7 8.93.7 3.12.7

4.5657 1.80.7 7.4658

6.14.7 2.61.7 1.386.7

1.13.7 8.688 1.40.6

1.02.8 6.44*7 4.48.7

6.68.7 2.19.7 8.65+0

4.66+*74.55.7

6.13+76.27+76.41+7

2.94.73.68+72.13.73.93+73.49.&7

1.99372.883.79.22.62.98*72.29.7

3.63.74.32.78.34.77.89+77.68.7

1.68*72.16571.62.72.99.o72.70.7

7.62+61.18.74.27.81.43.71.11.7

8.18.78.88+71.16581.27.81.383+

4.62.76.73+73.66+76.92.76.19.7

2.68.74.01.71.36-74.41-73.40.7

Page 77: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Abt. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO LOW DENSITY RACK CONFIURATION-POOL OPTION(1988 DOLLARS) (cont'd)

--------- --------- ------ ---- r-------------- m---------- ---

ADO. YEAR I COSTSHUTDOWN STORAGE WHEN CONS.I

PLANT NAME YEAR REQD AOL II TIME CONSTRUCTION 0 a M TOTAL(ASSEM- STOR. (MON.) - - ---- --- ------m--- ---m

LIES)NEEDEDm 1 5% lox a% I 5% -1 loIx I e1 Iloxeeeeeeee ------------...---- I

.0kmc~j

E SAN ONOFRE IE SAN ONOFRE 2E SAN ONOFRE 3

SEABROOK 1A SEQUOYAN 1A SEQUOYAH 2

SHOREHAMSOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE IST LUCIE 2SUMMER 1

A SURRY 2A SURRY 2B SUSQUEHANNA I8 SUSQUEHANNA 2

THREE MILE OSJTROJAN

E TURKEY PT 3E TURKEY PT 4B VOCTLE I0 VOOTLE 2

VT YANKEE 1WASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK 1YANKEE-ROWE 1

A ZION 1A ZION 2

TOTAL

1999291220182031

202220272927292820182023202429122012202229242182

29112997299720272928291220232924202520272292299120982098

3172

18499

(a)8871579670

183815581189

674(a)8ase(1)618661816(a)

8251(0)

1698484218713411

(a)

2841943

(a)

1989198919892006198919892090201?2018

(b)199219092005200519951995199719981995190520062009199319941997199419941999192019881988

87

6172

695685659595856

72

565658

71

56626973

695668

8.72*7 5.01.7 3.79+7 3.20+7 1.84+7 1.11.7

5.39,78.68*7

5.15474.56*74.55.75.15.75.14.75.004?4.* 55+7

4.* 55,74.65+7

8.38*7

4.65+?5.57.75.27*78.68*7

5.14.74.55676.68+7

2.86.78.44.7

2.25+78.67.68.286.4.04*73.28*72.29.71.56.7

4.89.7

2.80*72.19.72.54.7

8.86*7

2.89+73.26+72.86.75.9?77

2.36+73.24+74.39+7

1.87.74.85+7

1.02.71.78.61.62.86

2.16.71.89+75.6.+6

2.75*7

1.22.71.09971.45+7

1.88.7

1.76.71.95+7I * 96.71.30.78.84.7

1.12.72.84+73.48.7

8.87*71.22.8

7.18+72.27+72.27+76.*85,78.12+78.89*71.69+7

1.02.8

2.49.72.95.72.72.7

9.99.7

4.31.78.32.77.89.71.18-8

8.89.72.49+75-81.7

1.00+74.48*7

1.79.78.383.3.17.62.74+72.68.71.06574.48+6

8.0997

9.61.81.82+71.12.7

2.88+7

1.68+72.54.72.92.73.47*7

1.75.71.84+72.84+7

6.25+62.04.7

4.86*65.45.54.96.51.45-71.85+75.05.81.88-8

1.11.7

3.88+83.86*84.92.8

6.784.6

7.81.69.48+68.85+81.27+7

6.29M67.*5561.54+7

1.41.82.09+8

1.23.88.82#78.82*76.*82.71.19.81.32.81. 14.68.14.7

1.88.8

7.04.77.59.77.27+7

1.84+8

8.86.71.89.81.27.82.95,8

1.22.87.94,71.16.6

4.26-71.8998

8.95+71.2•.71. 14.76.78.75.91+78.94.72.01.7

7.89.7

3.25.78.21.73.68+7

8.02.7

4.48.7

4.68878.54+7

4. 10*74.58877.2387

1.69.78.89+7

1.51.72.83#62.12.64.66*73.21.71.66+78.96+6

3.86+7

1.59.71.48.71.94+7

2.34.7

2.49+72.89.72.08.74.31+7

1.85.73.16.74.97+7

9.92.7 8.85.7 4.99.7

-- -----------------------------------------------------------------------------------------......... ilililliI•IilimI•II5.18.9 8.94.9 1.98.9 5.85.9 1.97+9 8.568+ 19.78.9 5.61.9 2.84+9

ABE

INDICATES COMMON POOL SHARED BY TWO REACTORSs CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1.()NEED ADDITIONAL SPACE AS OF 1986.

Page 78: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - DRYWELL STORAGE OPTION(1983 DOLLARS).

I LOW DENI BEFORE CONVERSIONPLANT NAME TYPE RACKS -------------------

N EEDEDI OX 1 6% 1 10%i-- -- - - - - - - - I -- - - - - - - - - -I.

IAFTERRERACKINO -------- t

CONVERSION INCREMENTAL COST

5% 1 10% ex 1 5% 1 10%--I-------- -------------------------

ARK NUCLEAR 1ARK NUCLEAR 2BEAVER VALLEY 1BEAVER VALLEY 2BELLEFONTE 1BELLEFONTE 2BI1 ROCK 1

A BRAIDWOOD 1A BRAIDWOOD 2B BRO•NS FERRY 1B BROWNS FERRY 2

BROWNS FERRY 3BRUNSWICK 1

BRUNSWICK 2

A BYRON 1A BYRON 2

CALLAWAY 1B CALVERT CLF 18 CALVERT CLF 2

CATAWBA 1CATAWBA 2CLINTON 1

B COMANCHE PK 1B COMANCHE PK 2A COOK 1A COOK 2

COOPER STNCRYSTAL RVR 3DAVIS-BESSE 1DIABLO CANYON 1DIABLO CANYON 2DRESDEN 1DRESDEN 2DRESDEN 3DUANE ARNOLDENRICO FERMI 2FARLEY 1FARLEY 2FITZPATRICKFORT CALHOUNFT ST VRAINGINNAGRAND GULF 1HADDAM NECKHARRIS 1

120138is@14816816840

262(a)684(a)468378

376

284(a)168192(a)144144344198(a)268(a)282

72120

8a85

818316256552188

38090

24084

636104104

2.04.72.26*73.10+72.97.74.94+74.94+71.89.78.84+7

1.04.79.81+61.49.77.77+61.27+71.16571.83+73.82.7

S * 1.64.62+07.74+62.22.88.686+2.96+6S.8*+81.92+7

6.42,66.64.60.21.66.47+67.84.67.84+60.68.41.03.8

2.89#73.26+74.22.74.14.70.41+78.41.71.96.71.17.0

2.08.72.18.72.82*71.67+72.37.72.16871.23876.6.+7

1.66.71..64+7

2.07.78.62+69.94+88.22.67.96+64.3907

9.06+81.08.71.19+71.23+71.64+71.64+78.38+63.11+7

1.08.71.23.71.39+78.66.61.18+71.08-72.01+62.84.7

1.05.71.14+71.36.76.06+87.09.68.00.82.18.82.48+7

3.47+7 1.32+7 6.27.8

8.12.78.26+70.00*03.13870.00+08.84+7

1.22.7 6.03.82.11.7 1.44.7

1.94.7 1.27+7

4.21.7 2.33+7

1.32.8 4.67.7 2.09.7 9.98.8

9.02*6 4.04.7 2.02.7 1.08.77.69.6 3.90.7 2.73.7 2.0837

7.62*6 3.78+7 2.65+7 1.98.7

1.07.6 1.17+8 7.26+7 6.22+7

7.13.6 4.84.7 2.18.7 1.10#77.18.5 6.23+7 4.21.7 3.10.7

1.34.7 9.09.6 6.01.6

1.01.7 8.89.8 8.70+67.14+8 7.01.8 8.89.6

7.29+6 7.81.8 7.83+6

3.17.7 3.15.7 3.00+7

1.48+7 1.18.7 8.09.81.20-7 1.35+7 1.38.7

3.43+7 1.07+7 8.66+66.10+7 2.93+7 1.81.7

0.00+00.00+03.40.76.01.7

0.00•00.00+01.00+79.88.6

0.00+00.00+03.24+82.14.8

6.42.66.94.66.96868.7*76

1.83.71.81-74.20.78.26+7

2.84.62.66+81.67.71.62.7

4.83.63.96+64.07+8

1.90.71.87.78.68.61.83+7

3.48+83.14.80.43+86.20+8

1.13889.89+64.81.62.01-6

3.33+7 1.64.7 7.48+8 1.12.6 6.0817 3.16-7 2.07-7 1.6887 1.72+7 1.44.7

2.16+72.01+76.22+72.28.72.28+70.00*.1.99.71.94.72.01+78.01+71.89+71.83.73.08+72.01-70.00.01.89+74.97+71.90+70.06"00.00to

1.06.78.83.83.08.75.63#86.68.06.63.0

9.28÷88.28+88.88.82.67.76.06*8S.37*81.43+71.14.7

8.10.82.89.79.72+8

6.33.62.*3381.68.71.48.81.46.8

4.61.83.88+84.13.81. 24.72.08681.87.87.14.66.84+8

3.63.69.765.4.98+8

4.90*63.84+66.48.63.89+63.89.6

0.12+66.12.66.30+61.08.88.18.66.18.67.30,63.19+6

2.82.61.04.64.19.64.76*6

2.62*72.08377.41+72.91.72.91+7

2.64.72.24+72.69.77.29+72.67*72.32.73.84+72.38+7

2.04*78.18.72.45,7

1.62.71.12.74.88.78.89"88.69.8

1.64+71.24.71.61.74.14+71.28+71.02,72.29.71.73+7

1.14.78.33.71.63.7

9.18.66.11.83.67.72.84.82.84+6

9.69+67.19.61.08.72.72.78.39.64.88+61.48+71.92.7

6.67+02.01.71.12+7

6.23.80.61+81.24+76.78+86.73.8

8.10-63.63+66.29+81.89.78.47+66.60+88.36*83.94+8

1.78.81.31+76.06+6

6.19.84.93+81.88.7a. 66*63. 66*6

8.72*64.76867.7"61.68+77.32+66.40.69.28.86.29.8

3.67.81.34.78.97+8

4.*3383.12.01.96.71.77*81.77.6

6.79*64.12.86.98+81.59.74.96+88.63.88.98+86.980

3. 27.81.14.78.88.0

Page 79: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - DRYWELL STORAGE OPTION(1983 DOLLARS)(cont*'d)

PLANT-- NAM TP RAK---- m---- m-----mm-----m---------RAC--N----- m-w - - -- Im-w -mm --- --w

ILOW DEN 1 BEFORE CONVERSION IAFTER CONVERSION _I_ INCR!C ENTAL COSTINEEDEDJOX 1 5% 1 20% el oxI Ilol ox ox lox-- m I I m - ----- m-w-- -- mw---- - - ---- -- I --- - -.

B HATCH 1B HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT 1INDIAN PT 2INDIAN PT 3KEWAUNEE.LACROSSE

B LASALLE CTy IB LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEMCGUIRE 1MCGUIRE 2MILLSTONE 1

o• MILLSTONE 2ut MILLSTONE a

MONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE 1A OCONEE 2

OCONEE 3OYSTER CRK 1PALISADESPALO VERDE IPALO VERDE 2PALO VERDE 3PEACHBOTTOM 2PEACHBOTTOM 3PERRY 1PILGRIM 1

A POINT BEACH 1A POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 2B QUAD CITIES 1B QUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR BEND ISALEM 1SALEM 2

688(a)464

1S162

7448

666(a)44844614614414419815618246184278195(a)188(a)1262566817617017045644644819298

(a)126(a)486(a)138ISO4968841661688

9.11+7 1.83+7 6.8896 1.14.6 4.11+7 2.67+7

9.22+5 4.54.7 1.64.7

1.16+7 1.11+7 8.59.6

8.85.8 1.12+7 7.86+63.51+76.00.02.16.72.24+72.22+71.99.71.08.8

5.08+75.29+72.20+73.12+73.28+73 .37+72.80+72.18+71.81+71.98+72.79+75.605+7

9.99+8 3.11.6

1.21+77.74+69.59.61.24+78.80.7

2.38872.11+71.12+79.96+89.65+62.47+71.31.74.28+88.44+61.01+78.70+62.11+7

7 • 08.82.84.64.89+67.99.84.17.7

1.28+79.64.65.95+63.44.63.17.61.93+78.49+69.01+62.42+85.43881.78+69.*49.6

8.01.56.77.5

2.84+56.68+41.27.8

8.98+58.78+55.25+58.42468.42+54.05+58.13+57.45+54.89+58.86+65.71+58.91+5

3.08.78.86.72.79+72.12.71.16+8

8.30+7-6.6.+7

3.12.74.27.74.88+73.61+73.87+73.33+71.96+72.23+73.31+78.54+7

2.22.71.77+71.54+71.84+77.21.7

8.92+73.44+72.33+71.92;+71.84+72.65+72.62+79.51+89.18+61.49.79.38.83.83+7

1.8.+71.66.7

9.18+61.51.75.20+72.83+72.16+71.83+79.28+68.53+61.88+71.93+72.97+64.49+61.04+72.92+62.21+7

9.75.61.19+75.85+61.386+7.87+6

1.33+71.3887

9.77+81.22+71.25+72.82+61.14+71.22+72.03+683.05+65.77+61.63+7

1.67+71.0.+78.12+64.08.61.04.7

1.83+71.42.71.26+79.70+89.35+89.75+61.37+78.99+8

S. 17.63 .25+61.81+7

8.21.8

4.48.8

1.83+77.87+65.67+85.21-61.15+7

1.66+71.27+71.28+78.47+68.01+61.34+72.82+6

2.56+85.83+81.74+61.35.7

7.81+6

8.668+8.0+661.79+67.85+67.83+86.45+68.468+8.09+63.856+7.23,66.97+8

9.80+6

2.14+8

8.05+65S. 36.63.93+861.39,71.26+7

5.71.7 8.78+7 2.83.7 8.01+5 6.84.7 4.52+7 3.33+7 1.01+7 8.74.6

3.50.71.99.?2.94*73.28+73.29+73.29+72.56.72.41+73.24+72.44+72.56+7

2.10+71.13+72.05+71.03+79.81+89.34+81.24.71.17+78.48+81.41+71.36.7

.*37.78.81281.63+73.51+63.19.62.91+68.32.65.97+62.41+68.56+87.69+6

5.42+55.11.52.70+58.74.68.74+56.74+69.02+58.73+58.93+5a.97+63.84+5

4.35+72.38+73.26+74.69+74.59+74.59.73.35+73.18+74.19+72.88+73.11+7

2.9-o71.87+72.27+72.07+71.98+71.88+72.10+72.00+71.39+72.05+72.0667

2.18.71.22.71.89.71.05679.65,81.89,71.39+71.32+76.17+61.54+71.42+7

9.09*64.19+83.99+61.398+71.37+7

1.37+78.87+88.65+81.04+74.73+85.85+6

9.08+65.89+62.40.61.11.71.07+71.62.79.50+69.18+68.34.68.78.87.22+6

2.98+7 1.72+7 1.04+7

1.78+7 6.08+6 2.18.8

4.31+5 3.66+7 2.81+7

9.21+5 2.11+7 8.28.8

1.96+7 7.81+6 9.28.6

3.39+6 4.26+6 3.14+6

1.83+72.56+73.24+73.31+73.58*7

8.52+61.89+79.24+81.58+71.36+7

2.44+61.17+72.88+67.58+66.69.6

8.19+54.00+57.81+57.11+57.45+5

2.59+73.07+74.0.+74.62+75.07+7

1.56+72.21+71.49+72.96+72.79.7

9.87+61.88+76.03+82.08+71.89+7

8.18+65.69.89.01+81.39+71.57+7

9.72.65.64+68.47+81.60+71.50+7

Page 80: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - DRYWELL STORAGE OPTION(1983 DOLLARS)(contbd)

--------------------------------------------------------------------------------------------------------LOW DENI BEFORE

PLANT NAME TYPE RACKS ------I .. NEEDEDi as

CONVERSION I------IBIRW..--NG I--

AFTER

0%5S I lox I .ICONVERSION INCREMENTAL COST

---- --- ---- ---

------- I ---------I---------

E SAN ONOFRE IE SAN ONOFRE 2E SAN ONOFRE 3

SEABROOK IA SEQUOYAH 1A SEQUOYAN 2

SHOREHAMSOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE 1ST LUCIE 2SUMMER 1

A SURRY 1A SURRY 2B SUSQUEHANNA 1B SUSQUEHANNA 2

THREE MILE ISLTROJAN

on E 7URKEY PT30% E TURKEY PT 4B VOOTLE 1B VOOTLE 2

VT YANKEE 1WASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK 1YANKEE-ROWE 1

A ZION 1A ZION 2

TOTAL

PPPPPPBPPPPPPP

B

PpP

PP

PPPPP

276

128

240(a)388104104162144138159(a)89"(a)148

98144(a)262(a)204312178240(a)1152

78218(a)

4.03+7 2.23*7 1.26.7 9.5866 6.30+7 3.82+7 2.82+7 1.37+7 1.89.7 1.86.7

a.*94.78 .77.7

3.44+71.83+71.83+73.38+73.28+72.*78+71.73+7

8.76+7

1.78.71.*91+71.80.7

8.09.7

2.07+74.75+73.*28.70.63.7

2.*97.71.* 78.3.* 4+7

1.03473.26.7

1.01.72.68.82.46*02.47+71.22+77.69+84.19.0

2.80+7

6.784.68.78.8

7.27.8

1.78.7

9.01+61.99.79.86+82.41+7

8.17.68.12+81.08+7

3.03+81.73.7

8.20+.3.99,63.83.61.93.74.96+02.31.01.09,8

1.11.71.99+82.60+82.98.6

6.74.0

4.18.89.24.03.22+89.74+8

2.44+63.88+81.04.7

6.74,61.568.

7.38*66.61.6

6.46+66.62*66.26+56.56*67.03.5

1.31.8

8.64+64.37+66.39+6

1.11.8

6.63+61.59.68.90+6

6.77+61.80.69.64+6

6.19.79.03+7

4.28.72.44+72.43.74.03*74.32.73.64+72.18.7

8.4657

2.19.72.62+72.73*7

0.08+7

2.87.76.61.74.02.78.98*7

4.20.72.01,76.13+7

1.88.76.62+7

1.61+74.62+84.28.82.82+72.32.71.66.77.9386

4.52+7

1.07.71.18.71.48+7

3.01+7

1.61.72.72+72.08+74.34+7

1.67+71.8+.71.64*7

7.84.03.83.7

6.77.89.08.68.22.62.10+71.41.76.683+82.88.8

2.13+7

6.44+06.69+88.10.8

1.28.7

9.52.81.61+79.70+02.39.7

7.37*09.71.82.72+7

1.31.72.37+7

9.11+08.88+88.66+87.07+81.12+71.12+76.19.6

1.88+7

4.70868.61+89.33+8

2.10.7

8.60+88.24+81.41+72.44+7

1.29.72.61+81.689.7

9.02+82.38+7

8.72+82.49+82.37.84.02.81.16+78.87.83.84+6

1.6.+7

6.67+65.2578

7.93+8

1.24-7

8.69+67.98.81.09.72.03+7

9.18.66.89.81.86.7

6.38+82.21-7

4.23.81.00.81.00.02.32.09.68.06.13+82.21.6

1.10+7

4.11.83.62*86.76.8

8.01.8

6.41+88.46+87.18.61.62+7

8.04+81.78.7

--- ------------------------------ m ----------- m-mmm--mm ---- m --- m ----------------------- m3.15.9 1.34.9 8.85.8 8.6557 4.07.9 2.18+9 1.34.9 9.8+8 0.90+.8 7.48.6

ABE

INDICATES COMMON POOL SHARED BY TWO REACTORS s CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT I

Page 81: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE As&. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - DRYWELL OPTION(1993 DOLLARS)

I ADD. YEAR COSTSHUTDOWN STORAGE WHEN CONS - .... "i i -

PLANT NAME YEAR REQ'D ADD'L TIME CONSTRUCTION "0 S MI TOTAL(ASSEM- STOR. (MON.)I----------- -------------- -" ----- - -----IBLIES) NEEDED e I% 15x lox% ex 15x lox I o% 6x lo

--------------------------------------------- -------- ------ ------ ----------

ARK NUCLEAR 1 2008 $77 1990 47 1.73+7 9.1568 5.00.6 3.10.0 1.21.8 5.10.5 2.04.7 1.04.7 5.g1.6ARK NUCLEAR 2 2012 g5a 1999 47 1.68.7 8.69.6 4.0868 3.67.8 1.22.8 4.37.6 2.2567 9.81+8 4.52+6BEAVER VALLEY 1 2018 858 1996 47 2.3687 1.25.7 8.83+6 7.3686 2.4386 9.08.5 3.10.7 1.49+7 7.74+8BEAVER'VALLEY 2 2028 858 2009 47 2.35+7 8.61.+ 1.97+8 8.28+6 1.16.8 2.47+5 2.97+7 7.77.8 2.22+6BELLEFONTE 1 2028 1900 2009 46 3.74.7 1.05+7 3.14+6 1.20.7 2.1256 4.48+5 4.94.7 1.27.7 3.58.6BELLEFONTE 2 2030 1900 2011 48 3.74.7 9.6358 2.69.8 1.20+7 1.96*8 3.88.5 4.94+7 1.15*7 2.96.8BIG ROCK 1 2001 95 1995 47 1.7387 9.8128 5.50+8 1.55.8 7.30+5 3.68+5 1.89.7 1.03.7 5.8086

A BRAIDWOOD 1 2028 3627 1996 49 5.89.7 3.02+7 1.65+7 2.95.7 8.0128 2.68+8 8.64+7 8.82+7 1.92+7A BRAIDWOOD 2 2027 (a) 0.00+B BROWNS FERRY 1 2014 32268 202 48 2.90.7 1.15+7 4.74+8 5.67•8 1.68.6 5.27+6 3.47+7 1.82+7 5.27.8B BROWNS FERRY 2 2014 (a) 0.0010

BROWNS FERRY 3 2017 2441 2001 47 2.49+7 1.04.7 4.48.6 8.30.8 1.77+8 6.54.5 3.12+7 1.22.7 5.0.+6BRUNSWICK 1 2010 2401 1990 47 2.48+7 1.78.7 1.27+7 7.82+8 8.46+6 1.71+8 3.26.7 2.1127 1.44+7

0.0600BRUNSWICK 2 2010 2281 1991 47 2.4127 1.63+7 1.12+7 7.17+6 8.09+8 1.47+6 8.2137 1.94+7 .1.27+7

0.*00.0A BYRON 1 2024 3627 1994 49 5.69+7 3.33+7 2.00.7 2.9657 8.83+8 3.25+68 8.84+7 4.21.7 2.33+7A BYRON 2 2028 (a) 0.00+0

o" CALLAWAY 1 2024 1129 2005 47 2.83+7 8.99+6 3.23.8 7.99+8 1.74+6 4.82*5 3.4387 1.07.7 3.618.B CALVERT CLF 1 2014 2213 1992 48 3.72.7 2.40+7 1.58-7 1.38+7 5.33+6 2.34.6 5.10+7 2.93+7 1.81.7B CALVERT CLF 2 2018 (a) 0.00,0

CATAWBA 1 2025 0 2025 0 0.00+0 0.00+0 0.00+0 0.00.0 0.00+0 0.000 0.00*0 0.00.0 0.00.CATAWBA 2 2026 0 2026 0 0.00+0 0.00+0 0.00.0 0.00+0 0.00+0 0.00+0 0.00.0 0.00.0 0.00.0CLINTON 1 2027 2572 2006 47 2.6557 8.32+8 2.8568 8.52.8 1.69.8 3.92#5 3.40+7 1.00.7 3.24.6

B COMANCHE PK 1 2030 2087 2015 48 3.99+7 8.38+86 1.89+8 1.02*7 1.48.8 2.4655 5.01+7 9.86+8 2.14.8B COMANCHE PK 2 2030. (a) 0.00•0A COOK 1 2009 1241 1999 48 2.88+7 1.86+7 8.77,8 6.04+6 1.88+8 7.12+5 3.33.7 1.54.7 7.48.8A COOK 2 2009 (a) 0.00.,.

COOPER STN 2008 1228 1997 47 1.84+7 9.32+6 4.88+6 3.0656 1.1826 4.74*6 2.15.7 1.66.7 5.83.6CRYSTAL RVR 3 2016 482 2005 47 1.73.7 5.90.8 2.12.8 2.84.6 7.39.5 2.06.6 2.01.7 8.3.68 2.38.8DAVIS-BESSE 1 2017 2490 1995 48 4.61,7 2.6127 1.44.7 1.71+7 5.89+6 2.17.8 8.22.7 3.08+7 1.88+7DIABLO CANYON 1 2025 617 2011 47 1.88.7 4.81.6 1.31•6 S.97.6 7.17+5 1.45+5 2.28+7 5.586 1.468+6DIABLO CANYON 2 2025 517 2611 47 1.88+7 4.81.8 1.31+8 3.97+8 7.17+5 1.45+5 2.28+7 5.5386 1.46+6DRESDEN 1 1984 0 0. 00+0DRESDEN 2 2008 1016 1998 47 1.73.7 8.30.6 4.13+. 2.58.6 9.59+6 3.80.6 1.99+7 9.268+ 4.51+6DRESDEN 3 2008 893 2000 47 1.73+7 7.63+8 3.41+8 2.07•8 7.28,6 2.7386 1.94.7 8.28.6 8.88,8DUANE ARNOLD 2010 998 1999 47 1.73+7 7.90+8 3.78+8 2.84.8 9.83.5 3.86+5 2.01.7 8.88+8 4.16-8ENRICO FERMI 2 2025 5355 1997 48 4.07+7 2.05+7 1.07+7 1.94.7 5.22+8 1.70.6 8.01.7 2.57+7 1.24.7FARLEY 1 2012 298 2008 47 1.73+7 5.82.6 1.93.8 1.55+6 4.27.5 1.26+5 1.89+7 8.05+6 2.08,6FARLEY 2 2012 140 2008 47 1.73.7 6.10+8 1.59+8 1.08+8 2.70.5 7.55+4 1.83,7 5.87+8 1.87+8FITZPATRICK 2015 2248 1997 47 2.40+7 1.21.7 8.33+8 6.77+6 2.22.8 8.13.5 3.08.7 1.43+7 7.14.8FORT CALHOUN 2008 418 1994 47 1.7387 1.01+7 6.05+6 2.84+8 1.25.8 5.885+ 2.01+7 1.14.7 8.84.8FT ST VRAIN 2007 0.0+.0GINNA 2006 219 2600 47 1.78+7 7.5368 3.41+8 1.55+8 5.72*6 2.22.5 1.89+7 8.10.8 3.8.+6GRAND GULF 1 2022 4392 1998 48 3.54.7 1.70+7 8.47.6 1.43+7 3.94+8 1.28+8 4.97.7 2.09.7 9.75.8HADDAM NECK 2007 319 1997 47 1.73.7 8.7126 4.54+8 2.58+6 1.01+. 4.18+5 1.99.7 9.72.8 4.98+6HARRIS 1 2028 0 2028 0 0.00+0 0.00+0 0.00+0 0.00+0 0.00+0 0.00+0 0.00+0

0.00+0

Page 82: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Age. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - DRYWELL OPTION(1983 DOLLARS) (contd)

--------------------------------------------------

PLANT NAME

ADD. YEAR ISHUTDOWN STORAGE WHEN I CONS.

YEAR REQ'D ADDbL I TIME(ASSEM- STOR. I (MON.)BLIES) NEEDED

CONSTRUCTION I 0 $ M TOTAL

0% I6x lo I Iss I1lo% osx I Is 1 jx

-- I COST

B HATCH 1B HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT 1INDIAN PT 2INDIAN PT aKEWAUNEE

'LACROSSEB LASALLE CTY 1B LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEMCGUIRE 1MCGUIRE 2MILLSTONE I

ay MILLSTONE 20o MILLSTONE 3MONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE 1A OCONEE 2

OCONEE 3OYSTER CRK 1PALISADESPALO VERDE 1PALO VERDE 2PALO VERDE 3PEACHBOTTOM 2PEACHBOTTOM 3PERRY 1PILGRIM 1

A POINT BEACH 1A POINT BEACH 2A PRAIRIE ISL IA PRAIRIE ISL 2B QUAD CITIES 1B QUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR BEND 1SALEM ISALEM .2

20092012202619761980200820162014200220222023202420292008202120232010201620262007200620282018202020132013201420042011202420262028200820082028200820072008200820082007200720082007202620182020

2874(a)2820202

0493568679205

9824(a)

40964238

682985989

2480823641366884

19711866

(a)2102

(I)1021

912836

1117112111211812168926481512849(a)

1142(a)603(a)228688

245210071163

2000

19942004199919921990

199619981996200620061987199720182004199820111999

1989

19911994198820062002080719971997200919931996

1993

2006

20•41999200719972001

48

48

4747474749

484847474747474747474748

48

4747474747

.474747474747

47

47

4747474748

2.72.7

2.69+7

1.83,71.92+71.81.71.73.78.97+7

3.41.73.48*71.86+72.49+72.62.72.47.72.19+71.92.71.73+71.73+72.28+73.82+7

1.19.7

8.36+8

1.07+76 . 88.8.30+81.11+74.96+7

1.90+.71.87+79.88+88.50+68.19.82.04,71.11+73.86.86.19+69.165.6.77+81.7657

2.74+8

6.42+62.69.83.94+67.32.83.68.7

1.09.78.32+66.40483.08.82.81+61.89+76.78.68.29.62.33+86.00.61.67+88.31+8

3.9*+6

8.22.6

3.30+63.18.64.08+82.68+83.86.7

1.66871.81+7

8.28.88.77.88.98.48.06882.82*87.76562.32+86.26.81.23+7

1.38.8

1.82.6

1.48.68.62.61.29.+1.29+81.36+7

4.81+64.37+61.32.81.46581.46.44.33+81.99.44.28+6

2.62.69.73.69.28.63.68+8

4.98.6 3.11.70.00.0

3.87+6 3.61.70.00.00.00*0

8.67.6 2.18.72.64.6 2.24+74.60+6 2.22+76.73+6 1.99+76.88+8 1.08.8

0.00.01.70+8 6.08+71.32+6 6.29+76.64*6 2.20+73.77+6 3.12+73.6756 3.20.72.37+8 3.37,77.27.6 2.80+77.21.4 2.18+78.88+4 1.81.74.31+6 1.98.71.8656 2.79.71.18.8 6.05.7

0.00+03.6508 6.71.7

0.00+01.89.8 3.65076.6865 1.99.71.84+8 2.94.74.11.6 3.28+73.7456 3.29.73.40.6 3.29+76.74+5 2.66576.38.6 2.41.72.73+5 3.24+78.86.6 2.44+77.18.6 2.6.-7

0.00.01.11.0 2.98+7

6.60,4 1.78.70.*00.0

1.11.6 1.83.71.27.8 2.58-73.32+6 3.24.78.8756 3.31+78.64+5 3.68+7

1.33.7

9.98.4

1.21.77.74.69.69+61.24.76.30•7

2.38872.11.71.12+79.96.89.85+62.47*71.31.74.28.88.44.41.01.78.70.62.11.7

3.73.7

2.10.71.1372.08571.03.79.81.69.34.81.24.71.17-78.48.41.41.71.38.7

1.72.7

6.08.8

0.52.61.69+79.24.61.63671.98-7

6.88+6

3.11.8

7.08+82.84.84.39.67.99.64.17.7

1.28.79.64+85.96+83.44+83.17.81.93.78.49*89.01.52.42.66.43+61.76069.49+6

2.83.7

1.37.76.81.61.63.73.51.63.19.82.91.88.32*85.97+82.41.88.6*8+7.69+6

1.04+7

2.18.8

2.44*81.17.72.88.87.68+86.69+8

4.06+7 3.02.7 2.28+7 1.6867 7.10.6

2.66871.73+72.17.72.62+72.63+72.63+72.18+72.08.72.66571.99+72.16+7

1.73.71.01.71.*70+78.83+88.23+87.84.81.10.71.04.77.19+81.22+71.20.7

1.20.78.06681.3+,73.1*82.82.82.67,66.76+86.43+62.14.67.67.67.87.8

9.38+82.68.67.87+87.60.87.01+67.81.83.89+63.48.86.90.84.63+63.97+8

3.72+81.17.03.62+81.66+81.68.81.658.1.41.81.32.61.29.81.92+61.63+8

2.41+7 1.48+7

1.73.7 5.90+8

9.28.6 6.68.6 2.41.6

2.12.8 6.18+6 1.64.6

1.73+72.03.72.62.72.64+72.74.7

8.19.81.44+77.80.81.28+71.14+7

2.33.81.04.72.66.68.89.84.9386

1. 03.85.256+7.17.87.86.88.39+8

3.29.62.47+61.44.62.48+82.22.6

Page 83: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Aft. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - DRYWELL OPTION(1963 DOLLARS) (cont'd)

------------------------------------ ------- mm -------- m --- w ----- m ------ m ----------------- m ---ADD. I YEAR

SHUTDOWN STORAGE WHEN CONS.-PLANT NAME YEAR REQ'D IADD'L TIME CONSTRUCTI.

(ASSEM- ISTOR. (MON.) -------....IES) NEEDED

---- ---- ---- -- -- -

-I

H------I-

1o% I-T

- - --- ---- --

0% 15% lax e 1 r,% I l. . .

01'C

E SAN ONOFRE 1E SAN ONOFRE 2E SAN ONOFRE 8

SEABROOK 1.A SEQUOYAH 1A SEQUOYAH 2

SHOREHAMSOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE .1ST LUCIE 2SUMMER 1

A SURRY IA SURRY 2B SUSQUEHANNA 1B SUSQUEHANNA 2

THREE MILE ISL ITROJAN

E TURKEY PT 3E TURKEY PT 4B VOOTLE 1B VOCTLE 2

VT YANKEE 1WASH NUCLEAR 2WATERFORD S

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK 1YANKEE-ROWE 1

A ZION 1A ZION 2

TOTAL

1999201220132031202120222027202720282010202320242012201320222024200820112007200720272028201220232024202520272025200120082008

2362

12612890

2831258258

11821128

78197

(a)7289

373384(a)

2491(a)

lose401811432691

85736

1295(a)

1996 48 3.77.7 2.10.7 1.20.7 2.6558

2001995

2008202320241987200120092012

2000

200620042002

2006

1999199820082001

200819991995

4848

47474747474747

49

474747

48

47484748

474748

2.87.74.87.7

2.58.71.73.71.73*72.48.72.42.72.23+71.73+7

4.86+7

1.73+71.73+71.73.7

4.47+7

1.73.73.35,72.55.74.89.7

2.35.71.73.72.92+7

0.48.62.60.7

8.41.62.45.82.33+62.04*71.01+7

4.19+6

2.12.7

5.62.68.19+66.83+6

1.46.7

7.90+.1.61,79. 31.8

1.95.7

8.95+67.90.61.63.7

2.65.61.49.7

2.088"3.81.53.47*51.09+74.85+82.06.61.09+6

9.61.6

1.93.82.33.82.82.6

6.00.6

3.76+68.03.62. 85.68.43.6

2.17.83.76+69.*306

1.07.72.10+7

8.63.61.03,81.03.88.08+68.36.65.51+80.00,0

1.84.7

5.1,51.81+81.29.8

1.62,7

3.36.61.40.77.29.81.94,7

6.24+6

8.19.8

1.88.88.45*6

1.71.81.30*51.24.54.33.82.08.81.10.60.00.0

4.82*6

1.56855.36.54.42*5

8.21*8

1.11,63.79.61.94+04.88.6

1.22.62.20*52.49.8

3.83.52.35.8

3.97.51.81.41.64.42.37.65.99+52.49.50.00*0

1.46+6

5.00+41.70+51.60.6

7.43+5

3.99+51.21+63.71.61.31+6

2.72+59.75+41.08+6

1.26.6 6.44+5 4.03.70.00.00.00.03.94.78.77.70.00.03.44.71.83.71.83.73 * 38.73.26.72.78*7

1.73.70.00.06.70.70.*00.01.78.71.91.7I • 88.70.00,08.09,708.00+62.07,74.75+73.28.76.00+68.63.

2 . 97+71.78.73 . 64.70.00+0

3.15.9

1.03.73.25.7

1.01.72.58.62.45.62.47.71.22.77.69.84.19.8

2.60.7

5.78.66.73+87.27.6

1.78+7

9.01.61.99.79.85+62.41,7

8.17+68.12.61.88.7

3.03.61.73.7

8.28.83.99.53.63.51.93.74.95.82.31.61.09•6

1.11.7

1.98.62.50+62.98.8

5.74*6

4.18.69.24.63.22+69.74+8

2.44*63.80861.04*7

2.2387 1.28.7

------------ -----------------------------------------------------------------2.45+9 1.13.9 5.89.8 6.99.8 2.08.8 7.65+7 1.34+9 8.85.8

ABE

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1

Page 84: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Agb. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - DRYWELL OPTION(1983 DOLLARS)

--------------------------------------------------------------------------------------------------------------ADD. YEAR COS 5T

SHUTDOO N STORAGE WHEN CONS. I ........- I .......................PLAiT NAME YEAR REQ8D ADD'L TIME CONSTRUCTION I TOTAL

SLIES) NEEDED % 16x 1 tx s % 1 6% ex % 10K---------------------------------------m-----m---- ------ ----------------mm---

ARK NUCLEAR 1 2008 737 (b) 47 2.21+7 1.73.7 1.37.7 8.81.6 3.32*8 1.8.8 2.89.7 2.06#7 1.66.7ARK NUCLEAR 2 2012 973 1989 47 2.39.7 1.78.7 1.8567 8.68.8 3.70.8 1.87.8 3.25.7 2.1607 1.54.7BEAVER VALLEY 1 2010 1287 (b) 48 2.90+7 2.27+7 1.8007 1.32.7 6.66.8 2.72+8 4.22+7 2.82.7 2.07.7BEAVER VALLEY 2 2026 1298 280 48 2.91+7 1.27.7 6.76.8 1.23.7 2.98+8 8.6806 4.14.7 1.57.7 0.82.8BELLEFONTE 1 2028 2404 2880 48 4.33*7 1.89.7 8.57.8 2.08*7 4.83.8 1.37.0 8.41.7 2.37.7 9.94.8BELLEFONTE 2 2930 2404 2602 48 4.33.7 1.72.7 7.09.8 2.08.7 4.3880 1.13.8 8.41+7 2.10.7 8.22+8BIG ROCK 1 29081 176 1992 47 1.73+7 1.11+7 7.32.8 2.32+6 1.18.8 0.31.6 1.98+7 1.23.7 7.9568

A BRAIDWOOD 1 2028 4383 1990 49 7.18+7 6.10.7 3.6887 4.47.7 1.48+7 8.17+8 1.17+8 0.68.7 4.30.7A BRAIDWOOD 2 2027 (a) 1999B BROVKS FERRY 1 2014 4594 1998 48 3.88.7 1.77.7 8.0800 9.92.8 3.23+8 1.18.0 4.67.7 2.60+7 9.9688B BROWNS FERRY 2 2014 (a) 1998BROAIS FERRY 3 2017 3353 1995 48 2.97.7 1.68.7 9.47.8 1.07+7 3.68.8 1.386.8 4.04.7 2.02.7 1.08.7BRUNSWICK 1 2910 3153 (b) 48 2.07.7 2.26.7 1.78.7 1.03.7 4.81.8 2.64.8 3.90.7 2.73.7 2.03+7

BRUNSWICK 2 2010 3033 (b) 48 2.79+7 2.18.7 1.73+7 9.91+0 4.86.8 2.46+8 8.78.7 2.8657 1.98.7

A BYRON 1 2024 4413 (b) 49 7.20.7 6.84.7 4.47+7 4.6507 1.82.7 7.5088 1.17.8 7.2607 6.22.7A BYRON 2 2028 (a)

o CALLAWAY 1 2024 1633 1998 48 3.30.7 1.76.7 9.68.8 1.54+7 4.33+8 1.48+6 4.84.7 2.18.7 1.10.7B CALVERT CLIF 1 2014 2789 (b) 48 4.31.7 3.38.7 2.88.7 1.92.7 8.82.8 4.20.6 .23.7 4.21.7 3.18.78 CALVERT CLF 2 2018 (a) ()

CATAWBA 1 2026 228 2921 47 1.73.7 2.70+8 4.81+6 1.08.8 1.43.6 2.19+4 1.83.7 2.64+8 4.83*5CATAWBA 2 2028 210 2023 47 1.73.7 2.4658 3.81.5 7.76.6 9.99.4 1.42.4 1.81.7 2.55.8 3.95.5CLINTON 1 2027 3289 200 48 2.92+7 1.27.7 5.77.8 1.28.7 8.04.8 8.88+6 4.20.7 1.57.7 8.84.8

B COMANCHE PK 1 2030 2681 2910 48 4.85.7 1.25.7 3.66.6 1.6007 2.88.8 6.21.5 8.26.7 1.62+7 4.07.8B COMANCH PK 2 2030k (a) 2010A COOK 1 2009 2009 1991 48 3.89.7 2.63.7 1.82.7 1.19.7 6.23+8 2.65+. 5.08.7 3.16+7 2.07.7A COOK 2 2009 (a) 1991

COOPER 5TN 2908 1702 1993 47 2.13+7 1.321.7 8.22.6 4.89.8 2.08.8 9.57+5 2.82.7 1.62+7 9.18.8CRYSTAL RVR 3 2918 648 1999 47 2.09+7 9.68*8 4.55*8 5.42*6 1.65.68 6.676 2.83.7 1.12+7 5.11.8DAVIS-BWSSE 1 2017 2850 1988 49 4.94+7 3.87.7 3.07.7 2.47+7 1.01*7 4.98.8 7.41.7 4.88.7 3.67+7DIABLO CANYON 1 2026 772 200 47 2.2657 7.32*8 2.61.8 8.01.0 1.37.8 3.2656 2.91.7 8.89+8 2.84.6DIABLO CANYON 2 2026 772 208 47 2.26.7 7.32+0 2.61.8 8.618 1.37.8 3.2656 2.91.7 8.69.8 2.84.8DRESDEN 1 1984DRESDEN 2 208 1647 1992 47 2.04+7 1.32+7 8.6088 4.97.8 2.1*78 1.03+0 2.64.7 1.54.7 9.89+8DRESDEN 3 2008 1325 1994 47 1.85.7 1.08,7 8.47+8 3.89.8 1.81.8 7.17+6 2.24.7 1.24.7 7.19+8DUANE ARNOLD 2010 1510 1991 47 2.01.7 1.38.7 9.38.8 6.89.8 2.60+8 1.19+6 2.69+7 1.81.7 1.08.7ENRICO FERMI 2 2026 8469 1990 48 4.65+7 3.2387 2.33+7 2.74+7 9.12+8 3.88.8 7.29.7 4.14.7 2.72.7FARLEY 1 2012 708 1997 47 2.17.7 1.10.7 5.72.8 6.01.8 1.75.68 8.685 2.87+7 1.28.7 8.39+8FARLEY 2 2012 648 1999 -47 1.94+7 8.90.8 4.23.8 8.82+8 1.28+8 4.54.6 2.32+7 1.02.7 4.88.8FITZPATRICK 2015 2968 1991 48 2.77.7 1.87+7 1.29+7 1.07+7 4.17.8 1.87t8 3.84.7 2.29.7 1.48.7FORT CALHOUN 2098 883 (b) 47 1.89.7 1.48+7 1.18.7 4.84.8 2 62+0 1.42.8 2.3807 1.73.7 1.32*7FT ST VRAIN 2007QINNA 2008 411 1994 47 1.73.7 1.01.7 8.0586 3.10+6 1.34.8 8.17.6 2.04+7 1.14.7 8.67.8GRAND GULF 1 2022 6484 1992 48 4.09+7 2.84+7 1.78.7 2.09.7 8.91.8 2.79.0 8.10+7 3.33+7 2.01.7HADDAM NECK 2007 831 1999 47 1.96.7 1.39.7 1.09.7 5.02+8 2.37+0 1.22.8 2.4657 1.83+7 1.12.7HARRIS 1 2028 0 2028 0 0.00.0 0.00.9 0.00+0 0.00.0 0.090+ 0.00.0

Page 85: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Afb. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - DRYWELL OPTION(1983 DOLLARS) (cont'd)

------------------------ - ------------------------------------------------------------------------ ---

ADD. YEARSHUTDOWN STORAGE WHEN CONS. - ... ..----------

PLANT NAME YEAR REQ'D ADO'L TIME CONSTRUCTII(ASSEM- STOR. (MON.)BLIES) NEEDED e! I5

C 0 ST.. .. . I --- I . ... . ..

0 S M --I TOT•A I 6• I

B HATCH 1B HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT IINDIAN PT 2INDIAN PT 8KEWAUNEELACROSSE

B LASALLE CTY 1B LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEMCGUIRE 1MCOUIRE 2MILLSTONE 1

• .j MILLSTONE 2:-' MILLSTONE 3

MONTICELLOHNIE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE 1A OCONEE 2

OCONEE 8OYSTER CRK 1PALISADESPALO VERDE 1PALO VERDE 2PALO VERDE SPEACHBOTTOM 2PEACHBOTTOM 3PERRY 1PILGRIM 1

A POINT BEACH IA POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 2B qUAD CITIES 1B QUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR BEND 1SALEM 1SALEM 2

20092612202861976198620082016201420022022202320242029206820212023201020152028520072005202620182020201320132014200420112024202520262008200926282008200720082008200826072e8720082007202520162026

4050

9019928s1301

11144(a)

49925116107013971421287212911046

835125225382451

(a)2641

(a)138114241039162716311831272424693444189e1137

(a)1502

1488(m)640958

822014871667

199819982001

(b)199419981987

19981991198719971998

20071998199020071992

1992

2 bb

bI1989

(b)19961997199819911991200319881990199019881968200220021992

(b)200119891992

48

48

4?474?47

484847484848484747474748

48

484?4?4848464747404747

48

47

4747484848

3.38.7 1.79+7 9.79+8 7.33+8 2.81+8

3.21.7 1.83+7 5.78+8 1.83.7 8.12#6

1.168. 4.11.7 2.0*77 1.10.7

8.69*5 4.84.7 1.84.7

2.40.72.52.72.10.71.73877.15+7

8.91,7*3.95.72.35+73.06.73.16.72.87.72.70+72.59.71.78.71.*82,72.54.74.52.7

1.88.71.47.71.29.71.42.75.60.7

8.06.72.67.71.94.71.55671.49+.72.09.72.12.78.62.6

1.29.77.87+62.91.7

1.49+76.83+88.11+61.18*74.44.7

2.43.71.04+71.81.78.07+87.42+61.85.71.88.72.63+84.13+69. 32+82.68+61.91.7

6.75+88.38.88.75683.87+84.3147

2.39.72.65577.71+61.21.71.28.79.39.61.17.77.41.82.22+84.19987.65.62.82+7

8.44*.2.99.8

-2.55+8

2.20.61.61.7

8.86667.87.83.87.68.51+63.46+84.46.84.98.61.49.88.83+52.01#81.61.67.20+6

1.91.81.21+81.87+61.34+87.6*68

3.98+8

2.17.61.19.61.11.82.33+62.49#83.43.63.4805

1.06.88.42.53.02+8

3.09+78.86,7$.38#7

2.78+72.12.71.16-8

8.30+76.60+73.12-74.27+74.38+73.81+71.87*73.$3371.96.72.23+74.31.78.64.7

2.22.71.7?7-1.54.71.84.77.21*7

3.92.78 * 44.72.83871.90.71.84+72.53+72.82.79.51.89.18.61.49.79.68.7S.$9.7

4.84.7 3.84.7 2.88+7 2.0&?7 8.84.8 4.51+8 8.64.7 4.52.7

6.6568

1.68.71.00.79.18.61.31.75.20.7

2.83.72.16.71.83.79.268+8.9*681.88+71.93.72.97.64.49+61.04.72.92.62.21.7

3.33*7

2,18-71:22-7.1.89+71.05#79.556+8.19.71.39+71.32.75.17.61.54871.4297

1.98.7

3.3916

9.87+61.65.78.03+62.42.71.89.7

8.05.71.92÷72.39#78.14.73.14.73.14.72.68372.51.73.04.72.20+72.45.7

2.39+71.44+71.87.71.66.71.59.71.51.71.78.7

1.14+71.72.71.74+7

1.89.71.09+71.48.79.09.68.28,67.*5861.23871.17.74.51.61.36.71.26.7

1.38.74.38+88.59*81.46.71.45.71.45+77.16.66.74.81.15+?6.76.86.68+8

5.64+62.25.63.95.64.09.88.91+63.72+83.21+63.08362.53+83.30+83.09+8

2.85981.26+62.06+81.46.81.27#81.18-61.88.61.48.68.58-5

1.79.61.59.6

4.35572.36*73.25.74.59+74.89*74.89*73.35+73.18.74.19.72. 88+73.11.7

2.98.71.87+72.27.72.07+71.98-7I • 88.72.21.72.06.72.8957

2.08.7

2.77.7 2.17.7 1-72+7 8.94.6

1.98.7 7.77+6 3.2148 1.49-6

4.38.8 2.36.6 8.86*7 2.81.7

5.89.5 1.84.5 2.11.7 8.28"8

2.18872.37+72.92.73.19.73.45.7

1.34.71.86.71.22+72.38.72.28.7

8.82.61.47.75.26.81.80.71.46.7

5.07+67.6478

1.14+71.43871.62+7

2.22#63.51.82.73+65.78+85.56.6

1.05681.93+87.71252.76+62.28+6

2.59.78.67.7

4.68.74.62+75.07+7

1 56+,72.21+71 2 49+72.98.72.79+7

Page 86: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A3b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - DRYWELL OPTION(1983 DOLLARS) (cont'd)

ADD. YEAR C 0 S TSHUTDOWN STORAGE WHEN CONS. - ------------ ------- -------

PLANT NAME YEAR REQD ADDI'L TIME CONSTRUCTION O TOTAL(ASSEM- STOR. (MON.) ---

BLIES) NEEDED 0%x5 1 % I 0 ~ 5 1 % l K % 1 6----------------------------------------- ------- ------- ------ ------ --------- ---

E SAN ONOFRE 1 1999 3172 1989 48 4.62+7 3.37+7 2.66.7 7.78.6 4.4946 2.70.6 6.30.7 8.02+7 2.82+7E SAN OHOFRE 2 2012 (a) 1989E SAN ONOFRE 3 2013 1989

SEABROOK 1 2031 1646 2000 48 3.42.7 1.49+7 6.77+0 1.77.7 3.89.6 1.07+8 6.19+7 1.88-7 7.84.6A SEQUOYAH 1 2021 3400 1989 49 6.82.7 4.34+7 3.29+7 3.21+7 1.18-7 5.40+8 9.03.7 5.62+7 3.83.7A SEQUOYAN 2 2022 (a) 1989

SHORE"lA 2027 3371 200 48 2.97+7 1.30+7 6.88+6 1.31#7 3.10+6 8.88.5 4.28.7 1.61+7 6.77+8SOUTH TEXAS 1 2027 670 2017 47 2.12+7 4.04+8 8.30+5 3.24+6 4.77.5 7.80+4 2.44+7 4.52.6 9.08+6SOUTH TEXAS 2 2028 670 2018 47 2.11.7 3.83+6 7.61+6 3.23+6 4.62*6 7.08+4 2.43+7 4.28.6 8.22*6ST LUCIE 1 2010 1638 (b) 48 2.96.7 2.32+7 1.84.7 1.07.7 6.00+8 2.64+6 4.03+7 2.82+7 2.10+7ST LUCIE'2 2023 1668 1992 48 2.87.7 1.86+7 1.22+7 1.46+7 4.69+8 1.88+6 4.32+7 2.32+7 1.41+7SUMMER 1 2024 1169 1999 48 2.74.7 1.28+7 6.96+8 1.10+7 2.86+5 8.72+5 3.84+7 1.66+7 6.83+0

A SURRY 1 2012 674 2005 47 1.97,7 6.74+6 2.42+6 2.09+6 5.91.6 1.79+6 2.18.7 7.3.+6 2.80+6A SURRY 2 2013 (a) 20056 SUSQUEHANNA 1 2022 8680 1996 49 6.77+7 3.21+7 1.84.7 2.68+7 8.11+6 2.93+6 8.46+7 4.02+7 2.13+78 SUSQUEHANNA 2 2024 Ia) 1996

THREE MILE ISL 1 208 13 1997 47 1.88.7 9.60.8 4.96+8 3.12+6 1.19.8 4.86+6 2.19+7 1.07+7 6.44.6TROJAN 2011 661 1998 47 2.10.7 1.01.7 5.04.6 4.18+6 1.46.6 6.47.6 2.62.7 1.16+7 6.69.6

E TURKEY PT 3 2007 818 1996 47 2.30.7 1.28+7 7.32+6 4.28.6 1.76+8 7.76+6 2.73.7 1.46+7 8.1068E TURKEY PT 4 2087 (a) 1995B VOOTLE 1 2027 3261 200 49 6.61.7 2.40+7 1.09+7 2.67+7 6.088+6 1.74.6 8.0887 3.01+7 1.26+7B VOOTLE 2 2028 Ia) 2000

VT YANKEE 1 2012 1696 1993 47 2.07.7 1.27.7 8.00#0 6.01.6 2.35.8 1.02+6 2.67.7 1.61+7 9.02#6WASH NUCLEAR 2 2023 4642 1994 48 3.70+7 2.17+7 1.30+7 1.81.7 6.63+6 2.0656 6.61.7 2.72+7 1.61+7WATERFORD 3 2024 1671 1997 48 3.19+7 1.61+7 8.41+6 1.43.7 3.91+6 1.29+0 4.62+7 2.0*7 9.70.6

A WATTS BAR 1 2025 3411 1994 49 6.84.? ,ý42+7 2.06+7 3.12.7 9.18.6 3.36+6 8.96+7 4.34+7 2.39+7A WATTS BAR 2 2027 (a) 1994

WOLF CREEK 1 2026 1313 1999 48 2.9657 1.35,7 6.41+8 1.26+7 3.17.0 9.69+5 4.20+7 1.87+7 7.37,6YANKEE-ROWE 1 2001 264 1990 47 1.73,7 1.23.7 8.86+8 2.84+8 1.62+6 8.61+5 2.01+7 1.38+7 9.71+6

A ZION 1 2008 1943 1988 48 3.83+7 3.00+7 2.38+7 1.30.7 6.36*6 3.44+8 6.13+7 3.64.7 2.72+7A ZION 2 2"08 (a) 1988------------------------------------------------------------------------ ---------------- ----------------------------TOTAL 2.93+9 1.77.9 1.17+9 1.14.9 3.92+8 1.89+8 4.07.9 2.16+9 1.34.9

ABE

INDICATES COMMON POOL SHARED 13Y TWO REACTORSt CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEIND)ICATES POOLS CONNECTED BY TRANSFER" CANAL: CAPACITIES AND INVENI"ORIES ARE COMBZINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS REQUJIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INZCLUDED IN UNIT 1.NEED ADDITIONAL SPACE AS OF 198".

Page 87: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A4. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - VAULT STORAGE OPTION(1983 DOLLARS).

---------------- LOW---DEN -----BEFORE----CONVERSION--- ---I--- AFTER----CONVERSION----I LOW DIN1 BEFORE CONVERSIO! AFTER CONVERSION

PLANT NAME TYPE RACKS I----------------- RERACKINGNEEDEDI1 OX 15 lox

INCREMENTAL COSTex I 5% I 1e%

AABB

AA

(ABB

BBAA

ARK NUCLEAR 1ARK NUCLEAR 2BEAVER VALLEY 1BEAVER VALLEY 2BELLEFONTE 1BELLEFONTE 2BIG ROCK IBRAIDWOOD 1BRAIDWOOD 2BROWNS FERRY 1BROWNS FERRY 2BROWNS FERRY 3BRUNSWICK 1

BRUNSWICK 2

BYRON 1BYRON 2CALLAWAY 1CALVERT CLF 1CALVERT CLF 2CATAWBA 1CATAWBA 2CLINTON 1COMANCHE PK 1COMANCHE PK 2COOK 1COOK 2COOPER STHCRYSTAL RYR 3DAVIS-BESSE 1DIABLO CANYON 1DIABLO CANYON 2DRESDEN 1DRESDEN 2DRESDEN 3DUANE ARNOLDENRICO FERMI 2FARLEY 1FARLEY 2FITZPATRICKFORT CALHOUNFT ST VRAINGINNAGRAND GULF 1HADDAM NECKHARRIS 1

12013818814816816840

252(a)684(a)456378

378

284(a)188192(a)144144344198(a)2582(a),232

721201esB5

85

318318258552136138386

240854538184

104104

3.56073.94,76.89.75.82+71.04+81.04.83.19.72.01+8

1.77.71.71+72.89071.45+72.65+72.41.71.75.78.79+7

9.36.87.82.81.44.74.12.87.44.68.18+69.90884.39,7

5.42+55.54,58.21.56.47+57.34,57.34+58.56.41.03.8

5.39,78.23.78.62.78.38.71.44+81.44+83.35,72.81+8

3.79,74.08.75.69.73.11.75.28.74.79472.10+71.39.8

2.83.72.88+74.06+71.30+72.20.71.82+71.36578.59,7

1.94.72.35.72.89.72.80.74.08+74.08+71.82.68.08.7

2.07.72.41.72.85.71.72.72.70+72.46+73.58.86.20+7

8.86.7 2,57.7 1.03.7 1.32.8 9.78.7 4.35+7 2.07.7

5.99.78.33070.00+05.97#70.00+02.01+8

8.71.71.0808

0.00,00.00.08.84+71.08.8

2.30.7 9.51.84.02.7 2.72*7

3.8.+7 2.37.7

9.89+7 5.31.7

2.07.7 7.01.88.18.7 3.76,7

9.02+5 8.14+7 3.99+7 2.14+77.59.5 7.79+7 5.38+7 3.98+7

7.52+5 7.52+7 5.19+7 3.84.7

1.07.8 2.82+8 1.43,8 8.93+7

7.13.5 9.99+7 4.44+7 2.22+77.16+5 1.39+8 8.94+7 8.24+7

3.04.7 1.91.7 1.17.7

2.24+7 1.78.7 1.28+71.57.7 1.44.7 1.34.7

1.63.7 1.81.7 1.54+7

8.19+7 4.a9+7 3.73+7

3.35.7 2.44+7 1.59.73.22.7 2.88+7 2.5657

1.94.72.13,72.89+79.6a+81.53.71.29873.83+64.31#7

0.00,00.00+01.93.72.1207

0.00.00.00+08.17.84.6556

6.42.65.94+58.96858.78+6

3.09.73.04.70.49.71.44.8

4.88+84.20.83.12.73.47+7

8.14.68.84+51.31.79.29.8

3.16+73.09.71.92.73.74.7

5.44+84.88,81.27.71.46+7

1.46+61.2+6*7.58.85.62.8

8.52.7 3.00,7 1.45.7 1.12.6 1.08.8 8.89.7 4.36.7 4.42.7

3.74+73.45.71.42+84.01.74.01.70.00.03.40+73.29+73.45+71.31.83.19+73.09+75.88+73.45,70.00.03.19.71.04.83.40+70.*00.00.00.0

1.92*71.13.78.99479.84+69.64.6

1.58971.41.71.52.75.57.71.02+79.04.82.71.71.93+7

1.37.74.33.71.65.7

9.19,83.95+63.73+72.52.62.52+8

7.85.88.25+67.*0082.86+73.47+82.81,81.34.71.13.7

8.15.82.00+78.42+8

4.90+53.34+55.48e53.89+63.89+5

6.12.58.12.55.30.51.08.68. 13.58.13+57.30+53.19.5

2.32.51.04.84.19.54.75+5

4.79,74.8eO+71.74.85.45.75.45.7

4.59+73.92+74.69+71.88.84.91+74.12.77.65.74.23+7

3.60.71.36.84.39+7

2.74.72.03+71.06+81.86071.60.7

2.74+72.16.72.87.79.44.72.31.71.79+74.49+73.05.7

1.95.77.22.72.87.7

1.85,79.14.87.17.75.19+65.19+8

1.72.71.25.71.87+78.18+71.15+78.21962.87+72.29+7

1.13,74.34+71.97+7

1.10.71.39.73.26.71.48.71.48.7

1.26+76.89+81.29.73.79+71.78.71.09.71.84.78.09.8

3.33.63.29,71.04.7

3.79.7 3.02.7

9.73+8 7.84*69.29.8 5.52.63.70+7 3.49.78.80+6 3.0686.8086 3.0686

1.22+7 1.01.78.12.6 6.83+61.41+7 1.22.73.98+7 3.81+71.35+7 8.87,69.48.6 5.99.81.85+7 1.61.71.15,7 1.19+7

5.97.6 5.42+83.00,7 2.44+71.26.7 1.17+7

Page 88: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A4. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - VAULT STORAGE OPTION(1983 DOLLARS)(cont'd)

--------------------------------------------------------------------------------------------------------------

I LOW DEN I BEFORE CONVERSIONPLANT NAME TYPE RACKS I-----------------IjNEEDED! I 6X 1O%- -- - - - - -I --- I I-m ~ - - . - -

AFTER CONVERSION 1INCREMENTAL. COST

- - .. 10w--------- - ----------- I lox'I

B HATCH 1B HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT 1INDIAN PT 2INDIAN PT 3KEWAUNEELACROSSE

B LASALLE CTY 1B LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEMCGUIRE 1MCGUIRE 2MILLSTONE 1MILLSTONE 2MILLSTONE 3MONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE 1A OCONEE 2

OCONEE 8OYSTER CRK 1PALISADESPALO VERDE 1PALO VERDE 2PALO VERDE 3PEACHBOTTOM 2PEACHBOTTOM 3PERRY 1PILGRIM 1

A POINT BEACH 1A POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 26 QUAD CITIES 1B QUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR BEND 1SALEM 1SALEM 2

588(a)464

130162

74.48660(a)448440140144144

188241184

278195(a)18a(a)120268

170170170468440448192

(a)120(a)480(a)138

98384180188

6.01-7 2.64.7 1.18.7 1.14.6 .8.39.7 4.21+7

9.22.6 9.32.7 3.32.7

2.21.7 2.49.7 1.78.7

1.34+7 2.49+7 1.47.70.92+70.0+800.00.03.76873.92.78.60873.40*72.41+8

1.06.81.11+83.86576.98+76.18.78.64+76.18.73.83873.04.73.36*76.20.71.07.8

1.94.7 6.98+.

2.10.71.36.71.68.72.12.71.38.8

4.88.74.34+71.96+71.89.71.84.74.62.72.39+77.43.81.08.71.73.71.24.74.43.7

1.21.74.94.67.68*61.386.78.42+7

2.66571.97+71.03+76.47.66.99+63.48+71.18.71.67.84.06+09.20.63.21.61.99*7

6.01.66.77.62.84.66.68.4

1.27+8

8.98.68.73+66.26.68.42.66.42.64.06566.13+67.46*64.88+63. 80.66.71268.91+6

6.86.76.63+76.12.7808.672.69.8

1.38+81.42.86.96+78.68.78.92.77.11+77.72.76.48+73.86+73.89+76.41.71.66-.

4.18.7

2.80+72.81.71.47.8

8.14+77.37+74.29.73.80+73.68.74.91.76.11.71.83+71.67+72.69+71.80.78,23.7

3.13.71.91.71.86572.24+79.12.7

6.64.74.68+73.28.71.84.71.89.73.83+73.73.76.68+67.80.81.79+76.64.66.00+7

2.16-72.67+71.27.72.68.62.89.7

8.17.73.18.72.16872.76.72.•8276.11262.80.72.73.73.69+66.82.61.27.74.34,7

2.16.72.11+71.16.77.01+61.5607

3.36+73.12.72.89.71.98.71.90.73.38.62.79+71.18+76.36+89.01+66.12+63.89+7

1.20.7

8.0..6

1.98+71.48.79.18.8

8.27+6

3.17.72.68.72.81+71.26.71.16.71.87.82.01+74.84+84.03.69.04.62. 9063.09+7

1.19+7

1.77-71.06.74.08.81.60.71.37.71.26+71.60.71.62.78.64+81.34+71.33+7

1.89.7

3. 17.8

1.41.71.07.77. 16.62.80+72.44+7

1.24.8 8.04*7 6.66+7 8.01.6 1.64.8 9.79.7 8.76.7 3.03+7 1.83+7

6. 86.73.40.76.48.76.36876.38+78.88.74.66*74.82+76.28+74.37.74.6887

4.08.71.91+78.76871.97.71.88.71.78.72.26+72.10.71.68372.51+72.47.7

2.68071.12.72.77.78.68+88.086+86.61#81.14.71.08+74.69.01.60+71.38.7

6.42.66.11+62.70+68.74.66. 74#60.74.69.02+68.73*68.93+63.97.63.64.6

8.88.74.19.78.23*79.40.79.48379.43.76.64+78.13+78.47+76.36975. 98*7

6.91+72.91+74.28.74.17+73.98.73.80+74.08.73.81.72.79+78.77+73.68+7

4.31.72.12.73.16.72.10+71.91.71.73+72.86572.49+71.02+72.80+72.68+7

2.08.78.41+67.77+63.11.73.12.73.12+71.97+71.98+72.28+71.02.71.84.7

1.91.71.06.76.40+82.28.72.17*72.08+71.90+71.80+71.26.71.30-71.46+7

6.04.7 3.2387 1.94.7

2.98.7 1.02.7 3.66+0

4.31.6 7.26.7 6.1447

9.21+6 3.68+7 1.45.7

3.79*7 1.86.7 1.91.7

6.90+8 7.87+0 6.20.0

8.09+74.82+76.26+70.41.77.07+7

1.10.73.02.71.76*72.93.72.68.7

4.11.82.08+76.48+81.44.71.08.7

6.19.64.00+67.81.67.11.67.46+6

4.70.76.88*78,19.79.49.71.08.8

2.81.74.16.72.98+76.98.76.72.7

1.76.73.10+71.18.74.18.73.4657

1.67.71.28+72.02+73.16.73.68.7

1.77+71.17.71.27.73.13.73.14+7

Page 89: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A4. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - VAULT STORAGE OPTION(198I DOLLARS)(cont'd)

-- -------- - -------- ----------- - ----- - ----- - ---------- - ------ ---- - ----- ---

PLANT NAMEI |LOW DENITYPE RACKS I.

.NEEDED... ILO DNI'

BEFORE CON•

sexI

fERSION FAIYG. AFTER Co VERSION

~10%110 I.....-I- NCREMENTAL COST

I~ s ex 1o Ilo•Im•N•ml•o•w•m --------------------- I--------I-------------"-----

E SAN ONOFRE 1E SAN ONOFRE 2E SAN ONOFRE 3

SEABROOK 1A SEQUOYAH 1A SEQUOYAH 2

SHOREHAMSOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE 1ST LUCIE 2SUMMER 1

A SURRY 1A SURRY 2B SUSQUEHANNA IB SUSQUEHANNA 2

THREE MILE ISLTROJAN

E ThRKEY PT 3E TURKEY PT 4B VOCTLE IB VOOTLE 2

VT YANKEE 1WASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK 1YANKEE-ROWE 1

A ZION IA ZION 2

TOTAL

PPPPP

BP

PP

ipPPP

PP

P

270

(a)

240(a)388104104152144138159(a)890

14898144(a)252(a)264812176240(a)152

78218(a)

8.83+7 4.81.7 2.82.7 9.58.6 1.29.8 8.49#7 8.17+7

7.91.71.57#8

8.78+73.09.73.019÷78.654*78.27.75.18+72.89.7

1.6.8÷

2.9"+78.24.78.*14.7

1.89.9

8.55.79 *82.78.36.7

3.2453.1.63+8

3.65+7

2.99+77.00+7

2.04.77.46.7

1.95.74.358.4.1".84.82.72.83071.42+77.00.8

0.02+7

9.89.61.14.71.2.+7"

4.01+7

I .64.74.08.7

5.54+7

1.63+72.38+71.a8+7

6.94+83.94.7

8.25+08.72+58.11.63.49*79.29+64.21+61.82+8

2.5667

3.32+84.28.65.03+6

1.29+7

7.07+61.87.76.11282.23+7

4.53+86.47+82.03+7

5.74+51.06+67.38÷65.51.55.46÷66.52.55.26558.05657.03.5

1.81.8

8.54.54.37÷58.39÷5

1.11+8

6.58,5

8.90651.08+8

8.77+51.86+59.64+6

1.09.82.10.9

8.68874.41.74 • 88.78.11.78. 75.77.06+78S. 82.7

1.96+8

3.94+74.67+75.07.7

1.89.8

4.88+71.17.89.48.72.0898

8.48.78.45.71.09+8

8.81÷71.29+8

9.22*7

8.1.8+7.67.0

4.81.73.02.?

1.28.+7

9.22.7

1.86.72.08472.69.7

8.*97.7

2.71.7569.874.04.79.92.7

8.31.72.86+77.49+7

1.59.77.92.?

1.35+?

1.88+61.47.84.14.72.75.71.88.?4.54+8

4.88.7

9.41.69.99+61.49.7

2.90.7

1.82+7*.12.7

1.94+75.41.7

1.46.71.45+75.42.7

8.00+75.88.7

2.02.71.88.71.36+71.83+71.68.72.53+72.66+71.01+7

4.05+7

9.19+61.38+71.99.7

5.19.7

1.1S+71.95.73.19,75.62.7

2.92+74.84+84.02÷7

1.9.*74.89.?

1.82.74.80."4.08+01.04.72.37.71.86.76.52+.

9.59+69.84.61.5637

3.07.7

1.23.71.70÷72.23+74.49.7

1.85.71.01.78.91.7

1.08.73.99.7

7.79-61.50.681.40.6

7.08+01.89.79.65+63.42.8

2.44.7

8.75.68.20+61.05.7

1.73.7

9.84.61.32+71.40+78.29.7

1.06÷71.02.73.48.7

3.73.? 3.98.7 3.65.7

----------------- ----------------------- ----------------------------------------------------

8.25+9 2.62.9 1.3809 8.50+7 8.43+9 4.85.9 2.82+9 2.24+9 1.80+9 1.3889

ABE

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(I) INCLUDED IN UNIT I

Page 90: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A4a. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - VAULT OPTION(1983 DOLLARS)

ADD. YEAR C OSTSHUTDOWNISTORAGEI WHEN I CONS. I..... ....... I....... I............YEAR REq'D ADDIL TIME CONSTRCTION I 0 8 U I TOTAL(ASSEM- STOR. (MON.) -- - - - - - - - - -- -- - - - - - - - - - - I - - - - - - - - - - -

BLIES)NEEDED % I 5 1 % I o i S I 6% 110%

ARK NUCLEAR 1 2008 a77 1996 48 2.88.7 1.6537 8.34*6 0.20+8 2.43+0 1.02.6 3.60+7 1.77-7 9.3868ARK NUCLEAR 2 2012 G65 1999 48 3.19+7 1.48+7 8.938+ 7.50,6 2.48.4 8.92+6 3.94+7 1.71.7 7.82+6BEAVER VALLEY 1 2016 836 1998 52 4.28+7 2.27+7 1.24+7 1.81+7 5.31.0 1.98.0 6.89+7 2.80+7 1.44+7BEAVER VALLEY 2 2028 8a8 2009 62 4.26+7 1.20+7 3.68.6 1.8307 2.64+6 6.38*6 6.82+7 1.46+7 4.12+8BELLEFONTE 1 2028 1900 2009 68 7.07+7 2.10+7 8.43+8 2.74+7 4.90.8 1.01.6 1.04,8 2.66.7 7.44+6BELLEFONTE 2 2030 1900 2011 68 7.67+7 1.98.7 6.32.0 2.74.7 4.46+6 8.37.6 1.04.8 2.41+7 0.16+6BIG ROCK 1 2001 96 1996 48 2.88+7 1.680+7 9.18.8 3.10+0 1.48.4 7.17+6 a.19+7 1.75.7 9.90+8

A BRAIDWOOD 1 2028 3827 1998 87 1.28+8 8.80+7 3.72+7 7.32.7 1.99+7 6.88+6 2.01+9 8.79+7 4.39.7A BRAIDWOOD 2 2027 (a) 0.08+0B BROWNS FERRY 1 2014 3228 2002 58 6.67+7 2.20*7 9.10.6 1.28.7 3.78.8 1.18+8 6.86*7 2.67+7 1.03.7B BROWNS FERRY 2 2014 (a) 0.0.+0

BROWNS FERRY 3 2017 2441 2001 64 4.60.7 1.91+7 8.28.8 1.39+7 3.92+6 1.23+6 6.99.7 2.30+7 9.61.8BRUNSWICK 1 2010 2401 1990 64 4.67+7 3.2657 2.34+7 1.73+7 7.66+8 3.77+0 8.30+7 4.02+7 2.72+7

0.00+0BRUNSWICK 2 2010 2281 1991 63 4.40.7 2.98+7 2.05+7 1.67.7 6.7+86 8.23.6 6.97+7 3.68+7 2.37+7

0.00+0A BYRON 1 2024 3827 1994 87 1.28.8 7.60+7 4.60+7 7.32+7 2.19+7 8.06+6 2.01.8 9.69+7 5.31+7A BYRON 2 2028 (a) 0.00+0

' CALLAWAY 1 2024 1129 2006 66 4.93*7 1.6887 6.06*8 1.78.7 3.87.6 9.62+6 6.71+7 2.07.7 7.01+6B CALVERT CLF 1 2014 2213 1992 68 7.62.7 4.91+7 3.23+7 3.18+7 1.22+7 6.34+8 1.08,8 6.13.7 3.76,7B CALVERT CLF 2 2016 (a) 0.00+0

CATAWBA 1 2025 0 2026 0 0.0080 0.00.0 0.00+0 0.00.0 0.00.0 0.00+0 0.00+0 0.00+0 0.."+0CATAWBA 2 2026 0 2026 0 0.000 0.00.0, 0.00.0 0.00+0 9.00+0 0.00.0 0.00+0 0.00.0 0.00+0CLINTON 1 2027 2672 200 66 4.76+7 1.66+7 6.30+. 1.89+7 3.78.8 8.70.6 6.64.7 1.93.7 8.17.8

B COMANCHE PK 1 2030 2087 2016 89 8.40.7 1.78+7 8.98.0 2.3657 3.42.8 5.8.+6 1.08.8 2.10+7 4.66+8B COMANCHE PK 2 20830 (a) 0.00+0A COOK 1 2009 1241 1998 67 6.39.7 2.69+7 1.29.7 1.13.7 4.11.6 1.6800 6.62+7 3.00+7 1.46+7A COOK 2 2009 (a) 0.00.0

COOPER STN 2008 1238 1997 47 3.1227 1.58+7 8.2286 6.20.8 2.87+6 9.6655 3.74+7 1.82+7 9.19+6CRYSTAL RVR 3 2018 432 2005 47 2.88+7 9.85+6 3.648 5.688+0 1.47+. 4.1256 3.4657 1.13+7 3.96+6DAVIS-BESSE 1 2017 2490 1996 76 1.01+8 6.61+7 3.21+7 4.10.7 1.37+7 6.21.6 1.42+8 6.98.7 3.73+7DIABLO CANYON 1 2026 617 2011 48 3.20+7 8.17+8 2.22+8 8.1.86 1.47+8 2.97+6 4.01+7 9.64*6 2.62+6DIABLO CANYON 2 2026 617 2011 48 3.20.7 8.17+8 2.22+6 8.13.6 1.47.6 2.97+6 4.01.7 9.84+8 2.62+6DRESDEN 1 1984 0 0.00+0DRESDEN 2 2008 1016 1998 46 2.88+7 1.39+7 6.890+ 6.16+6 1.92+0 7.88+6 3.40*7 1.66+7 7.66+0DRESDEN 3 2008 893 2000 48 2.88.7 1.26+7 6.70.8 4.13+6 1.4686 6.46+6 3.29+7 1.41.7 6.26+5DUANE ARNOLD 2010 998 1999 48 2.86*7 1.32+7 6.27+8 6.68.6 1.97.6 7.3056 3.4657 1.62+7 7.00+6ENRICO FERMI 2 2026 6366 1997 70 8.83+7 4.30+7 2.27+7 4.60+7 1.21+7 3.94+8 1.31+8 6.67+7 2.6807FARLEY 1 2012 298 2000 46 2.88+7 9.38+6 3.22+6 3.10+8 8.68+5 2.61+6 3.19,7 1.02+7 3.47+8FARLEY 2 2012 140 2088 48 2.88+7 8.60+6 2.8088 2.07.8 6.41+6 1.6156 3.09.7 9.04+8 2.81.6FITZPATRICK 2016 2246 1997 65 4.39+7 2.22+7 1.16+7 1.49+7 4.88.0 1.78+6 6.88+7 2.71.7 1.34+7FORT CALHOUN 2008 413 1994 48 2.88*7 1.6887 1.01.7 6.68.6 2.61+0 1.18+6 3.46+7 1.93.7 1.13+7FT ST VRAIN 2007 0.00+0GoNNA 2088 219 2000 48 2.88.7 1.28+7 6.70.0 3.18,6 1.14+6 4.46+6 3.19+7 1.37+7 8.16+6GRAND GULF 1 2022 4392 1998 64 7.13.7 3.48.7 1.71.7 3.24+7 8.98+6 2.9080 1.04+8 4.33+7 2.00+7HADDAM NECK 2007 819 1997 48 2.88*7 1.46+7 7.68+0 6.16.8 2.01+0 8.38+6 8.40.7 1.66.7 8.42+8HARRIS 1 2028 0 2020 0 0.00+0 0.00+0 0.00+0 0.00+0 0.00+0 0.00+0 0.00+0

- - 0.00+0

Page 91: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A4a. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - VAULT OPTION(19893 DOLLARS) (cont*d)

--------------------------------------------------------------- !------------------------------------------------ADD. YEAR C 0 S T

SHUTDOWN STORAGE WHEN CONS. - "-.........-I-.....-------- .w-PLANT NAME YEAR REQD ADD'L TIME CONSTRCTION I 0 a U I TOTAL

(ASSEM_ STOR. (MON.) -- ; ------BLIES)NEEDED -%1 -o, 1 I e i 5%

eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee--- ------

B HATCH 1 2009 2874 2000 s6 5.18*. 2.24.7 1.02+7 8.80,6 A.03,8 1.11.6 6.01.7 2.54.7 1.18.78 HATCH 2 2012 (0) o.0o+o

HOPE CREEK 2028 2920 2007 s6 5.09.7 1.68+7 5.16.8 1.84+7 3.82+8 8.22.5 8.92#7 1.94.7 5.98.6HUMBOLDT BAY 1978 0 -. 0*00INDIAN PT 1 1998 -a0.00.0INDIAN PT 2 2006 493 1994 47 3.0997 1.81.7 1.08.7 8.70.6 2.89.6 1.3.68 3.7867 2.1207 1.21.7INDIAN PT 3 2016 536 2004 48 3.27.7 1.17+7 4.42.8 6.54.6 1.77.8 5.22.5 3.02+7 1.3567 4.94.6KEWAUNEE 2014 579 1999 47 3.05.7 1.40,7 6.65.8 8.2686 2.62.6 9.12.5 8.88.7 1.8667 7.68+8LACROSSE 2002 205 1992 47 2.89.7 1.8867 1.22.7 5.1868 2.57.6 1.35+6 8.40.7 2.12.7 1.3867

B LASALLE CTY 1 2022 9824 1990 95 1.49.8 1.01.8 7.01+7 9.24.7 3.24.7 1.41+7 2.41+8 1.83.5 8.42.7B LASALLE CTY 2 2023 (a) 0.00.0

LIMERICK 1 2024 4096 1995 63 8.81.7 3.79*7 2.17.7 3.76,7 1.09.7 3.86.6 1.06.8 4.88.7 2.56.7LIMERICK 2 2029 4236 1998 84 6.97+7 3.38+7 1.67.7 4.10.7 9.91.8 3.00.6 1.11+8 4.34.7 1.97+7MAINM YANKEE 2008 682 1996 47 8.1867 1.8897 9.15,6 8.88,8 2.89.6 1.1386 3.85+7 1.95.7 1.03.7UCCUIRE 1 2021 96a 2005 54 4.59.7 1.57+7 5.84+6 1.39+7 8.21.8 8.34+5 5.98+7 1.89+7 8.47.8MCGUIRE 2 2023 989 2006 64 4.88,7 1.52+7 5.20,8 1.60+7 3.24.6 7.90.5 8.18+7 1.84+7 5.99+6MILLSTONE 1 2010 2480 1987 54 4.66.7 3.8667 2.96+7 1.98+7 9.68.8 5.2386 8.54.7 4.62+7 3.48,7

-, MILLSTONE 2 2015 828 1997 51 8.8987 1.96.7 1.02.7 1.30+7 4.2568 1.56+8 5.18.7 2.89.7 1.18.7, MILLSTONE 3 2025 541 2018 46 8.29.7 6.586+ 1.42.8 5.8836 8.49*5 1.48.5 3.83+7 7.43.6 1.57.6

MONTICELLO 2007 355 2004 48 2.88+7 1.0387 3.89.8 1.55.6 5.05+5 1.74+5 3.04,7 1.0987 4.086.NINE MILE PT 1 2005 884 1998 48 2.98.7 1.53+7 8.34.6 4.65,8 1.95.6 0.81.5 3.38+7 1.7387 9.20.8NINE MILE PT 2 2026 1971 2011 61 4.06*7 1.04*7 2.81.6 1.14+7 2.00+6 3.99+5 5.20,7 1.24.7 8.21.6

A NORTH ANNA 1 20918 186 1999 87 7.89*7 3.81+7 1.72.7 2.81.7 8.20.8 2.70+6 1.07.8 4.43.7 1.99.7A NORTH ANNA 2 2020 (a) 0.00.0A OCONEE 1 2013" 2102 1989 70 8.57.7 8.39+7 4.84.7 3.84.7 1,6857 8.11.6 1.24+. 9.04.7 5.65.7A OCONEE 2 2013 (a) 0.00.0

OCONEE 8 2014 1021 1991 65 4.77*7 8.23.7 2.22.7 2.08.7 8.26.8 3.75.6 6.85+7 4.06*7 2.8607OYSTER CRK 1 2004 912 1994 46 2.88.7 1.68.7 1.01.7 5.16.6 2.93.6 1.11.6 3.40+7 1.9147 1.12.7PALISADES 2011 835 1988 s0 3.84.7 8.01.7 2.38.7 1.64.7 7.52.8 3.92,6 6.48.7 3.76.7 2.77.7PALO VERDE 1 2024 1117 2005 64 4.88,7 1.80,7 5.75.6 1.8.+7 8.6868. 9.10.5 6.36+7 1.97.7 8.8868PALO VERDE 2 2025 1121 2006 64 4.89.7 1.63.7 5.23,8 1.69+7 3.49.8 8.30.5 6.38.7 1.88.7 6.06.6PALO VERDE 3 2026 1121 2007 54 4.89+7 1.45,7 4.7686 1.89.7 3.33.8 7.64.5 6.38.7 1.7897 5.51.6PEACHBOTTOM 2 2009 1812 1997 50 3.67+7 1.95+7 1.02,7 7.89.8 3.01.8 1.23+8 4.88.7 2.25.7 1.14.7PEACHBOTTOM 3 2008 1689 1997 49 3.69.7 1.82.7 9.46*6 7.2866 2.77,+ 1.13+8 4.32+7 2.10.7 1.08*7PERRY 1 2028 2548 2009 55 4.75*7 1.34+7 3.98.6 1.53+7 2.8686 6.06.5 6.28.7 1.63.7 4.59.6PILGRIM 1 20098 1512 1993 40 3.43.7 2.11.7 1.32.7 9.4086 3.99+6 1.84+8 4.37+7 2.51+7 1.50+7

A POINT BEACH 1 2007 849 1995 50 3.81+7 2.12.7 1.21.7 8.4686 3.48.8 1.53+6 4.6867 2.47.7 1.3867A POINT BEACH 2 2008 (a) 0.00.0A PRAIRIE ISL 1 2008 1142 1993 53 4.40.7 2.70,7 1.70,7 1.24+7 6.28.6 2.43.8 5.84.7 3.2387 1.94.7A PRAIRIE ISL 2 2008 •a) 0.00.0B QUAO'CITIES 1 2007 A08 2005 46 2.88.7 9.8486 8.64+8 1.0386 3.28+5 1.10.5 2.98+7 1.02+7 8.5.68B QUAD CITIES 2 2007 (a) 0.00.0

RANCHO SECO 1 2008 228 2004 46 2.86.7 1.03+7 8.89.8 2.07,8 8.67.5 2.21+5 3.09*7 1.10,7 4.11.8ROBINSON 2 2007 688 1990 49 3.52+7 2.50.7 1.81+7 1.10,7 6.17,6 2.6.+8 4.62+7 3.02,7 2.08.7RYR BEND I 2025 2462 2007 54 4.6867 1.44,7 4.78.6 1.59.7 3.20.8 7.34.5 6.25+7 1.76,7 5.4868SALEM 1 2016 1007 1997 54 4.71.7 2.88,7 1.24,7 1.70.7 5.45+6 1.9768 6.41.7 2.93.7 1.44.7SALEM 2 2020 1183 2001 57 5.19.7 2.16+7 9.33+6 1.88.7 4.9686 1.49.6 7.07.7 2.8667 1.08.7

Page 92: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A4a. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - VAULT OPTION(1983 DOLLARS) (contd)

ADD. YEAR C 0 S TISHUT)OWHISTORAG WHEN ICONSI. I .....PLANT NAME YEAR REQ'D ADD*L TIME CONSTRCTION I 8 S u TOTAL

(ASSEM- STOR. (MON.) ----------------------- I ------------------BLIES) NEEDED o% 61 I 1% I JI I 10 15% 11o

E SAN ONOFRE 1 1999 2382 1996 67 7.75.7 4.32.7 2.47+7 6.8360 2.88+6 1.47,6 8.33+7 4.81+7 2.62.7E SAN ONOFRE 2 2012 (a) 0.00.0E SAN ONOFRE 3 2013 0.00+0

SEABROOK 1 2031 1281 2008 58 6.60+7 1.82+7 5.08+0 2.41+7 4.18.6 8.81+5 7.91.7 2.04,7 6.94+8A SEQUOYAH 1 2021 2880 1995 78 1.80.8 6.89#7 3.37.7 6.10.7 1.57.7 6.72+8 1.57.8 7.48.7 3.94*7A SEQUOYAN 2 2022 (a) 0.00+0

SHOREHAM 2827 2036 2008 66 4.81.7 1.67.7 6.37.0 1.92+7 3.81+6 8.82+5 6.73*7 1.96,7 6.26*5SOUTH TEXAS 1 2027 268 2023 46 2.88+7 4.09.8 6.3865 2.07.0 2.00.6 3.62+4 3.09+7 4.3656 6.72.6

-SOUTH TEXAS 2 2028 268 2824 40 2.88+7 3.90#8 6.78+6 2.07+0 2.48+6 3.29+4 3.09+7 4.16+8 6.11.6ST LUCIE 1 2010 1182 1987 64 4.68+7 3.68*7 2.97+7 1.98.7 9.6706 6.23+8 6.64+7 4.62+7 3.49.7ST LUCIE 2 2023 1120 2001 63 4.43.7 1.84.7 7.97.8 1.64+7 4.67*6 1.32+6 6.27+7 2.30+7 9.29+6SUMMER 1 2024 761 2"8 61 3.98.7 1.19.7 3.67.6 1.18.7 2.37+6 6.3656 6.16+7 1.42+7 4.21+8

A SURRY 1 2012 97 2012 46 2.88+7 7.00+d 1.82.6 0.00+0 0.08+0 0.00+0 2.88+7 7.00.6 1.82.6A SURRY 2 2013 (a) 0.00+0B SUSQUEHANNA 1 2022 7288 2000 80 1.11+8 4.84+7 2.19.7 4.64.7 1.18.7 3.68.6 1.568+8 6.02.7 2.6657B SUSQUEHANNA 2 2024 (a) 0.00.0

THREE MILE ISL 1 2008 76 200 46 2.88+7 9.38.8 3.22+0 1.03*8 3.13.6 1.00.5 2.98.7 9.0906 3.32*8TROJAN 2011 373 2004 46 2.88.7 1.03+7 3.89+8 3.61.8 1.07.6 3.40+6 3.24.7 1.14,7 4.23+6

E TURKEY PT 3 2007 884 2002 46 2.8807 1.14+7 4.71.6 2.65*8 8.86*6 3.20+6 3.14+7 1.23+7 6.63+8E TURKEY PT 4 2007 (a) 0.00+0B VOOTLE 1 2027 2496 28" 76 9.94+7 3.24.7 1.11+7 3.87+7 7.69.8 1.78,6 1.38+8 4.01+7 1.29+78 VOOTLE 2 2028 (a) 0.00+0

VT YANKEE 1 2012 1088 1999 48 2.88.7 1.32.7 6.27+6 6.71.0 2.22.6 7.98+6 3.5657 1.64+7 7.07+6WASH NUCLEAR 2 2023 4018 1998 63 6.6087 3.20.7 1.69.7 3.1687 8.67*6 2.7650 9.82+7 4.00+7 1.87+7WATERFORD 3 2024 1143 200 66 4.74+7 1.64.7 6.29.8 1.62.7 a.42+6 8.23+6 6.38+7 1.88.7 6.11+8

A WATTS BAR 1 2026 2691 2W01 78 1.00.8 4.41.7 1.91.7 4.72.7 1.13.7 3.18.6 1.53.8 6.64.7 2.23.7A WATTS BAR 2 2027 (a) 0.00.0

WOLF CREEK 1 2025 867 2"08 62 4.27.7 1.26.7 3.94+8 1.3487 2.67+8 6.94,5 6.63,7 1.6587 4.65*6YANKEE-ROWE 1 2001 30 1999 48 2.88+7 1.32+7 6.27+0 1.03.0 4.40+6 1.96,6 2.98.7 1.36,7 6.47+8

A ZION 1 2008 1296 1995 68 5.61.7 3.12+7 1.79.7 1.39+7 6.60+6 2.42+6 7.00+7 3.6887 2.03+7A ZION 2 2000 (a) 0.000.

------------- ------------------------------------------------------------------------------------TOTAL 4.67.9 2.15.9 1.13.9 1.58.9 4.6868 1.70+8 0.25.9 2.62+9 1.38+9

ABE

INDICATES COMMON POOL SHARED BY TWO REACTORS& CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1

Page 93: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A4b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - VAULT OPTION

(1983 DOLLARS)

---------------------------------- aaaaaaaaaaaaaaaaaaaaaaaaaaaaaaa------------------ - -

AABB

AA

B

BBAA

ARK NUCLEAR 1ARK NUCLEAR 2BEAVER VALLEY 1BEAVER VALLEY 2BELLEFONTE 1BELLEFONTE 2BG ROCK 1BRAIDWOOD IBRAIDWOOD 2BROWNS FERRY 1BROWNS FgRRY2BROWNS FERRY 3BRUNSWICK 1

BRUNSWICK 2

BYRON IBYRON 2CALLAWAY 1CALVERT CLF 1CALVERT CLF 2CATAWBA 1CATAWBA 2CLINTON 1COMANCHE PK 1COMANCHE PK 2COOK 1COOK 2COOPER SThCRYSTAL RVR 3DAVIS-BESSE 1DIABLO CANYON 1DIABLO CANYON 2DRESDEN 1DRESDEN 2DRESDEN 3DUANE ARNOLDENRICO FERMI 2FARLEY 1FARLEY 2FITZPATRICKFORT CALHOUNFT ST VRAINGINNAGRAND GULF 1HADDAM NECKHARRIS 1

20•8201220162028202920302001202820272014201420172010

2010

2024202820242014201620252028202720302038020092009200820282017202520251984200892008201020252012201220162008200720062022200"2028

737973

1267129624042404

1754398

3153

3033

4413(a)

18832789

(a)228210

32802881

(a)2009

(a)1702648

2850772772

1647132515108459

7T8548

298883a

4115464

6310

(b)1989

(b)2000

20021991990

199819981995

(b)

(b)

1996

202120232000201020161991199119931999198820962006

1992199419911990199719991991

(b)

1994199219902026

5158S8B878784698

a6

5958

57

97

6278

46485877

a8

o060815151

494749785s485748

4876480

3.93+74.86575.65576.59*79.49+79.49+72.88.71.64.87 * 9*77.50+7

5.73.76.49+7

5.*30+7

1.55.6+

a.92+79.40+7

2.88+72.88+76.60.71.05+8

3.75+78.06.71.18*84.82+74.02+7

8.55+73.13+78.48+71.02+83.84+73.33+76.25+73.28+7

2.88+78.70+73.35,78.00.+

8.08+73.24+74.35+72.44+74.24+73.75+71.86+71.04+8

3.61+7

3.19.74.30+7

4.16.7

1.04,8

8.46+78.98.7

4.51284.09.82.44.72.82+7

I,.49*7

2.30.71.88+78.13*71.31+71.31*7

2.29+71.88.72.86+77.24+71.94+71.53+73 .55.72.58+7

1.68+75.81+72.38.70.0+00

2.44+72.45+78.45.71.11.7

1.81271.00÷7

31.2+7

3.29.7

7.14.7

1,•89.?1.99+7

5.25.7

7.70+58.88+61.11+78.02+6

3.78.7

1.46+77. 98+85.94+74.49+84.49+8

1. 50+71.10.71.62+75.23+71.01*77.25+62.46+72.M+7

1.01+73.89+71.72+70 .00+0

1.48671.88+72.97+72.77#74.99+74.98+7

4.865+81.07+8

2.28+7

2.41+72.80+7

2.22+7

1.07+8

3.47+74.93+7

2.07+61.55+62.89+73.90+7

2.7837

1.04.71.14+76.11+71.48+71.43+7

1.04+77.91+81.21+78.61+71.07+77.86.82.40+79.95+6

6.20+84.86.71.04+70.00,+

7.13.88.238+1.24.78.89+61.14+71.04*72.37.83.49÷7

7.37+6

8.02+81.08+7

1.04.7

3.87+7

9.80+61.96.7

2.87.62.00+56.83+86.50.6

1.20.7

4.41+68.48+6.2.56072.95+62.9568

4.54+83.27+85.21.62.20*78.73+82.61+69.85+686.17+8

2.69+61.81.74.8998

8.88+64.10+88.13+61.93+88.24+62.88+81.28+61.47+7

2.65+6

3.06+88.7*+6

1.79+7

3.34+89.92+8

4.38+42.04+41.95.61.27+6

9.81+.

2.03+61.18+81.23+77.01*57.01+6

2.18+81.46+62.48.69.84.81.438*69.37+54.20+62.91+6

1.23+68.48162. 51.8

5.30978.2B+78.52*78.38+71.44+81.44.83.85+72.81+8

9.78+7

8.14+77,79+7

7.52+7

2.62+8

9.99+71.39+8

3.09+78.04+78.49*71.44.8

1.08.8

4.79.74.80+71.74+86.45+76.46+7

4.59+73.92+74.69.71.88+84.91+74,12+77.85+74.23.7

8.50+71.86+84.89+7

3.79+74.08+75.69+78.11+75.28+74.79,72.10+71.69+9

4.86*7

8.99.76.88+7

5.19.7

1.438+

4.44+78.94+7

4.80+84.20+88.12+78.47+7

8.88.7

2.74+72.08+71.06*81.80+71.80+7

2.74+72.16+72.87.79.44+72.31+71.79+74.49+73.05+7

1.95+77.22+72.87+7

2.88372.88.74.08.71.30*72.20+71.82.71.35478.59+7

2.07+7

2.14.73.98+7

8.84+7

8.98.7

2.22476.24+7

8.14+58.04*51.31.79.29+8

4.38+7

1.65.79.14+67.17*76.19+65.19+8

1.72+71.25+71.87+76.18+71.15+78.19.82.87+72.29+7

1.18+74.34+71.97+7

0.000+ 0.0

Page 94: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A4b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO'LOW DENSITY RACK CONFIGURATION - VAULT OPTION(1983 DOLLARS)(cont'd)

-------------------------- m----- ------------- m--------------- m--------- m------ -- m----

ADD. YEARSHUTDOWN STORAGE WHEN CONS. - --------------------

PLANT NAME YEAR REQ'O ADDIL TIME CONSTRUCTION(ASSEU- STOR. (LMON.) ------------ m.-------.BLIES) NEEDED ox I 65 I 1x

-------------------------------- -- -.-.. ------.

C OST

a 8 . --- ---.TOTAL-.

I e0 I 65 I 105 0% I 55 I 10i

B HATCH 1B HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT 1INDIAN PT 2INDIAN PT aKEWAUNEELACROSSE

B LASALLE CTY 1B LASALLE CrY 2

LIMERICK 1LIMERICK 2MAINE YANKEEMCGUIRE IMCGUIRE 2MILLSTONE 1

co MILLSTONE 2D MILLSTONE 3

MONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE 1A OCONEE 2

OCONEE aOYSTER CRK 1PALISADESPALO VERDE 1PALO VERDE 2PALO VERDE 3P.ACHBOTTOM 2PEACHBOTTOM 3PERRY 1PILGRIM 1

A POINT BEACH 1A POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 2B QUAD CITIES 1B QUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR BEND 1SALEM 1SALEM 2

2009201220281978198020020162014200220222823202420292006202120232010201620262007200620282018202020132013201420042011202420262020200820082826208020072008200820082007200720082007202520162020

4860

901

9928e1301

11144(a)

49925116107013971421287212911046835

125225332461

(1)2841• (a)

1424103916271631103127242489344418ss1137

(6)1483

(a)640958

322014871667

199819962001

(b)199419931987

19881991

198719971998

200719981990208719921992

1989(b)1998

1997190819911991200319881990199019881988200220021992

(b)200119891992

6361

646047

182

68696280

6058so6648476478

77

6048636181616664606163

57

48

4953586164

8.7317 8.5727 1.9147

8.31.7 2.62,7 1.14.7

1.68+7 6.3868 2.83.8

3.01.7 7.04+6 1.98.6

88. 887 4.21.7 2.21.7

9.32.7 8.32+7 1.34+7

4.87.74.67+73.89.72.88.71.84.8

8.15.7

8.28.74.27.76.96578.04.76.01,76.10.74.83.72.88.73.08+74.71.71.01.8

3.43,72.73+72.28672.37+71.08,8

6.18676.80+73.44,73.01.7.2.90.73.93.74.00.71.60+71.30.72.18.71.48.70.6*57

2.71.71.64,71.42+71.97,77.28+7

4.72+73. 88.72.81+71.67+71.44+73.11,73.17+74.90+66.89+81.57.74.78.84.27*7

1.48+71.88#71.43.77.76.81.06+8

6.49+76.88.71.88.72.73+72.88.72.10+72.62.71.86.74.86588.29+81.70,74.86+7

7.64.88.83+86.36584.41+83.91+7

1.98+71.77,78.46+87.92,67.80.89.83+81.11+78.32.81.77.64.08.83.35,6.1.73+7

4.19.82.68.82.28+8

2.88+81.84.7

9.17+67.03+64.73.62.69.82.6*066.19.86.67*67.57.6

7.12.52.18.87.68+67.2658

6.86+76.63,76.12.73.68.72.89.8

1.38.81.42.86.96+78.68+78.92.77.11,77.72.76.48+7

8.89+76.41.71.60.8

4.18,73.39.72.80*72.81.71.47*8

8.14,77.37+74.29.7

3.68.74.91+76.11+71.83+71.57.72.69+7

1.80.78.23.7

1.05.8 7.64.7 5.68+7 4.88.7 2.1657 1.10.7 1.64.8 9.79+7

5.92+73.29.74.36576.13,78. 16*78. 16*7

4.94+74.64+76.89+73.90+74.61.7

4.64.72.46573.41.73.26*73.10.72. 98.73.34+73.14.72.22.73.08.73.20,7

3.87+71.88.72.70.71.78+71.62.71.47+72.38.72.16878.76+82.42+72.31,7

2.94.78.98.81.88.73.27+73.29+73.28*71.88.71.49.72.68.71.46,71.4657

1.27.74.83.88.86+89.24+88.82.80.48*67.17.86.70*66.71*87.07,68.82.8

8.43+82567.64.61.83.16.82.87+62.81.63.51+83.28.61.48.83.83+63.60+8

8.80+74.19.78.23.79.40879.43.79.43.7

6.13+78.47+76.56,76.98+7

S. 91.72.91.74.28+74.17.73.98*73.86074.08.73.81.72.79.73.77*73.88.7

3.13+71.91+71 • 65.72.24.79.12.7

5.84.74.68+73.28.71.64,71.69.73.8637a.73+76.86,67.60.6

1.79.76.64+66.00.7

8.76.7

4.31.72.12.73.16+72.10.71.91.71.73.72.65.72.49,71.02.72.80+72.68.7

3.79,7

5 .90.8

1.78,73 .10,71.•18,74.18,73.46.7

5.2657 4.12,7 3.28+7 2.80+7 9.78.6 6.30+8 7.26+7 6.10.7

3.37+7

8.83+74.32.75.62+78.27+76.91+7

1.34.7

2.34.73.38+72. 34+74.68.74.48.7

6.62.6

1.64.72.68.71.01,72.64*72.93+7

3.08.8

1.07.71.64+72.67.73.22.73.67+7

1.*60.

4.67+87.88.60.16581.36+71.28.7

3.81.5

2.22+64.21.+1.738.68.22.85.17+8

3.88+7

4.70.76.88.79.19.79.49,71.08,8

1.4657

2.81+74.16.72.98+75.98.76.72+7

Page 95: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A4b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - VAULT OPTION(1983 DOLLARS) (cont'd)

ADD. YEAR COSTSHUTDOWN STORAGE WHEN CONS.------------- m---------- -

PLANT NAME YEAR REq'D ADD'L TIME CONSTRUCTION I 0 8 TMT(ASSEII- STOR. (MION.) ---- 5Io - -e -- 5x------x0LS I S 10 I NEEDEI Dl I IlO

---------- -------- ------- ------ ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

E SAN ONOFRE 1 1999 8172 1989 76 1.01+0 7.41+7 5.52+7 1.87+7 1.09+7 6.49.8 1.20.8 8.49.7 6.17+7E SAN ONOFRE 2 2012 (a) 1989E SAN ONOFRE 3 2013 1989

SEABROOK 1 2031 1845 2 800 8.6.87 2.98+7 1.36+7 4.02#7 6.82+8 2.43+6 1.09.8 3.88.7 1.59+7A SEQUOYAH 1 2021 3400 1989 88 1.30+8 9.11+7 6.48+7 7.98+7 2.93+7 1.34+7 2.10.8 1.20+8 7.8247A SEQUOYAH 2 2022 (a) 1989

SHOREHAM 2627 8371 200 69 5.73+7 2.50.7 1.13+7 2.95+7 8.99+8 2.00+6 8.89+7 3.20+7 1.33+7SOUTH TEXAS 1 2027 570 2017 50 3.72+7 7.09+6 1.46+6 6.87+8 1.01#6 1.65+6 4.41.7 8.1086 1.63*6SOUTH TEXAS 2 2028 670 2018 60 3.70+7 6.71.6 1.82.6 6.83#8 9.66+5 1.49+5 4.38+7 7.67*6 1.47+6ST LUCIE 1 2010 1686 (b) 69 5.71+7 4.48+7 3.55+7 2.40+7 1.12+7 5.94+6 8.11.7 5.60.7 4.14.7ST LUCIE 2 2023 1558 1992 58 5.60+7 3.55+7 2.33+7 3.25+7 1.06+7 4.22+6 8.75+7 4.61+7 2.75+7SUMMER 1 2024 1169 1999 57 5.19+7" 2.38+7 1.13+7 2.47*7 8.38+6 1.95+8 7.86+7 3.02+7 1.83.7

A SURRY 1 2012 574 2005 48 3.39+7 1.16+7 4.17+8 4.33+6 1.22+6 8.70+6 3.82*7 1.28+7 4.54+6A SURRY 2 2013 (a) 2005B SUSQUEHANNA 1 2022 8680 1995 67 1.29+8 7.21+7 4.13+7 8.66+7 2.01+7 7.26+8 1.98+8 9.22+7 4.86+7B SUSqUEHANNA 2 2024 (a) 1995

THREE MILE SL I 2008 518 1997 48 3.20+7 1.62.7 8.42+6 6.37+8 2.43.6 9.91+5 8.84+7 1.86+7 9.41+8TROJAN 2011 861 1998 50 3.69+7 1.77+7 8.83+6 8.84+6 3.07+6 1.16+8 4.57.7 2.08.7 9.99+6

E TURKEY PT 8 2007 816 1995 52 4.14+7 2.31+7 1.32,7 9.29+6 3:82+8 1.6848 5.07+7 2.69,7 1.49+7E TURKEY PT 4 2007 (a) 1995B VOGTLE 1 2027 3251 2000 85 1.2658 5.48+7 2.47+7 8.39+7 1.51+7 4.32.6 1.89+8 6.97+7 2.90+7B VOOTLE 2 2028 (a) 2000

VT YANKEE 1 2012 1596 1993 49 3.62+7 2.22+7 1.4067 1.2867 4.94,6 2.1256 4.88.7 2.71+7 1.62+7WASH NUCLEAR 2 2028 4642 1994 68 7.57+7 4.48.7 2.65+7 4.14+7 1.26+7 4.88+6 1.17+8 5.89+7 3.12+7WATERFORD 8 2024 1671 1997 61 6.26+7 3.16+7 1.6567 8.22+7 8.82+6 2.90+6 9.48+7 4.04+7 1.94.7

A WATTS BAR 1 2025 8411 1994 88 1.31+8 7.65.7 4.58.7 7.78.7 2.27+7 8.29+8 2.08.8 9.92.7 5.41+7A WATTS BAR 2 2027 (a) 1994

WOLF CREEK 1 2025 1313 1999 59 5.67+7 2.680+7 1.23.7 2.81+7 7.13+6 2.16+6 8.48*7 8.31*7 1.45+7YANKEE-ROWE 1 2001 264 1990 48 2.88+7 2.05+7 1.48+7 5.88+6 3.05+6 1.72+8 3.46.7 2.36+7 1.66.7

A ZION 1 2008 1943 1988 67 7.94+7 8.03+7 4.8387 2.98.7 1.46#7 7.88+6 1.09+8 7.49+7 5.42.7A ZION 2 2008 (a) 1988-------- m -------- m -------------- ----------------- mm -.-- - 2.--------------------------------

TOTAL 5.81+9 3.45+9 2.23.9 2.62+9 8.99,8 3.87.8 8.43.9 4.85+9 2.62+9

Co

AsE

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

iINDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDI1CATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

Page 96: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREUENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - CASK STORAGE OPTION(1983 DOLLARS).

I ILOW DENPLANT NAME ITYPE IRACKSI

NEEDEDj

---------------------------------------------------------------------------------BEFORE CONVERSION I----I AFTER CONVERSION I INCREMENTAL COST

----------- RERACKINI ------------------------ Iex I 6% 1 lox I - I 0% I 6% 110% ex% I 6% 1 10%

--------- -------- I---------I------------I-----------M

ARK NUCLEAR 1ARK NUCLEAR 2BEAVER VALLEY 1BEAVER VALLEY 2BELLEFONTE 1BELLEFONTE 2BIG ROCK 1

A BRAIDWOOD IA BRAIDWOOD 2B BROWNS FERRY 1.B BROWNS FERRY 2

BROWNS FERRY 3BRUNSWICK 1

BRUNSWICK 2

A

A

BB

BBAA

BYRON 1BYRON 2CALLAWAY 1CALVERT CLF 1CALVERT CLF 2CATAWBA 1CATAWBA 2CLINTON 1COMANCHE PK 1COMANCHE PK 2COOK 1COOK 2COOPER SYNCRYSTAL RVR 3DAVIS-BESSE 1DIABLO CANYON 1DIABLO CANYON 2DRESDEN 1DRESDENJ 2DRESDEN 3DUANE ARNOLDENRICO FERMI 2FARLEY IFARLEY 2FITZPATRICKFORT CALHOUNFT ST VRAINGIN"GRAND GULF 1HADDAM NECKHARRIS 1

120136138140188188

40262(a)084(0)468370

376

284(a)108192(a)144144344198(a)268(a)232

72120

8586

3103162•0662138130380

902406463.104104

1.99.72.30+73.68+73.49+70.76+70.76+71.91+71.33+8

1.04+71.03+71.83+79.69+81.87+71.69#71.8+.7

0.75+7

6.68+.4.83+89.682.82.82+06.62+84.68+80.06+53.82+7

6.42+66.64+68.21+68.47+67.34+67.34.66.60+41.038+

3.18+7

4.03+74.94+78.92+78.92+71.96+71.6658

2.40.72.04.73.71+72.08+73.78+73.41#71.26571.05+.

1.87.71.96+72.89+79.28+01.88+71.39+78.12.87.46+7

1.26+71.43.71.43+71.61+72.24+72.24+74.38+62.38+7

1.42+71.60+71.94+71 . 19+71.97+71.79+71.88+63.89+7

4.71+7 1.86+7 7.68*6

3.64+7a.88+70.090.3.07+70.00+01.33+8

1.67+7 .68+802.88+7 1.89+7

2.41+7 1.64+7

7.44.7 4.38+.

1.32+8 8.64+7 3.11.7 1.63+7 1.98+7 1.39+7 9.04+8

9.02.6 6.01.7 2.72+7 1.63+7 1.2807 1.24+7 9.653+87.69+6 4.78+7 3.8657 2.86+? 1.00+7 1.08+7 1.03.7

7.62+6 4.80+7 3.61+7 2.74+7 1.01+7 1.17+7 1.18.7

1.07+8 1.6658 1.18.8 9.06+7 2.36+7 4.24+7 4.78+7

7.13.6 6.82+7 2.98+7 1.60+7 1.69.7 1.06+7 1.17+77.1806 8.77+7 8.87+7 6.21+7 2.08.7 2.48+7 2.61.7

2.38.71.63#71.97+77.11+82.20+71.00+72.13+83.94.7

I

4.20.7 1.40+7 4.97+08.76+7 4.28+7 2.77+7

0.00.00.00+04.06+77.42+7

0.00+00.090+1 * 26.1.28+71.64+7

0.00+00.00+04.32.03.45+8

8.42+6S. 94.68.99+68.70+6

1.89.71.88.74.96871.0•.8

2.98+62.67*82.08+72.02.7

6.03+64.14+69.30.87.39+8

1.96.71.94+79.72+82.88+7

3.86083.26+88.71+81.17+7

1.16-61.01+86.87+84.82+8

4.63+7 2.16+7 1.07+7 A k12+8 7.17+7 4.77+7 3.26+7 2.76+7 2.72+7 2.30+7

2.29+71.98+79.65+72.33+72.33+70.00+61 . 98+71.94+71.97+77.91-71.91+71.89+73.64+71.97+70.80+01.91+70.32.71.98+70.00.00.00.0

1.09+78.68+866.18+76.80+66.88+9

9.32+08.40+80.92+83.87.70.90+06.68+81.07971.14+7

8.32.02.96+79.79+8

6.68+82.37+82.92+71.68+81.68+8

4.680+83.78.84.18.+1.99+72.12+61.74+69.20+08.74+8

3.70+81.46.76.06.8

4.90.63.34+66.48+63.89+63.89+6

0.12+68.12+66.30+61.08+88.13.68.13+67.30.68.19.5

2.32*61.04+84.19+64.76+6

2.91+72.84+71.13+83.27+73.27+7

2.71.72.26572.68+71.00.83.02+72.46,74.69+72.40.7

1 . 99+78.03+72.61+7

1.74+71.28+78. 66#71.03+71.03+7

1.70+71.29+71.74+78.78,71.49+71.10+7a.01+71.82+7

1.14+74.99+71.73+7

1.08+76.90+86.05.73.48+83.48.8

1.10.77.69+81.18+74.78+77.86+86.14+82.04+71.41+7

6.76+63.23+71.23+7

7.62.68.91+01.9.+79.83.09.83+.

8.04+83.76+87.88+82.28+71.17+7a. 18*61.03+74.64+6

9.69+61.82+7

6.91+8

0.90+06.31+83.44.74.89.84.89.8

8.27+06.07+89.08+03.00.?9.27+00.02+81.29+77.*10.8

a .34+62.13+77.92+0

6.66+83.87+83 .78+72.31+82.31+.

0.98+84.42.88.19+82.90.76.14+04.02.81.19+77.04+6

3.2*281.88+77.02+8

Page 97: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - CASK STORAGE OPTION(g983 DOLLARS)(cont'd)

-------------------------------------------------------- M ----------- M ---- mm ----------- m- --- mm --- m ----------

ILOW DEN BEFORE CONVERSIONPLANT NAME TYPEI RACKS I----- - ----

NEEDEDI 60 lox..... I -- -I--

AFTER CONVERSION ! INCREMENTAL COST--- I ^NAILKI4 I .----------- I ---------- ---------

I I 5% 11lo I 0x 1 6% 1 10%-------I----------------- - ---------------------

|

B HATCH 1B HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT 1INDIAN PT 2INDIAN PT 3KEWAUNEELACROSSE

B LASALLE CTY 1B LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEMCGUIRE 1MCGUIRE 2MILLSTONE 1

oo MILLSTONE 2MILLSTONE 3MONTICELLO

* NINE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE 1A OCONEE 2

OCONEE 3OYSTER CRK 1PALISADESPALO VERDE 1PALO VERDE 2PALO VERDE 3PEACHBOTTOM 2PEACHBOTTOM 3PERRY 1PILGRIM 1

A POINT BEACH 1A POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 2B QUAD CITIES 1B qUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR BENM 1SALEM 1SALEM 2

588(a)464

138152

7448

680(a)448440146144144198156188240184276195

(-)1S0(m)120256868170170178468440448192

96(a)120(-)480(-)138

98384180168

4.28.7 1.85.7 8.34+6 1.14+6 5.78+7

9.22+6 5.58+7

3.04+7 1.85.7 1.63+7

2.25.7 9.61.6 1.31+7

1.30+.7 9.31.6

1.02.7 8.27.84.*3678.00.00.00•02.20+72.36.72.19.71.98.71.61.8

8.10+78.28+72.26+73.82+73.91,73.89+73.09+72.35.71.88+71.95.73.24+78.97+7

1.31.7 4.2.68

1.26.78.33+89.78+61.25+71.03+8

3.28*72.91.71.17+71.27*71.24.73.09+71.62+7

4.84.86.74+61.02*78.10+83.14+7

7.48.83.11.84.57.88.14.67.30.7

1.85.71.42+78.36*64.64.64.21.62.62.77.77+89.92*52.636*85.64+62. 18.81.40.7

8.01*56.77.5

2.84+66.68.4

1.27.6

8.93+68.73+56.25.68.42.56.42.64.05.56 *13.57.45.54.89+53.80.56.71.58.91.5

3.63+73.97+72.93.72.02.71.57+8

7.54+77.71+73.6.575.24+76.33+74.33+74.50+74.09.71.95+72.20+73.99.79.81.7

2.77*72.25*71.72.71.82.71.19.8

6.63*74.96*72.83*72.57*72.49*73.29*73. 38*71.24.79.29*81.52.71.21.78.00.7

2.16.71.32.71.08,71.32.79.31.7

4.39+73.36*72.31.71.32.71.22.72.57*72.82+74.00+84.69.61.08.73.90.83.89+7

1.49.71.68.77.8688.77+56.78.8

1.53+71.52.71.38.71.49+71.48.74.84,61.46.71.81+71.22+82.90.88.07+62.74+7

1.67+71.49.77.73*8S.80.81.77+7

2.44+72.14.71.71.71.36.71.31+72.49+6

1.92+78.64.83.04+85.38+64.53.62.96+7

1.47+71.09878.29m65.18+62.14,7

2.83.72.02.71.73+79.36+88.65689.06.51.91+73.78*82.65*66.64.62.29.82.50+7

7.78.7 5.85.7 4.22.7 8.01.5 1.01.8 7.69+7 8.01.7 2.44.7 2.1227 1.87.7

4.11+71.96+73.12.73.96+73.98+73.9a+72.98+72.6987

4.0•*72.58.72.93+7

2.69+71.14.72.34.71.32.71.26.71.20+71.49.71.34.71.10+71.54.71.81+7

1.82.76.72+61.81.74.86884.25683.87867.68868.91.63.24.89.54.89.10+8

5.42+56.11-62.70.58.74+58.74.58.74.5

9.02+58.73.58.93.63.97.53.84.5

6.24+72.42.73.88+75.46*75.47+75.47+74.19.78.*88.7

6.17.73.15.73.7657

3.97+71.76872.77+72.80.72.67*72.154.72.77+72.57.71.89.72.38872.61,7

3.10.71.32-72.16.71.50+71.37.71.24.71.90#71.75.77.37+81.86.71.8687

1.e18.75.11286.86+61.68+71.58.71.58e71.30+71.28.71.25.76.14.68.54.6

1.34,76.80+84.51#61.64+71.48.71.41.71.37,71.32.78.87+88.84+61.03+7

1.34*76.97.63.89.61.10,71.01+79.24.61.22.71.14.75.03.69.33+89.87.8

3.81+7 2.17+7 1.35.7 4.31.5 4.63.7 3.48+7 2.71.7

1.8687 8.38+8 2.30+8 9.21.5 2.38.7 9.37+6 3.86.6

9.83+8 1.33,7 1.40+7

6.06.6 3.92+6 2.49+6

1.89.72.70.73.92.73.99+74.46*7.

6.78,81.8+.71.18,71.98+71.81.7

2.54+61.32+73.83.61.01+77.74.8

8.19.64.00+57.81.67.11.67.45.5

2.80.73.58.74.94+75.67.76O.1*7

1.78672.72.71.99,74.02.73.85.7

1.14.72.13,78.49+63.00+72.60+7

9.710+69.23.81.10+71.65+71.*0.7

1.14.78.98.68.88.82.13.72.11,7

9.45+88.49+66.43.62.06.71.80.7

Page 98: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - CASK STORAGE OPTION(1983 DOLLARS)(cont'd)

---------------------------------------------------------------------------------------------------------------PLOW DEN, I EI

PLANT NAME TYPE RACKS __!----------RION------ RERACKINO--------- TE-CNE!!-------

I I--- -- I --- -- --- --- -- --- -- -- ---- - - -

INCREUENTAL COST

a% SI 5 lox0

2.7657 3.27.7 3.16+7

1.40.7 1.28.7 7.8183.39*7 4.23.7 4.16.7

E SAN ONOFRE 1E SAN ONOFRE 2E SAN ONOFRE 3

SEABROOK 1A SEQUOYAH IA SEQUOYAH 2

SHOREiHA•SOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE IST LUCIE 2SUMMER 1

A SURRY IA SURRY 2a SUSQUEHANNA IB SUSQUEHANNA 2

THREE MILE ISL9 TROJAN

E TURKEY PT 3E TURKEY PT 4B VOOTLE 1B VOOTLE'2

VT YANKEE 1WASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK 1YANKEE-ROWE 1

A ZION IA ZION 2

PPPPPPB

PPP

P

IPPBB

iPP

PPPP

PP

p

270

128240

104104162144138159(a)

(a)146

96144(a)252(a)284312178240(a)162

78218(a)

8.68+7 3.86+7

4.80+7 1.38871.03.8 6.64+7

4.12271.89+71.89+73.90+73.76+73.17+71.84.7

1.30.72.686.2.66+63.09.71.60.79.16-84.48+6

1.09+8 4.6127

2.09+7

4.26+63.12.7

4.40+84.16+63.78+62.62+76.38+62.82.61.16.6

2.06.7

2.08+62.67+63.10+6

1.01.7

4.20+61.36+74.82.61.77+7

3.11-64.06.61.49+7

7.38066.61+65.46+66.62,66.25+57.056+7.08+5

6.08+72.81.72.79*74.99+74.92.74.66+72.43.7

2.14.75. 29*86.80*63.81+73.03+72.06.78.23.8

9.64+61.07+89.73,52.98.71.96.79.38+82.94.6

1.04+79.79+89.59.61.15.71.23.71.43.76.568+

9.16583.1.8*3.00867.71.61.68+71.15.74.4658

6.67*61.21+81.14+a6.16+61.37*77.17+62.49+6

9.68*6 9.23+7 6.84.7 6.16+7

6.74+6 6.16.7 2.6587 1.16.71.06.6 1.36.8 9.66+7 7.17.7

1.31+6 1.33.8 7.14+7 4.02.7 2.49.7 2.68.7 2.08+7

1.88.71.93+71.90+7

6.07+66.87+07.61+6

6.64.64.37.66.39+6

2.29.72.82+73.29+7

1.14.71.33+71.80.7

6.88+68.54.61.02.7

4.86889.34.61.4657

5.93+68.91.81.12.7

4.43.84.41.87.78.8

9.31.7 2.98.7 1.11.6 1.28.8 6.38+7 2.40+7 3.82.7 2.63.7 1.60.7

2.00.75.9*+74.01.71.03+8

3.50+71.88.74.77+7

8.98.62.76571.28+74.16+7

1.01.72.66362.83+7

6.65866.39+66.98+61.8+8.

6.77.61.88+69.64.6

2.83-70.83+76.67.71.38.8

6.01+71.97+77.04.7

1.68+73.88+72.72.77.69+7

2.22+71.38+76.41+7

1.03.72.27*71.40.74.47+7

1.04.79.87.64.24.7

8.85+69.97*81.63.7a.47+7

1.67+71.28+62.38.7

8.33861.17+71.62173.6657

1.27+76.46+82.88+7

6.68+89.86+81.03+72.01+7

7.96.86.00.62.84.7

--- ------------------- ----------------------------------------------------------------------------TOTAL 3.98+9 1.79.9 9.37+8 6.6507 6.17.9 3.0659 2.00+9 1.30.9 1.32.9 1.1839

ABE

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT I

Page 99: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE AS*. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - CASK OPTION(1983 DOLLARS)

---- --- --- --- --- --- --- ---- --- --- --- --- --- --- ---- --- --- --- --- --- --- ---- --- --- --- --- -- m - ---

ADD. YEARSHUTDOWN STORAGE WHEN CONS.

PLANT NAME YEAR REQ'D ADDIL TIME(ASSEM- STOR. (MON.)BLIES) NEEDED

---- I.--COST... I"$M -- -- -- -

CONSTRUCTION -I_ -I TOTAL"-% ---- --- ---

I % 110% 1s0% 1 6% 11lo-------------

ARK NUCLEAR 1ARK NUCLEAR 2BEAVER VALLEY 1BEAVER VALLEY 2BELLEFONTE 1BELLEFONTE 2BIG ROCK 1

A BRAIDWOOD 1A BRAIDWOOD 28 BROWNS FERRY 1B BROWNS FERRY 2

BROWNS FERRY 3BRUNSWICK 1

BRUNSWICK 2

A BYRON 1A BYRON 2

CALLAWAY ICo B CALVERT CLF 1UT B CALVERT CLF 2

CATAWBA 1CATAWBA 2CLINTON 1

8 COMANCHE PK 1B COMANCHE PK 2A COOK 1A COOK 2

COOPER STmCRYSTAL RVR 3DAVIS-BESSE 1DIABLO CANYON 1DIABLO CANYON 2DRESDEN 1DRESDEN 2DRESDEN 8DUANE ARNOLDENRICO FERMI 2FARLEY 1FARLEY 2FITZPATRICKFORT CALHOUNFT ST VRAINGINNAGRAND OULF 1HADDAM NECKHARRIS 1

2008201220182026202820302001202820272014201420172010

2010

2024202620242014201820252028202728302030200920092008201820172025202519842008200820102025201220122015200820072008202220072028

377565853

85919001900

953827

(a)32282441

2401

2281

3827(a)11292213

(a)00

26722067

(a)1241

(a)1238.432

2490517617

01815693998

5355298140

2248413

2194392

319a

19981999199620092009201119951998

2002

20011990

1991

1994

20051992

2025202820062015

1998

19972005199520112011

19982000199919972006200819971994

2000199819972026

3939404043433947

41

4040

40

47

4043

00

4043

41

3939453939

3939394339394039

3942390

1.84+72.13+73.28+73.24+78.43+78.43+71.84+71.21+8

4.54,7

3.60.73.56+7

3.89.7

1.21.8

3.92.78.39.7

0.060.0.00+03.75+77.14.7

4.37+7

2.08+7

8.93+72.14+72.14.7

1.84.71.84+71.84+77.38.71.84+71.84.73.37.71 *84.7

1.84+75.94+71.84+70.00+0

9.78+69.74+61.73+79.12+81.81+71.84+71.03.78.43,7

1.80.7

1 . 60.72.53+7

2.29.7

7.09+7

1.34.74.12+7

0.00.00.00+01.22+7

1 • 50,72 • 10.71.60+7

2.18+7

1.04+76.31+64.97+75.47.65.47+6

8.87.88.05+868.46.83.72+78.00.65.45681.70.71.08.7

8.05+862.86+79.31+60.00+0

5.34+84.83+69.45.82.72+85.40+84.48+86.88+63.51+7

7.42.8

8.47+81.83+7

1.68.7

4.25+7

4.82+62.71+7

0.00+00.00+04.18+83.38+8

1.05+7

6.44+62.27+82.85+71.49+81.49+6

4.42+63.865+64.01+61.94+72.086+81.70+8

8.46+6.

3.85+61.42+74.86+86.60+6

1.47,81.71,82.96+82.61+63.17.63.17,87.33+61.18.7

1.74+6

2.37+82.90+8

2.81,8

1.18.7

2.79.83.8568

0.00,80.00+03.10+82.81+6

1.60+8

1.43.81.34+85.70+61.86581.85,8

1.22+89.78.51. 34+86.48+87.33+64.89.62.67+81.34+8

7.33.53.75+61.22+60.00,0

5.74.56.67+59.78+54.69+55.67.55.14+63.45.5S 8.168

6.10+6

8.88+51.31+8

1.21+8

3.48*6

8.07+51.41.8

0.00+00.*00.06.186+54.08+5

5.82+5

5.465+3.47+61.90+63.34+53.34.5

4.64+5

3.45.54.86+61.47+82.02+51.28+68.74.56.94+5

2.71.51.04.64.77+60.00+0

2.41+52.04+63.85+59.98+41.17+59.67+41.70+61.08+8

1.62+5

2.08+68.47+6

5.78+6

1.28+6

1.51+68.17.5

0.*00+00.00+01.43+58.75.4

2.26+5

2.22+59.78+47.24+56.76+48.76+4

1.80+51.29+51.73+54.78+5

*.94+4

3 .58+43.20+52.78+5

1.05+53.386+51.98+50.00+0

1.99+72. 0+73.56+73.49+76.76+76.75+71.91+71.33+80.00+04.71+70.80003.84+73. 86,70.00+03.67+70.00,01.33+80.00+04.20+78.76+70.00,00.00+00.00+04.68.77.42+70.00+04.63.70.00+02.20+71.98+79.50+72.33+72.33+70.00+01.96+71.94.71.97.77.91+71.91+71.89+73.84+71.97+70.00+01.91,76.32+71.98+70.00.00.00+0

1.04+71.03+71.83+79.59+61.87+71.89+7

1.85+7

1.67+72.68+7

2.41.7

7.44+7

1.40+74.26a7

0.00+00.00+01.28.71.54+7

2.16,7

1.09+78.68+85.18+75.80889.00+6

9.32+68.40+68.92+83.87+78.20+65.68+81.79.71.14+7

8.32+a2.96+79.79,8

5.68,84.*3+89.82+82.82.85.52*84.68+88.065.3.82+7

7.58+8

68.88+81.89+7

1.84+7

4.38+7

4.97*82.77+7

0.00+00.00+04.32+83.46+8

1.07.7

5.88.82.37+62.92*71.58+61.56,8

4.60+83.78.84.18+81.99+72.12281.74+69.20+86.74+6

3.78*61.46575.068+

Page 100: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

v

TABLE ASs. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - CASK OPTION(1983 DOLLARS) (cont'd)

ADD . YEAR COSTSHUTDOWN STORAGE WHEN CONS. I I

PLANT NAME YEAR REQ80 ADDOL TIME CONSTRUCTION . 0 S U TOTAL(ASSEM- STOR. (MON.) ----- I-- ---... .. - -- - -- I-- - - -- -- - - -- - --- - - -BLIES)NEEDED e. 1..% .10 l- 16% -10- I e. 1.6% lox

B HATCH 1B HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT 1INDIAN PT 2INDIAN PT 3KEWAUNEELACROSSE

B LASALLE CTY 18 LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEUCGUIRE 1MCGUIRE 2MILLSTONE 1

co MILLSTONE 2o• MILLSTONE 3

MONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE 1A OCONEE 2

OCONEE 3OYSTER CRK 1PALISADESPALO VERDE 1PALO VERDE 2PALO VERDE 3PEACHBOTTOM 2PEACHBOTTOM 3PERRY IPILGRIM 1

A POINT BEACH 1A POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 2B QUAD CITIES 1B QUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR 8N 1SALEM 1SALEM 2

2009201220261976198020982016201420022822202320242029200S202120232010201620262007200520282018202020132013201420042011202420262028200820082026208S20072008208D20082007200720082007202620182020

2874(a)

282000

49336o

679206

9824(a)

40964238632966989

2480623$41365884

19711886

(a)2102

(a)1921

912a35

1117112111211812168926481612

849(a)1142

(a(a)228888

246210071168

20"

2007

199420041999

19921990

199619981998200520919871997201620"4199820111099

1089

1991199419882005208200719971997200919931996

1993

2086

20041990200719972001

41

41

3939s93948

424239404040403939394043

43

403939494040-3939403939

40

39

3939404041

4.13.7 1.80.7 8.17,6 1.32+6

4.08.7 1.28.7 4.14.8 2.78+8

4.64+6

6.49,6

2.04.72.21,72.00,71.84.71.39+8

6.88+76.80+72.10+78.68+73.88+73.66572.83+72.23.71.84.71.84+73.02+78.84+7

1.19,77.93+09.17.81.19+79.86.7

3.16+72.79+71.11+71.22-71.19+72.92+71.43,74.46#06.82+89.78+87.71.83.04+7

7.16+82.99.84.906+

7.62+87.11.7

1.80.71.39.78.09+64.*40*64.08.62.43+77.46+89.69+62.49.66.34+62.10.81.46.7

1.66J 8 6.69+61.47.8 4.00.61.92.6 8.08+61.228 6.08.861.23+7 4.33.6

4.40+6 1.28.84.77+6 1.16+01.67.8 6.16852.37.8 6.48+62.61+8 6.43+63.40+6 1.64#82.62+6 8.69*.1.21+6 1.91-63.67.6 1.19.61.10.6 4.81.62.21.8 3.89.63.27.8 9.64.5

4.63.6 1.99.6

3.39*6 1.36+01.22.6 6.62+63.33+0 1.63+82.81.6 6.11.52.81+8 6.81#62.81.8 6.64+61.6806 6.10+61.65+6 6.93+62.61.6 4.68862.07.8 8.79+61.74+8 7.14.6

2.22+8 9.44+5

1.67.6

1.24+6

3.68*61.18+62.12+63.18+61.89.8

4.63,53.49+62.69.61.42.61.32+58.98+63.14.63.34.44.11.42.04*67.76543.14.6

9.78+6

8.11.62.83*68.00.61.62#61.38-61.26+62.49.62.42+69.93,44.06,63.14.6

4.34+6

2.81+4

6.24+46.78+61.23.53.26*52.20+6

4.26.70.00+04.38.70.00.80.60+02.20*72.38+72.19.71.98+71.61+80.00.08.10.78.29+72.28+73.82.73.91+73.89+73.09-72.36+71.88,71.95.73.24.76.97.70.00.07.76870.00+04.11.71.96073.12.73.96.73.98+73.98.72.98+72.69.74.0a.72.68+72.93+7

3.81.70.00+01.88+70.00.01.89.72.70+73.92.73.99+74.46+7

1.8657

1.31.7

1.28+78.33+89.78+81.26+71.03.8

3.28.72.91.71.17,71.27+71.24.73.08,71.62.74.64+86.74.81.02.78.10+83.14.7

6.8667

2.69.71.14.72.34.71.32.71.28.71.20+71.49.71.34.71.10*71.64+71.61+7

2.17+7

6.38.6

6.78.81.88.71.18.71.96.71.81.7

8.34.8

4.26+6

7.48.63.11+84.67.88.14.67.30+7

1.86571.42.76.36+04.64+64.21.62.62.77.77+69.92.62.63.86.64+62. 18.61.48.7

4.22.7

1.82+78.72+61.81.74.68.64.26+83.87.87.68*868.91.63.24*69.64+69.19+8

1.3657

2.30+6

2.64.81.32+73.83.61.01.77.74+8

7.30+7 6.45+7 4.12.7

3.77.71.84+72.79.73.87.73.68.73.68872.82.72.63.73.76572.37+72.78.7

2.66+71.08.72.19.71.26871.20.71.14+71.43+71.28.71.06571.46571.64+7

1.76.78.48681.73.74.61.84.11.63.74+67.43+6.6.67.63.14.69.13+68.79+4

a.39+7 2.08.7 1.31+7

1.84.7

1.84.72.46873.85+73.71.74.18.7

6.30.8

8.62+01.76571.13+71.87+71.74+7

2.27+6 2.44+6

2.49+61.28+73.71.89.77+67.62+0

4.89.62.38+82.68+62.81262.78+0

7.77,4

1.68+61. 12.86.90+69.01.67.34.6

Page 101: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE ASa. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - CASK OPTION(1992 DOLLARS)(contId)

----------------------------------------------------------------------------------------------------------------------

co

E SAN ONOFRE 1E SAN ONOFRE 2E SAN ONOFRE 8

SEABROOK 1A SEQUOYAH 1A SEQUOYAH 2

SHOREHAMSOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE 1ST LUCIE 2SUtMER 1

A SURRY 1A SURRY 2B SUSQUEHAINA 18 SUSQUEHANNA 2

THREE MILE ISLTROJAN

E TURKEY PT 3E TURKEY PT 4B VOGTLE 1B VOCTLE 2

VT YANKEE 1WASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK IYANKEE-ROWE 1

A ZION 1A ZION 2

TOTAL

1999201220182031202120222027202720282021202320242012201320222024

1 2008201120072007202720282012202832024202520272025200120082008

2382

128126802588

25825O11821128

78197

(a)7288

(a)75r

873384(a)

2495(a)10888

401811432691

(a)85736

1295(a)

20081995

20082028320241987200I20082012

2000

200620042002

2006

1999199820082001

200819991995

4145

40393940404039

45

393939

44

39424045

403941

4.47+79.53.7

3.81+71.84+71.84+73.58+73.42+72.94+71.84+7

1.02+8

1.84.71.84+71.84+7

8.778.7

1.84.75.52+73.74+79.57+7

3.25+71.84+74.58.7

1.32+75.31*7

1.24+72.82+82.49+82.93+71.42+78.89+14.48.8

4.43+7

8.62.67.30.8

2.8a+7

8.45682.85+71.22.73.99*7

9.81+68.45+62.55.7

4.13.83.04.7

4.28+64.07*53.70+52.43+78a. 15.82.71+81.18+8

2.01+7

2.08+82.49+83.02+8

9.81.8

4.01+61.32.74.18.81.72+7

3.00.+4.01+81.46+7

3.3"+7.43+6

3.108+4.89+54. 89+53.40*83.26*62.34+80.00.0

8.90.8

2.44+58.56856.11+5

5.380+8

1.59+63.75+82.688+8.90+8

2.62+62.44+51.89+8

5.79.52.29.8

8.15.58.18+456.86.41.64+88.10+54.89+66.00+0

1. 80.8

7.40+42.54+52.09+5

1.05+8

5.28.51.02+65.82.51.85.8

4.93+51.04+57.80+5

1.19+59.34+5

1.42+58.58+37.78.38.98+62.34.51.08650.00+0

5.44+5

2.37+48.04+47.68+4

2.44*5

1.89+53.28#61.35.54.85+5

1.10+54.62#43.29+5

1995 43 8.51.7 3.83+7 2.07.7 8.75.5 3.33+5 1.79.5 6.58+76.00.00.*00.04.80.71.03+80.00+04.12+7I. 89+71.89+7

3.90+.73.76+73.17+71.•84.7

1.09.80.00+01.88+81.• 8+71.93+71.90+70.*00+09.31+76.00+62.00+75.90+74.01+71.03+80.00+08.50+71.86+74.77+70.00+0

3.93+9

3.66.7

1.39.75.54,7

1.30.*72.69+62.66563.09.71.50+79.15+84.48.6

4.61.7

8.07+86.87+67.51+6

2.98+7

8.98+62.75+71.29-074.15+7

1.01.78.55+62.63+7

2.019+7

4.25.63.12+7

4.40+84.16+53.78.52.62#78.38+82.82+81.16+8

2.08.7

2.088+62.57+8

1.01.7

4.20861.35.74.32.81.77+7

3.51+84.06+81.49+7

3.88*9 1.72.9 9.09+8 2.49+8 7.44+7 2.75+7 1.79.9 9.37+8

A INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEB INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEE INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1

Page 102: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A6b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - CASK OPTION(1983 DOLLARS) (cont'd)

-- -- -- -- -- -- -- -- -- -- -- -- -- - -- -- -- -- -- -- -- -- -- -- -- -- - -- -- -- -- -- -- -- -- -- -- -- -- -

ADD. YEARSHUTDOWN STORAGE WHEN CONS.

PLANT NAME YEAR REQ'D ADD'L TIME(ASSEU- STOR. (MON.)BLIES) NEEDED

--------- -------- ------- ------ ------

COST

CONSTRUCTION 0S a TOTAL

-- -s6 110% --- x - 1-1-0i -

013

E SAN ONOFRE 1E SAN ONOFRE-2E SAN ONOFRE 3

SEABROOK 1A SEQUOYAH 1A SEqUoYAH 2

SHOREHAMiSOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE 1ST LUCIE 2SUMMER 1

A SURRY 1A SURRY 2B SUSqUEHANNA 1B SUSQUEHANNA 2

THREE MILE ISLTROJAN

E TURKEY PT 3E TURKEY PT 4B VOGTLE 1B VOOTLE 2

VT YANKEE 1WASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK IYANKEE-ROWE 1

A ZION 1A ZION 2

TOTAL

1999201220132031202120222027202720282010202320242012201320222024

1 200820112007200720272028201220232024202620272026200120082008

8172

16468400

(a)3371670670

183816681189

674(a)

86880(a)613681816(a)

3251(a)

1690484218713411

(a)1813

2641943

(a)

1989198919892001989198920020172018(b)19921999200620061995199619971998199619952"0200199319941997199419941999199019881988

45 8.97+7 8.69+7 6.00+7 2.61.6 1.50.8

4247

41393941414139

47

393940

48

39434247

413943

6.88+71.238.

4.69.72.87.72.65.74.87.74.47.74.18.72.33+7

1.22.8

2.14.72.68373.11+7

1.18+8

2.66+76.36+76.17+71.24+8

4.83+71.84+78.28*7

2.48+79.20.7

2.06.76.08+8

3.68672.88.71.91+77.96+6

8.82+7

1.08.71.27+71.78.7

6.14.7

1.67,78.71,72.81.77.23+7

2.12.71.31+76.24+7

1.12+78.98+7

9.27.61.04.89.42+62.90.71.90.79.09+82.88+6

3.90.7

6.83.86.*3069.92.6

2.33+7

9.87+62.22*72.*38+74.84.7

1.01+79.48+04.16.7

4.71.61.28.7

3.92.61.43.81.43.63.20+64.61.63.86+69.6806

1.06+7

1.46+61.68+81.77.6

1.02.7

2.69+64.78+83.97+81.22.7

3.78.61.34.63.47+8

1.03.64.8363

9.29.52.11+62.00+51.65061.48.69.44+62.71+5

8.19.6

6.64+66.48+67.28+5

2.42+8

1.06+81.46.61.09.63.69+6

9.67.6

7.21+61.708.6

2.86562.11.6

2.88+63.46543.18+47.92,56.86+62.89+68.20*4

1.16.6

2.26+.2.43*63.22,6

6.91.6

4.57+66.41.53.67+61.31-6

2.90+64.07.69.18-6

6.15.71.36.8

6.08.72.81.72.79+74.99+74.92.74.66572.43.7

1.33.8

2.29+72.82.78.29+7

1.28.8

2.*83.76.83+76.67+71.36.8

6.61.71.97+77.04+7

2.68#79.6887

2.14.76.29.86.00.88.81+73.03.72.00.78.23.6

7.14.7

1.14.71.33.71.80.7

6.38.7

1.68.73.86.?2.72+77.69.7

2.22+71.38.76.41+7

9.04+6 9.23+7 8.84+7 6.16+7

1.16.77.17.7

9.64+61.07.89.73+82.98.71.96879.38+62.94+0

4.02.7

5.88.66.4+*61.02+7

2.40.7

1.03.72.27.71.40-74.47+7

1.04+79.87+64.24+7

------------------------------------------------------------------------------------------------------4.79+9 2.92+9 1.94.9 8.78+8 1.381+ 5.67,7 6.17.9 3.0659 2.00.9

ABE

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COUBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS CONNECTED BY TRANSFER CANALs CAPACITIES AND INVENTORIES ARE COMKINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS REqUIRINQ CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

I INCLUDED IN UNIT 1.NEED ADDITIONAL SPACE AS OF 1988.

Page 103: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - SILO STORAGE OPTION(1983 DOLLARS)

PLANT NAME TYPE RACKS ------------------------------------------------------REACIN --LOW DEN BEFORE CONVERSION AFTER CONVERSION INCREMENTAL COST

PLANT NAME ITYPEI RACKS ----------------- RERACKZINK ----------...------------

I INEEDEDI0 OX 6 1 0 86 S 110 16 0% s0w e I 5x I lox- -- - -- ------ -- - - - - - - - -

ARK NUCLEAR 1 P 120 3.83.7 1.47+7 7.58.6 5.42.5 4.689+7 8.10+7 2.23+7 1.70+7 1.69+7 1.82.7

ARK NUCLEAR 2 P 136 8.39+7 1.41+7 8.28+8 5.54+5 5.88.7 3.27+7 2.22.7 2.00+7 1.9147 1.84+7

BEAVER VALLEY 1 P 138 4.97.7 2.24.7 1.1117 8.21+5 8.91.7 4.2867 2.98+7 2.00+7 2.08+7 1.93+7

BEAVER VALLEY 2 P 146 4.66.7 1.15+7 8.17+6 6.47+6 8.73+7 2.86.7 9.65.8 2.13+7 1.29+7 7.12+8

BELLEFONTE I P 168 7.70.7 1.91+7 6.31.8 7.34+5 1.04+8 8.72+7 1.53+7 2.77.7 1.8897 1.88+7

BELLEFONTE 2 P 168 7.70*7" 1.74+7 4.39+8 7.84,5 1.0408 3.37#7 1.27#7 2.77.7 1.71+7 9.02+8

BIG ROCK I B 46 2.6557 1.38.7 7.70+. 8.56+4 2.79.7 1.70+7 1.07.7 2.49.6 3.29+8 3.10-8

A BRAIDWOOD I P 252 1.87.8 6.95.7 2.96.7 1.88+6 1.82.8 9.59.7 5.96+7 4.52+7 3.74+7 3.10.7

A BRAIDWOOD 2 P (a)B BROWNS FERRY 1 B 684 5.17+7 1.91.7 7.63,6 1.32+6 7.18+7 3.14+7 1.47+7 2.14+7 1.36+7 8.48.6

B BROWNS FERRY 2 B (a)BROWNS FERRY 3 B 456 4.84.7 1.80+7 7.21.8 9.02+5 6.41+7 3.02+7 1.58+7 1.8.+7 1.32+7 9.49+6

BRUNSWICK 1 B 876 5.21+7 3.1867 2.08+7 7.59+5 6.20.7 4.08+7 2.92+7 1.87+7 9.92+6 9.16+6

P 0.00+0BRUNSWICK 2 B 376 4.97.7 2.91.7 1.83+7 7.52+5 8.0387 3.97.7 2.84+7 1.14.7 1.14+7 1.09.7

P 0.88,0A BYRON 1 P 264 1.37.8 6.67.7 3.58+7 1.07.6 1.82+8 9.90+7 6.20+7 4.5657 3.44+7 2.73.7

A BYRON 2 P (a)CALLAWAY I P 168 5.40.7 1.6807 5.29.8 7.13+5 7.82+7 3.32+7 1.62+7 2.49.7 1.79+7 1.16+7

B CALVERT CLF I P 192 8.06.7 4.45+7 2.69+7 7.16+5 1.00+8 8.28+7 4.31+7 2.0657 1.98+7 1.89,7

B CALVERT CLF 2 P - (a)CATAWBA I P 144 0.080+ 0.0+0 0.800+0 6.42.5 2.38+7 3.68.6 8.21+5 2.45+7 4.32+6 1.26+8

CATAWBA 2 P 144 0.00+0 8.08,+ 0.00.0 5.94+5 2.38.7 8.24+6 6.0085 2.36.7 3.84+6 1.09.6

CLINTON 1 B 844 5.46.7 1.51.7 4.89.8 6.98+5 8.84.7 2.39.7 9.89+6 1.45.7 9.53.6 5.69.6

B COMANCHE PK I P 198 7.75+7 1.50+7 3.20+6 8.78+6 1.80.8 2.38.7 6.34+6 2.36.7 9.70+6 4.02+6

B COMANCHE PK 2 P (a)A COOK I P 256 4.92.7 2.23+7 1.06+7 1 1.12+6 7.93+7 4.79.7 8.89.7 8.12+7 2.67+7 2.14.7

A COOK 2 P (a)COOPER STH B 232 3.17.7 1.49.7 7.33+6 4.90+5 4.08.7 2.23.7 i.3807 9.42+6 7.98+6 6.11+6

CRYSTAL RVR 3 P 72 2.96.7 9.36+8 3.19.6 8.34+5 4.17.7 1.67.7 7.26+8 1.24+7 7.6+8 4.48.6

DAVIS-BESSE 1 P 128 9.98.7 4.84.7 2.56.7 5.48+5 1.28+8 7.24.7 4.84.7 2.09+7 2.45.7 2.33+7

DIABLO CANYON 1 P 85 3.49+7 8.01+8 2.02+6 3.89+5 4.68+7 1.30+7 4.0686 1.21+7 5.40.6 2.43+6

DIABLO CANYON 2 P 85 3.49+7 8.01.6 2.02+6 3.89+5 4.68+7 1.8067 4.08+8 1.21+7 5.40+8 2.43.8

DRESDEN 1 B 0.080+DRESDEN 2 B 316 2.87+7 1.29.7 8.1868 6.12.5 3.98.7 2.26.7 1.37+7 1.17.7 1.0347 8.21.6

DRESDEN 3 B 318 2.71+7 1.13.7 4.93.8 6.12.6 3.42.7 1.88+7 1.08+7 7.74+6 7.36+8 5.70+6

DUANE ARNOLD B 266 2.95.7 1.25.7 6.83.6 5.,3+5 4.19+7 2.41.7 1.60+7 1.29+7 1.21.7 9.93+6

ENRICO FERMI 2 B 652 9.70.7 3.997 1.88.7 1.088 1.28.8 6.57+7 4.24+7 2.40+7 2.89+7 2.47+7

FARLEY I P 136 2.5657 8.0868 2.7068 6.13+5 4.13.7 1.87+7 9.05+6 1.6567 1.12.7 6.98+8

FARLEY 2 P 136 2.38.7 8.9568 2.15+. 6.13.6 3.62+7 1.47+7 6.53+6 1.20.7 8.38.6 6.00+6

FITZPATRICK B 368 4.88+7 2.14+7 1.82.7 7.30+5 8.28+7 3.46.7 2.15+7 1.41.7 1.40+7 1.28+7

FORT CALHOUN P 98 2.95+7 1.60.7 9.08.6 3.19+5 3.78+7 2.57+7 1.86+7 8.63+6 9.98+6 9.87+6

FT ST VRAIN 0 240 0.00,8GINNA P 84 2.55.7 1.08+7 4.78+8 2.32+5 3.03.7 1.6837 9.17+8 5.08G6 6.72+6 4.63+8

GRAND GULF 1 B 536 7.88.7 3.18.7 1.44+7 1.04.8 1.08.8 5.17.7 3.05.7 2.26+7 2.89+7 1.72.7

HADDAM NECK P 104 2.87.7 1.36+7 6.7568 4.19+5 3.89.7 2.48.7 1.59.7 1.06+7 1.09.7 9.62+8

HARRIS I P 184 0.88+0 4.75+5B 0.00+0

Page 104: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A8. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - SILO STORAGE OPTION(1983 DOLLARS)((cont/d)

a-- -- - ---- -- --- -- -- --- -- -- --- -e e- --- ew-- --- -- -- --- :e-- --- -- -- --- -- -- --e e- -- --e ---e

J I LOW DENIPLANT NAME TYPE RACKS I

I NEEDED I-- -- - - -- - - I

II

BEFORE

0---- T

CONVERSION

-; -- ,1--oS -

I_._ _..! AFTER CONVERSION

I KtNAKAfKNU I IREAKN - - - ------- I-

I INCREMENTAL COST

a HATCH 1B HATCH 2

HOPE CREEKHUMBOLDT SAYINDIAN PT 1INDIAN PT 2INDIAN PT aKEWAUNEELACROSSE

B LASALLE CTY 1B LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEMCGUIRE IMCGUIRE 2MILLSTONE 1

o MILLSTONE 2MILLSTONE aMONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE 1A OCONEE 2

OCONEE aOYSTER CRK 1PALISADESPALO VERDE 1PALO VERDE 2PALO VERDE 3PEACHOOTTOM 2PEACH4BOTTOM 3PERRY 1PILGRIM 1

A POINT BEACH 1A POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 2B QUAD CITIES IB QUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR BEND ISALEM 1SALEM 2

aBBB

PPPBBB

B

BPP

PBPPBaBPPPP

BPP

PPBB

PP

seBB(a)484

136162

7448

(a)448440148144144198168188240184278196(a)18O(a)120268

88170170170468440448192

98(a)120

Ig)

98a84160168

4.62.7 1.89.7 8.28.4 1.14.6 7.19.7

9.22.5 7.•2.77

3.06+7 1.69+7 1.79.7

2.49+7 9.7386 1.84.7

1.29+7 8.78.6

1.09.7 6.17.+6.62.70 .000.0.600.

3.23.73.29.73.44.72.87+71.68.8

8.21.78.60*7a.29.74.83+74.98.76.61,74.46+73.13.72.30*72.79+74.31+77.88+7

9.10+7

6.69+72.87+74.89.7S. 20.76.21+76.21+73.78+73.68+76.06+7a.79+73.82+7

1.49+.7 4.48+6

1. 73.71.10.71.40+71.73.79.24+7

3.86378.23*71.60.71.47.71.48.73.63.71.94+76.93.88.20.61.40.79.84.63.20+7

6.76+7

3.19.71.68.73.12+71.54+71.47.71.39.71.78.71.08.71.26.72.07.71.97+7

9.77+63.92.66.14+61.09+76.83+7

1.86671.43.78. 22.64.91+64.64+62.61+79.26.81.23+63.08.67.*33.2.49+81.4127

3.97+7

1.98*78.98*62.20+76.06+84.61.64.19+68.08268.28+63.47+61.20.71.06+7

6.01.66.77.62.84+68.68.41.27-6

8.93.68.73.66.26+66.42.66.42.64.05+66.13+67.46564.89+63.80*66.71.58.91.6

8.01-6

6.42+66. 11.62.70*68.74.68.74*68.74.69.02468.73.68.93+63.*97.53.64+6

4.86*76.40.74.66+73.27.71.81+8

1.04.81.08.86.07+76.83.77.01276.79+76.39+76.21.72.79+73.46575.23.71.08.8

1.07+8

7.03+73.68876.33+77.46577.48.77.46876.21+74.98.78.68+74.66874.80+7

3.31+72.87+72.33,72.*38.79.97+7

6.89.76.36573.41+72.87.72.78.73.81,73.98.71.41.71.27.72.18.71.40+75.72+7

6.74.7

4.43+72.43.73.44+73.16.73.00+72.66,73.12+72.98.72.11.78.09+73.05+7

2.41.71.46,71.32.71.78.76.23.7

3.9*973.24,72.48+71.36571.26#72.73.72.79.74.28.6

1.46574.21.03.44.7

4.69+7

3.11.71.70.72.44*71.54.71.40.71.28+71.99+7T.89+77.64.62.21+72.03+7

1.68872.17.71.16.74.09.61.43*7

2.23+72.24.71.83.72.06.72.09.73.21.82.68+72.16.76.34.67.01.89.77.62.79*7

1.72.7

1.39+78.43+84.67+62.32.72.32+72.32+71.62.71.49+71.69.79.18.61.08.7

1.64.71.64.79.61.86.356+8.67+6

2.36572.21+71.86.71.48+71.41+72.21+82.10.78.9.864.98+68.24+84.76+82.61+7

1.07+7

1.30.79.68.83.47+61.68871.00+71.64+71.43+71.38+79.44.01.08+71.12+7

1.49.71.12+77.34.67.00+66.27.0

2.20.71.90.71.71+79.20.68.68.61 . 68.61 . 93.73.79.83.48+67.564+2.29+62.12.7

8.9+86

1.19+78.60*82.62+61.10.71.01.79.26+81.20.71.16.,74.98.81.06571.01.7

4.67.7 2.6837 1.48.7

2.22+7 7.67.6 2.71.8

4.31.5 6.78*7 3.89.7 2.81.7 1.2657

9.21+6 2.8657 1.10.7 4.47.6 7.18+6

1.41+7 1.87.7

4.38+8 2.68+6

2.38+74.06+76.08+76.23+75.62+7

8.44+62.61+71.38+72.28.72.03#7

3. 14.61.68-74.16.81.09+78.08+6

6.19+64.00.67.81+57.11+67.46+6

4.06574.91+78.53+77.48+78.17-7

2.31+7

2.26+74.60+74.23+7

1 • 40.72.39,78.78+63.04+72.5 07

1.73.79.08.61.63+72.30.72.62+7

1.56279.37.89.49*82.29#72.27.7

1.18-77.79+86.42+42.02*71.77.7

Page 105: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TOLOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITYTO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNTRATES - SILO STORAGE OPTION(1983 DOLLARS)(contsd)

LOW DENI BEFORE CONVERSION I I AFTER CONVERSION I INCREMENTAL COST

PLANT NAME TYPE RACKS ---------- ..... RERACKINo .---. -- ------------ ..NEEDEDIOe eI 1%I 6 I lox___ 1% I 6 16%....--- I . . ..I ------.. .. .. ------ m.. . . -- --- --. . . . . . . . .. - I ----------- . ...

E SAN ONOFRE 1E SAN ONOFRE 2E SAN ONOFRE 3

SEAOROOK 1A SEQUOYAH IA SEQUOYAH 2

SHOREHAMSOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE 1ST LUCIE 2SUMMER 1

A SURRY 2A SURRY 2B SUSQUEHANNA 1B SUSQUEHANNA 2

THREE MILE ISL 1L.o TROJANw E TURKEY PT 3

E TURKEY PT 4B VOCTLE 1B VOOTLE 2

VT YANKEE IWASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK 1YANKEE-ROWE 1

A ZION 1A ZION 2

TOTAL

276

128246(a)368104104152144136159(a)

68(a)14698

144(a)252(a)284312176246(a)152

76216(a)

5.82.7 3.21+7 1.82+7 9.68+5 8.25+7 6.60+7 4.18+7 2.53+7 2.08.7 2.45+7

1.10+8

5.52+72.38+72.38+75.51+75.30+74.34+72.08+7

1.08+8

2.22+72.63.72.46+7

9.74+7

3.11.77.58+76.15.71.67.0

4.68+72.22.75.32+7

1.58.76.14.7

1.52+73. 34.63.18+63.84+71.84+71.14+75.02+6

4.11+7

7.21269.09+69.55+6

2.79+7

1.29+73.02.71.47+73.81+7

1.21+71.01+72.74+7

4.41+62.70.7

4.74+65.13.54.87.52.62+77.18+63.28+61.30+6

1.74+7

2.47+63.32.63.88+6

8.87+6

S.74.61.38*74.63*61.52+7

3. 6.64.40961.49#7

5.74.51.08+6

7.38+55.51+65.48+56.52+65.25+66.06557.03+5

1.31.6

6.54+54.37+58.39#5

1.11.6

5.5$+S6.39*66.96.51.06+6

6.77+51.98+59.64+5

8.46+71.48.8

8.96+73.57.7

8.39+77.18+76.25+73.04+7

1.34.8

3.23.73.82+74.08+7

1.29+8

4.31.78.90+77.45+71.42+8

8.79.72.95.78.06+7

2.88+78.18+7

2.44+76.88+86.06+84.20+73.55+72.33+71.06+7

a.26+7

1.51+71.88+72.10+7

4.72+7

2.28+74.17.73.04+76.72+7

2.53.71.95+76.36+7

1.18+75.29+7

9.87+61.26+6

1.14.63.00+'7

2.08.79.94+63.66.8

3.27+7

7.49+67.83.61.14+7

1.9867

1.29+72.24+71.42.?

1.68.?

1.33+73.80+7

2.21273.49+?

1.51,71.24.71.22+79.35+61.93+71.97+71.065+7

2.73+7

1.67.71.24.71.68.7

3.25.7

1.26.71.38.72.07.73.64+7

2.18+7

7.46+62.83+7

1.37+73.16+7

9.98.63.59.63.43+68.16+61.77+71.26.76.76.8

2.27.78.58868.16861.21*7

2.04.7

1.102+71.21.71.84+73.02.7

1.38.79.51.82.71+7

7.74+62 . 70+7

5.87+81.29+61.22+64.35+61 . 39+77.26+62.90+6

1.87+7

5.68+64.95+68.16+8

1.18.7

?,69+69.46+61.03+72.24+7

7.93+68.68.62.46,+7

---------- - ----------------------------- w ------------- - -----------------------------------4.86+9 1.97+9 9.56+8 6.6597 6.46+9 3.23+9 1.96.9 1.68+9 1.32+9 1.01+9

ABE

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITh ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1

Page 106: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Aaa. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - SILO OPTION(1988 DOLLARS)

---------------------------------------------------------------------------------------------------------------ADD. YEAR

SHUTDOW• STORAGE WHEN CONS.PLANT NAME YEAR REQ'D ADD'L TIME

(ASSEM- STOR. (MON.)I-ES) NEEDED

------------------- --- ------ ------

C OTm------------------------------------------- I-----------------

CONSTRUCTION I SIM I TOTAL.- -------- --------------------

ox I5 10 I0 15% I0 x i o I 5% I lox---------- ------------

ARK NUCLEAR 1ARK NUCLEAR 2BEAVER VALLEY 1BEAVER VALLEY 2BELLEFONTE 1BELLEFONTE 2BIG ROCK 1

A BRAIDWOOD 1A BRAIDWOOD 2B BROWNS FERRY 1B BROWNS FERRY 2

BROWNS FERRY 3BRUNSWICK 1

BRUNSWICK 2

A BYRON IA BYRON 2

PA CALLAWAY 1B CALVERT CLF IB CALVERT CLF 2

CATAWBA 1CATAWBA 2CLINTON 1

B COMANCHE PK 1B COMANCHE PK 2A COOK 1A COOK 2

COOPER STNCRYSTAL RVR 8DAVIS-BESSE 1DIABLO CANYON 1DIABLO CANYON 2DRESDEN 1DRESDEN 2DRESDEN 3DUANE ARNOLDENRICO FERUI 2FARLEY 1FARLEY 2FITZPATRICKFORT CALHOUNFT ST VRAINGINNAGRAND GULF 1HADDAM NECKHARRIS 1

2008201220102026202820302001202620272014281420172010

2010

20242028202428142018202620282027203020382808920092008201828172026202619842008200820102026201220122015200820072088202220072028

3775858638as

190

963627

(a)3226

2 44112401

2281

3627(a)11292213

(a)00

2672207

(a)1241

(a)1238

4322490

6175170

1016893998

6366298140

2246413

2194392

3190

1999199820092009201119961998

2002

20011990

1991

1994

20061992

282620282002016

1998

19972006199620112011

1998200019991997208200819971994

2000199819972026

6263675769895287

62

5868

67

87

6989

00

6971

81

526277635a

6262627262626762

6267620

2.80.72.27.73.00.72.99+76.24.76.24.72.00.78.68.7

8.86+7

3.22.73.19.7

3.08+7

8.68+7

3.43,76.22+7

0.00.00.00*03.31.76.72-7

3.74*79

2.23.72.07,768.76.72.28972.28.7

2.08.72.08+72.06*76.86872.08+72.08673.07.72.0687

2.08.74.00+72.08+70.00+0

1.09*71.04.71.69+,78.41.61.47+71.34.71 . 16574.66+74 • 66.7

1.53.7

1.34.72.27.7

2.09+7

6.02.7

1.17.73.38+7

0.00.00.00.01.08+71 . 20+7

1.80+7

1.13.77.08+63.77.75.83.6

9.93+89.01.89.46*82.96870.72+88.10.81.56671.21+7

9.01.82.38.71.04+70.00.0

6.98+64.96+68.70.82.51.84.40+83.64,68. 68.62.49.7

6.31.6

6.79061.64.7

1.44-7

3.01.7

4.22+62.21+7

8.00+00.00.03.70+62.71+6

8.90.8

5.87+62.64+62.16.71.68+81.58.6

4.94+84.08.64.49+61.64+72.31+81.91.68.09+.7.24.6

4.88.61.17.76.44+80.08,0

9.70+61.12.71.97.71.87+72.48+72.48+74.86+06.18.7

1.31.7

1.62.72.02+7

1.89.7

6.1.87

1.97+72.84.7

0.680+0.00.02.16+72.03.7

1.18.7

9.37+68.89+83.22.71.21.71.21+7

8.08.66.47+68.89.63.84+74.86+03.23+81.79.78.89.8

4.86.62.98+70.08+60.60+0

3.80.83.71.86.62.68.*12.64.39+63.99+62.28.81 . 48.7

3.83.8

4.66868.94.6

8.16-6

1.66.7

4.29+61.09+7

0.00.00.00.04.27.82.96+8

4.30.6

3.67.82.30.61.07,72.18.82.18.6

3.00.62.28+63.08+61.03.71 . 34.88.48+66.87.63.92.8

1.79+68.26+63.16-60.00.0

1.6086 3.03.71.33.6 3.39.72.48-6 4.97.70.63.6 4.68.79.07.6 7.70.77.6506 7.70.71.12.8 2.66574.70+6 1.37*8

0.00+01.22.6 6.17+7

0.00.01.42.8 4.84.74.41.6 6.21.7

0.80+03.89+6 4.97+7

0.00.06.88.6 1.37.8

0.00+01.07+8 6.40+74.79+6 8.08+7

0.0+00.00.0 0.00.00.00+0 0.900.9.88.5 6.48+74.88+6 7.75+7

0.00+01.67+6 4.92.7

1.4686 3.17+78.4656 2.96+74.09+8 9.98+74.4256 3.49+74.42.6 3.49+7

0.00.01.19.6 2.87.78.63.5 2.71+71.14+8 2.9567

.936.6 9.70.73.93+6 2.56572.38+6 2.38+72.16.8 4.88.71.84+6 2.95+7

0.*00.06.98+6 2.66+72.87+8 7.88+71.31-6 2.87+70..0+0 0.080+

0.00+0

1.47+71.41+72.24.71.16.71.91+71.74.71.38.76.96+7

1.91+7

1. 80.7

8.16.7

2.91.7

8.67+7

1.68074.4657

0.00.00.00*01.61+71.66+7

2.23.7

1.49.79.38+84.84+78.01÷80.01.0

1.29.71.13+71.26573.99+70.68686,96.62.14+71.88,71.68+71.08,73.18.71.38+7

7.68+68.28+61.11.73.17*66.31+64.39+87.*70+6

7.*63.6

7.21.62.08.7

1.83.7

5.29.52.89+7

0.00+00.00.04.69+63.20+6

1.08+7

7.33.3.19682.60+72.02*62.*02+

8.13.64.98+65.63.61.88.72.70+82.16+82.02+79.086+

.13.

4.78+81.44.78.7658

Page 107: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE A~m. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - SILO OPTION(1983 DOLLARS) (cont'd)

ADD. YEAR I CO S TSHUTDOWN STORAGE WHEN CONS. -------- -m1----- 7 -m----- I- -- ----

PLANT NAME YEAR REq'D ADD&L ITIME CONSTRUCTION J 0M j TOTAL(ASSEM- STOR. '(MON.)- ------ ---------- -.------- -BLIES) NEEDEDI e% 6I lax10 e0% 5% 11% ex oI 5 le10

I-- w - -- - - - -- ----- - - -

B HATCH 1B HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT 1INDIAN PT 2INDIAN PT 8KEWAUNEELACROSSE

B LASALLE CTY 1B LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEMCGUIRE 1MCGUIRE 2MILLSTONE 1

o MILLSTONE 2ui MILLSTONE 3

MONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE 1A OCONEE 2

OCONEE 3OYSTER CRK 1PALISADESPALO VERDE 1PALO VERDE 2PALO VERDE 3PEACHBOTTOM 2PEACHBOTTOM 8PERRY 1PILGRIM 1

A POINT BEACH 1A POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 2B QUAD CITIES 1B QUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR BEND 1SALEM ISALEM 2

20092012202619781980200820152014200220222028202420292008202120232010201520252007200520262018202020132013201420042011202420252028200820082026200820072008200820082007200720082007202520162020

* 2874(a)

282000

493536679205

9824

40984236

832966989

2480823541355884

19711866

(a)2102

(a)1021912836

1117112111211812168926481512

849(a)

1142(a)503(a)2286e6

245210071183

2000 60 3.57.7 1.56.7

200? 60 3.58,7 1.10.7

1994 52 2.21.7 1.29.72004 53 2.38$7 8.37+61999 62 2.18.7 1.00+.1992 52 2.086.7 1.38.71990 98 1.01.8 8.9127

1995 66 4.89.7 2.81.71998 67 4.79.7 2.31.71996 53 2.2687 1.20+72005 58 3.21.7 1.10.72006 58 8.25,7 1.06.71987 58 3.19.7 2.51+71997 55 2.74.7 1.38.72018 53 2.34.7 4.68+82004 52 2.06.7 7.41+61996 52 2.06+7 1.09.72011 56 2.86.7 7.28*61999 70 5.39.7 2.47.7

1989 72 5.82+7 4.34.7

1991 59 3.33.7 2.25.71994 52 2.08.7 1.21+71988 55 2.71.7 2.12,72005 58 3.27+7 1.12.72006 58 3.27.7 1.07.72007 58 3.27.7 1.01.71997 55 2.73.7 1.38.71997 54 2.65.7 1.29.72009 59 3.31.7 9.32+.1993 53 2.44.7 1.50.71995 55 2.89.7 1.50.7

1993 57 3.08.7 1.89.7

2005 52 2.06,7 7.06.6

2004 52 2.08.7 7.41.81990 64 2.0.507 1.78.72007 58 3.25.7 1.01.71997 59 3.29,7 1.66.72001 60 3.817 1.50+7

7.06.6 9.49.8

3.59.8 1.99+7

7.75.68.15+84.745.88.76+64.81+7

1.49.71.15.76.53* 83.94.68.63.82.00+77.21.61.01.82.79.6S .98+81.989.61.17.7

1.02.79.64.81.20470.09.68.89+7

8.52.73.81+7

1.62+,71.788,72.32.7

1.71.77.91.62.42.87.27.61.45.72.49+7

8.27.8 1.20-8 4.52.70.00.0

3.98.8 8.92.5 5.62+70.00.00.00.0

4.39.6 2.02.8 3.23.72.61.8 7.89.5 3.29+74.00.6 1.39.6 3.44+74.02.6 2.11+6 2.87.72.38,7 1.02+7 1.68.8

0.00+01.02-7 3.82.8 8.21,79.21.8 2.796 8.0.0074.03,6 1.89.6 3.29.73.74+8 9.71.5 4.88.73.73.8 9.10.5 4.98.71.12+7 8.12+8 5.51+75.82+8 2.05+6 4.45.71.25.6 2.18.5 3.13.77.90,6 2.72.5 2.30+78.05.8 1.3568 2.79.72.56." 5.10.6 4.31.77.27.8 2.39.0 7.88.7

0.00.01.41#7 6.94.8 9.10÷7

0.00+09.36.8 4.25.8 5.69.73.8658 1.74.6 2.87.71.00.7 5.22.8 4.89.74.20+6 1.0568 5.20.74.01,6 9.61.5 5.21.73.82.6 8.86.5 5.21.73.99.8 1.83.8 3.78.73.86+8 1.576 3.68+.73.24+. 8.89+5 5.05.75.73+8 2.64+8 8.79.74.86,8 2.05.8 8.82+7

0.00.0.35+.6 2.92+8 4.67+7

0.*00+05.14.5 1.72+5 2.22,7

0.00+01.08.6 3.4865 2.38.77.30.8 3.75.8 4.06+73.88+8 8.46,5 5.08.76.23+8 2.25+8 5.23.75.32+8 1.59.8 5.62.7

1.89.7

1.49,7

1.73.71.*10.71.40471.78+79.24,7

8.86.78.2+2.71 . 60,71.47.71.43873.68.71.94+76.98.88.228.61.40+79.84+68.20+7

5.75.7

3.19.71.58.78.12+71.54.71.47+71. 39.72.778+71.88+71.28.72.07.71.97.7

2.58.7

7.567+8

8.44.62.51.71.38+72.28.72.03.7

8.20.6

4.48.6

9.77.68.92.88.14+81.09.75.83.7

1.86.71.43.78.22,84.91.64.54*82.61-79. 28#81.23.88.06,67.33,62.49+.1.41.7

3.97.7

1. 98.78.98+62.20.76.06.64.81.84.19.88.82+6S. 28+.3.47.81.20.71.06.7

1.48.7

2.71.6

3.14+.1.88.74.1*.61.09.78.08+8

3.28.7 8.28,7

1.55.77.24.81.688.74.01.83.68#6

.32+.87.19+.8.71.62.78.89.40.88.57.8

2.38678.08+82.218.71.93.71.94+71.94.71.05.71.01271.74.71.35.71.13+7

1.194.7 1.49.7

2.64+6 1.62.8

2.79.81.2897

8.88.88.49.8

3.238.61.56.71.83.71.94.72.01.7

Page 108: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Asa. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYIN THE CURRENT HIGH DENSITY RACK CONFIGURATION - SILO OPTION(1983 DOLLARS) (cont*d)

----------------------------------------------------------------------------------------------------------------------I ADD. YEARI SHUTDOWN STORAGE W4EN CONS.

PLANT NAME I YEAR REQ'D ADDIL TIMEI (ASSEM- STOR. (MON,)

IBLIES) NEEDED

COST

CONSTRUCTION 0 . Mi TOTAL

-- e- -- ---- -- --o---- 1-x 6I loxs

E SAN ONOFRE 1E SAN ONOFRE 2E SAN ONOFRE 3

SEABROOK 1A SEQUOYAN 1A SEQUOYAN 2

SHOREHAMSOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE 1ST LUCIE 2SUMMER 1

A SURRY 1A SURRY 2B SUSQUEHANNA 18 SUSQUEHANNA 2

•o THREE MILE ISLo• TROJAN

E TURKEY PT aE TURKEY PT 4a VOCTLE 1B VOOTLE 2

VT YANKEE 1WASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK 1YANKEE-ROWE 1

A ZION 1A ZION 2

TOTAL

1999201220132031202120222027202720282010202320242012201320222024

1 200820112007200720272028201220232024202620272026200120082008

23862

12812680

(a)2836258268

11821128781

97(a)

7288(a)75

373384(a)

2495(a)

1088401811432891

381295

(a)

1985 69 5.30.7 2.96.7 1.6897 6.20.6 2.67+6

20981996

200202320241987200120082012

200

200820042802

2008

19991998200201

200819991995

6279

596262s867so62

80

626262

78

626086979

676202

3.81-77.08.7

3.38.72.08.72.08.73.19.73.10.72.809.72.08*7

7.41.7

2.80.72.00.72.68+7

6.68.7

2.08.74.69+73.31.77.10+.7

3.00+72.00*73.89+7

1.18.73.94.7

1.09.72.93.02.79.82.62+71.29.78.28.86.02+8

3.23.7

6.72.67.41.68.17.6

2.1867

9.4.682.21.71.08.72.96+7

8.865+9.42+1.2.17+7

3.52#82.28.7

3.76+864.68564.16+62.01.756,68.862.69+*81.30+8

1.47.7

2.31.62.79.83.38.*8

7.406+

4.49.+1.10+73.69+81.28.7

2.77.04.49.01.24.7

2.60.73.88.7

2.16+73.23.83.23+02.32.72.20.71.64.70.00.0

3.38.7

1.62.66.68+84.04.6

3.06.7

1.06.72.99+71.84.73.69.7

1.68.71.82.81.43.7

4.33+81.220.7

4.29.64.07.63.88+51.12.76.48.63.07+60.00+0

0.77.6

4.89.61.88+81.38.8+

6.08.6

3.48+68.12.63.89+88.68.+8

3. 28.08.88+*66.73+6

1.31+6 6.82+70.090.00.0

8.91+6 6.31.74.386+8 1.18.8

0.60.09.93.6 6.62.76.88.4 2.38.76.16.4 2.38+78.12.8 6.61.71.68.6 6.38.76.94.6 4.34.70.00+0 2.08.7

0.00+02.8656 1.08+8

0.06+01.67.6 2.22.76.32+6 2.63.76.01+6 2.46+7

0.00+01.41.0 9.74+7

0.00.01.2568 3.11.72.60.6 7.68*79.37+6 6.16.72.42.8 1.07.8

0.00*07.380.6 4.68*73.0.56 2.22.72.48+8 6.32+7

0.0+.0

1.77.8 4.86.9

3.21.7 1.82+7

1.65076.14+7

1.62+.73.34.83.18.83.84.71.*84-.71.14+76.02+6

4.11+7

7.21.89.09.89.66.6

2.79+7

1.29.78 .02.*71.47.73.81.7

1.21*71.01.72.74.*7

4.41.82.704.7

4.74.86.13.64.7.+62.62.77.18.83.28.61 • 30.8

1.74.7

2.47.63 .32.83.88.6

8.*87,6

S .74.81.38.74.83.61.62.7

3.60+*64.80+01.49+7

---------------------------- m --------3.24.9 1.49.9 7.79.8 1.81+9 4.79+8 1.97.9 9.65.8

A INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEB INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEE INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1

Page 109: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Abf. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - SILO. OPTION(19S DOLLARS)

----------------------------------------------------------------------------------------------- ------ -------ADO. YEAR CO0S T

SHUTDOWN STORAGE WHEN CONS. - - --------------

PLANT NAME YEAR REQ'D ADOIL TIME CONSTRUCTION O08M' TOTAL(ASSEM- STOR. (MON.) . ...- .. .... .BLIES) NEEDED ex I 5; 1% 6% I 5% i o6 1 1- 16%

-ee----------------- ------ -- -- - - - - - - - - - - - - - - -

ARK NUCLEAR I 2068 787 (b) 55 2.77*7 2.17.7 1.72.7 1.91.7 9.34.6 5.65.6 4.80.7 3.1.+7 2.23*7

ARK NUCLEAR 2 2612 973 1989 57 3.05+7 2.27.7 1.72.7 2.26.7 9.99+6 4.9786 5.33*7 3.27+7 2.22.7

BEAVER VALLEY 1 2618 1287 (b) 62 3.85.7 2.99.7 2.35+7 3.0687 1.27.7 6.31.6 6.91.7 4.28.7 2.98.7

BEAVER VALLEY 2 2028 129 2969 82 3.89.7 1.89.7 7.67.6 2.85.7 8.88.6 1.9.06 6.7387 2.38.7 9.65.6

BELLEFONTE 1 2628 2404 2906 75 8.4067 2.79*7 1.27+7 4.60.7 9.29+6 2.83.6 1.64.8 3.72.7 1.53.7

BELLEFONTE 2 2030 2404 2602 75 6.46*7 2.63+7 1.0657 4.0987 8.43.6 2.18.8 1.04.8 8.37.7 1.27+7

BI1 ROCK 1 2061 175 1992 52 2.08.7 1.33.7 8.78.8 7.27.6 3.76*6 1.97.6 2.79.7 1.70+7 1.67'7

A BRAIDWOOD 1 2026 4383 1990 9 1.065.8 7.69.? 4.99.7 7.68*7 2.56.7 1.0667 1.82.8 9.59*7 5.96.7

A BRAIDWOOD 2 2627 (a) 1996B BROWNS FERRY 1 2014 4594 1998 68 6.14.7 2.47.7 1.23.7 2.04.7 6.68.8 2.39+6 7.18*7 3.14.7 1.47.7

B BROWNS FERRY 2 2014 (a) 1998BROWNS FERRY 3 2017 3353 1995 62 3.97.7 2.21.7 1.27.7 2.44.7 8.12.6 3816.8 6.41.7 3.62.7 1.68.7

BRUNSWICK 1 2016 8153 (b) 82 3.8127 2.96+7 2.33.7 2.39.7 1.12.7 5.91.6 6.2067 4.68.7 2.92.7

BRUNSWICK 2 2010 3633 (b) 81 3.68.7 2.87.7 2.26.7 2.35.7 1.16.7 6.82.8 6.03+7 3.97.7 2.84.7

A BYRON 2 2026 (4) b

CALLAWAY 1 2024 1633 1996 65 4.5607 2.38.7 1.36.7 3.32.7 9.3656 3.19+6 7.82.7 3.32.7 1.6247

8-. B CALVERT CLF 1 2014 2789 (b) 75 8.34*7 4.68.7 3.60.7 3.76.7 1.60.7 8.18.6 1.60.8 6.28+7 4.31.7

B CALVERT CLF 2 2016 (a) bCATAWBA 1 2925 226 2021 52 2.8667 3.23+6 6.52+5 3.23.6 4.49+5 6.05.4 2.38.7 3.89+6 6.21.5

CATAWBA 2 2026 216 2628 52 2.86*7 2.93+6 4.56+5 2.4286 3.13+5 4.44+4 2.30.7 3.24.8 5.6065

CLINTON 1 2027 3260 2696 62 3.89.7 1.89.7 7.68.6 2.96.7 7.00.6 2.66.6 8.84.7 2.39+7 9.6+88

B COMANCHE PK 1 2630 2061 2610 78 7.64.7 1.88.7 6.37.8 2.99*7 4.97.6 9.67.5 1.00.8 2.38.7 6.34.6

o COMANCHE PK 2 2036 (a) 2610A COOK 1 2009 2909 1991 70 5.63+7 3.74.7 2.68*7 2.40+7 1.05.7 5.09.8 7.93.7 4.79*7 3.89.7

A COOK 2 2009 (a) 1l91COOPER STN 20098 1702 1993 55 2.85.7 1.63.7 1.62.7 1.41.7 6.98.6 2.75.6 4.66.7 2.23.7 1.39.7

CRYSTAL RVR 3 2618 848 1999 54 2.59.7 1.19.7 5.63.6 1.58.7 4.79.6 1.62.6 4.17.7 1.67+7 7.25.6

DAVIS-BESSE 1 2617 2866 1998 81 7.54.7 6.41.7 3.94.7 4.48,7 1.83.7 8.98.8 1.26.8 7.24.7 4.84.7

DIABLO CANYON 1 2625 772 20068 6 2.83.7 9.22.6 3.16.6 1.83+7 3.89+8 9.61.6 4.68+7 1.30+7 4.08+6

DIABLO CANYON 2 2025 772 2006 56 2.83.7 9.22.6 3.16.6 1.83.7 3.8066 9.01.6 4.68.7 1.39.7 4.68+0

DRESDEN 1 1984DRESDEN 2 2008 1647 1992 54' 2.52.7 1.62.7 1.67.7 1.46.7 6.39.6 3.03.6 3.99+7 2.26+7 1.37.7

DRESDEN 3 2908 1325 1994 62 2.23+7 1.31+7 7.82.6 1.19.7 .4.93.6 2.2098 3.42.7 1.89.7 1.00+7

DUANE ARNOLD 2016 116e 1991 54 2.47.7 1.67.7 1.15-7 1.72.7 7.41.8 3.53.6 4.19.7 2.41.7 1.5607

ENRICO FERMI 2 2026 8459 1996 77 8.84.7 4.86.7 8.61.7 5.15.7 1.71.7 7.28.8 1.20+8 6.67+7 4.24.7

FARLEY 1 2012 768 1997 65 2.7127 1.37.7 7.15.6 1.42+7 4.97.6 1.9.86 4.13.7 1.87.7 9.05+6

FARLEY 2 2012 648 1999 53 2.37.7 1.09+7 5.1868 1.15.7 3.81.8 1.37+8 3.52+7 1.47.7 6.5386

FITZPATRICK 2616 2966 1991 81 3.65+7 2.47.7 1.70.7 2.55.7 9.94.8 4.46.8 6.26.7 3.46.7 2.15+7

FORT CALHOUN 2008 683 (b) 53 2.38.7 1.80.7 1.43.7 1.48.7 7.68+6 4.33.6 3.78.7 2.57.7 1.86.7

FT ST VRAIN 2067GINNA 2006 411 1994 62 2.0867 1.21.7 7.24+8 9.76+8 4.19.8 1.93+8 3.03+7 1.83.7 9.17+6

GRAND GULF 1 2922 5464 1992 72 5.91.7 3.81.7 2.68+7 4.13.7 1.36+7 5.51.8 1.66.8 6.17.7 3.05.7

HADDAM NECK 2007 631 1990 53 2.38+7 1.69.7 1.22.7 1.51+7 7.11+6 3.65+8 3.89.7 2.4067 1.59.7

HARRIS 1 2026 6 2026 6 0.66.6 6.66.0 6.9.6 0.69.6 9.666 60.6.008

Page 110: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Ahb. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - SILO OPTION(1983 DOLLARS) (cont'd)

ADD. YEAR COS TSHUTDOVWI STORAGE WHEN CONS. - I ........ i.

PLANT NAE IYEAR REQ'D ADD'L TIME CONSTRUCTION j 0 6 M" TOTAL(ASSEM- STOR. (UON.).-- ------------------- --------P ABLIES)NEEDED -1 106 0 I , Ia 0% Io 1a0lI~~~ sI ..... 1 ... I...- ................

B HATCH 1B HATCH 2

HOPE CREEKHUMBOLDT BAYINDIAN PT 1INDIAN PT 2INDIAN PT aKEWAUNEELACROSSE

B LASALLE CTY 1B LASALLE CTY 2

LIMERICK 1LIMERICK 2MAINE YANKEEMCGUIRE 1UCGUIRE 2MILLSTONE 1MILLSTONE 200 MILLSTONE 3MONTICELLONINE MILE PT 1NINE MILE PT 2

A NORTH ANNA 1A NORTH ANNA 2A OCONEE IA OCONEE 2

OCONEE 3OYSTER CRK 1PALISADESPALO VERDE 1PALO VERDE 2PALO VERDE 3PEACHBOTTOM 2PEACHBDTTOM 3PERRY 1PILGRIM I

A POINT BEACH 1A POINT BEACH 2A PRAIRIE ISL 1A PRAIRIE ISL 2B QUAD CITIES IB QUAD CITIES 2

RANCHO SECO 1ROBINSON 2RVR BEND 1SALEM 1SALEM 2

2009201220281976198020020162014200220222023202420292008202120232010201620262007200620282018202020132013201420042011202420262026200820082028200820072008280820082007200720082007202620162020

4050(a)

3748

901992801301

11144* (a)49926116107013971421287212911046835125225332461

(a)2641(a)

138114241039162716311831

27242469344418981137

(a)1602

(a)640956

322014811667

19982998

2001

(b)199419931987

19881991198719971998

200719981990200719921992

1989(b)

19981997199819911991200319881990199019881988208220021992

(b)200119891992

68

64

67586462

100

7071676384680606962625977

78

63"53

6764646459s863e668

81

63

5467626466

4.63+7 2.48+7

4.38+7 1.81+7

1.34.7 1.66+7

7.88"6 2.91+7

8.00+8 2.48"0 6.19.7 3.8+.7

6.81+6 1.g086 7.27+7 2.49.7

8.08+73.26.72.61+72.08+71.11+8

6.66+*76.64+73.00.74.12+74.17.73.49+73.66.73.36.72.06.72.19.73.29+76.77+7

2.40+71.91.71.60.71.67+77.38.7

4.16.73.81.72.37.72.08872.01.72.73872.77.71.04.79.93+61.68.71.02.74.36+7

1.90.71.14.71.01+71.38676.91-7

9.16+72.63+71.+9,71.08.79.99+62.18672.19+73.42*64.94*61.12+73.34+62.87+7

1.79.72.14.71.96+71.21.76.9657

4.80.76.11+72.07.72.71.72.84+72.90+72.84.71.86.77.27.61.28+71.94.73.81,7

9.10.87.62.87.33,66.9*982.69.7

1.73+71.64+71.04+77.88687.70+61.08+71.21+73.73+82.76866.21.83.82,61.36.7

6.08+63.08+68a. 10.64.20.61.22.7

8.02.88.11-86.82+62.67.62.47+66.89.66.03.68.67+61.11.63.29.88.68655.69.6

4.86*76.40+74.6.*73.27.71.81.8

1.04.81.08+86.07.76.83.77.01.76.79.76.39.76.21272.79.73.45+76.23.71.0•.8

3.81+72.67+72.99+72.38+79.97.7

6.89+76.35.73.41+72.87.72.78.73.81.73.98+71.41.71.27.72.18+71.40.76.72+7

1.69+7

9.73*6

2.41.71.46+71.32.71.78,76.23+7

3.96*73.24.72.48.71.36571.26+72.73+72.79.74.28.68.06*61.46574.21+63.44+7

7.02,7 6.10.7 3.7657 3.72+7 1.64+7 8.39+6 1.07+8 6.74+7 4.69.7

4.10.72.34.73.05+74.24.74.26+74.26.73.44+73.24+74.07*72.76573.1657

3.16871.76-72.29+72.26+72.14+72.04+72.33.72.19+71.64.72.16.72.24.7

2.47.71.32.71.89.71.23+71.12.71.82.71.680+71.61+71.08.61.71-7I1.8627

2.93.71.32.72.28.73.21.73.21.73.21.71.77.71.72+72.68#71.91,71.7127

1.27.76.880.1.06,79.06+88.63*68.22+07.92*87. 74*86.71+89.31.68.0586

6.40+83.77.66.47.63.09.62.81.82.686+3.69*68.89+6

1.48.66.04+64.13+6

7.03.73.68876.3a+77.46*77.48.77.46876.21+74. 98.78.86+74.66.74.8687

4.48372.43.73.44.73.16.7

2.86.73.122+72.96+72.11,73.09.73.6+7

3.11,71.70+72.44+71.64.71.4+.71.28.71.99.71.89.77.64+62.21.72.03.7

3.65.7 2.8657 2.2657 2.13.7

2.40.7 9.6086 3.92.6 4.46+0

1.04.7 6.63.6 6.78.7

1.63+6 6.62+6 2.86+7

3.89,7 2.81,7

1.10,7 4.47+8

2.67.73.03.73.90+.74.33+74.7657

1.68672.37+71.68273.23.73.0687

1.09971.88+77.01.62.44.72.02+7

1.48.71.88+72.63+73.13+73.42+7

8.46.89. 37.66.29.61.27.71.17.7

3.07+06.14+61.77-66.04+64.82.8

4.06.74.91.78.63+77.46.76.17.7

2.31,73.81-72.26574.65074.23+7

1.40.72.39.78.78.63.04.72.6*57

Page 111: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

TABLE Afb. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITYAFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - SILO OPTION(1983 DOLLARS)(cont'd)

------------------------------- w---------------------------------------- w--------------

ADD. YEARSHUTDOWN STORAGE WHEN CONS.

PLANT NAME YEAR REQ'D ADtD'L TIME(ASSEM- STOR. (MON.)BLIES) NEEDED

-------- 7-------- -------------- --------

CONSTRUCTIONII

COST

OSM I TOTAL

a

0o I 5 - lO- 10 --- I r o0x --- 10% ---

E SAN ONOFRE 1E SAN ONOFREi2E SAN ONOFRE 3

SEABROOK 1A SEQUOYAH 1A SEQUOYAH 2

SHOREHAMSOUTH TEXAS 1SOUTH TEXAS 2ST LUCIE 1ST LUCIE 2SUMMER 1

A SURRY 1A SURRY 2B SUSQUEHANNA 1B SUSQUEHANNA 2

to THREE MILE ISLto TROJAN

E TURKEY PT 3E TURKEY PT 4B VOOTLE 1B VOOTLE 2

VT YANKEE 1WASH NUCLEAR 2WATERFORD 3

A WATTS BAR 1A WATTS BAR 2

WOLF CREEK 1YANKEE-ROWE 1

A ZION 1A ZION 2

TOTAL

1999201220132031202120222027202720282010202320242012201320222024

1 20082011207200720272028201220232024202520272025200120082008

3172

18458400

(a)337167057016381838

15581169

574(a)

861

816(a)

3251

484218713411

(a)1813264

1943(a)

19891989198920019891989200020172018

(b)199219992005200519951995199719981995199520002000199319941997199419941999199219881998

77 6.78+7 4.95.7 3.67+7 1.47.7 8.45.8 5.0806 8.25*7 5.80+7 4.18.7

8687

62555462826053

87

53545s

85

54896487

625270

4.70+78.73.7

3.97+72.83.72.82.73.96+73.81+73.80.72.41.7

8.67+7

2.28.72.81+72.91+7

8.38+7

2.56+75.18+74.32.78.78+7

3.93*72.06+76.42+7

2.05.78.11.7

1.7 7.75 .01,64.75.63.08.72.46+71.65+78.25.8

4.83+7

1.15+71.26.71.82+7

3.65.7

1.57.73.03.72.18+75.1227

1.80.71.47+74.07+7

9. 30+64.86,7

7.85*61.03+89.32.62.40+71.62+77.8e652.96.6

2.76*7

6.*01+66.25.69.27+6

1.66.7

9.89.61.82.71.14473.07.7

8.55+61.08673.1207

3.76.75.61.7

2.99.79.35,69.338.6

.2.43873.37,72.85.76.26.6

4.70.7

9.51.61.21.71.17+7

4.52.7

1.75.73.72.73.13.75.46.7

2.86.78.89+62.83+7

8.26.62.07.7

7.08.61. 37,61.31.81.14.71.09.76.*84,61.77.6

1.42.7

3.683.64.21264.81,6

1.07+7

6.85.61. 14.78.57*61.80.7

7.26.84.77*81.29+7

2.28.69.43.6

2.02.62.25.52.04+56.02+64.37+82.09.65.35+8

5.12.6

1.48.61.58.62.12.8

3.06.6

2.98964.22+82.82*65.85.6

2.20+62.89+86.968+

8.46.71.43.8

6.96.?3.57+73.55,78.39.77.18.76.25.73.04.7

1.34.8

8.23.73.82+74.08.7

1.29.8

4.31+78.90.77.45+71.42*8

6.79.72.95.78.05.7

2.88.78.18.7

2.44.76.38.66.06+64.20+7

2.33*71.00.7

6.25+7

1.51.71.68872.1*+.7

4.72.7

2.26.74.17.78.04+78.72.7

2.53.71.95+75.3687

1.18.75. 29+7

9.87.6-1.26.61.14.68.00.72.08+79.94.63. 50*8

3.27+7

7.49.87.83.61.14+7

1.96.7

1.29.72.24.71.42.73.68+7

1.08.71.33.73.80+7

------------------------------------------------------------------------------------------------------4.00+9 2.37.9 1.53+9 2.4869 8.67*8 3.71.8 6.48.9 3.23+9 1.90+9

ABE

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVEINDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

I . INCLUDED IN UNIT 1.NEED ADDITIONAL SPACE AS OF 1986.

Page 112: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes
Page 113: NUREG/CR-5281, 'Value/Impact Analyses of Accident ... · value-impact assessment was performed fotlowing guidelines in the Handbook for Value-Impact Assessment (NUREG/CR-3568). Attributes

NBC FORM 3x62441NACM I M2.3201.202

U.ILL NUCLEAR REGULATORY COMMISSION

BIBUOGRAPHIC DATA SHEET

1. REPORT NUMBER IAWaipdaV TIOC. MO 1,W ". MOW~'

NUREG/CR-5281BNL-NUREG-511180

sea P&SMUCTIONS Ohl THE RevERSt.

*. TITLE AND SUSTITLE &3 LEAVE BLANK

Value/Impact Analyses of Accident Preventive andMitligative Options for Spent Fuel Pools

4. DATE REPORT COMPLETED

MONTN YEAR

* AUToRIS] January 1989J.H. Jo, P.F. Rose, S.D. Unwin, V.L. Sailor, . " DATE REPORT .53U'

K.R. Perkins, A.G. Tingle MoNr" YE"AMarch 1989

1. PERFORMING ORGANIZATION NAME AND MAIUNG ADVRES3 tIhei go C.OP .. PROJECTITAKMDORK U4NIT NUMIER

Brookhaven National Laboratory a. PI OR GRANT NUMBER

Upton, NY 11973 FIN A-3963

Id. SPONSORING ORGANIZATION NAME ANO MAILING ADDRESS I•KAWh Z* i " I I& TYPE OF REPORTDivision of Safety Issue Resolution FinalOffice of Nuclear Regulatory ResearchU.S. Nuclear Regulatory Commission 1L P• RO1 COVEI RE f,, ,,,Washington, DC 20555

12. SUPPLEMENTARY NOTES

IS& ABSTRACT R- wr* e11at

A series of value/impact studies were performed for accident preventive and mitiga-tive options intended to reduce the risks posed by the storage of spent fuel at nuclearpower plants In spent fuel storage pools. Options studied included limited low-densityreracking of spent fuel, installation of water sprays above the spent fuel pool, and theinstallation of redundant cooling and/or makeup systems. The results of these studiesindicated that the measures were in general not likely to be cost effective. The reasonfor this is due to both the low likelihood of a spent fuel pool accident that couldresult in a significant radiological release and high cost of proposed modifications.These insights are largely contingent upon compliance with guidelines developed forlicensees to assure the safe handling of heavy loads in the vicinity of spent fuel poolsthus reducing the likelihood of the structural failure of the pool and rapid loss ofwater inventory due to a cask drop event.

I4 DOCUMENT ANALYSIS -. KEYWOROSIOESCRIPTORS

Spent Fuel PoolsValue/Impact AnalysisRerackitng

Zircaloy FireGeneric Safety Issue 82

b. IDENTIPIERSIOPEN.ENOEO TERMS

IS AVAILAIITYSTATEMENTUnlimited

IS. SECURITY CLASSIFICATION

(Thom W"i

Unclassifiedr('rho mo

Unclassified1?. NUMIER OF PAGES

Is. PRICE

d

111-'n If/. A/-/,.,

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