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August 2016 MAGNASTOR® (.Modular Advanced generation Nuclear All-purpose STORage) Amendment 7 RAI Response Package NON-PROPRIETARY VERSION .. - . ANAC ffif I I NT E RN AT I0 NA L Atlanta Corporate Headquarters: 3930 East Jones Bridge Road, Norcross, Georgia 30092 USA Phone 770-447-1144, Fax 770-447-1797, www.nacintl.com

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Page 1: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

August 2016

MAGNASTOR® (.Modular Advanced generation Nuclear All-purpose STORage)

Amendment 7 RAI

Response Package

NON-PROPRIETARY VERSION

. . - . ANAC ffif I I NT E RN AT I 0 NA L

Atlanta Corporate Headquarters: 3930 East Jones Bridge Road, Norcross, Georgia 30092 USA Phone 770-447-1144, Fax 770-447-1797, www.nacintl.com

Page 2: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

' \\,..

Attachment I

Attachment 1

Request for Additional Information No. 2 Response

August 2016

Page 1 of2

Page 3: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

NAC PROPRIETARY INFORMATION REMOVED

Chapter 4 Thermal Evaluation

NAC Response:

Attachment 1 Page 2 of2

Page 4: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Attachment 2

Proposed Changes

for

MAGNASTOR® Technical Specifications, Amendment 7

(Docket No 72-1031)

NAC International

August 2016

Attachment 2 Page I of I

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APPENDIX A

Certificate of Compliance No. 1031 A-1 Amendment No. 7

Page 6: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Appendix A Table of Contents

1.0 USE AND APPLICATION ........................................................................................... A1-1

1.1 Definitions ............................................................................................................... A1-1 1.2 Logical Connectors ................................................................................................. A 1-7 1.3 Completion Times ................................................................. , ................................. A1-9 1.4 Frequency ............................................................................................................. A1-13

2.0 [Reserved] .............................................................................................. . ............. A2-1

3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ...... A3-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY............. ............... . .. A3-2

3.1 MAGNASTOR SYSTEM Integrity ..................................... .. A3-3

3.1.1 Transportable Storage Canister (TSC) .. .. .... ..... ... . . ... A3-3

3.1.2 CONCRETE CASK Heat Removal System . .. .... .. . ........ A3-9

3.3.2 TSC Surface Contamination ... .

4.0 DESIGN FEATURES ...................... . 4.1 Design Features Significant to Saf

4.1.1 Criticality Control ....

4.1.2 Fuel Cladding Int

............. A3-10

.................. A3-10

........................... A3-12

.............................. A3-12

... ::-........................... A3-15

. ................................................ A4-1 . ............................................... A4-1

.................................................. A4-1

. ....................................................................... A4-1

4.1.3 Transfer Cask Shi ........................................................................... A4-1

4.1.4 TSC Confi.)'r,;),~.,, ............................................................................. A4-2 11.~,rr

4.2 Codes and St~mtlards . . . . . . . . . . ....................................................................... A4-2

4.2.1 Alternativ~~~o Codes, :,1,,·andards, and Criteria .............................................. A4-2

4.2.2 9:~~f5..ti~\~:~,~YA1ternatives to Codes, Standards, and Criteria ...... A4-2 pec1 aramefg[§;;,and Analyses ................................................................. A4-3

ecific Parameters and Analyses ........................................... A4-3

ansfer Facility ....................................................................... A4-4

5.3 nsport Evaluation Program ............................................................................... A5-2

5.4 IS ·:s1 Operations Program .................................................................................... A5-2

5.5 Radiation Protection Program ................................................................................ A5-3

5.6 Special Requirements for the First System Placed in Service ............................... A5-3 5. 7 Training Program .................................................................................................... A5-4

5.8 Pre-operational Testing and Training Exercises ..................................................... A5-4

Certificate of Compliance No. 1031 A-2 Amendment No. 7

Page 7: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

List of Figures

Figure A3-1 CONCRETE CASK Surface Dose Rate Measurement ................................. A3-14

List of Tables

Table A3-1 Helium Mass per Unit Volume for MAGNASTOR TSCs ..................................... A3-8 Table A4-1 Load Combinations and Service Condition Definitions for the TSC Handling

and Transfer Facility Structure........................................................ . ............. A4-6

Certificate of Compliance No. 1031 A-3 Amendment No. 7

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Definitions 1.1

1.0 USE AND APPLICATION

1.1 Definitions

NOTE The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and_Bases. _________ _

ACTIONS

ASSEMBLY AVERAGE FUEL ENRICHMENT

BREACHED SPENT FUEL ROD

BURNUP

LID

CONCRETE CASK

Definition

ACTIONS shall be that part of a Specifi<?fiY~~ Required Actions to be taken under iJ>i1~ignated within specified Completion Times.

Value calculated by averaging th the entire fuel region (U02) of a including axial blankets, if pr s n .

ver

e · it the release of gas el rod breach may be a

, nhole), allowing the rod to e a gross breach requiring a

,, y averaging the burn up over the entire fuel 02) of an individual fuel assembly, including axial

s, if present. Assembly average burnup represents .:~~e r record, nominal, value. The assembly average

b ~up 1s equal to the reactor record, nominal, energy prq~\iction (MWd) over the life of the fuel assembly divided

;~l'&f!J'iJ;. Aw,1'fhe fuel assembly pre-irradiation heavy metal (U) mass in metric tons.

Nonfuel Hardware Burnup:

Equivalent accumulated irradiation exposure for activation evaluation.

A closure lid assembly, consisting of a stainless steel TRANSPORTABLE STORAGE CANISTER closure lid and a separate shield plate bolted together, that provides closure of a TRANSPORTABLE STORAGE CANISTER.

The CONCRETE CASK is the vertical storage module that receives, holds and protects the sealed TSC for storage at the ISFSL The CONCRETE CASK passively provides the radiation shielding, structural protection, and heat dissipation capabilities for the safe storage of spent fuel in a TSC.

(continued)

Certificate of Compliance No. 1031 A1-1 Amendment No. 7

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DAMAGED FUEL

Definitions 1.1

SPENT NUCLEAR FUEL (SNF) assembly that cannot fulfill its fuel-specific or system-related function. SNF is classified as damaged under the following conditions.

1. There is visible deformation of the rods in the SNF assembly. Note: This is not referring to the uniform bowing that

occurs in the reactor; this refers to bowing that significantly opens up the lattice

2. Individual fuel rods are missing from the missing rods are not replace. y

3.

or zirconium dummy rod that d" greater than, the original fu

3.1. Radiological affected (e .. , s1

fety is adversely ged rod pitch); or

be handled by normal pple); or

ontains fuel rods with damaged or traps, and/or grid springs producing

ength greater than 60 inches.

NF assemblies with the following structural defects eet MAGNASTOR system-related functional · uirements and are, therefore, classified as

undamaged: Assemblies with missing or damaged grids, grid straps and/or grid springs resulting in an unsupported fuel rod length not to excee.d 60 inches.

Any SNF assembly that contains fuel rods for which reactor operating records (or other records or tests) cannot support the conclusion that they do not contain gross breaches. Note: BREACHED SPENT FUEL RODs with minor

cladding defects (i.e., pinhole leaks or hairline cracks that will not permit significant release of particulate matter from the spent fuel rod) meet MAGNASTOR system-related functional requirements and are, therefore, classified as undamaged.

5. FUEL DEBRIS such as ruptured fuel rods, severed rods, loose fuel pellets, containers or structures that are supporting loose PWR fuel assembly parts.

(continued)

Certificate of Compliance No. 1031 A1-2 Amendment No. 7

Page 10: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

DAMAGED FUEL CAN (DFC)

FUEL DEBRIS

GROSSLY BREACHED SPENT FUEL ROD

INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

INITIAL PEAK PLANAR­AVERAGE ENRICHMENT

Definitions 1.1

A specially designed stainless steel screened can sized to hold UNDAMAGED PWR FUEL, DAMAGED PWR FUEL, and/or FUEL DEBRIS. The screens preclude the release of gross particulate from the DFC into the canister cavity. DFCs are only authorized for loading in specified locations of a DF Basket Assembly.

FUEL DEBRl.S is ruptured fuel rods, seve~~~fdl~- ,~~loose fuel pellets, containers or structures that are s' ?fjortm · · se PWR fuel assembly parts.

R-AVERAGE ENRICHMENT is the nar-a e enrichment at any height along the fuel assembly. The INITIAL PEAK PLANAR­

ENRICHMENT may be higher than the bundle

NG OPERATIONS include all licensed activities while a ~[k~'ii.MAGNASTOR SYSTEM is being loaded with fuel assemblies.

OADING OPERATIONS begin when the first assembly is placed in the TSC and end when the TSC is lowered into a CONCRETE CASK.

MAGN <t'•~OR SYSTEM (MAGNA~~ )

The MAGNASTOR (Modular Advanced Generation Nuclear All­purpose STORage) SYSTEM includes the components certified for the storage of spent fuel assemblies at an ISFSI. The MAGNASTOR SYSTEM consists of a CONCRETE CASK and a TSC. A MAGNASTOR TRANSFER CASK (MTC) or Passive MAGNASTOR TRANSFER CASK (PMTC) is provided and utilized to load and place a TSC in a CONCRETE CASK or to remove a TSC from a CONCRETE CASK.

(continued)

Certificate of Compliance No. 1031 A1-3 Amendment No. 7

Page 11: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

NONFUEL HARDWARE

Definitions 1.1

NONFUEL HARDWARE is defined as reactor control components (RCCs), burnable poison absorber assemblies (BPAAs), guide tube plug devices (GTPDs), neutron sources/ neutron source assemblies (NSAs), hafnium absorber assemblies (HFRAs), instrument tube tie components, guide tube anchors or other similar devices, in-core instrument thimbles, steel rod inserts (used to displace water from lower section of guide tube), and components of these devices such as individual rods. All nonfuel hardware, with the exception of · ent tube tie components, guide tube anchors or oth steel rod inserts, may be activated durin

RCCs are commonly referred assemblies (RCCAs), control ro element assemblies (CEAs). pr~vide reactor shutdown~A~~!vi guide tubes of the ass€(iffi3'1y,~n

r:flt,'f!li significant number of o · assemblies (BPAAs) a rod assembli

control r control

employed for a up poison absorber

rred to as burnup poison have vendor specific

uch as ex BPRA or WABA (wet le absor~~JJ BPAAs are used to control

fuel or Wti>~ reactivity fuels and are commonly t may be used for multiple cycles.

block guide tube openings when no ployed and are commonly referred to as thimble

, thimble plug devices (TPDs), flow mixers (FMs), ement guide tube plugs, or vibration suppressor

'' Ds may be employed for multiple cycles. NSAs are p ary and secondary neutron sources used during reactor

, , and may be used for multiple cycles.

Integral fuel burnable absorbers, either integral to a fuel rod or ~~i\l~;as a substitution for a fuel rod, and fuel replacement rods

(fueled, stainless steel, or zirconium alloy) are considered components of spent nuclear fuel (SNF) assemblies and are not considered to be nonfuel hardware.

A system, component, or device is OPERABLE when it is capable of performing its specified safety functions.

(continued)

Certificate of Compliance No. 1031 A1-4 Amendment No. 7

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SPENT NUCLEAR FUEL (SNF)

STORAGE OPERATIONS

TRANSFER CASK

TRANSFER OPERATIONS

TRANSPORT OPERAT

Definitions 1.1

Irradiated fuel assemblies consisting of end-fittings, grids, fuel rods and integral hardware. Integral hardware for PWR assemblies primarily consists of guide/instrument tubes, but may contain integral fuel burnable absorbers, either integral to a fuel rod or as a fuel rod substitution, and fuel replacement rods (another fuel rod, stainless steel rod, or zirconium alloy rod). For BWR fuel, integral hardware may consist of water rods in various shapes, inert rods, fuel rod cluster dividers, and/or fuel assembly channels (optional). PWR ay contain NONFUEL HARDWARE.

STORAGE OPERATIONS include a at are CRETE

CASK containing a loaded location on the storage pad.

OPERATIONS, MAGNASTOR l;-1*~~'11!~1~ MAGNASTO

elude all licensed activities involved RANSFER CASK (MTC) or Passive

R CASK (PMTC) to move a loaded and from a CONCRETE CASK to another CONCRETE

TRA .·' O • OPERATIONS include all licensed activities \it' perforti~d on a loaded MAGNASTOR CONCRETE CASK when

· · · fi~ing moved to and from its designated location on the . TRANSPORT OPERATIONS begin when the loaded

,'&t&<J~~fl.~11~CONCRETE CASK is placed on or lifted by a transporter and end when the CONCRETE CASK is set down in its storage position on the ISFSI pad.

The TRANSPORTABLE STORAGE CANISTER (TSC) is the welded container consisting of a basket in a weldment composed of a cylindrical shell welded to a baseplate. The TSC includes a closure lid, a shield plate (optional), a closure ring, and redundant port covers at the vent and the drain ports. The closure lid is welded to the TSC shell and the closure ring is welded to the closure lid and the TSC shell. The port covers are welded to the closure lid. The TSC provides the confinement boundary for the radioactive material contained in the TSC cavity.

(continued)

Certificate of Compliance No. 1031 A1-5 Amendment No. 7

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Definitions 1.1

TSC TRANSFER FACILITY The TSC TRANSFER FACILITY includes: 1) a transfer location for the lifting and transfer of a TRANSFER CASK and placement of a TSC into or out of a CONCRETE CASK; and 2) either a stationary lift device or a mobile lifting device used to lift the TRANSFER CASK and TSC, but not licensed as part of the 10 CFR 50 facility.

UNDAMAGED FUEL SNF that can meet all fuel specific and syste UNDAMAGED FUEL is SNF that is not "

a)

b)

UNLOADING OPERATIONS

Certificate of Compliance No. 1031

ructural safety.

PERATI ~.;· include the activities required to :~ssemblief~from a sealed TSC. UNLOADING \"~~?the movement of the TSC from a ASK info a TRANSFER CASK in an unloading

nd when the last fuel assembly has been removed C.

A1-6 Amendment No. 7

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Logical Connectors 1.2

1.0 USE AND APPLICATION

1.2 Logical Connectors

PURPOSE The purpose of this section is to explain the meaning of logical connectors.

BACKGROUND

EXAMPLES

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequ ·es. The only logical connectors that appear in Technical Sp~Jt' are "AND" and "OR". The physical arrangement of these,fl, , nnectors logical conventions with specific meanings.

Several levels of logic may be used to~s,,, . These levels are identified by the placem"e'ti;l connectors and by the number a~Jft~ed first level of logic is identified byt;~?ftrfS't di a Required Action and the placf~ment o level of nesting (i.e., left just' · Action). The successiv~ley~ls o

<fr'~ i§51iJEf/'lt/I?;,,_,, of the Required Actiorhr'humff'

&1!' logical connectors. t: When logical c nn '.i-~t2[s are u to state a Condition, Completion Time, Surv · :~{ ~1 only the first level of logic is used, and the I ec justified with the statement of the

LCO not met

n Time, Surveillance, or Frequency.

les illustrate the use of logical connectors.

REQUIRED ACTION COMPLETION TIME

A.1

AND

Verify ...

A.2 Restore ...

In this example, the logical connector "AND" is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.

(continued)

Certificate of Compliance No. 1031 A1-7 Amendment No. 7

Page 15: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

EXAMPLES

(continued)

EXAMPLE 1.2-2

ACTIONS

CONDITION

A. LCO not met

REQUIRED ACTION

A.1 Stop ...

OR

A.2.1 Verify ...

AND

A.2.2

A.2.2.1

OR

Logical Connectors 1.2

COMPLETION TIME

This example4~'tJ,~.. $ a more .k:1

plicated use of logical connectors. Required ~~~(fifs '.~ are alternative choices, only one of which ,·'t be ff!f

1 indicated by the use of the logical

connector · . " ..;n; J'the left justified placement. Any one of these three

A~»J.i _, osen. _If ~.2 is chosen, the~ both A.2.1 and A.2.2 ~pst be ,'i;'~; .. , ·"i;;~g\ as indicated by the logical connector "AND". ~!equired Ac1i.~3n A:2..2 is met by performing A.2.2.1 or A.2.2.2. The ~:~nted posi~\pn of the l~gical c~nnector "OR" indicate~ that A.2.2.1 an~ . are alternative choices, only one of which must be pe

Certificate of Compliance No. 1031 A1-8 Amendment No. 7

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Completion Times 1.3

1.0 USE AND APPLICATION

1.3 Completion Times

PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND

DESCRIPTION

Limiting Conditions for Operation (LCOs) specify the lowest functional capability or performance levels of equipment required for safe operation of the facility. The ACTIONS associate "'!,~~CO state conditions that typically describe the ways in wh· e reqfliij~Jrents of the LCO can fail to be met. Specified with a ted Con"~'ition are Required Action(s) and Completion Time(s

: , pleting a

isco},~#Y of a si~uation at ~llres entering an ~~J .. Cl, provided that

n lll•' ed'ifn the Applicability of e compl~tld prior to the expiration of ~JlbNS Condition remains in pply until the Condition no longer the LCO Applicability.

entered, subsequent subsystems, bles ex ressed in the Condition, discovered to be

II not result in separate entry into the Condition stated. The Required Actions of the Condition

p '~)! o each additional failure, with Completion Times ·~

entry into the Condition.

(continued)

Certificate of Compliance No. 1031 A1-9 Amendment No. 7

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EXAMPLES

Completion Times 1.3

The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1

ACTIONS

CONDITION REQUIRED ACTION

B. Required Action B.1 and associated Completion Time AND not met B.2

Condition B has two Required Actions. own Completion Time. Each Co. ~~>n that Condition B is entered.

COMPLETION TIME

The Required Actions of Con ete action B.1 within 12 hours AND complet~, · ·, B. within ·ours. A total of 12 hours is allowed for complffng , ~{-.,, . .;)_~~£! total of 36 hours (not 48 hours) is allowed fo~~ompleting~a~~ion~B.2 from the time that Condition B was entere1+4'1~ If. at~on. B.1 is }/mpleted within six hours, the time allowed for ~~r;npl' · · .r~~t1on B.~r§ the next 30 hours because the total time allo e~~for c letl1f~~eff~flJ' B.2 is 36 hours.

(continued)

Certificate of Compliance No. 1031 A1-10 Amendment No. 7

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EXAMPLES

(continued)

EXAMPLE 1.3-2

ACTIONS

Completion Times 1.3

CONDITION REQUIRED ACTION COMPLETION TIME

A. One system not A.1 Restore system to within limit.

7 days within limit.

B. Required Action B.1 Complete action B. and associated Completion Time AND not met.

When a system is determined not to -entered. If the system is not re?tf'~ith entered, and the Completion "Uf-~ cl B.2 start. If the system is Conditions A and B ar -· d Condition B may be t

ys dition B is also - . , · d Actions B.1 and C~rldition B is entered, , the Required Actions of

(continued)

Certificate of Compliance No. 1031 A1-11 Amendment No. 7

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EXAMPLES

(continued)

EXAMPLE 1.3-3

ACTIONS

NOTE

Completion Times 1.3

Separate Condition entry is allowed for each component.

CONDITION REQUIRED ACTION COMPLETION TIME

A. LCO not met A.1 Restore complian with LCO.

B. Required Action and associated Completion Time AND not met.

The Note above the ACTION Completion Time is tracked. Completion Time is t~#.­the Note would app · r in tha ACTIONS Table.

, modifying how the of modifying how the

applicabl ly to a specific Condition, , ther than at the top of the

entered separately for each s to be tracked on a per component

mponent is determined to not meet the LCO, ed and its Completion Time starts. If subsequent termined to not meet the LCO, Condition A is

c mponent and separate Completion Times are component.

, 1ately" is used as a Completion Time, the Required Action pursued without delay and in a controlled manner.

Certificate of Compliance No. 1031 A1-12 Amendment No. 7

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Frequency 1.4

1.0 USE AND APPLICATION

1.4 Frequency

PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated Limiting Condition for Operation (LCO). An ,'~~ng of the correct application of the specified Frequ is nec,sary for

compliance with the SR. ..• ::-1" _) Each "specified Frequency" is referred t@~rougho , is s~Jtlon and each of the Specifications of Sectio · S 1 ~ilia 1~jt;quirement (SR) Applicability. The "specified Freq f f{quirem·ents of the Frequency column of eac -~jt

(i.e., its Frequency r not desired that it be

(continued)

Certificate of Compliance No. 1031 A1-13 Amendment No. 7

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EXAMPLES

Frequency 1.4

The following examples illustrate the various ways that Frequencies are specified.

EXAMPLE 1.4-1

SURVEILLANCE REQUIREMENTS

SURVEILLANCE

Verify pressure within limit

FREQUENCY

12 hours

in the

12 hours, an I specified in the

e '"' al flexibility. The a a,, imes, even when the SR

is not required to be · s when the equipment or variables are outsi , . specifie i the facility is outside the

Applicability ?f the If?).. ~f '"t", int~_rval sp~~ifie~ by SR ~.0.2 __ is exceeded wh I f~,11t,y 1s m -~~0nd1t1on spe~1f1ed m the Apphcab11Jty of the LCO L 1s ~accordance with SR 3.0.1.

s .9 ~ citied by SR 3.0.2 is exceeded while the facility is not . . , rspecified in the Applicability of the LCO for which

, :i;,<f' "-th. SR is required, the Surveillance must be performed !:?:~ i~ the Pf~~~en~ r~quirements of SR 3.0.2, pr~or to _ent~ into the ~~citied co ~ ion. Failure to do so would result m a v1olat1on of SR 3~©~,..

(continued)

Certificate of Compliance No. 1031 A1-14 Amendment No. 7

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EXAMPLES

(continued) EXAMPLE 1.4-2

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

Frequency 1.4

Verify flow is within limit Once within 12 hours prior to

Example 1.4-2 has two Frequenci performance Frequency, and the se Example 1.4-1. The logical t Frequency requirements must is to be performed, the Surveil prior to starting the activi .

The use of "once" specified Frequency "AND"). This tyj'.:2e o allowed by

dica"'\,~ fu ur ormances must be established per SR ··"'·~ a specified condition is first met (i.e., the "once''.

pe,lifQ'.'ft~· example). If the specified activity is canceled or not tf!j,-~'~iT'

gfrrorme , .'~~urement of both. ~nterva~s. stops. New intervals · art upon pr ·,. nng to restart the spec1f1ed act1v1ty.

h{,;~

Certificate of Compliance No. 1031 A1-15 Amendment No. 7

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2.0

2.0 [Reserved]

Certificate of Compliance No. 1031 A2-1 Amendment No. 7

Page 24: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

3.0

LCO 3.0.1

LCO 3.0.2

LCO 3.0.3

LCO 3.0.4

LCO 3.0.5

LCO Applicability 3.0

LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY

LCOs shall be met during specified conditions in the Applicability, except as provided in LCO 3.0.2.

Upon failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5.

If the LCO is met or is no longer applicable prior Jg~QE~tion of the specified Completion Time(s), completion of the ,, ~·"~rea~. · tion(s) is not required, unless otherwise stated.

Not applicable to MAGNASTOR.

When an LCO · is not met, entry Applicability shall not be made to be entered permit continue the Applicability for an unlimite. 1

not prevent changes in s ifi~ required to comply wi MAGNASTOR.

Exceptions to this C \it>i!tion are ft·;< ted in the_ individual ~pecifi~ations. The~e ~~c al~~~/rnto specified condrtrons rn the Apphc~b1 her ,.tllJ. he ""'asso-~~ated_ ACTION~ t~ . be entered . al_low operat10 s .Alcrfied condrtrons rn the Applrcabrlrty only for a hmrted per"·

) 0 3.0.2 is not applicable for the MAGNASTOR ... rn to service under administrative control to perform the -J_'i' ~: rt•,

Certificate of Compliance No. 1031 A3-1 Amendment No. 7

Page 25: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

3.0

SR 3.0.1

SR 3.0.2

SR 3.0.3

SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

SR Applicability 3.0

SRs shall be met during the specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be a failure to meet the LCO. Failure to perform Surveillance within the specified Frequency shall be a failure to meet

the LCO, except as ~rovided in S~ 3.0.3. S~rveilla~~~~~, ~ot have to be performed on equipment or variables outside s ··lfie~tf'<l1 · s.

The specified Frequency for each SR is i,et performed within 1.25 times the interval sw$'€ified . measured from the previous performan .#If· as rt1,§asu a specified condition of the Frequency t. ~;

4

For Frequencies specified as "o . ~~be not apply. If a Completion T "once per ... " basis, the abov performance after the i · ·

erformance on a applies to each

Exceptions to Specifications.

in the individual

rveil nee was not performed within its .·.:;y;j.v

;'.ffipliance with the requirement to declare ay be delayed from the time of discovery up to 24 limit of the specified Frequency, whichever is less.

], I ,,:;,,.permitted to allow performance of the Surveillance. t~'q '\~ 1l~the Survei ._, ce 'y5 not performed within the delay period, the LCO ~! immedjtely be declared not met, and the applicable Condition(s) usit~~j,$$Fed. When the Surveillance is performed within the delay

eriod an'cr'"the Surveillance is not met, the LCO must immediately be ,~~d not met, and the applicable Condition(s) must be entered.

Entry into a specified Condition in the Applicability of an LCO shall not be made, unless the LCO's Surveillances have been met within their specified Frequency. This provision shall not prevent entry into specified conditions in the Applicability that are required to comply with Actions or that are related to the unloading of MAGNASTOR.

Certificate of Compliance No. 1031 A3-2 Amendment No. 7

Page 26: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

3.1

3.1.1

LCO 3.1.1

Transportable Storage Canister (TSC) 3.1.1

MAGNASTOR SYSTEM Integrity

Transportable Storage Canister (TSC)

The TSC shall be dry and helium filled. The following vacuum drying

times, helium backfill and TSC transfer times shall be met as

appropriate to the fuel content type and heat load:

1. The time durations covering the beginning of~,

through completion of vacuum drying and Q. £': backfil

minimum helium backfill times, and TS

the following:

A. PWR TSC Transfer Usin

Heat Load (kW)

:::; 20

7

7

meet

Maximum TSC Transfer Time (hours)

600

70.5

8

8

MTC with Maximum TSC Transfer

Minimum Maximum Helium TSC Transfer

Backfill Time Time (hours) (hours)

No limit 24 48

32 24 22

24 24 22

C. BWR Using MTC with 8 Hours TSC Transfer

Maximum Minimum Maximum Heat Load Vacuum Time Helium TSC Transfer

(kW) Limit (hours) Backfill Time Time (hours) (hours)

:::; 25 No limit 0 8 :::;29 34 6 8

:::; 30 31 6 8

:::;33 26 6 8

(continued)

Certificate of Compliance No. 1031 A3-3 Amendment No. 7

Page 27: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Transportable Storage Canister (TSC) 3.1.1

D. BWR Using MTC with Maximum TSC Transfer

Maximum Minimum Maximum

Heat Load Vacuum Time Helium TSC Transfer

(kW) Limit (hours) Backfill Time Time (hours) (hours)

$ 25 No limit 24

::;29 No limit

$ 30 44

$ 33 33

E.

Maximu"& Maximum

Heat Load Vacuum Ti'' TSC Transfer

(kW) Li Time (hours)

$20 600

0 600

0 600

· tion from the end of TSC annulus cooling, either by

Heat Load Time Limit (hours)

35.5 11

BWR 33 16

The helium backfill times and TSC transfer times provided in

Tables 1.B and 1.0 shall be used for operations following the

second or subsequent vacuum drying cycles using the MTG.

(continued)

1 CE 16 x 16 fuel only, with a maximum storage cell location heat load of 811 watts.

Certificate of Compliance No. 1031 A3-4 Amendment No. 7

Page 28: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

APPLICABILITY:

Transportable Storage Canister (TSC) 3.1.1

3. The time duration from the end of TSC annulus cooling, either by

24 hours in the pool or by the annulus circulating water system,

through completion of vacuum drying and helium backfill using a

PMTC shall not exceed the following:

Heat Load

PWR :::;25

PWR

Note:

(continued)

Certificate of Compliance No. 1031 A3-5 Amendment No. 7

Page 29: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Transportable Storage Canister (TSC) 3.1.1

ACTIONS

NOTE Separat~ Cond_~!ion entry is ~!!Q_we~_!or e~~h TS_9_:_ _________ _

CONDITION

A. TSC cavity vacuum drying pressure limit not met.

REQUIRED ACTION

A.1 Perform an engineering evaluation to determine the quantity of moisture remaining in the TSC.

AND

A.2 Develop and initiate corrective ac · - , necessary to return the TSC to analyzed condition.

8. TSC helium backfill 8.1 Perform an engineerin density limit not met. determine the effect of

differential.

C. Required Actions and associated Completion Times not met.

Certificate of Compliance No. 1031 A3-6

COMPLETION TIME

7 days

14 days

30 days

(continued)

Amendment No. 7

Page 30: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Transportable Storage Canister (TSC) 3.1.1

SURVEILLANCE REQUIREMENTS

SURVEILLANCE

SR 3.1.1.1

SR 3.1.1.2

Verify TSC cavity vacuum drying pressure is less than or equal to 10 torr for greater than or equal to 10 minutes with the vacuum pump turned off and isolated.

Following vacuum drying and evacuation to < 3 torr, backfill the cavity with high purity helium until a mass Mhelium corresponding to the free volume of the TSC measured during draining (Vrsc), multiplied by the helium density (Lhelium) required for the design basis heat load and specifie Table A3-1, is reached.

Certificate of Compliance No. 1031 A3-7

FREQUENCY

Once, prior to TRANSPORT OPERATIONS.

ORT

Amendment No. 7

Page 31: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Transportable Storage Canister (TSC) 3.1.1

Table A3-1 Helium Mass per Unit Volume for MAGNASTOR TSCs

Fuel Type

PWR BWR

Helium Density /liter

0.694 - 0.802 0.704 - 0.814

Certificate of Compliance No. 1031 A3-8 Amendment No. 7

Page 32: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

CONCRETE CASK Heat Removal System 3.1.2

3.1 MAGNASTOR SYSTEM Integrity

3.1.2 CONCRETE CASK Heat Removal System

LCO 3.1.2 The CONCRETE CASK Heat Removal System shall be OPERABLE.

APPLICABILITY: During STORAGE OPERATIONS

ACTIONS ·---------------------

NOTE

§~~~_Q_~~-~~'!__~~~--~~~~-~~~-~~~GNASTOR SYSTEM.

CONDITION

A. CONCRETE CASK Heat Removal System inoperable.

REQUIRED ACTION

A.1 Ensure adequate heat removal to preve exceeding short temperature limi

A.2

---

FREQUENCY

SR 3.1.2.1

ure and ISFSI ambient p indicates that the CONCRETE

SK Heat Removal System is operable in , rdance with the FSAR thermal

Visually verify all CONCRETE CASK air inlet and outlet screens are free of blockage.

Certificate of Compliance No. 1031 A3-9

24 hours

24 hours

Amendment No. 7

Page 33: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Dissolved Boron Concentration 3.2.1

3.2 MAGNASTOR SYSTEM Criticality Control for PWR Fuel

3.2.1 Dissolved Boron Concentration

LCO 3.2.1

APPLICABILITY:

ACTIONS

The dissolved boron concentration in the water in the TSC cavity shall be greater than, or equal to, the concentration specified in Appendix B, Table B2-4. A minimum concentration of 1,500 ppm is required for all PWR fuel types. Higher concentrations are required, depending on the fuel type and enrichment.

During LOADING OPERATIONS with water and at least one fuel assembly in e

NOTE -~eparate Condition __ ~nt~J~lowed for each TSC.

A.

CONDITION

Dissolved boron concentration not met.

A.1

boron concentration to within limits.

Certificate of Compliance No. 1031 A3-10

Immediately

Immediately

(continued)

Amendment No. 7

Page 34: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

SURVEILLANCE REQUIREMENTS

SR 3.2.1.1

SURVEILLANCE

Verify the dissolved boron concentration is met using two independent measure­ments.

Certificate of Compliance No. 1031 A3-11

Dissolved Boron Concentration 3.2.1

FREQUENCY

Once within 4 hours prior to commencing LOADING OPERATIONS or UNLOAD!

Amendment No. 7

Page 35: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Concrete Cask Maximum Surface Dose Rate 3.3.1

3.3 MAGNASTOR SYSTEM Radiation Protection

3.3.1 CONCRETE CASK Maximum Surface Dose Rate

LCO 3.3.1 The maximum surface dose rates for the CONCRETE CASK, Reference Figure A3-1, shall not exceed the following limits:

a. PWR and BWR - 120 mrem/hour gamma and 5 mrem/hour neutron on the vertical concrete surfaces; an

b. PWR and BWR - 450 mrem/hour (neu , top.

APPLICABILITY: Prior to start of STORAGE OPERA TIO

ACTIONS

-------------------------------------------------------N 0 TE----------

Separate Condition entry is allowed for each MAGNAS

CONDITION

A. CONCRETE CASK A.1 maximum surface dose rate limits not met

7 days

B. Perform (and document) an 60 days engineering assessment and take appropriate corrective action to ensure the dose limits of 1 O CFR 20 and 1 O CFR 72 are not exceeded

(continued)

Certificate of Compliance No. 1031 A3-12 Amendment No. 7

Page 36: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Concrete Cask Maximum Surface Dose Rate 3.3.1

SURVEILLANCE REQUIREMENTS

SR 3.3.1.1

SURVEILLANCE

Verify maximum surface dose rates of CONCRETE CASK loaded with a TSC containing fuel assemblies are within limits. Dose rates shall be measured at the locations shown in Figure A3-1.

Certificate of Compliance No. 1031 A3-13

FREQUENCY

Prior to start of STORAGE OPERATIONS of each loaded CONCRETE CASK before or

the ISFSI

Amendment No. 7

Page 37: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Concrete Cask Maximum Surface Dose Rate 3.3.1

Figure A3-1 CONCRETE CASK Surface Dose Rate Measurement

Measure dose rates at approximate 70-inch diameter at four points approximately on 90-degree axes.

TSC mid-plane - approximately 92 inches from bottom. Measure dose rates at four target points (approximately 0, 90, 180 & 270 degrees) on the mid-plane.

Certificate of Compliance No. 1031 A3-14

90"

Amendment No. 7

Page 38: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

3.3

3.3.2

MAGNASTOR SYSTEM Radiation Protection

TSC Surface Contamination

TSC Surface Contamination 3.3.2

LCO 3.3.2 Removable contamination on the exterior surfaces of the TSC shall not exceed:

a. 10,000 dpm/100 cm2 from beta and gamma sour es; and

b. 100 dpm/100 cm2 from alpha sources.

APPLICABILITY: During LOADING OPERATIONS

ACTIONS

-----------------------------------------------------N 0 TE-----------

S e para te Condition entry is allowed for each M

A.

CONDITION

contamination limits met

Certificate of Compliance No. 1031

. store TSC removable ~jti/:;

ur.t~.9e contamination o wi~~in limits

A3-15

COMPLETION TIME

Prior to TRANSPORT OPERATIONS

(continued)

Amendment No. 7

Page 39: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

SURVEILLANCE REQUIREMENTS

SR 3.3.2

SURVEILLANCE

Verify by either direct or indirect methods that the removable contamination on the exterior surfaces of the TSC is within limits

Certificate of Compliance No. 1031 A3-16

TSC Surface Contamination 3.3.2

FREQUENCY

Amendment No. 7

Page 40: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

DESIGN FEATURES 4.0

4.0 DESIGN FEATURES

4.1 Design Features Significant to Safety

4.1.1 Criticality Control

a) Minimum 10B loading in the neutron absorber material:

Neutron Absorber

T e

Required Minimum Effective Areal Density

(10B /cm2) PWR Fuel BWR Fuel

% Credit Used in Criticality Anal ses

Borated 0.036 0.027 Aluminum Alloy 0.030 0.0225

r--~~~~+-~~~----1 90

0.027 0.020 Borated MMC 0.036 0.027

Bora I

4.1.2

0.030 0.0225 0.027 0.020 0.036 0.027 0.030 0.0225 0.027 0.020

,1;.1

Enrichment/soluble boron ti'.~its for P ystems and enrichment limits for BWR systems are i .,..,,,. r~~.,~ in App ix B Section 2.0.

b) Acceptance an J;~~n ~i]J]J1,.o.· orated aluminum alloy and borated MMC neutron :"'.'~terial shall be in accordance with Sections 10.1.6.4. 10.1.6.4. 7. Acceptance testing of Bora I shall be in

,,,,,, 10.1.6.4.8. These sections of the FSAR are hereby incoq:f©tated into \,;,1; <NASTOR Coe.

bl '.f~on conc~ptration in the PWR fuel pool and water in the TSC shall r;,f cc©~~j~~ith LCO 3.2.1, with a minimum water temperature 5-10°F ' · than tile minimum needed to ensure solubility.

tube outer diagonal dimension

- 13.08 inches - 8.72 inches

Note: Not applicable to DFC locations of the DF Basket Assembly.

uel Cladding Integrity

The licensee shall ensure that fuel oxidation and the resultant consequences are precluded during canister loading and unloading operations.

4.1.3 Transfer Cask Shielding

The nominal configuration transfer cask radial bulk shielding (i.e., shielding

integral to the transfer cask; excludes supplemental shielding) must provide a

(continued) Certificate of Compliance No. 1031 A4-1 Amendment No. 7

Page 41: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

DESIGN FEATURES 4.0

minimum radiation shield equivalent to 2 inches of carbon steel or stainless steel and 3.2 inches of lead gamma shielding and 2.25 inches of NS-4-FR (with 0.6 wt % 84C and 6.0 wt % H) neutron shielding. Material and dimensions of the individual shield layers may vary provided maximum calculated radial dose rates of 1100 mrem/hr (PWR system) and 1600 mrem/hr (BWR system) are maintained on the vertical surface (not including doors or vent shielding).

4.1.4 TSC Confinement Integrity

4.2

4.2.2

The TSC shell, bottom plate, all confinement welds, a CLOSURE LID shall be fabrication helium leak-tested i N14.5 to leaktight criterion.

The closure lid shall be helium leak-tested durin ANSI N14.5 to leaktight criterion) if it is constru 9 inches (nominal).

Codes and Standards

The American Society of Mech Code (ASME Code), 2001 ~d" .. ,~,.11.l '~~ Subsection NB, is the gave · 'ng Code fabrication, and testing of the C.

er and Pressure Vessel rough 2003, Section Ill,

sign, material procurement,

The ASME Code, through 2003, Section Ill, or the design, material procurement,

pent fuel baskets.

·tute Specifications ACl-349 and ACl-318 govern the construction, respectively.

Standards Institute ANSI N14.6 (1993) and NUREG­SFER CASK design, operation, fabrication, testing,

des, Standards, and Criteria

. 1-2 of the FSAR lists approved alternatives to the ASME Code for the

and testing of MAGNASTOR

onstruction/Fabrication Alternatives to Codes, Standards, and Criteria

Proposed alternatives to ASME Code, Section Ill, 2001 Edition with Addenda

through 2003, other than the alternatives listed in Table 2.1-2 of the FSAR, may

be used when authorized by the Director of the Office of Nuclear Material Safety

and Safeguards or designee. The request for such alternatives should demonstrate that:

(continued)

Certificate of Compliance No. 1031 A4-2 Amendment No. 7

Page 42: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

4.3

DESIGN FEATURES 4.0

1. The proposed alternatives would provide an acceptable level of quality and

safety, or

2. Compliance with the specified requirements of ASME Code, Section Ill,

Subsections NB and NG, 2001 Edition with Addenda through 2003, would

result in hardship or unusual difficulty without a compensating increase in the

level of quality and safety.

Requests for alternatives shall be submitted in accordance wit

Site-Specific Parameters and Analyses

This section presents site-specific parameters an

verified by the MAGNASTOR SYSTEM use

presented in Section 4.3.1 are those applied in alysis.

ust be

bases

4.3.1 Design Basis Specific Parameters and

The design basis site-specificAg~· nd~IY! s that require verification by the MAGNASTOR SYSTEf ser are: "tlil.Jt!iiJ

a. A temperature of 7 ° i ~',. e maximu 1 , average yearly temperature. The

three-day avera hall be :5106°F.

b. '\extremes, averaged over a three-day period, shall

c. yzed fl con ~,1Mpn of 15 fps water velocity and a depth of 50 ft of " ' "fJ{

water II submer ~J11ce of the loaded cask) are not exceeded.

d.&~P.O · I for f~~~and explosion shall be addressed, based on site-specific co~~J~per , ~His includes the condition that the fuel tank(s) of the cask

~'Jil)l@~~g_uipment used to move the loaded CONCRETE CASK onto or ~''"'-'::¢::/:~f.'<r

the l'SFSI site contains a total of no more than 50 gallons of fuel.

ases where engineered features (i.e., berms, shield walls) are used to ensafe that requirements of 10 CFR 72.104(a) are met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category on a site-specific basis.

The TRANSFER CASK shall not be operated and used when surrounding air

temperature is < 0°F. This limit is NOT applicable to the stainless steel MTC or PMTC.

g. The CONCRETE CASK shall not be lifted by the lifting lugs with surrounding air temperatures< 0°F.

h. Loaded CONCRETE CASK lifting height limit :::;24 inches.

(continued)

Certificate of Compliance No. 1031 A4-3 Amendment No. 7

Page 43: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

4.4

DESIGN FEATURES 4.0

i. The maximum design basis earthquake acceleration of 0.37g in the horizontal direction (without cask sliding) and 0.25g in the vertical direction at the ISFSI pad top surface do not result in cask tip-over.

For design basis earthquake accelerations up to and greater than 0.37g in the horizontal direction and 0.25g in the vertical direction at the ISFSI pad top surface, site-specific cask sliding is permitted with validation by the cask user that the cask does not slide off the pad and that the g-load resulting from the collision of two sliding casks remains bounded by the c -ver accident condition analysis presented in Chapter 3 of the FSAR.

The TSC provides and off-normal ha TSC and TR

ccident condition and bollards are

capable of handling the any contact between the

o oundary and is evaluated for normal . A handling and transfer facility is not required for handling and transfer operations within a 10 CFR

· · ing an external crane structure integral to a 1 O CFR

f the TR . , SFER CASK and TSC outside of a 10 CFR 50 licensed !:fJi

. : wd unless a TSC TRANSFER FACILITY is designed, ~~t.1~ ested, inspected, and maintained in accordance with the · ements. These requirements do not apply to handling heavy

· CFR 50 license.

manent or stationary weldment structure of the TSC TRANSFER shall be designed to comply with the stress limits of ASME Code,

Section Ill, Subsection NF, Class 3 for linear structures. All compression loaded members shall satisfy the buckling criteria of ASME Code, Section Ill, Subsection

F.

The reinforced concrete structure of the facility shall be designed in accordance with ACl-349 and the factored load combinations set forth in ACl-318 for the loads defined in Table A4-1 shall apply. TRANSFER CASK and TSC lifting devices installed in the handling facility shall be designed, fabricated, operated, tested, inspected, and maintained in accordance with NUREG-0612, Section 5.1.

(continued)

Certificate of Compliance No. 1031 A4-4 Amendment No. 7

Page 44: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

DESIGN FEATURES 4.0

If mobile load lifting and handling equipment is used at the facility, that equipment shall meet the guidelines of NUREG-0612, Section 5.1, with the following conditions:

a. The mobile lifting device shall have a minimum safety factor of two over the

allowable load table for the lifting device in accordance with the guidance of

NUREG-0612, Section 5.1.6 (1)(a), and shall be capable of stopping and

holding the load during a design earthquake event;

b. The mobile lifting device shall contain :::;50 gallons of fuel

inside the ISFSI;

c. Mobile cranes are not required to meet the

Section 5.1.6(2) for new cranes;

d. The mobile lifting device shall conform to th

"Mobile and Locomotive Cranes";

e. Movement of the TSC or CONCRE

permitted.

Certificate of Compliance No. 1031 A4-5

-0612,

I orientation is not

Amendment No. 7

Page 45: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

1.

DESIGN FEATURES 4.0

Table A4-1 Load Combinations and Service Condition Definitions for the TSC Handling and Transfer Facility Structure

Load Combination

D*

D+S

D + M + W'1

D+F

D+E

D+Y

D

D*

s M

W'

F

E y

= = = = = = =

ASME Section Ill Service

Condition for Definition of

Allowable Stress

Level A

LevelD

Crane hook dead load "-·~

Note

·~~liminated based on a Probabilistic Risk

Certificate of Compliance No. 1031 A4-6 Amendment No. 7

Page 46: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

5.0

5.1

5.2

ADMINISTRATIVE CONTROLS AND PROGRAMS 5.0

ADMINISTRATIVE CONTROLS AND PROGRAMS The following programs shall be established, implemented and maintained.

Radioactive Effluent Control Program

5.1.1 A program shall be established and maintained to implement the requirements of 10 CFR 72.44 (d) or 10 CFR 72.126, as appropriate.

5.1.2 The MAGNASTOR SYSTEM does not create any radi ~~~~, have any radioactive waste treatment systems. ;n operating procedures for the control of radioa" required. LCO 3.3.2, TSC Surface Contami.~io , that excessive surface contamination is n .,Jj~availabl radioactive effluent.

5.1.3 This program includes an environ general license user may incorpor: into their environmental operations.

TSC Loading, Unloading, and

A program shall be establ' ed and ,.,,., ntained to implement the FSAR, Chapter 9 requirement ~ig fuel anfomponents into the TSC, unloading fuel and compone r-$"~.dJ~preparing the TSC and CONCRETE CASK for storage. r ements of the program for loading and preparing the TSC shall be co t~'tl prior to removing the TSC from the 10 CFR 50 structure. ,tJ;~~~ I provide for evaluation and control of the following FSAR re!jjf"ements"e~i\ • applicable operation:

a. VJirl}Jy that no T'ftNSFER CASK handling or CONCRETE CASK a~'Ct}1~~ usin~sm:e lifting lugs occurs when the ambient temperature is

°F:<'il~lL,r;rJ'ifis NOT applicable to the stainless steel MTC or PMTC.

,;;;~.ater temperature of a water-filled, or partially filled, loaded TSC '·:·'~ 1~We1ishown by analysis and/or measurement to be less than boiling at

II times.

~erify that the drying time, cavity vacuum pressure, and component and gas temperatures ensure that the fuel cladding temperature limit of 400°C is not exceeded during TSC preparation activities, including TRANSFER OPERATIONS, and that the TSC is adequately dry. For fuel with burnup > 45 GWd/MTU, limit cooling cycles to :5 10 for temperature changes greater than 65°C.

d. Verify that the helium backfill purity and mass assure adequate heat transfer and preclude fuel cladding corrosion.

e. The integrity of the inner port cover welds to the closure lid at the vent port and at the drain port shall be verified in accordance with the procedures in Section 9.1.1.

(continued)

Certificate of Compliance No. 1031 AS-1 Amendment No. 7

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5.3

5.4

ADMINISTRATIVE CONTROLS AND PROGRAMS 5.0

f. Verify that the time to complete the transfer of the TSC from the TRANSFER CASK to the CONCRETE CASK and from a CONCRETE CASK to another CONCRETE CASK assures that the fuel cladding temperature limit of 400°C is not exceeded.

g. The surface dose rates of the CONCRETE CASK are adequate to allow proper storage and to assure consistency with the offsite dose analysis.

h. The equipment used to move the loaded CONCRETE CASK onto or from the ISFSI site contains no more than 50 gallons of fuel.

This program will control limits, surveillances, compe · ory appropriate completion times to assure the integri!X:~Of t times in preparation for and during LOADING · ERATIO ,,;,;~.

OPERATIONS, TRANSPORT OPERATIONS, OP . STORAGE OPERATIONS, as applicable.

Transport Evaluation Program

ram to implement FSAR requirements for ISFSI rens.

At a ~!mum, the program shall include the following criteria to be verified and controlled:

Minimum CONCRETE CASK center-to-center spacing.

b. ISFSI pad parameters (i.e., thickness, concrete strength, soil modulus, reinforcement, etc.) are consistent with the FSAR analyses.

c. Maximum CONCRETE CASK lift heights ensure that the g-load limits analyzed in the FSAR are not exceeded.

(continued)

Certificate of Compliance No. 1031 A5-2 Amendment No. 7

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5.5

5.6

ADMINISTRATIVE CONTROLS AND PROGRAMS 5.0

Radiation Protection Program

5.5.1 Each cask user shall ensure that the 10 CFR 50 radiation protection program appropriately addresses dry storage cask loading and unloading, and ISFSI operations, including transport of the loaded CONCRETE CASK outside of facilities governed by 10 CFR 50. The radiation protection program shall include appropriate controls and monitoring for direct radiation and surface contamination, ensuring compliance with applicable regulations, and implementing actions to maintain personnel occupational exposures ALARA. The actions and c ;ittirf'~~<<be included in the program are provided as follows.

5.5.2 CASK

occurrences, such as handling transfer cask.

5.5.3 FR 72.212(b)(5)(iii), the that the dose limits of 10

5.5.4 blish limits on the surface contamination of the , TSC and TRANSFER CASK, and procedures for the

1 n -~\ :fiJp the established limits prior to ren:ov~I of_ t~e ponents fr~~ t~::t;lO CFR 50 structure. Surface contamination llm1ts

fo e TSC pri~W to placement in STORAGE OPERATIONS shall meet e 1 ~d1s establJ~hed in LCO 3.3.2.

"<!!,'f~1t1tflY nts for the First System Placed in Service

at trans er characteristics and thermal performance of the MAGNASTOR 1\.11 will be validated by recorded mass flow measurements in the air flow

coolin ·~assages of the first system placed in service with a heat load equal to or greater than 30 kW. A letter report summarizing the results of the measurements with respect to analyses of the actual canister content will be submitted to the

RC in accordance with 10 CFR 72.4 within 60 days of placing the loaded cask on the ISFSI pad. The report will include a comparison of the calculated mass flow of the MAGNASTOR SYSTEM at the loaded heat load to the measured mass flow. A report is not required to be submitted for the MAGNASTOR SYSTEMs that are subsequently loaded, provided that the performance of the first system placed in service with a heat load of;;::: 30 kW is demonstrated by the comparison of the calculated and measured mass flow rates.

(continued)

Certificate of Compliance No. 1031 AS-3 Amendment No. 7

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5.7

5.8

ADMINISTRATIVE CONTROLS AND PROGRAMS 5.0

Training Program

A training program for the MAGNASTOR system shall be developed under the general licensee's systematic approach to training (SAT). Training modules shall include comprehensive instructions for the operation and maintenance of the MAGNASTOR system and the independent spent fuel storage installation (ISFSI).

Preoperational Testing and Training Exercises

a. Moving the CONCRETE CASK into b. Moving the TRANSFER CASK cont

pool c. Loading one or more dum

independent verification

, area , TSC into the spent fuel

d. Selection and verifi appropriate load·

s to ensure conformance with

e. Installing the c f. Removal of th R CASK from the spent fuel pool g. e TSC to demonstrate pressure testing, vacuum

elding, weld inspection and documentation, and

ovement through the designated load path stallation on the CONCRETE CASK

~~~~to the CONCRETE CASK

\lir~li1Jhl!$~r&~CASK lid assembly installation po the CONCRETE CASK to the ISFSI removal from the CONCRETE CASK 'nloading, including reflooding and weld removal or cutting

propriate mock-up fixtures may be used to demonstrate and/or to qualify edures, processes or personnel in welding, weld inspection, vacuum drying,

he rum backfilling, leak testing and weld removal or cutting. Previously completed and documented demonstrations of specific processes and procedures may be used, as applicable, for implementation of the MAGNASTOR SYSTEM at a specific loading facility.

Certificate of Compliance No. 1031 A5-4 Amendment No. 7

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APPENDIXB

Certificate of Compliance No. 1031 B-1 Amendment No. 7

Page 51: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Appendix B Table of Contents

1.0 FUEL SPECIFICATIONS AND LOADING CONDITIONS ......................................................... B1-1

2.0 FUEL TO BE STORED IN THE MAGNASTOR SYSTEM ......................................................... B2-1

Figure B2-1 Figure B2-2 Figure B2-3

Figure B2-4 Figure B2-5 Figure B2-6

Table B2-1 Table B2-2 Table B2-3 Table B2-4

Table B2-5

Table B2-6 Table B2-7 Table B2-8 Table B2-9 Table B2-10 Table B2-11 Table B2-12

Table 82-13

List of Figures

Schematic of 37-Assembly PWR Basket. ................................... . Schematic of 37-Assembly PWR Basket Preferential Loading Patte Schematic of OF Basket Assembly Configuration for PWR SNF DFCs .................................................................... . Schematic of 87-Assembly BWR Basket. ....................... . Schematic of 82-Assembly BWR Basket ........................ . BWR Partial Length Fuel Rod Location Sketches ....... .

List of Tables

TSC with PWR Fuel Limits ............................ . PWR Fuel Assembly Characteristics ........... . Bounding PWR Fuel Assembly Loadin Crit Bounding PWR Fuel Assembly Lo Ulilt Boron Limits . . . . .. . .. . . . . . .. . .. . ............ "'· Additional SNF Assembly Cool HARDWARE .............................. .

B2-13 B2-14

B2-15 .B2-21

.. B2-22 . .... B2-23

Allowed BPAA/NSA Bur Allowed GTPD/NSA B · PWR Fuel Prefereni· TSC with BWR Fuel BWR SNF As BWRSNF

nations ........................................ B2-11 inations ........................................ B2-11

ions .................................................... B2-12

BWRSNF · eria - Enrichment Limits for onfigurations .......................................................... B2-20

Table B2-14 in , SNF Assembly Average Burnup Enrichment its.. . ................................................................................................................... B2-24

Table B2-15 · , ·:r~WR Fuel - 959 W/Assembly ....................................................... B2-25 Table B ing Table orPWR Fuel - 911 W/Assembly ....................................................... B2-30 Tab!. Table for PWR Fuel - 1,200 W/Assembly .................................................... B2-38 Ta " oa '~j51ble for PWR Fuel - 1, 140 W/Assembly .................................................... B2-43 Tab Loading · able for PWR Fuel - 922 W/Assembly ....................................................... B2-51 Table . . Loading Table for PWR Fuel - 876 W/Assembly ....................................................... B2-56 Table B2~2f , Loading Table for PWR Fuel - 800 W/Assembly ....................................................... B2-64 Table B2-22~~Loading Table for PWR Fuel - 760 W/Assembly ....................................................... B2-69 Table B2-23 ''"Loading Table for BWR Fuel - 379 W/Assembly ....................................................... B2-77 Table B2-24 Loading Table for BWR Fuel - 360 W/Assembly ............................................................. B2-82 Table B2-25 Loading Table for PWR Fuel - 959 W/Assembly-WE 14x14 Fuel. ............................. B2-90 Table B2-26 Loading Table for PWR Fuel - 513 W/Assembly-WE 14x14 Fuel. ............................. B2-93 Table B2-27 Loading Table for PWR Fuel -1300 W/Assembly- WE 14x14 Fuel ........................... B2-96 Table B2-28 Loading Table for PWR Fuel -1800 W/Assembly-WE 14x14 Fuel ........................... B2-99 Table B2-29 Loading Table for PWR Fuel - 830 W/Assembly-WE 14x14 Fuel. ........................... B2-102 Table B2-30 Loading Table for PWR Fuel - 487 W/Assembly - WE 14x14 Fuel. ........................... B2-105 Table B2-31 Loading Table for PWR Fuel -1235 W/Assembly- WE 14x14 Fuel ......................... B2-108 Table B2-32 Loading Table for PWR Fuel - 1710 W/Assembly - WE 14x14 Fuel ......................... B2-111 Table B2-33 Loading Table for PWR Fuel - 788 W/Assembly- WE 14x14 Fuel. ........................... B2-114

Certificate of Compliance No. 1031 B-2 Amendment No. 7

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Table 82-34 Table 82-35 Table 82-36 Table 82-37 Table 82-38 Table 82-39 Table 82-40 Table 82-41 Table 82-42

Table 82-43

Loading Table for PWR Fuel - 513 W/Assembly - CE 16x16 Fuel ............................ 82-117 Loading Table for PWR Fuel -1300 W/Assembly- CE 16x16 Fuel .......................... 82-120 Loading Table for PWR Fuel - 1800 W/Assembly - CE 16x16 Fuel .......................... 82-123 Loading Table for PWR Fuel - 830 W/Assembly - CE 16x16 Fuel ............................ 82-126 Loading Table for PWR Fuel - 487 W/Assembly- CE 16x16 Fuel ............................ 82-129 Loading Table for PWR Fuel-1235 W/Assembly- CE 16x16 Fuel .......................... 82-132 Loading Table for PWR Fuel - 1710 W/Assembly - CE 16x16 Fuel .......................... 82-135 Loading Table for PWR Fuel - 788 W/Assembly - CE 16x16 Fuel ............................ 82-138 Low SNF Assembly Average 8urnup Enrichment Limits for CE 16x16 Fuel Loaded via the PMTC ........................................................................ . ....... 82-141 Loading Table for CE 16x16 Fuel Loaded via the PMTC .............. . ... 82-141

Certificate of Compliance No. 1031 8-3 Amendment No. 7

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1.0 FUEL SPECIFICATIONS AND LOADING CONDITIONS

Appendix B Approved Contents

The MAGNASTOR SYSTEM is designed to safely store up to 37 undamaged PWR fuel assemblies in the 37 PWR Basket Assembly or up to 87 undamaged BWR fuel assemblies in the 87 BWR Basket Assembly. The system is also designed to store up to 4 damaged fuel cans (DFCs) in the OF Basket Assembly. The OF Basket Assembly has a capacity of up to 37 undamaged PWR fuel assemblies including 4 DFC locations. DFCs may be placed in up to 4 of the DFC locations. Each DFC may contain an undamaged PW ·~~,mbly, a damaged PWR fuel assembly, or PWR FUEL DEBRIS eq,\c!i' nt to WR fuel assembly. FUEL DEBRIS is included in the definiti n'a MAGE EL (Appendix A, Section 1.1). PWR UNDAMAGED FU placed directly in the DFC locations of a OF Baske a DFC.

The system requires few operating contr~:IUp MAGNASTOR are satisfied by the selec ':'n of fue Approved Contents presented in this se design basis spent fuels.

If any Fuel Specification or Lo following actions shall be co

"' at meets the ah. for MAGNASTOR

ction is violated, the

• ced in a safe condition .

Certificate of Compliance No. 1031

special report that describes the cause of the n to restore or demonstrate compliance and

81-1 Amendment No. 7

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2.0 FUEL TO BE STORED IN THE MAGNASTOR SYSTEM

UNDAMAGED PWR FUEL ASSEMBLIES, DAMAGED PWR FUEL ASSEMBLIES, PWR FUEL DEBRIS (DAMAGED FUEL), UNDAMAGED BWR FUEL ASSEMBLIES and NONFUEL HARDWARE meeting the limits specified in Tables B2-1 through B2-41 may be stored in the MAGNASTOR SYSTEM.

Certificate of Compliance No. 1031 82-1 Amendment No. 7

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Appendix B Approved Contents

Table 82-1 TSC with PWR Fuel Limits

I. TSC with PWR Fuel Basket

A. Allowable Contents

1. Uranium PWR UNDAMAGED FUEL ASSEMBLIES listed in Tables B2-2 and B2-3 and meeting the following specifications:

a. Cladding Type:

b. Enrichment, Post-irradiation Cooling Time and Average Assembly Burnup:

. Total Canister Contents Weight (lbs.):

Zirconium-based alloy.

Generic maximum enrichment limits are shown in Table B2-2. The physical characteristics · erent PWR SNF ASSEMBLIES are defined i The fuel

1,200 wausa

:::; 959 wattsb

:::; 178.3

:::; 8.54

imum

u cool time

2-15 through in Tables B2-25

ables B2-34 through erage burnup levels

s B2-15 through B2-22, an 1 ool time is specified le B2-13, provided that the minimum bly average enrichment limits are imum cool times for fuel in TSCs

he PMTC are specified in Tables B2-42

:::; 1,765, including SNF Assembly, NONFUEL HARDWARE and fuel spacers :::; 62, 160, including SNF Assemblies, NON FUEL HARDWARE and fuel spacers

B. Quantity per TSC: Up to 37 PWR UNDAMAGED SNF ASSEMBLIES as shown in Figure B2-1.

a 1,800 Watts for the four-zone preferential loading with WE l 4x 14 and CE l 6x 16 fuel

b 811 Watts for the PMTC with CE l 6x 16 fuel only

(continued)

Certificate of Compliance No. 1031 82-2 Amendment No. 7

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Table 82-1 TSC with PWR Fuel Limits (continued)

C. PWR UNDAMAGED SNF ASSEMBLIES may contain NONFUEL HARDWARE. SNF assembly lattices possessing less than the nominal number of undamaged fuel rods specified in Table 82-3 must contain solid filler rods that displace a volume equal to, or greater than, that of the fuel rod that the filler rod replaces. SNF assemblies may have stainless steel rods inserted to displace guide tube "dashpot" water. NONFUEL HARDWARE cool times shall be in accordance with Tables 82-5, 82-6, and 82-7. Alternatively, the 6°Co curie limits in Tables 82-6 and 82-7 may be used to establish site-specific NONFUEL HARDWARE constraints.

D. Spacers may be used in a TSC to axially position SNF assemblies to facili operations.

E. Unenriched fuel assemblies and unirradiated (i.e., not inserted in-co )'fuel asse

F. S~F may be loaded un!formly at a maxi~um h~at l~~~-:9.'. 9 ~·t as~em.!;5Jy, . . (Figure 82-1). Alternatively, a preferential loadin1~~ttei~may fu~ ft~Ph described in Tabl~ 82-8 and Figure 82-2. TSCs to be transfe. · d via tB~@.~T ·~~~; e loaded at a

maximum heat load of 811 watts/assembly. TS b,~an·sfe"@··.·· .. ·.-.·.';,i .. ~.·.··· d via the PMTC may be loaded at a maximum heat load of 811 w se y. J:&!/f

G. RCCs are restricted to fuel storage IOEi3 ions No. ··''" 12f'J~9, 20, 25, 26 and 27 (Figure 82-1). Minimum RCC cool times ar '\"i··.·,

Minimum Cool

(year .

10

I:

180

270

360

H. One Neutron Sit~ ce, or Neu~)i Source Assembly (NSA) is permitted to be loaded in a TSC in fu;j:sf.?1:a~7~0 ·~!!.~ No . .Y,1/12, 13, 18, 19, 20, 25, 26, o~ 27_ (F!gure 82-1 ) .. Neutron_ source as)~bhes ,?iY conta~c::e rods attached to hardware s1m1lar in configuration to guide tube p~~~~e · .\Q~~e plugs) and burnable absorbers, in addition to containing burnable poison rodlets-, tliimo~lug rodlets. For NSAs containing absorber rodlets, the BPAA cool time

ili p/exposure or hardware 6°Co curie limit listed in Table 82-6 are applied to the neutron Ji),,

e . ~f\s having only thimble plug rodlets require the thimble plug restriction in Table 82-7 appliea~ombination NSAs, containing both thimble plug and burnable absorber rodlets

ust apply the more limiting of the two minimum cool time/curie limit.

i;L,Jel assemblies may contain any number of unirradiated (i.e., not inserted in-core) nonfuel §6~ filler fuel replacement rods. Activated stainless steel rods are limited to 5 per assembly at a maximum burnup/exposure of 32.5 GWd/MTU.

J. Fuel assemblies may contain an HFRA at a maximum burnup/exposure of 4.0 GWd/MTU and a minimum cool time of 16 years.

(continued)

a 2.5 years for the WE 14x14 RCC in uniform and four-zone preferential loading and 5.0 years for the CE

16x16 RCC in uniform and four-zone preferential loading (footnote not applicable for PMTC payloads)

Certificate of Compliance No. 1031 82-3 Amendment No. 7

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Table 82-1 TSC with PWR Fuel Limits (continued)

II. TSC with OF Basket Assembly

A. Allowable Contents

1. Uranium PWR UNDAMAGED SNF ASSEMBLIES and DAMAGED FUEL (PWR DAMAGED SNF ASSEMBLIES or PWR FUEL DEBRIS) listed in Tables 82-2 and B2-3 and meeting the following specifications:

a. Cladding Type: Zirconium-based alloy.

b. Enrichment, Post-irradiation Cooling Time and Average Assembly Burnup:

c.

-~~resh SNF Assy:

omin~l(~resh SNF Assembly Width (in.):

Weight Per Storage location lbs.)

g. Total Canister Contents Weight (lbs.):

Generic maximum enrichment limits are shown in Table

B2-2. The physical characteristics oft ifferent PWR

SNF ASSEMBLIES are defined in ·•· The fuel type specific maximum enrich~tiJYas a func ·'-'of

neutron absorber sheet are de~~~-<at various l.!Pimum ~ ~:;,,.~

soluble boron levels are ned in' T &1~2-4; .• pr

variable enrichment se~i~J~es, ~~~ SNF enrichments represen lenrichments. Combined

minimum enri~,~~b· . ,111i;~ S . embly average

burnup and~.:'lnimum cool t~~l!iJp: re shown generically f ro"dgli B2-22 and

14x14 i ... ables B2-25 through B2-33 ,,,.~ff.

T · •·34 through B2-41. For SNF

p levels below those shown in

ugh B2-22, an SNF assembly

e is specified generically in Table B2-

,3, t the minimum initial SNF assembly

verage enrichment limits are applied. The minimum

cool times for fuel in TSCs transferred via the PMTC are

specified in Tables B2-42 and B2-43.

:5 1,200 wattsa :5 959 wattsb

:5 178.3

:5 8.54

:5 1,765, including SNF Assembly, NONFUEL HARDWARE, DFC and fuel spacer

:5 61, 184, including SNF Assemblies, NON FUEL HARDWARE, DFCs and fuel spacers c

(continued)

a 1,800 Watts for the four-zone preferential loading with WE 14x14 and CE 16x16 fuel

b 811 Watts for the PMTC with CE l 6x 16 fuel only

c Nominal TSC weight plus maximum contents ::; I 04,500 lbs.

Certificate of Compliance No. 1031 82-4 Amendment No. 7

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Table 82-1 TSC with PWR Fuel Limits (continued)

B. Quantity per TSC: Up to a total of 37 PWR UNDAMAGED SNF ASSEMBLIES including up to four (4) DFCs containing PWR UNDAMAGED SNF ASSEMBLIES, PWR DAMAGED SNF ASSEMBLIES, and/or PWR FUEL DEBRIS loaded in the DFC locations No. 4, 8, 30 and 34, as shown on Figure B2-3, for the OF Basket Assembly.

C. The contents of a DFC must be less than, or equivalent to, one PWR UNDAMAGED SNF ASSEMBLY. PWR SNF ASSEMBLIES loaded in a DFC shall not contain

NONFUEL HARD_W~RE wi_th the exceptio~ of instrument tube .. ·.t .. · ... ~e.·· .. ~~.·.·."·f~~J;i~~ .. t ...••• s •. •···, guide tube anchors or s1m1lar devices, and steel inserts. {{ "'\

D. PWR UNDAMAGED SNF ASSEMBLIES not loaded in a Z;.qJ!.~iC ni~'fO. n.tain. )·'· ,~!~ NON FUEL HARDWARE consistent with Table B2-5. S~ ass~m~,!pttice.~)1ot containing the nominal number of fuel rods specifie able.~3 ~t1~¢]htain solid filler rods that displace a volume equal to, or greater · , J~~ of th~ll~od that the filler rod replaces. SNF assemblies may hav aiftJless s~4f ro · <erted to displace guide tube "dashpot" water. NONF L HA~.O,WAf'R·~'.>.- times shall be in accordance with Tables B2-5, B2-6, and B2~~~~~~iy~tl'.le 6°Co curie limits in Tables B2-6 and B2-7 may be used to,~~~!f3blisf.t:!site-speq~~ NONFUEL HARDWARE constrai~ts. ~lterna9:(dJy~tfr~<(o 9-:~f~li~fs in Tables ~2-6 and B2-7 may be used to establish s1te-spec~fic NONF~.~;t RARE>WARE constraints.

E. Spacers may be used in a TSC to :,,. ally positi~~ PWR UNDAMAGED SNF ASSEMBLIES, and DFC~&'PCJJitat~,::.~.~dlin nd operation.

F. Unenric~ed fuel asseQi,l~~s an ir~iaf .e., n_ot inserted i~-core) fuel assemblies are not auth©:nzed"",· oading. Low ennched, unennched, and/or annular fuel pellet axial e c;l~blgni?ef' fjJ't permitted, provided that the nominal length of the end blanket is. rgfe!:i~t ix (6) inches.

G. RCCs are re1 ~1cted to fue\s,,tor g.e locations No. 11, 12, 13, 18, 19, 20, 25, 26 and

27 (Fi~,~~:B2~~\ Minimun;i~if CC cool times are:

/~M!niml:Jm,~ogJ'.'!l)me Maximum Exposure / . . (Yeaf-s7.wv (GWd/MTU)

180 270

20 360

(continued)

a 2.5 years for the WE 14x14 RCC in uniform and four-zone preferential loading and 5.0

years for the CE 16x16 RCC in uniform and four-zone preferential loading (footnote

not applicable for PMTC payloads)

Certificate of Compliance No. 1031 82-5 Amendment No. 7

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Table 82-1 TSC with PWR Fuel Limits (continued)

H. One Neutron Source, or Neutron Source Assembly (NSA) is permitted to be loaded in a TSC in fuel storage locations No. 11, 12, 13, 18, 19, 20, 25, 26 or 27 (Figure 82-1). Neutron source assemblies may contain source rods attached to hardware similar in configuration to guide tube plug devices (thimble plugs) and burnable absorbers, in addition to containing burnable poison rodlets and/or thimble plug rodlets. For NSAs containing absorber rodlets, the 8PAA cool time and burnup/exposure or hardware 6°Co curie limit listed in Table 82-6 are applied to the neutron sources. NSAs having only thimbl~ pl~g rodlets requir~ ~he thimbl~ plug restriction in Table 82~~iflied. Combrnatron NSAs, contarnrng both thimble plug and burnable al;>$'Orber roale must apply the more limiting of the two minimum cool time/curie li~.it <~\.,

I. Fuel assemblies may contain any number of unirradiate~11~., not'fi~~rted i~"' ore)

nonfuel solid filler fuel replacement rods. Activated ~\r.l~s. s••· .~~r~I roe.. ifuited to 5 per assembly at a maximum burnup/exposure of 3ll~~TU. .

J. Fuel assemblies may contain an-HFRA at a Jrn:tl!m oi:iti;l;i'.1 /exp ~e of 4.0 GWd/MTU and a minimum cool time of 16 y

Certificate of Compliance No. 1031 82-6 Amendment No. 7

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Table 82-2 PWR Fuel Assembly Characteristic

Characteristic 14x14 Max Initial Enrichment wt% 23su 5.0 5.0 Min Initial Enrichment wt % 23su 1.3 1.3 Number of Fuel Rods 176 179 Max Assembly Average Burnup 60,000 60,000 MWd/MTU

62,500

Max Decay Heat (Watts) per 1,200

62,500 4

See Note 1 1, 800

Appendix B Approved Contents

17x17 5.0 1.3 264

60,000

62,500 4

See Note 1 1,200

Preferential Stora e Location ;:\ ~~~---.__,._~~~~~~~~~~~~~~~-

A I I rt d . h t I ,.;. ·' I' d' ·~ f ).It. I • r~po e_ ~-nnc ~en va u~s are n~_lll1a ~ . l.:· 1 ~rca ion va ues. . . . • Maximum 1nit1al enrichment 1s based o~m1 Jm soluble boron concentration 1n the spent fuel pool water. Required

soluble boron content is fuel ty1=1~~?r!R en'ff': nt specific. Minimum soluble boron content varies between 1,500 and 2,500 ppm. Maximum initial eJ~tietfmt'nt esents the peak fuel rod enrichment for variably-enriched fuel assemblies. t.f.u.ff.·:s "'.;~s:H

~ . '~

1" :~,, ·~h ··•"· Notes: /'" )'.~: ";.;;t;::;~~~··, 1. Maximum weighf'~~r, stori;9g~~JJ=?Ration is as detailed in Table 82-1

2. Minimum c~qJ~!!'.P~ "~67JWE 14x14 PWR fuel for uniform and four-zone preferential loading

Certificate of Compliance No. 1031 82-7 Amendment No. 7

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Appendix B Approved Contents

Table 82-3 Bounding PWR Fuel Assembly Loading Criteria

Geometry2

Min Min Max Max

No. of No. of Max Clad Clad Pellet

Assembly Fuel Guide Pitch OD Thick. OD Type Rods Tubes1 (inch) (inch) (inch)

BW15H1 208 17 0.568 0.43 0.0265

BW15H2 208 17 0.568 0.43 0.025

BW15H3 208 17 0.568 0.428

BW15H4 208 17 0.568 0.414

BW17H1 264 25 0.502

CE14H1 176 5

CE16H1 236 5 0.4463

WE14H1 179 0.3674 145.2 0.4188

WE15H1 204 0.3669 144.0 0.4720

WE15H2 0.357 144.0 0.4469

WE17H1 0.372 0.0205 0.3232 144.0 0.4740

WE17H2 0.36 0.0225 0.3088 144.0 0.4327

cold, unirradiated, nominal configurations.

Certificate of Compliance No. 1031 82-8 Amendment No. 7

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Appendix B Approved Contents

Table B2-4 Bounding PWR Fuel Assembly Loading Criteria -Enrichment/Soluble Boron Limits

TSC with Undamaged PWR Fuel Basket Assembly Max. Initial Enrichment (wt% 235U) Absorber• 0.036 10B g/cm2 Absorber• 0.030 10B g/cm2 Absorber• 0.027 10B g/cm2

Soluble 1500 1750 2000 2250 2500 1500 1750 2000 2250 2500 1500 1750 2000 2250 Boron (ppm) (ppm) (ppm) (ppm) (ppm) (ppm) (ppm) (ppm) (ppm) (ppm) (ppm) (ppm) (ppm) (ppm)

BW15H1 3.7% 4.1% 4.4% 4.7% 5.0% 3.6% 4.0% 4.2% 4.5% 4.8% 3.6% A!!3" ~2o/c 4.5% "'3;!V/o- "'-;J'. '',0

BW15H2 3.7% 4.0% 4.3% 4.6% 4.9% 3.6% 3.9% 4.2% 4.5% 4.8% 3 6o/f0 . p,,,• tr.a% '-;,;;.;,,

4.1%: 4.4% '\'

~~o ~.4% BW15H3 3.7% 4.0% 4.3% 4.6% 4.9% 3.6% 3.9% 4.2% 4.4% 4.7% ,.<3,§%. 4.1%

5 Oo/cdi 73.7% ~£\\!~

4 3Y<A 1

BW15H4 3.8% 4.2% 4.5% 4.8% 5.0% 3.7% 4.1% 4.4% 4.7% . u,o:;J 4.o~;'~ >... • ,o .. : 4.6% ,&:::/

3.p%S ::>3.9% ~ '. ¥6( BW17H1 3.7% 4.0% 4.3% 4.6% 4.9% 3.6% 3.9% 4.2% 4.5% Lt~S?L<1- \.;~,j;Yo 4.5% ,,,

CE14H1 4.5% 5.0% 5.0%

~ I> 5.0% 4.8% 5.0% 4.3% 4.7% 5.0% s 3% 4

5.0%

CE16H1 4.4% 4.8% 5.0% 5.0% 5.0% 4.3% 4.6% 5.0% . Yo 4.9% 5.0%

WE14H1 4.7% 5.0% 5.0% 5.0% 5.0% 4.6% 5.0% 5.0% ~,.5% 5.0% 5.0% 5.0%

WE15H1 3.8% 4.2% 4.5% 4.8% 5.0% 3.7% 4.1o/c %!' ,4.7% 5.0% lh% 4.0% 4.3% 4.6%

"' (:~P/o < ~ 73.8% WE15H2 4.0% 4.4% 4.7% 5.0% 5.0% 3.9% 4. 4.6% 4.2% 4.5% 4.8%

WE17H1 3.7% 4.1% 4.4% 4.7% 5.0% 3.7% 4. 4.3% \'~ 4.6,~ 4.9% 3.6% 3.9% 4.2% 4.5%

39~~ k"J WE17H2 4.0% 4.3% 4.7% 5.0% 5.0% ;.,"" ~ l ~~ ~' .6% 49% 5.0% 3.8% 4.2% 4.5% 4.9%

.-;if" , '.

•'. ".•" -FueJJket Assembl Max. Initial Enrichment wt % 235U

BW15H1 3.7% 4.0% 4.3% 4.4%

BW15H2 3.6% 3.9% 4.2% 4.1% 4.4% 4.7% 3.5% 3.8% 4.1% 4.3%

BW15H3 3.6% 3.9% 4.2% 4.1% 4.4% 4.6% 3.5% 3.8% 4.0% 4.3%

BW15H4 3.8% 4.1% 4.4%~ \' \ !: 1

4.7%·' 5.0% 3..Z0,1! 4.0% 4.3% 4.6% 4.9% 3.6% 3.9% 4.2% 4.5%

BW17H1 0 /-~ 3.6% 3.9 Yo.A fiA.2 Yo 3.9% 4.1% 4.4% 4.7% 3.5% 3.8% 4.1% 4.4%

CE14H1 4.3% 4.7% 5.0% 5.0% 5.0% 4.3% 4.6% 4.9% 5.0%

CE16H1 4.2% 4.6% 5.0% 5.0% 5.0% 4.2% 4.5% 4.9% 5.0%

WE14H1 5.0% 4.5% 5.0% 5.0% 5.0% 5.0% 4.5% 4.9% 5.0% 5.0%

WE15H1 5.0% 3.7% 4.0% 4.3% 4.6% 4.9% 3.6% 4.0% 4.3% 4.6%

WE15H2 4.6% 4.9% 5.0% 3.8% 4.2% 4.5% 4.8% 5.0% 3.8% 4.1% 4.4% 4.7%

WE17H1 4.3% 4.6% 4.9% 3.6% 3.9% 4.2% 4.5% 4.8% 3.6% 3.9% 4.2% 4.5% v

WE17H2 3.9% 4.3% 4.6% 5.0% 5.0% 3.9% 4.2% 4.5% 4.9% 5.0% 3.8% 4.1% 4.5% 4.8%

• Specified soluble boron concentrations are independent of whether an assembly contains a nonfuel insert.

a Borated aluminum neutron absorber sheet effective areal 108 density.

2500 (ppm)

4.8%

4.7%

4.7%

5.0%

4.7%

5.0%

5.0%

5.0%

4.9%

5.0%

4.9%

5.0%

4.7%

4.6%

4.6%

4.8%

4.6%

5.0%

5.0%

5.0%

4.8%

5.0%

4.8%

5.0%

Certificate of Compliance No. 1031 B2-9 Amendment No. 7

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Appendix B Approved Contents

Table 82-5 Additional SNF Assembly Cool Time Required to Load NONFUEL HARDWARE

Three-Zone Four-Zone Assy Uniform A 8 C A 81 82 C

CE 14x14 BPAA/HFRA

GTPD/NSA RCC 0.2 0.2 0.1 0.2

WE 14x14 BPAA/HFRA 0.5 0.5 0.2 0.7 GTPD/NSA 0.1 0.1 0.1

RC Ca 0.7 2.3 0.7 WE 15x15 BPAA/HFRA 0.5 0.6

GTPD/NSA 0.1 RCC 3.1

8&W 15x15 BPAA/HFRA GTPD/NSA

RCC CE 16x16 BPAA/HFRA

0.8 0.1 0.1 0.4 WE 17x17

0.1 0.1 3.3 1.4 4.3 0.1 0.1 0.1 0.1 0.1 0.1

0.2 0.2 0.1 0.2

. Ad'),,,~ al bly cooling time to be added to the minimum SNF assembly cool time ):l~qQ;Sf)l(_assembly initial enrichment and SNF assembly average burnup listed in Tables "Stnro·1:1gb{ff2-22 and 82-25 through 82-43.

a WE14x14 Uniform and four-zone preferential are evaluated using RCC with 2.5-year minimum

cool time

b CE16x16 Uniform and four-zone preferential are evaluated using RCC with 5-year minimum

cool time

c 0.4 years for RCC in the PMTC (reduced storage location heat load). For all other cask types,

0.3 years for RCC with 5-year minimum cool time or 0.2 years for RCC with I 0-year

minimum cool time.

Certificate of Compliance No. 1031 82-10 Amendment No. 7

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Appendix B Approved Contents

Table 82-6 Allowed 8PAA/NSA 8urnup and Cool Time Combinations

Maximum Burnup (GWd/MTU)

10 15 20 25 30

32.5 35

37.5 40 45 50 55 60 65 70

Max Go Co Activity (Ci)

WE 14x14 0.5 0.5 0.5 1.0 2.5 3.0 3.5 4.0 4.5 5.0 6.0 7.0 7.0 8.0 8.0 718

Certificate of Compliance No. 1031

Minimum Cool Time ( rs) WE 15x15 B&W 15x15

0.5 0.5 0.5 0.5 1.0 2.0 2.5 3.5 4.0 5.0 4.5 6.0 5.0 6.0 6.0 7.0 6.0 7.0 7.0 8.0 8.0 9.0_ 8.0 9.0 ~~10.0 10.0

Minimum Cool Time (yrs) B&W 15x15 WE 17x17 B&W 17x17

7.0 5.0 6.0 10.0 9.0 10.0 12.0 10.0 12.0 14.0 12.0 12.0 56.9 64.0 63.6

82-11 Amendment No. 7

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Appendix B Approved Contents

Table 82-8 PWR Fuel Preferential Loading Pattern Definitions

Three-Zone

Zone Description Maximum Heat Load see Fi ure 82-2 Desi nator W/ass #Assemblies

Inner Zone A 922 9 Middle Zone 8 1,200 1 •

~~~~~~--t~~~~-t-~~----'-~~~-+-~~

Outer Zone C 800

Four-Zone

Zone Description see Fi ure 82-2 Desi nator

Inner Zone A Middle Zone 81

82 Outer Zone c

Certificate of Compliance No. 1031 82-12 Amendment No. 7

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Figure 82-1 Schematic of 37-Assembly PWR Basket

(1) (2) (3)

(4) (5) (6) (7)

(9) (10) (11) (12)

(17) (18)

(24) (25) i (2

Certificate of Compliance No. 1031 82-13 Amendment No. 7

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Figure 82-2 Schematic of 37-Assembly PWR Basket Preferential Loading Patterns

Three-Zone

Refer to Table 82-8 for Maximum Heat Loads

Certificate of Compliance No. 1031 82-14 Amendment No. 7

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Figure 82-3 Schematic of OF Basket Assembly Configuration for PWR SNF with DFCs

DFC Location DFC Location

(1) (2) (3)

(5) (6) (7)

(9) (10) (11) (12)

(17) (18)

(24)

ed locations may contain a loaded DFC or a PWR UNDAMAGED SNF ASS EMBLY.

Certificate of Compliance No. 1031 82-15 Amendment No. 7

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Table 82-9 TSC with 8WR Fuel Limits

I. BWR FUEL

Appendix B Approved Contents

A. Allowable Contents

1. Uranium BWR UNDAMAGED FUEL assemblies listed in Tables 82-10 and 82-11 and meeting the following specifications:

a. Cladding Type: Zirconium-based alloy.

b. Enrichment: Post-irradiation Cooling Time and Assembly Average Burnup

Generic maximum INITIA'::,d[W~r:~LANAR­AVERAGE ENRICHM~~'5 ares ·. wn in Table 82-10. The ph~~~ charact '*'~ics of

~~~~

the different BWRL$).IF A"S~EMBLIErffire defined in Tabl~~2-11. F~·· • e ~~7cific enrichment lir:r:fits'ior th,e".87-a . mqly and 82-assembly BW~!Jel ,~~ket confi~Hrations are defined i le' .. ..- as a ction of neutrl1?i 0rber , .~J~;7 y. Combined minif~.m ~J!J~~{1~ITla)c1mum ?~F asse~ly~9s,reraQ~p1ur~p and mrrnmum cool

.,fJWry~mr~re sh ,p in Table 82-23 and it''? ~le;~~-24 ·NF assembly average

.0:~·:··. burnu"i5\~.v. el ow those shown in Table ·:~~' 82-23 a~]El Table 82-24, an SNF assembly

. .. .;;.;;{>,*minimu~l~ool time is s~~cified _in_ !able 82-.. ·1.~:4;;prpV1tled that the mmrmum m1t1al SNF • . •·q• '.::-% · · assembly average enrichment limits are

applied.

c. Decay )~!af·p~i1~··~·~ Assemb>ly: "<''\ · :5 379 watts

d. Nomi~~ll{resh Fue1piesign

- A'ksembly Ler;i§th (in.): :::; 176.2

al I Design "·•~~~~ly Width (in.): :5 5.52

Assembly Weight (lb): :5 704, including channels

antity per TSC: Up to 87 BWR UNDAMAGED SNF ASSEMBLIES. With the '•~\,exception of the designated nonfuel locations in the 82-assembly basket "-tq~iguration, fuel storage locations not containing a fuel assembly shall have an

efupty fuel cell insert installed. Prior to use of the 86 and 82-assembly configurations, the cell fuel storage locations as noted and shown in Figures 82-4 and 82-5 must be physically blocked to prevent fuel assembly loading, respectively.

(continued)

Certificate of Compliance No. 1031 82-16 Amendment No. 7

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Table 82-9 TSC with 8WR Fuel Limits (continued)

C. 8WR fuel assemblies may be unchanneled, or channeled with zirconium-based alloy channels.

D. 8WR fuel assemblies with stainless steel channels are not authorized.

E. SNF Assembly lattices possessing less than the nominal number of undamaged fuel rods (see Table 82-11) must contain solid filler rods that displace a volume equal to, or greater than, that of the fuel rod that the filler rod replaces.

F. Spacers may be used in a TSC to axially position 8WR SNF assemblies to facilitate handling.

G. Unirra?iated (i._e., not inserted in-co~e) fuel as~emblies are not ~<-~~~r loading. Unennched axial blankets are permitted, provided that the norm ·al leng~o'lltthe blanket is not greater than six (6) inches. . ,~

H. Allowable SNF assembly locations for the 86-assembly M~as e ·:~.s>nfigu~r~~ion is shown in Figure 82-4. ~ ~~ - ,,I;:/

41g,, '!l~~'\!i I. Allowable SNF assembly locations for the standard alteJlate 82-ass~tnbly fuel basket configurations are shown in Figure 82-5.: '"'

Certificate of Compliance No. 1031 82-17 Amendment No. 7

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Table 82-10 8WR SNF Assembly Characteristics

Characteristic 7x7

Max Initial Enrichment (wt % 23SU) 4.5

Number of Fuel Rods 48/49

Max Assembly Average Burnup (MWd/MTU) 60,000

Peak Average Rod Burn up (MWd/MTU) 62,500

Min Cool Time (years) .4

Min Average Enrichment (wt % 23SU)

Max Weight (lb) per Storage Location

Max Decay Heat (Watts) per Storage Location

Fuel Class

axa

4.5

59/60/61/ 62/63/64

gxg

4.5

• Each BWR fu_el a~sembly may in~lude a 41~\onium-ba ,1~~d alloy channel.

• Assembly weight includes the we1gh,t;~ft~ · hannel. J'

1ox10

4.5

0.7

704

379

• Maximum initial enrichment isU;r ~~f n \l·~*~g~nrichment. • Water rods may occupy more4fi,C!,Q o ? el lattice location. Fuel assembly to contain

nominal number of wate~~pds f'dr~"-> . · cific assembly design.

• All enrichment values;@. ~mG.U_ 1 p~1re)i;_r_ .. _ .• a __ . diation fabrication values. l/:! "\;'. \. "("·)i,_

• Spacers may be use~~ axially p'f'itiorli;f.tiel assemblies to facilitate handling.

v

(a) Assemblies may contain partial-length fuel rods.

Certificate of Compliance No. 1031 82-18 Amendment No. 7

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Assembly Type

87 48A 87 49A 87 498 88 59A 88 60A 88_608 88 618 88 62A 88_63A 88_64A 88 6485

89 72A 89 74A 89_76A 89 79A 89_80A 810_91A 810_92A 810 96A5

810_100A5

Table 82-11 BWR SNF Assembly Loading Criteria

Geometry 3.4

Min Min Max Max Number Number of Max Clad Clad Pellet Active Max of Fuel Partial Length Pitch OD Thick. OD Length Loading Rods Rods 1 (inch) (inch) (inch) (inch) (inch) (MTU)

48 N/A 0.7380 0.5700 0.03600 0.4900 ~1AA,,_O 0.1981 49 N/A 0.7380 0.5630 0.03200 0.488 1:t6~0?:, . "- ,,_,. 0.2034 49 N/A 0.7380 0.5630 0.03200 0.4 :

150.0 '\ 1~0.2115 59 N/A 0.6400 0.4930 0.03400 ,,,tM1 150.0 'i'Q.1828 60 N/A 0.6417 0.4840 0.03150~ ~0:4110 .0 t::y'0.1815 60 N/A 0.6400 0.4830 O.O~Qd_OY 0.41.40> .~Q/

'""'"!. ~ -'t . .J / 0.1841

61 N/A 0.6400 0.4830 o.o3o00'iJ o<4J4'6 Ui0~0/ 0.1872 62 N/A 0.6417 0.48304r J~2:!300"1~1'~d:'A160 ~.o 0.1921 63 N/A 0.6420 0.48, ,' 0.02725 b~~11Q.!?0~ 150.0 0.1985 64 N/A 0.6420 0.48.\d._ Q.0~¥~~!!

~ "·-,)·' ·'"~~y ;\Q.41'95 150.0 0.2017

64 N/A 0.6090 -00j576"- _:E)'.62900 }0}3913 150.0 0.1755 72 N/A 0.5720¥ o!b(j~48}30.., om ;o.3140 150.0 0.1803 742 8 o.5t~o 0.4240~1

i 0.3760 150.0 0.1873

76 N/A 0.5~2~ 0.4170 .02090 0.3750 150.0 0.1914 79 N/A d ""'fr.-5720~ ' 0.4240) ; ' .02390 0.3760 150.0 0.2000 ~ ·.~.·~ JL;,

80 N/A,L'f/ 6$~20~ ~0;4-230:, 1 0.02950 0.3565 150.0 0.1821 91 2 8~,~ O~'j100 . " ) 0.3957 0.02385 0.3420 150.0 0.1906 922 ;@~5100 0.4040 0.02600 0.3455 150.0 0.1966 962 4880 0.3780 0.02430 0.3224 150.0 0.1787

100 ~ N/A ~80 0.3780 0.02430 0.3224 150.0 0.1861 ,,

< ., A''>;; c"'

' ~ ""'~>t:1 .;-

A /'";'f

, Note: Amendment No. 2 removed the enrichment/soluble boron limits from this table. This information is now presented in Table 82-12.

Certificate of Compliance No. 1031 82-19 Amendment No. 7

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Table 82-12 BWR SNF Assembly Loading Criteria - Enrichment Limits for 87-Assembly and 82-Assembly Configurations

Max. Initial Enrichmenta wt % 235LJ

Absorber!> 0.027 108 /cm2 Absorber 0.0225 108 /cm2

87-Assy 82-Assy 87-Assy 82-Assy Basket Basket Basket Basket

87_48A 4.0% 4.5% 3.7% 4.5%

87_49A 3.8% 4.5% 3.6% 4.4% 87_498 3.8% 4.5% 3.6%

88_59A 3.9% 4.5% 3.7%

88_60A 3.8% 4.5% 3.7% 88_608 3.8% 4.5% 3.6% 88_618 3.8% 4.5% 3.6%

88_62A 3.8% 4.5%

88_63A 3.8% 4.5%

88_64A 3.8% 4.5%

88_648 3.6% 3.3% 89_72A 3.8% 3.4%

89_74A 3.7o/oC 3.4% 89_76A 4.0% 3.3%

89_79A 4.2% 3.3%

4.3% 3.5%

4.3% 3.5%

3.6% 4.3% 3.5%

3.5% 4.1% 3.4%

3.5% 4.1% 3.4%

a Maximum planar average.

b Borated aluminum neutron absorber sheet effective areal 108 density.

c 3.85% in the 86-assembly basket configuration

d 4.55% in the alternate 82-assembly basket configuration

Certificate of Compliance No. 1031 82-20

4.1%

4.2%

4.2%

4.0%

4.1%

4.0% 3.9%

4.0%

4.2%

4.1%

4.1%

4.0%

4.0%

Amendment No. 7

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Figure 82-4 Schematic of 87-Assembly BWR Basket

. · ·ation ust have an empty fuel cell insert installed in order to use the embly configuration.

Certificate of Compliance No. 1031 82-21 Amendment No. 7

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Figure 82-5 Schematic of 82-Assembly BWR Basket

Port Locations

Designated Nonfuel Locations fo1-Stan dmd 82-Assem bl y Con fig

Designated Nonfuel Locations fo1-Altemote 82-Assembly Config

Certificate of Compliance No. 1031 82-22 Amendment No. 7

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Figure 82-6 8WR Partial Length Fuel Rod Location Sketches

0 0000000 0 000000!0000 0 xOOxOOx O oxoooxooxo 0 0000000 0 0000000000 0 000 QOO 0 00000,0,0000

000 ooxo 0 X00 QX Q Q1X0 0000 0 00 000 0 000 0000 0 0000000 0 0000000000 0 xOOxOOx 0 OxOOxOOOxO 0 0000000 0 0000000000

0 = Fuel Rod Location

0 = Fuel Rod Location X = Partial Rod Location

X = Partial Rod Location

B9 _74A 8 Partial Length Rods '\.f211L'!...dff£1JJ!r01i:1JrJ{tfflfJLength Rods

~ 0000000000 0000000000 0 x 0 xoox ox 0 ~ oxoxo oxoxo

\ 0000000000 ~ 0000000000 , ) lloxoooooxo oxooo oooxo

oooox 000 0000 0000 ooooxoooo 0000 0000 0 xo ooox 0 oxooo oooxo 0000000000 0000000000 0 xOxOOxOx 0 oxoxo oxoxo 0000000000 0000000000

0 = Fuel Rod Location 0 = Fuel Rod Location

X = Partial Rod Location X = Partial Rod Location

0_92A 14 Partial Length Rods Bl0_96A 12 Partial Length Rods

\

Certificate of Compliance No. 1031 82-23 Amendment No. 7

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Table 82-13 PWR Loading Table- Low SNF Assembly Average 8urnup Enrichment Limits

Max. Assembly Avg. Min. Assembly Avg. Minimum Cool Time Burn up Initial Enrichment (yrs)

MWd/MTU wt% 235LJ

Heat Load er Ass 959W 800W 10,000 1.3 4.0 4.0 15,000 1.5 4.0 4.0 20,000 1.7 4.0 4.0 25,000 1.9 4.0 4.3 30,000 2.1 4.4 5.2

Table 82-14 8WR Loading Table - Low SNF Asse,plijiY?Av 11!~.\!ili"

Limits f,1{ ~~·

Max. Assembly Avg. Min. As~e~,:tv~. Burnup lnitial~~nrichmeritc~

MWd/MTU ~f/o 23su \;

Certificate of Compliance No. 1031 82-24

4.0 4.3

Amendment No. 7

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Table 82-15 Loading Table for PWR Fuel - 959 W/Assembly

30 <Assembly Average Burn up:::; 32.5 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 23su E 14x14 14x14 15x15 15x15 16x16 2.1 s E < 2.3 4.1 4.1 4.6 4.7 4.4 2.3 s E < 2.5 4.0 4.1 4.5 4.7 4.4 2.5:::; E < 2.7 4.0 4.0 4.5 4.6 4.3 2.7 s E < 2.9 4.0 4.0 4.5 4.5 4.3 2.9 s E < 3.1 4.0 4.0 4.4 4.5 4.2 3.1sE<3.3 4.0 4.0 4.4 4.5 4.2 3.3:::; E < 3.5 4.0 4.0 4.3 4.4 4 3.5 s E < 3.7 4.0 4.0 4.3 4.4 3.7 s E < 3.9 4.0 4.0 4.3 4.4 3.9 s E < 4.1 4.0 4.0 4.2 4 4.1 sE<4.3 4.0 4.0 4.2 4.3 s E < 4.5 4.0 4.0 4.2 4.5 s E < 4.7 4.0 4.0 4 4.7sE<4.9 4.0 4.0

E :2: 4.9 4.0 4.0

Initial Assembly Avg. Enrichment CE WE B&W

wt% 235U E 16x16 17x17 17x17 2.1sE<2.3 2.3 s E < 2.5 .0 5.1 4.7 5.0 5.0 2.5 s E < 2.7 4.9 5.0 4.7 5.0 5.0 2.7sE 4.8 5.0 4.6 4.9 4.9 2.9 4.8 4.9 4.6 4.9 4.9 3. 4.2 4.7 4.9 4.5 4.8 4.8

4.2 4.7 4.8 4.5 4.8 4.8 4.1 4.1 4.6 4.8 4.4 4.7 4.7 4.0 4.1 4.6 4.7 4.4 4.7 4.7 4.0 4.1 4.6 4.7 4.4 4.7 4.7 4.0 4.0 4.5 4.7 4.3 4.6 4.6

. c~E<4.5 4.0 4.0 4.5 4.6 4.3 4.6 4.6 4.5 ~ E < 4.7 4.0 4.0 4.5 4.6 4.3 4.6 4.6 4.7 s E < 4.9 4.0 4.0 4.4 4.6 4.3 4.5 4.5

E :2: 4.9 4.0 4.0 4.4 4.5 4.2 4.5 4.5

Certificate of Compliance No.1031 82-25 Amendment No. 7

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Table 82-15 Loading Table for PWR Fuel - 959 W/Assembly (continued)

35 <Assembly Average Burnup~ 37.5 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1~E<2.3

2.3 ~ E < 2.5 4.7 4.8 5.5 5.7 5.2 2.5 ~ E < 2.7 4.6 4.7 5.4 5.6 5.1 2.7~E<2.9 4.6 4.7 5.3 5.5 5.0 2.9~E<3.1 4.5 4.6 5.3 5.4 3.1~E<3.3 4.5 4.5 5.2 5.4 3.3 ~ E < 3.5 4.4 4.5 5.1 3.5 ~ E < 3.7 4.4 4.5 5.0 3.7 ~ E < 3.9 4.3 4.4 5.0 3.9 ~ E < 4.1 4.3 4.4 4.1~E<4.3 4.3 4.4 4.3 ~ E < 4.5 4.2 4.3 4.5 ~ E < 4.7 4.2 4.3 5.0 4.7~E<4.9 4.2 4.3 4.9

E z4.9 4.1 4.2 4.9

Initial Assembly Avg. Enrichment WE B&W

wt% 235U E 15x15 16x16 17x17 17x17 2.1~E<2.3

2.3 ~ E < 2.5 6.1 5.6 6.0 6.0 6.0 5.5 5.9 5.9 6.0 5.5 5.9 5.9

5.7 5.9 5.4 5.8 5.8 5.7 5.8 5.3 5.7 5.7

4.7 5.6 5.8 5.2 5.7 5.7 4.7 5.5 5.7 5.2 5.6 5.6 4.6 5.5 5.7 5.1 5.6 5.6

~ E < 4.3 4.6 5.4 5.6 5.1 5.5 5.5 4> , E < 4.5 4.5 4.7 5.4 5.6 5.0 5.5 5.5 4.5 ~ E < 4.7 4.5 4.6 5.3 5.5 5.0 5.4 5.4 4.7 ~ E < 4.9 4.5 4.6 5.3 5.5 5.0 5.4 5.4

Ez4.9 4.5 4.5 5.2 5.4 4.9 5.4 5.4

Certificate of Compliance No.1031 82-26 Amendment No. 7

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Table 82-15 Loading Table for PWR Fuel - 959 W/Assembly (continued)

40 <Assembly Average Burnup ~ 41 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 5.3 5.4 6.2 2.7 ~ E < 2.9 5.2 5.3 6.1 2.9 ~ E < 3.1 5.1 5.2 6.0 3.1~E<3.3 5.0 5.1 5.9 3.3 ~ E < 3.5 4.9 5.1 5.9 3.5 ~ E < 3.7 4.9 5.0 5.8 3.7 ~ E < 3.9 4.8 4.9 5.7 3.9 ~ E < 4.1 4.8 4.9 4.1~E<4.3 4.7 4.9 4.3 ~ E < 4.5 4.7 4.8 5.7 4.5 ~ E < 4.7 4.7 4.8 5.6 4.7 ~ E < 4.9 4.6 5.6

E~4.9 4.6 5.6 5.6

Initial Assembly Avg. Enrichment WE B&W

wt% 235U E 15x15 16x16 17x17 17x17 2.1~E<2.3

6.5 6.7 6.0 6.6 6.6 6.4 6.6 5.9 6.5 6.5 6.3 6.5 5.9 6.4 6.4 6.2 6.4 5.8 6.3 6.3

5.3 6.1 6.3 5.7 6.2 6.2 5.0 5.2 6.0 6.2 5.7 6.1 6.1 5.0 5.1 5.9 6.2 5.6 6.0 6.0 4.9 5.1 5.9 6.1 5.5 6.0 6.0 4.9 5.0 5.8 6.0 5.5 5.9 5.9 4.9 5.0 5.8 6.0 5.4 5.9 5.9

4.5~E<4.7 4.8 4.9 5.7 5.9 5.4 5.8 5.8 4.7 ~ E < 4.9 4.8 4.9 5.7 5.9 5.3 5.8 5.8

E~4.9 4.7 4.9 5.7 5.9 5.3 5.8 5.8

Certificate of Compliance No.1031 82-27 Amendment No. 7

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Table 82-15 Loading Table for PWR Fuel - 959 W/Assembly (continued)

42 < Assembly Average Burnup s 43 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235LJ E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1sE<2.3 2.3 ~ E < 2.5 2.5 ~ E < 2.7 5.7 5.8 6.8 2.7 ~ E < 2.9 5.6 5.7 6.7 2.9 ~ E < 3.1 5.5 5.6 6.6 3.1 ~E<3.3 5.4 5.6 6.5 3.3 ~ E < 3.5 5.3 5.5 6.4 3.5 ~ E < 3.7 5.3 5.4 6.3 3.7 ~ E < 3.9 5.2 5.3 6.2 3.9 ~ E < 4.1 5.1 5.3 6.1 5.7 4.1 ~E<4.3 5.0 5.2 6.0

\i'.'"~ 6~~ 4.3 ~ E < 4.5 5.0 5.2 6.0 6~~ ~·.1 "'I 4.5 ~ E < 4.7 5.0 5.1 5;,~ b.,,, ~f· ·o.n•''62

~·In ~} 7 4.7 ~ E < 4.9 4.9 5.0 5.9 ·~ ~~

4.9 ~ \;

E~4.9 5.0 8 6.0 ;:~ 5.5 5.9 . ' 43 ~s~~b)~y~e ~

1

~foup s 44 GWd/MTU Initial Assembly MiJ;rl,mui1'~c.o.~Ifii :;: Time ears Avg. Enrichment E AP'WE B&W CE WE B&W

' wt% 235LJ E 4x\ 4'' 15x15 15x15 16x16 17x17 17x17 2.1~E<2.3

:9 ~ 2.3 ~ E < 2.5 2.5 s E < 2.7 7.1 7.4 6.6 7.2 7.2

~ /\'

7.0 7.3 6.5 7.0 7.0 2.7 ~ i::/ . :•8.__ -<§'.9 2.9bt < 3.1

' y ..... ·,·/

6.9 7.1 6.4 5.7~~5.8 6.9 6.9 31~~~ < 3. ;6,/ 5.8 6.8 7.0 6.2 6.8 6.8 . ---~.,:

s~s· ,£3~ <"t~5 5.7 6.7 6.9 6.1 6.8 6.7 . • "vy,,.~

5.5 5.6 6.6 6.8 6.0 6.7 6.7 3. t. E< z~ $,F'j ~:.

5.4 5.6 6.5 6.8 6.0 6.6 317!!,< E < 3.g\/ 6.6 ~·'.r

5.3 5.5 6.4 6.7 5.9 6.5 6.5 :¥.'9 ~ E < 4.1 ~:~E<4.3 5.3 5.4 6.3 6.6 5.9 6.4 6.4 4.3~E < 4.5 5.2 5.4 6.2 6.5 5.8 6.4 6.4 4.5 ~ E < 4.7 5.1 5.3 6.2 6.5 5.8 6.3 6.3 4.7 ~ E < 4.9 5.1 5.3 6.1 6.4 5.7 6.2 6.2

E ;:::4.9 5.0 5.2 6.0 6.3 5.7 6.2 6.2

Certificate of Compliance No.1031 82-28 Amendment No. 7

Page 82: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-15 Loading Table for PWR Fuel - 959 W/Assembly (continued)

44 <Assembly Average Burnup $; 45 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235LJ E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 2.7 ~ E < 2.9 6.0 6.2 7.3 7.7 2.9~E<3.1 5.9 6.0 7.2 7.6 3.1~E<3.3 5.8 6.0 7.0 7.4 3.3 ~ E < 3.5 5.7 5.9 6.9 3.5 ~ E < 3.7 5.7 5.8 6.8 3.7 ~ E < 3.9 5.6 5.8 6.8 3.9 ~ E < 4.1 5.5 5.7 6.7 4.1~E<4.3 5.5 5.6 6.6 4.3 ~ E < 4.5 5.4 5.6 4.5:::; E < 4.7 5.3 5.5 4.7 ~ E < 4.9 5.3 5.5 6.5

EC: 4.9 5.2 5.4 6.5 6.5

Certificate of Compliance No.1031 82-29 Amendment No. 7

Page 83: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Note: For fuel assembly average burn up greater than 45 GWd/MTU, cool time tables have been revised to account for a 5% margin in heat load.

Table 82-16 Loading Table for PWR Fuel - 911 W/Assembly

45 < Assembly Average Burnup ::;; 46 GWd/MTU Initial Assembly ,___-~---M~i_n_im_u_m_C~o_o_lin~T~im_e~_ea_r...,...s __ ~---Avg. Enrichment CE WE WE B&W CE

wt% 235U E 2.1::; E < 2.3 2.3::; E < 2.5 2.5::; E < 2.7 2.7::; E < 2.9 2.9:s;E<3.1 3.1::; E < 3.3 3.3::; E < 3.5 3.5::; E < 3.7 3.7::; E < 3.9 3.9::; E < 4.1 4.1::; E < 4.3 4.3 ::; E < 4.5 4.5::; E < 4.7 4.7::; E < 4.9

E~4.9

14x14

6.7 6.6 6.5 6.4 6.3 6.2 6.1 6.0 6.0

14x14

6.9 6.8 6.7 6.6 6.5 6.4 6.3 6.2

Certificate of Compliance No. 1031

15x15 15x15 16x16

8.5 8.3 8.1 8.0 7.8

82-30

7.7 7.7 7.6 7.5 7.5 7.4 7.4 7.3 7.3

Amendment No. 7

Page 84: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-16 Loading Table for PWR Fuel - 911 W/Assembly (continued)

46 < Assembly Average Burnup::; 47 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1 sE<2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9 7.0 7.3 9.6 8.0 2.9 s E < 3.1 6.9 7.1 9.4 7.9 3.1 s E < 3.3 6.8 7.0 9.2 7.8 3.3 s E < 3.5 6.7 6.9 9.0 3.5 s E < 3.7 6.6 6.8 8.8 3.7 s E < 3.9 6.5 6.7 8.7 3.9 s E < 4.1 6.4 6.6 4.1sE<4.3 6.3 6.5 4.3 s E < 4.5 6.2 6.5 4.5 s E < 4.7 6.1 6.4 7.8 4.7 s E < 4.9 6.0 6.3 7.8 7.8

E;:::: 4.9 6.0 7.7

Initial Assembly Avg. Enrichment B&W

16x16 17x17 17x17

9.6 10.3 8.6 9.7 9.7 9.4 10.0 8.4 9.5 9.5 9.1 9.8 8.2 9.3 9.3 8.9 9.6 8.0 9.1 9.0 8.8 9.4 7.9 8.9 8.9 8.6 9.2 7.8 8.8 8.7 8.5 9.0 7.6 8.6 8.6 8.4 8.9 7.6 8.5 8.5

6.5 8.2 8.8 7.4 8.4 8.4 6.4 8.1 8.7 7.4 8.3 8.3 6.3 8.0 8.6 7.3 8.2 8.2 6.2 7.9 8.5 7.2 8.1 8.1

Certificate of Compliance No. 1031 82-31 Amendment No. 7

Page 85: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-16 Loading Table for PWR Fuel - 911 W/Assembly (continued)

48 < Assembly Average Burnup =:::; 49 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1:::; E < 2.3 2.3:::; E < 2.5 2.5:::; E < 2.7 2.7 =:::; E < 2.9 7.8 8.1 10.2 11.1 2.9 =:::; E < 3.1 7.6 7.9 10.0 10.8 3.1:::; E < 3.3 7.5 7.8 10.5 3.3:::; E < 3.5 7.3 7.6 10.2 3.5:::; E < 3.7 7.2 7.5 10.0 3.7:::; E < 3.9 7.0 7.4 9.8 3.9:::; E < 4.1 6.9 7.2 9.6 4.1 :::;E<4.3 6.8 7.1 9/

l

4.3:::; E < 4.5 6.8 7.0 4.5:::; E < 4.7 6.7 6.9 4.7:::; E < 4.9 6.6 6.9

E 2::4.9 6.5 6.8

Initial Assembly Avg. Enrichment CE WE B&W

wt% 235U E 16x16 17x17 17x17 2.1 :::;E<2.3 2.3:::; E < 2.5 2.5:::; E < 2.7 2.7:::; E < 2.9 2.9:::;5 10.7 11.6 9.4 10.9 10.9 3.1 10.4 11.3 9.1 10.6 10.6 3. 10.1 11.0 9.0 10.3 10.3

9.9 10.8 8.8 10.0 10.0 7.4 9.7 10.5 8.6 9.9 9.9 7.3 7.5 9.5 10.3 8.5 9.7 9.7 7.1 7.4 9.4 10.1 8.3 9.6 9.5

:::; E <4.5 7.0 7.3 9.2 9.9 8.2 9.4 9.4 E <4.7 6.9 7.2 9.1 9.8 8.1 9.3 9.2

4.7:::; E < 4.9 6.9 7.1 9.0 9.6 8.0 9.1 9.1 E 2::4.9 6.8 7.0 8.9 9.5 7.9 9.0 9.0

Certificate of Compliance No. 1031 82-32 Amendment No. 7

Page 86: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-16 Loading Table for PWR Fuel - 911 W/Assembly (continued)

50 <Assembly Average Burn up:::; 51 GWd/MTU Initial Assembly 1--------=-M:.:..:.i=ni.:..::..:m=um:..:.c........;C....:...oo"-l=in....___Ti'-m_e-->L..::e-'-ar_s.t__ ___ _ Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 2.1:::; E < 2.3 2.3::; E < 2.5 2.5::; E < 2.7 2.7::; E < 2.9 2.9::; E < 3.1 3.1 ::; E < 3.3 3.3 ::; E < 3.5 3.5::; E < 3.7 3.7::; E < 3.9 3.9 ::; E < 4.1 4.1::; E < 4.3 4.3 ::; E < 4.5 4.5::; E < 4.7 4.7::; E < 4.9

E~4.9

14x14

8.3 8.0 7.9 7.8 7.6 7.5 7.4 7.3 7.1 7.0 7.0

14x14

8.7 8.5 8.3 8.1 8.0 7.9 7.8 7.6 7.5 7.4

15x15

11.5 11.2 10.9 10.6 10.4 10.1 10.0 9.8

15x15 16x16 17x17 17x17

Initial Assembly f---------r---z~~"r---"~--.---~..-----"'---.-L--------.---B&W Avg. Enrichment CE

wt% 23su E 14x14

Certificate of Compliance No. 1031

12.2 11.9 11.6 11.4 11.1 10.9 10.7 10.5 10.3 10.1 10.0

82-33

16x16 17x17 17x17

13.0 10.7 12.4 12.4 12.6 10.4 12.1 12.0 12.3 10.1 11.8 11.8 11.9 9.9 11.6 11.5 11.7 9.7 11.3 11.3 11.5 9.5 11.1 11.1 11.3 9.3 10.9 10.9 11.1 9.2 10.7 10.7 11.0 9.0 10.5 10.5 10.8 8.9 10.3 10.3 10.6 8.8 10.2 10.2

Amendment No. 7

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Table 82-16 Loading Table for PWR Fuel - 911 W/Assembly (continued)

52 <Assembly Average Burnup ~ 53 GWd/MTU Initial Assembly 1----~---M~in_i_m_um~C_oo_l_in,,.__Ti~m_e__,,._e_ar~s,____~---Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 2.1~E<2.3

2.3:::; E < 2.5 2.5:::; E < 2.7 2.7 :::; E < 2.9 2.9 :::; E < 3.1 3.1 :::; E < 3.3 3.3 :::; E < 3.5 3.5 ~ E < 3.7 3.7:::; E < 3.9 3.9 :::; E < 4.1 4.1 :::; E < 4.3 4.3 ~ E < 4.5 4.5:::; E < 4.7 4.7:::; E < 4.9

E~4.9

14x14

9.3 9.0 8.8 8.6 8.4 8.2 8.1 8.0 7.9 7.8 7.7

14x14

9.8 9.6 9.3 9.1 9.0 8.8 8.6 8.5 8.3 8.2

Initial Assembly 1----~-----.c~~ Avg. Enrichment

wt% 235U E 2.1:::; E < 2.3 2.3 :::; E < 2.5 2.5:::; E < 2.7 2.7:::; E < 2.9

8.7 8.8

Certificate of Compliance No. 1031

15x15

13.6 13.3 12.9 12.6 12.3 12.0 11.8 11.6 11.4 11.3 11.1

82-34

15x15

13.8 13.5 13.2 12.8 12.6

14.9 14.4 14.0 13.7 13.4 13.2 12.9 12.6 12.4 12.2 12.0

16x16 17x17 17x17

WE B&W 16x16 17x17 17x17

12.2 11.8 11.6 11.3 11.0 10.8 10.6 10.4 10.1 10.0 9.9

14.2 13.8 13.5 13.2 12.9 12.6 12.4 12.1 11.9 11.8 11.6

14.2 13.8 13.5 13.2 12.9 12.6 12.4 12.1 11.9 11.7 11.6

Amendment No. 7

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Table 82-16 Loading Table for PWR Fuel - 911 W/Assembly (continued)

54 < Assembly Average Burnup :::;; 55 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1:::;; E < 2.3 2.3:::;; E < 2.5 2.5::;; E < 2.7 2.7:::;; E < 2.9 2.9::;; E < 3.1 3.1::;; E < 3.3 10.1 10.9 14.1 3.3::;; E < 3.5 9.9 10.6 13.8 3.5::;; E < 3.7 9.6 10.3 13.5 3.7::;; E < 3.9 9.4 10.1 13.1 3.9::;; E < 4.1 9.2 9.8 12.9 4.1::;; E < 4.3 9.0 12.6 4.3::;; E < 4.5 8.9 12.3 4.5::;; E < 4.7 8.7 1 12.7 4.7::;; E < 4.9 8.6 12.5

E ~4.9 8.5 12.3

Initial Assembly Avg. Enrichment B&W

wt% 235U E 16x16 17x17 17x17 2.1::;; E < 2.3

11.6 15.1 16.5 13.1 15.8 15.8 11.3 14.7 16.0 12.8 15.4 15.4 11.0 14.3 15.7 12.4 15.1 15.0 10.8 14.0 15.3 12.1 14.7 14.7 10.5 13.7 15.0 11.9 14.4 14.4

::;; E <4.3 10.2 13.4 14.7 11.7 14.1 14.1 .~E <4.5 10.0 13.2 14.5 11.4 13.8 13.8

4.5 s:; E < 4.7 9.2 9.9 12.9 14.2 11.2 13.6 13.6 4.7::;; E < 4.9 9.0 9.7 12.7 13.9 11.1 13.4 13.4

E~4.9 8.9 9.5 12.5 13.8 10.9 13.2 13.2

Certificate of Compliance No. 1031 82-35 Amendment No. 7

Page 89: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-16 Loading Table for PWR Fuel - 911 W/Assembly (continued)

56 <Assembly Average Burnup s 57 GWd/MTU Initial Assembly 1---------'-M:.:..:.i=ni.:..:..:m=umc_:___;.C--=-o..:....:ol-'--'in_,,,__T.:..:..:im--"e--1.L.:e_a_rsL__ ____ _ Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 2.1sE<2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9 2.9 s E < 3.1 3.1sE<3.3 3.3 ~ E < 3.5 3.5 s E < 3.7 3.7 ~ E < 3.9 3.9 ~ E < 4.1 4.1sE<4.3 4.3 ~ E < 4.5 4.5 ~ E < 4.7 4.7 ~ E < 4.9

E;:::: 4.9

14x14

11.5 11.2 10.9 10.6 10.3 10.1 9.9 9.7 9.5 9.4

14x14

12.3 12.0 11.7 11.4 11.2 10.9 10.7 10.5 10.3

Initial Assembly f------.-------.-£'~ Avg. Enrichment CE

wt% 235U E

11.3 11.0 10.7 10.5 10.3 10.0 9.9

.2 12.8 12.4 12.1 11.9 11.6 11.4 11.2 10.9 10.8

Certificate of Compliance No. 1031

15x15

16.0 15.6 15.3 14.9 14.6 14.2 14.0 13.8

17.0 16.7 16.2 15.9 15.6 15.3 15.0 14.7 14.4 14.2

82-36

15x15

17.4 17.1

18.5 18.1 17.7 17.3 17.0 16.7 16.4 16.1 15.8 15.6

16x16 17x17 17x17

B&W 16x16 17x17 17x17

14.9 14.5 14.1 13.8 13.5 13.2 12.9 12.7 12.4 12.2

17.8 17.4 17.0 16.7 16.3 16.0 15.7 15.5 15.2 15.0

17.7 17.4 17.0 16.6 16.3 16.0 15.7 15.4 15.2 14.9

Amendment No. 7

Page 90: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-16 Loading Table for PWR Fuel - 911 W/Assembly (continued)

58 <Assembly Average Burnup :::; 59 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 23su E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1:::; E < 2.3 2.3:::; E < 2.5 2.5:::; E < 2.7 2.7:::; E < 2.9 2.9:::; E < 3.1 3.1:::; E < 3.3 13.0 18.0 3.3:::; E < 3.5 12.6 17.6 3.5:::; E < 3.7 12.2 17.2 3.7:::; E < 3.9 11.9 16.9 3.9:::; E < 4.1 11.6 16.5 4.1:::; E < 4.3 11.4 16.2 4.3:::; E < 4.5 11.1 15.9 4.5:::; E < 4.7 10.9 4.7:::; E < 4.9 10.7

E~4.9 10.5

Initial Assembly Avg. Enrichment B&W

wt% 23su E 16x16 17x17 17x17 2.1:::; E < 2.3 2.3:::; E < 2.5 2.5:::; E < 2.7

14.4 18.6 20.1 16.3 19.0 19.0 14.1 18.2 19.7 15.9 18.6 18.5

12.7 13.7 17.8 19.4 15.5 18.2 18.1 12.3 13.4 17.5 19.0 15.2 17.9 17.8 12.0 13.1 17.1 18.7 14.9 17.5 17.5

, ,3:::; E < 4.5 11.8 12.8 16.8 18.4 14.6 17.2 17.2 4~~:::;.E <4.7 11.6 12.6 16.5 18.0 14.3 16.9 16.9 v 4.7:::; E < 4.9 11.3 12.3 16.2 17.8 14.0 16.6 16.6

E ~4.9 11.2 12.1 16.0 17.6 13.8 16.4 16.3

Certificate of Compliance No. 1031 82-37 Amendment No. 7

Page 91: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-17 Loading Table for PWR Fuel - 1,200 W/Assembly

30 <Assembly Average Burnup s 32.5 GWd/MTU Initial Assembly 1---~---M_in_im_um~Co_o_li_,n .._T~im_e--.l.L_ea_rs+---~---Avg. Enrichment CE WE WE B&W CE WE B&W

17x17 wt% 235U E 2.1sE<2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9 2.9 s E < 3.1 3.1sE<3.3 3.3:::; E < 3.5 3.5:::; E < 3.7 3.7:::; E < 3.9 3.9:::; E < 4.1 4.1:::; E < 4.3 4.3:::; E < 4.5 4.5:::; E < 4.7 4.7:::; E < 4.9

E~4.9

14x14 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0

14x14 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0

15x15 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0

17x17 4.0 4.0 4.0

4.0 4.0 4.0

Initial AssemblY1----~~~~~~..=-=-=~ ~::___u_=-=-;.J___~---Avg. Enrichment CE

wt% 235LJ E 14x14

4.1 4.1 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0

" :::; E < 4.5 4.0 4. < 4.7 4.0 4.7 :::; E < 4.9 4.0

E~4.9 4.0

Certificate of Compliance No. 1031 82-38

B&W 16x16 17x17 17x17

4.0 4.1 4.1 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0

Amendment No. 7

Page 92: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-17 Loading Table for PWR Fuel - 1,200 W/Assembly (continued)

35 <Assembly Average Burnup~ 37.5 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 23su E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1 :SE<2.3 2.3:::; E < 2.5 4.0 4.0 4.3 4.4 4.2 2.5:::; E < 2.7 4.0 4.0 4.3 4.4 4.1 2.7:::; E < 2.9 4.0 4.0 4.2 4.3 4.1 2.9:SE<3.1 4.0 4.0 4.2 4.3 4.0 3.1:::; E < 3.3 4.0 4.0 4.1 4.2 3.3:::; E < 3.5 4.0 4.0 4.1 3.5:::; E < 3.7 4.0 4.0 4.0 3.7:::; E < 3.9 4.0 4.0 4.0 3.9:::; E < 4.1 4.0 4.0 4.0 4.1 :::; E < 4.3 4.0 4.0 4.0 4.3 :::; E < 4.5 4.0 4.0 4.0 4.' 4. 4.0

4.0 4.0 ~ ~4"0 4.5:::; E < 4.7 r ~9>·· 4.0

4.7:::; E < 4.9 4.0 4.0 ~.O ~~ ~4{'. 4.0 . E ~4.9 4.0 4.0 ~,~o 4.0 :',~ 4.0 4.0

37 ~~e,~l~rly?&Yerag~~'tirnup ~ 40 GWd/MTU Initial Assembly A/Y M\h1mumteJ>~~lln' Time ears Avg. Enrichment CE , ,,~,,~ ~WE B&W CE WE B&W ~· ,, ' ' ,r'''

wt% 235U E 14 ~~ - 1~~1'!1} 15x15 15x15 16x16 17x17 17x17 2.1:::; E < 2.3 -~ '~~ ~-)' -

4.6 4.8 4.4 4.7 4.7 ;Q 4.6 4.7 4.4 4.7 4.7 4:0~ 11\ll<i~o 4.5 4.6 4.3 4.6 4.6 ;;;;;Y' •

4,.0 4.0 4.5 4.6 4.3 4.5 4.5 ~~&v 4.0 4.4 4.5 4.2 4.5 4.5 4.0 4.0 4.4 4.5 4.2 4.5 4.4 4.0 4.0 4.3 4.4 4.1 4.4 4.4 4.0 4.0 4.3 4.4 4.1 4.4 4.4 4.0 4.0 4.2 4.3 4.1 4.3 4.3 4.0 4.0 4.2 4.3 4.0 4.3 4.3 4.0 4.0 4.2 4.3 4.0 4.3 4.3

4.7:::; E < 4.9 4.0 4.0 4.1 4.3 4.0 4.3 4.3 E~4.9 4.0 4.0 4.1 4.2 4.0 4.2 4.2

Certificate of Compliance No. 1031 82-39 Amendment No. 7

Page 93: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-17

Initial Assembly Avg. Enrichment

wt% 235U E 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 2.7 ~ E < 2.9 2.9~E<3.1

3.1~E<3.3

3.3 ~ E < 3.5 3.5 ~ E < 3.7 3.7 ~ E < 3.9 3.9~E<4.1

4.1~E<4.3

4.3 ~ E < 4.5 4.5 ~ E < 4.7 4.7 ~ E < 4.9

E ;:::4.9

4.7 ~ E < 4.9 E ;:::4.9

Loading Table for PWR Fuel -1,200 W/Assembly (continued)

CE 14x14

4.2 4.1 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0

40 <Assembly Average Burnup ~ 41 GWd/MTU

WE 14x14

4.2 4.2 4.1 4.1 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0

Minimum Coolin Time ears WE

15x15

4.9 4.9 4.8 4.7 4.7 4.6 4.6 4.5 4.5 4.4 4.4 4.4 4.3

B&W CE WE B&W 15x15 16x16 17x17 17x17

4.5 4.5 4.4 4.4 4.4 4.3

B&W 15x15 16x16 17x17 17x17

5.1 4.7 5.0 5.0 5.0 4.6 5.0 5.0 4.9 4.6 4.9 4.9 4.9 4.5 4.8 4.8 4.8 4.5 4.8 4.8 4.8 4.4 4.7 4.7 4.7 4.4 4.7 4.7 4.6 4.3 4.6 4.6 4.6 4.3 4.6 4.6 4.6 4.3 4.5 4.5 4.5 4.2 4.5 4.5 4.5 4.2 4.5 4.5 4.5 4.2 4.5 4.5

Certificate of Compliance No. 1031 82-40 Amendment No. 7

Page 94: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-17 Loading Table for PWR Fuel - 1,200 W/Assembly (continued)

42 < Assembly Average Burnup :::; 43 GWd/MTU Initial Assembly f---~---M~in_im_um~C_oo_li_n ___ Ti~m_e--"'--e_ar_.....s'----~--Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1sE<2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9 2.9sE<3.1 3.1sE<3.3 3.3 s E < 3.5 3.5 s E < 3.7 3.7 s E < 3.9 3.9sE<4.1 4.1sE<4.3 4.3 s E < 4.5 4.5 s E < 4.7 4.7sE<4.9

E 24.9

4.4 4.4 4.3 4.2 4.2 4.1 4.1 4.0 4.0 4.0 4.0 4.0 4.0

4~~~S~R. l~~~~~~·rnup:::; 44 GWd/MTU Initial Assembly /~!Y MU){mum<t€0'.dlin1 Time ears A E . h t CE ~WE .~V'WE B&W CE WE vg. nnc men ,,~4""

wt% 235U E t4x1:4~~J4~j~? 15x15 15x15 16x16 17x17

2.1sE<2.3 £:., .. ~··"'~ ·-...~~ .. ~~ -2.3 s E < 2.5 l{ ~ ~~~ 'J> -2.5 s E ~/ \'ts 4}~' 5.3

2.7···s 7.~~~ ~·~ .. ,2,~s 5.2 2.~f:S"E < 3. ]2!1 4.4~ ~4.5 5.1 3 "'11\)~~·c / "''~ ~4~4 4 4 5 0 . ~ .. [ii,< :3.[..22 \·, .. ,?'i'J' • • :' -~>4:,~·.·;>: "-*. ... .;~i:!;fJ;}J\~1

f .... ~.3.: .. ~ .... ·.<.. ~~~3.5. .·.··· 4.3 4.4 5.0 · 3)v~ E ~3~ 4.2 4.3 4.9 . J~ ''I~,

.. , ~(fs E < 3.* 4.2 4.3 4.9 ~9 s E < 4.1 4.1 4.3 4.8 · ··~~ E < 4.3 4.1 4.2 4.8 4.3~ E < 4.5 4.1 4.2 4.7 4.5 s E < 4.7 4.0 4.2 4.7 4.7 s E < 4.9 4.0 4.1 4.6

E 2 4.9 4.0 4.1 4.6

5.5 5.4 5.3 5.2 5.1 5.1 5.0 5.0 4.9 4.9 4.8 4.8 4.8

5.0 4.9 4.9 4.8 4.7 4.7 4.6 4.6 4.5 4.5 4.5 4.4 4.4

5.4 5.3 5.2 5.2 5.1 5.0 5.0 4.9 4.9 4.8 4.8 4.8 4.7

B&W 17x17

5.4 5.3 5.2 5.2 5.1 5.0 5.0 4.9 4.9 4.8 4.8 4.7 4.7

Certificate of Compliance No. 1031 82-41 Amendment No. 7

Page 95: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-17 Loading Table for PWR Fuel -1,200 W/Assembly (continued)

44 <Assembly Average Burnup ~ 45 GWd/MTU

Initial Assembly Minimum Coolin Time ears

Avg. Enrichment CE WE WE B&W CE WE B&W wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1~E<2.3

2.3 s E < 2.5 2.5 ~ E < 2.7 2.7 s E < 2.9 4.6 4.7 5.6 2.9 s E < 3.1 4.5 4.6 5.5 3.1sE<3.3 4.5 4.6 5.4 3.3 s E < 3.5 4.4 4.5 5.4 3.5 s E < 3.7 4.4 4.5 5.3 3.7 s E < 3.9 4.3 4.4 3.9 s E < 4.1 4.3 4.4 4.1sE<4.3 4.2 4.3 4.3 s E < 4.5 4.2 4.3 4.5 s E < 4.7 4.1 4.2 4.7 s E < 4.9 4.1 4.2

E ::::4.9 4.0 4.2

Certificate of Compliance No. 1031 82-42 Amendment No. 7

Page 96: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Note: For fuel assembly average burn up greater than 45 GWd/MTU, cool time tables have been revised to account for a 5% margin in heat load.

Table 82-18 Loading Table for PWR Fuel -1,140 W/Assembly

45 < Assembly Average Burnup ::::; 46 GWd/MTU Initial Assembly 1------.---M-.-i_ni_m_u_m_C,-o_o_lin~T_..im_e ~ea_r_.,,s~-~---Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U (E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1::::; E < 2.3 2.3::::; E < 2.5 2.5::::; E < 2.7 2.7::::; E < 2.9 2.9::::; E < 3.1 3.1 sE<3.3 3.3::::; E < 3.5 3.5::::; E < 3.7 3.7::::; E < 3.9 3.9::::; E < 4.1 4.1::::; E < 4.3 4.3::::; E < 4.5 4.5::::; E < 4.7 4.7::::; E < 4.9

E ~4.9

5.0 5.0 4.9 4.8 4.8 4.7 4.6 4.6 4.5 4.5 4.4 4.4

5.2 5.1 5.0 4.9 4.9 4.8 4.8 4.7 4.6 4.6

Certificate of Compliance No. 1031

6.0 5.9 5.8 5.7 5.6 5.6 5.5

82-43

6.2 6.0 6.0

5.5 5.5 5.4 5.4 5.4

5.6 5.5 5.4 5.4 5.3

Amendment No. 7

Page 97: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-18 Loading Table for PWR Fuel -1,140 W/Assembly (continued)

46 <Assembly Average Burn up=:;; 47 GWd/MTU Initial Assembly .__ _____ M_in_im_um_C_oo_li_n,,.__Ti_m_e--"'-e_ar_s.___ ___ _ Avg. Enrichment CE WE WE B&W CE WE

wt% 235LJ E 14x14 14x14 15x15 15x15 16x16 17x17 B&W 17x17

2.1:::; E < 2.3 2.3:::; E < 2.5 2.5:::; E < 2.7 2.7:::; E < 2.9 2.9:::; E < 3.1 3.1 :::; E < 3.3 3.3:::; E < 3.5 3.5:::; E < 3.7 3.7:::; E < 3.9 3.9:::; E < 4.1 4.1:::; E < 4.3 4.3:::; E < 4.5 4.5:::; E < 4.7 4.7:::; E < 4.9

E ?'.'. 4.9

5.2 5.1 5.0 5.0 4.9 4.8 4.8 4.7 4.7 4.6 4.6 4.5

Certificate of Compliance No. 1031

6.5 6.4 6.2 6.1 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6

82-44

6.8 6.6 6.5 6.4 6.3 6.2 6.1 6.0 6.0 5.9 5.8 5.8

6.0 5.9 5.8 5.8 5.7 5.6 5.5 5.5 5.4 5.3 5.3 5.2

6.6 6.5 6.4 6.2 6.2 6.0 6.0 5.9 5.9 5.8 5.8 5.7

6.6 6.5 6.4 6.2 6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.7

Amendment No. 7

Page 98: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-18 Loading Table for PWR Fuel -1,140 W/Assembly (continued)

48 <Assembly Average Burnup::; 49 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 23su E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1 ::; E < 2.3 2.3::; E < 2.5 2.5::; E < 2.7 2.7::; E < 2.9 5.6 5.8 6.8 7.0 6.3 2.9::; E < 3.1 5.5 5.7 6.7 6.9 6.1 3.1::; E < 3.3 5.4 5.6 6.5 6.8 6.0 3.3 ::; E < 3.5 5.3 5.5 6.4 6.7 3.5::; E < 3.7 5.2 5.4 6.3 6.6 3.7::; E < 3.9 5.2 5.3 6.2 3.9::; E < 4.1 5.1 5.2 6.1 4.1 ::; E < 4.3 5.0 5.2 6.0 4.3 ::; E < 4.5 5.0 5.1 5.9 4.5::; E < 4.7 4.9 5.0 4.7::; E < 4.9 4.8 5.0

E ;:::4.9 4.8 4.9

Initial Assembly Avg. Enrichment CE B&W

wt% 23SU E 14x14 16x16 17x17 17x17 2.1 ::;E<2.3 2.3 ::; E < 2.5 2.5::; E < 2.7

6.9 7.3 6.4 7.0 7.0 6.8 7.1 6.3 6.9 6.9 6.7 7.0 6.2 6.8 6.8 6.6 6.9 6.0 6.7 6.7

'")\ . ,,..:.. E 5.5 6.5 6.8 6.0 6.6 6.6 i;;t 3.9,~ E < 4. 5.4 6.4 6.7 5.9 6.5 6.5

~Y<E<43 5.3 6.3 6.6 5.8 6.4 6.4 "'"'.!'/ - .

5.2 6.2 6.5 ''.,;~i::; E < 4.5 5.8 6.3 6.3 4~o~E <4.7 5.2 6.1 6.4 5.7 6.2 6.2 4.7 ::; E < 4.9 5.1 6.0 6.3 5.7 6.2 6.2

E ;:::4.9 5.0 6.0 6.2 5.6 6.1 6.1

Certificate of Compliance No. 1031 82-45 Amendment No. 7

Page 99: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-18 Loading Table for PWR Fuel-1,140 W/Assembly (continued)

50 < Assembly Average Burnup:::; 51 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1sE<2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9 2.9 s E < 3.1 5.8 6.0 7.6 3.1sE<3.3 5.8 5.9 7.5 3.3 s E < 3.5 5.7 5.8 3.5 s E < 3.7 5.6 5.7 3.7 s E < 3.9 5.5 5.7 3.9 s E < 4.1 5.4 5.6 4.1sE<4.3 5.3 5.5 4.3 s E < 4.5 5.2 5.4 4.5 s E < 4.7 5.2 5.4 6.5 6.5 4.7 s E < 4.9 5.1 5.3 6.4 6.4

E~4.9 5.0 6.3

Initial Assembly Avg. Enrichment B&W

wt% 235U E 16x16 17x17 17x17 2.1sE<2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9 ~- ~vi .. , 2.9s~~1:\ ~b_ 6~~ 7.6 7.9 6.9 7.7 7.7

A:% 7.5 7.7 6.8 7.6 7.6 3.w<3.3i~1 5~~ .,z;;s.1

3.S~)E < 3 .~~~ ~!!~9~ 6.0 7.3 7.6 6.7 7.4 7.4 ,9s~8;J'rr ~51!8' 5.9 7.1 7.4 6.6 7.3 7.3 ... ~ :;,; .. x

5.7 5.9 7.0 7.3 6.5 7.1 7.1 ':'l<f- E <'~~9, ·~ ~+?, 5.6 5.8 6.9 7.1 6.4 7.0 7.0 3.911'- E < 4.1~

/" 4041'< E < 4 3 5.5 5.7 6.8 7.0 6.3 6.9 6.9 ?if' - .

5.4 5.6 6.7 6.9 6.2 6.8 6.8 ),;,~,3 s E < 4.5 p,1: 5.4 5.6 6.6 6.8 6.1 6.8 6.8 4~~~ E < 4.7 v·

6.8 6.0 6.7 6.7 4.7 s E < 4.9 5.3 5.5 6.5 E ~4.9 5.2 5.4 6.5 6.7 6.0 6.6 6.6

Certificate of Compliance No. 1031 82-46 Amendment No. 7

Page 100: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-18 Loading Table for PWR Fuel -1,140 W/Assembly (continued)

52 < Assembly Average Burnup ~ 53 GWd/MTU Initial Assembly 1-------~----=M.:.:-:i=n i=m=u=mc_:;C-=-o-=-=ol=in'""'--T-'r-im_e--'-"-e_a_rs,,___-----.-__ _ Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 23su E 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 2.7~E<2.9

2.9 ~ E < 3.1 3.1~E<3.3

3.3 ~ E < 3.5 3.5 ~ E < 3.7 3.7 ~ E < 3.9 3.9 ~ E < 4.1 4.1 ~E<4.3 4.3 ~ E < 4.5 4.5 ~ E < 4.7 4.7 ~ E < 4.9

E ::::4.9

14x14

6.3 6.2 6.0 5.9 5.8 5.8 5.7 5.6 5.5 5.5 5.4

14x14 15x15 15x15 16x16 17x17 17x17

6.5 7.9 8.3 7.3 8( /,{\

6.4 7.7 8.1 7.1 '<i.9A 6.3 7.5 7.9 7.0 ·'~ ?:a~ 6.1 7.4 7.8 6g~y ~~ . ~·"7.61flJ 6.1 7.2 7.6 ~7:,, ~~:5 ~ ·:5?"' 6.o 7.1 7.5 . 6.6~~.4 59 70 7·~~65~~ 72/< . . ~;~v . ~)'. zt~Y9 5.8 6.9 ~1!~ Af;T~ ~P' 5.7 6.8 . . . 7~1y ,YB~) 7.0 5.7 2p~}l~ ~& 6.9 5.6 {Q'.6 fo~<.~ ~t:k1 . 6.9

8.3 8.8 7.6 8.6 8.0 8.6 7.5 8.3 7.9 8.3 7.3 8.2 7.7 8.1 7.1 8.0 7.6 8.0 7.0 7.9 7.4 7.8 6.9 7.7 7.3 7.7 6.8 7.6 7.2 7.6 6.7 7.5 7.0 7.5 6.6 7.4 7.0 7.4 6.5 7.2 6.9 7.3 6.4 7.1

7.1 7.0 6.9 6.9

8.6 8.3 8.1 8.0 7.8 7.7 7.6 7.5 7.3 7.2 7.1

Certificate of Compliance No. 1031 82-47 Amendment No. 7

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Table 82-18 Loading Table for PWR Fuel -1,140 W/Assembly (continued)

54 < Assembly Average Burnup ::;; 55 GWd/MTU Initial Assembly ~-~---=-M:,:..:.in=i=m=umc::..:.._c;:.C-=-oo~li=n,.,_Ti:.--m_e_,,,_e=ar--Ts'-------.---Avg. Enrichment CE WE WE B&W CE WE

wt% 23su E 14x14 2.1sE<2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9 2.9 s E < 3.1 3.1sE<3.3 6.7 3.3 s E < 3.5 6.6 3.5 s E < 3.7 6.4 3.7 s E < 3.9 6.3 3.9 s E < 4.1 6.2 4.1sE<4.3 6.1 4.3 s E < 4.5 6.0 4.5 s E < 4.7 5.9 4.7 s E < 4.9 5.9

E2::4.9 5.8

Initial Assembly Avg. Enrichment CE

wt% 23su E 2.1sE<2.3 2.3 s E < 2.5 2.5 s E < 2.7

. '6:-:7~ 6.6 6.4 6.3 6.2 6.1 6.0 6.0

14x14 15x15 15x15 16x16 17x17

6.9 8.5 9.0 6.8 8.3 8.8 6.7 8.1 8.6 6.6 7.9 8.4

~:; ~:~ ;:~ 6.2 7.5 fl9 4 6.1 7.4 7~31dV6.

6.0 17!'~:-!fi:l7:i ~6.~ 6 .0 1112 7~(?\~ ~6.'.1i 7 .5

55 < Assem~J;Y Average Bp~nup::;; 56 GWd/MTU ~Mj.niril)Jlll Coolin ::Jiime ears)

8.9 9.6 8.0 9.3 7.1 8.7 9.3 7.8 9.0 6.9 8.5 9.1 7.7 8.8 6.8 8.3 8.9 7.5 8.7 6.7 8.1 8.7 7.4 8.5 6.6 8.0 8.5 7.2 8.3 6.5 7.9 8.4 7.1 8.2 6.4 7.7 8.2 7.0 8.0 6.3 7.6 8.1 6.9 7.9 6.2 7.5 8.0 6.8 7.8

B&W 17x17

7.7 7.6 7.5

B&W 17x17

9.3 9.0 8.9 8.7 8.5 8.3 8.1 8.0 7.9 7.8

Certificate of Compliance No. 1031 82-48 Amendment No. 7

Page 102: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-18 Loading Table for PWR Fuel -1,140 W/Assembly {continued)

56 < Assembly Average Burnup ~ 57 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1~E<2.3

2.3 ~ E < 2.5 2.5~E<2.7

2.7 ~ E < 2.9 2.9 ~ E < 3.1 3.1~E<3.3 7.3 7.6 9.4 3.3 ~ E < 3.5 7.1 7.4 9.2 3.5 ~ E < 3.7 6.9 7.3 9.0 3.7 ~ E < 3.9 6.8 7.1 8.8 3.9 ~ E < 4.1 6.7 7.0 8.6 4.1~E<4.3 6.6 6.9 8.4 4.3 ~ E < 4.5 6.5 6.8 8.2 4.5 ~ E < 4.7 6.4 6.7 4.7 ~ E < 4.9 6.3 6.6

E 2:: 4.9 6.2

Initial Assembly Avg. Enrichment B&W

wt% 235U E 16x16 17x17 17x17 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 ..

': ~~· 2.7 ~ E < 2.9 !'' "~, 2.9 ~ E,~3~1~

. !!'{,'

4~~" ··~ ~.O 10.0 10.8 8.9 10.5 10.4 3. ~11Z < 3.3)·11 7:6~ ·z .. 3.S~W: < 3.~)\f ~~~ 7.8 9.7 10.5 8.7 10.2 10.1 ·;·5:0Mrr ~2.v 7.6 9.5 10.2 8.4 9.9 9.9 ~):_ E'\~1@~.g 7.1 7.5 9.3 9.9 8.2 9.7 9.6 -~J ~·~ 3 91, E < 41~ 6.9 7.3 9.0 9.7 8.1 9.5 9.4 / M:- • W,;

··~~ E <4.3 6.8 7.1 8.8 9.5 7.9 9.2 9.2 ~ E < 4.5 6.7 7.0 8.7 9.3 7.8 9.0 9.0

4~5Y~ E < 4.7 6.6 6.9 8.5 9.1 7.7 8.9 8.9 v 4.7 ~ E <4.9 6.5 6.8 8.4 8.9 7.5 8.7 8.7

E 2:: 4.9 6.4 6.7 8.2 8.8 7.4 8.6 8.6

Certificate of Compliance No. 1031 82-49 Amendment No. 7

Page 103: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-18 Loading Table for PWR Fuel -1,140 W/Assembly (continued)

58 <Assembly Average Burnup ::;; 59 GWd/MTU Initial Assembly 1----~-__ M_in_im_um~C_oo_l_in_,,,__Ti~m_e---'L-e_ar~s,___~--Avg. Enrichment CE WE WE B&W CE

wt% 23su E 2.1 ::;; E < 2.3 2.3::;; E < 2.5 2.5::;; E < 2.7 2.7::;; E < 2.9 2.9::;; E < 3.1 3.1 ::;; E < 3.3 3.3::;; E < 3.5 3.5::;; E < 3.7 3.7::;; E < 3.9 3.9::;; E < 4.1 4.1::;; E < 4.3 4.3::;; E < 4.5 4.5::;; E < 4.7 4.7::;; E < 4.9

E 2: 4.9

14x14

7.9 7.8 7.6 7.4 7.2 7.1 7.0 6.9 6.8 6.7

14x14 15x15 15x15 16x16 WE B&W

17x17 17x17

59 < Assem'tll~Average B'u~nup ::;; 60 GWd/MTU Initial Assembly 1----~_,="~+>}r_1F·.--'·'1V1_Ji:i""'""i~_·.;""""~•l:J'.l'-': :...,,,C_oo_l-='-in,,.,·1;,_!fi_m_e---'L-e_ar~s,___~--Avg. Enrichment CE .A*>WE J*.jWE~'idB'!W CE WE B&W

wt% 235LJ E 14x14 ·~,~~14 ~15x15 15x15 16x16 17x17 17x17 -----'--.<.......+---+-~~~~

2.1::;; E < 2.3 2.3::;; E < 2.5 2.5::;; E < 2.7 2.7::;; E < 2.9

2.9~~ 3.11jS~ir< 3.~i\i) 3 ~~'\ 345i~~ ~···~ ,,,•,

~~5.~~~g-"}"''"}~ '; ~ . ' '

.fl • 3J1i E <'S~-·:~: 3.19f~ E < 4.~

\'' .4'l"V-:.+t•, fi~ < E < 4 3

'=.11~.· - . . 4'~~~ E < 4.5 4.5~E <4.7 4.7::;; E < 4.9

E 2: 4.9

"'""&1 8.6 ,\, N '"}? ~i:; .. ;.•

7.9 8.4 7.7 8.2 7.6 8.0 7.4 7.8 7.3 7.7 7.1 7.6 7.0 7.4 6.9 7.3

Certificate of Compliance No. 1031

11.0 11.8 9.6 11.2 11.2 10.7 11.5 9.4 10.9 10.8 10.3 11.2 9.1 10.6 10.5 10.1 11.0 8.9 10.3 10.3 9.8 10.7 8.7 10.0 10.0 9.6 10.4 8.5 9.8 9.8 9.4 10.2 8.4 9.7 9.6 9.2 10.0 8.2 9.5 9.4 9.1 9.8 8.1 9.3 9.3

82-50 Amendment No. 7

Page 104: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-19 Loading Table for PWR Fuel - 922 W/Assembly

30 < Assembly Average Burnup:::;; 32.5 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1:::;; E < 2.3 4.2 4.3 4.8 4.9 4.6 4.9 4.9 2.3:::;; E < 2.5 4.2 4.2 4.7 4.8 4.5 4.8 4.8 2.5:::;; E < 2.7 4.1 4.2 4.7 4.8 4.5 4.8 4.8 2.7:::;; E < 2.9 4.1 4.1 4.6 4.7 4.4 2.9::::; E < 3.1 4.0 4.1 4.6 4.4 3.1 :::;; E < 3.3 4.0 4.0 4.5 4.3 3.3:::;; E < 3.5 4.0 4.0 4.5 4.3d·· 3.5::::; E < 3.7 4.0 4.0 4.5 , '

3.7:::;; E < 3.9 4.0 4.0 4.4 3.9:::;; E < 4.1 4.0 4.0 4.4 4.1:::;; E < 4.3 4.0 4.0 4.4 4.3:::;; E < 4.5 4.0 4.0 4.3 4.5:::;; E < 4.7 4.0 4.0 4.3 4.7:::;; E < 4.9 4.0 4.0 4.4

E~4.9 4.0 4.0

Initial Assembly Avg. Enrichment CE B&W

wt% 235U E 14x14 16x16 17x17 17x17 2.1:::;; E < 2.3 2.3:::;; E < 2.5 5.2 5.3 4.9 5.3 5.3 2.5:::;; E < 2.7 .5.1 5.3 4.9 5.2 5.2 ,,,

5.0 5.2 4.8 5.1 5.1 5.0 5.1 4.8 5.1 5.1 4.9 5.0 4.7 5.0 5.0 4.9 5.0 4.7 5.0 5.0 4.8 5.0 4.6 4.9 4.9

4.2 4.8 4.9 4.6 4.9 4.9 4.1 4.8 4.9 4.5 4.9 4.9 4.1 4.7 4.9 4.5 4.8 4.8 4.1 4.7 4.8 4.5 4.8 4.8 4.0 4.7 4.8 4.5 4.8 4.8 4.0 4.6 4.8 4.4 4.7 4.7 4.0 4.6 4.7 4.4 4.7 4.7

Certificate of Compliance No. 1031 82-51 Amendment No. 7

Page 105: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-19 Loading Table for PWR Fuel - 922 W/Assembly (continued)

35 <Assembly Average Burnup::;; 37.5 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 23su E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1::; E < 2.3 2.3 ::; E < 2.5 4.9 5.0 5.7 5.9 5.4 2.5::; E < 2.7 4.8 4.9 5.7 5.8 2.7::; E < 2.9 4.8 4.9 5.6 5.8 2.9 ::; E < 3.1 4.7 4.8 5.7 3.1 ::; E < 3.3 4.6 4.7 5.6 3.3 ::; E < 3.5 4.6 4.7 5.6 3.5::; E < 3.7 4.5 4.6 5.5 3.7::; E < 3.9 4.5 4.6 5.4 3.9 ::; E < 4.1 4.5 4.6 4.1 :s;E<4.3 4.4 4.5 4.3 ::; E < 4.5 4.4 4.5 4.5::; E < 4.7 4.4 4.5 4.7::; E < 4.9 4.3 4.4

E:?: 4.9 4.3 4.4

Initial Assembly Avg. Enrichment CE ~WE WE B&W

wt% 23su E 14*1.04~ '14':.· 15x15 16x16 17x17 17x17 2.1 ::; E < 2.3

r~ -~ 2.3 ::; E < 2.5 ,, - . -· ~" '.}\~::,

2.5::; E < 2.7 ~3 5f 6.2 6.5 5.9 6.3 6.3 27<,~~ ~L ~.3 6.1 6.4 5.8 6.2 6.2

ti:?:~·,,'~· i> ~· 2' - 3'1}·': 5''1~·d5:;'3 6.0 6.3 5.7 6.1 6.1 < }»'*'f:, . ···•!i'''''' . 3: _ E < 3~3:"'.l JJk;~~Y' ~:~ 6.0 6.2 5.6 6.0 6.0 '~~§~15' 5.9 6.1 5.6 6.0 6.0 ·l~t~ -~~

3.5/1:$ E <·@'~~~ 4.9 5.0 5.9 6.0 5.5 5.9 5.9 t;:c:J "'" 4.9 5.0 5.8 6.0 5.5 5.9 5.9 ''!( E < 3.9~

4.8 5.0 5.7 5.9 5.4 5.8 5.8 4.8 4.9 5.7 5.9 5.4 5.8 5.8 4.8 4.9 5.7 5.8 5.3 5.8 5.7

4.5::; E < 4.7 4.7 4.8 5.6 5.8 5.3 5.7 5.7 4.7::; E < 4.9 4.7 4.8 5.6 5.8 5.2 5.7 5.7

E:?: 4.9 4.6 4.8 5.5 5.7 5.2 5.6 5.6

Certificate of Compliance No. 1031 82-52 Amendment No. 7

Page 106: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-19 Loading Table for PWR Fuel - 922 W/Assembly (continued)

40 <Assembly Average Burnup s 41 GWd/MTU Initial Assemblyl---_____ M_in_i_m_um_C_oo_l_in...__Ti_m_e_,...__e_ar_s,__ ____ _

Avg. Enrichment CE WE WE B&W CE WE B&W 17x17 wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17

2.1sE<2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9 2.9 s E < 3.1 3.1sE<3.3 3.3 s E < 3.5 3.5 s E < 3.7 3.7 s E < 3.9 3.9 s E < 4.1 4.1sE<4.3 4.3 s E < 4.5 4.5 s E < 4.7 4.7 s E < 4.9

E~4.9

,,,,,s E < 4.3 4.S~E <4.5 4.5 s E < 4.7 4.7 s E < 4.9

E~4.9

5.5 5.4 5.3 5.3 5.2 5.1 5.0 5.0 5.0 4.9 4.9 4.8 4.8

5.6 6.6 6.8 5.6 6.4 6.7 5.5 6.3 6.6 5.4 6.2 6.5 . 0.J' 5.3 6.1 6.4 5~8' 6~ '\;,~~.2 ,.< 5.3 6.1 6.3 ~5~'\, ~2 ·~¥"'' 5.2 6.0 6.~;~5J~;t~· 6.1 •• ~6.1

mr~w ~ ~' ·"' .w 5.1 5.9 6.2,)" - ' 5.6 ~::6.0/~,' 6.0 1•7, "' ·¥ 5.1 5.9 ~. ''"'" 0~~ @J© 6.0

5.0 5.9 ... ,, 6.0"'~/ 5.5 ~q 5.9 5.9

;:~ (s'1';qtP ~ ;~ ~:~ 4.9 $·} 5.9 ~j 5.4 5.8 5.8

7.1 7.0 6.9 6.8 6.7 6.6 6.6 6.5 6.4 6.3 6.3 6.2 6.2

6.4 6.2 6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6 5.6

6.9 6.8 6.7 6.6 6.6 6.5 6.4 6.3 6.3 6.2 6.1 6.1 6.0

B&W

6.9 6.8 6.7 6.6 6.5 6.5 6.4 6.3 6.2 6.2 6.1 6.1 6.0

Certificate of Compliance No. 1031 82-53 Amendment No. 7

Page 107: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-19 Loading Table for PWR Fuel - 922 W/Assembly (continued)

42 <Assembly Average Burnup ~ 43 GWd/MTU Initial Assembly,__ _____ M_in_i_m_um_C_oo_li_n~Ti_m_e--"'--e_ar_sL_._ ___ _

Avg. Enrichment CE WE WE B&W CE wt% 235U E 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 2.7 ~ E < 2.9 2.9 ~ E < 3.1 3.1~E<3.3

3.3 ~ E < 3.5 3.5 ~ E < 3.7 3.7 ~ E < 3.9 3.9 ~ E < 4.1 4.1~E<4.3

4.3 ~ E < 4.5 4.5 ~ E < 4.7 4.7 ~ E < 4.9

E~4.9

14x14

5.9 5.8 5.8 5.7 5.6 5.5 5.5 5.4 5.3 5.3 5.2 5.2 5.1

14x14

6.1 6.0 5.9 5.8 5.8 5.7 5.6 5.6 5.5 5.5

15x15 15x15 16x16

6.7

WE 17x17

4~-?~;;·~p ~v~ag~~~rnup ~ 44 GWd/MTU Initial Assembly Afr Mil:HmunfGaoliny Time ears Avg. Enrichment CE ~~.E ~ vWE B&W CE WE

wt% 235U E t4~J40,.J4~~~ 15x15 15x15 16x16 17x17 2.1~E<2.3 tr """,),: ~~: -;~~~%t ~~ l \6 8.0 6.9 77

~:~~f:1~~1~ ~i~n~~~ ;:~ 7.8 6.8 7.5 , ·~0,, Yi 7.7 6.7 7.4

3.f's,,i;. < ... 3~~1lll~ii~J:S?;. 6.0 7.2 7.5 6 6 7 3 . ·,·;3~'3i-~Wts ?s" 6.o 7.o 7.4 6:5 7:1 . 3, E <~~~, 5.8 5.9 6.9 7.3 6.4 7.0

31(~!:;, E < 3~ 5.7 5.8 6.9 7.2 6.3 7.0 ".!·3~9 ~ E < 4.1 5.6 5.8 6.8 7.1 6.3 6.9 '~~1~ E < 4.3 5.5 5.7 6.7 7.0 6.2 6.8

4.3..:& E < 4.5 5.5 5.7 6.7 6.9 6.1 6.8 4.5::; E < 4.7 5.4 5.6 6.6 6.9 6.0 6.7 4.7 ::; E < 4.9 5.4 5.6 6.5 6.8 6.0 6.6

E ~ 4.9 5.3 5.5 6.5 6.8 6.0 6.6

B&W 17x17

B&W 17x17

7.7 7.5 7.4 7.3 7.1 7.0 7.0 6.9 6.8 6.8 6.7 6.6 6.6

Certificate of Compliance No. 1031 82-54 Amendment No. 7

Page 108: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-19 Loading Table for PWR Fuel - 922 W/Assembly (continued)

44 <Assembly Average Burn up~ 45 GWd/MTU Initial Assembly Minimum Coolin Time ears

Avg. Enrichment CE WE WE B&W CE WE B&W wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1 ::;E<2.3 2.3 ::; E < 2.5 2.5::; E < 2.7 2.7 ::; E < 2.9 6.3 6.6 8.3 2.9::; E < 3.1 6.2 6.4 8.1 3.1 ::; E < 3.3 6.1 6.3 7.9 3.3 ::; E < 3.5 6.0 6.2 7.8 3.5::; E < 3.7 5.9 6.1 7.7 3.7::; E < 3.9 5.9 6.0 7.6 ,' 3.9 ::; E < 4.1 5.8 6.0 q, 4.1 ::; E < 4.3 5.7 5.9 4.3 ::; E < 4.5 5.7 5.9 4.5::; E < 4.7 5.6 5.8 7.0 4.7::; E < 4.9 5.6 5.8 6.9

E 2: 4.9 5.5 5.7 6.9

Certificate of Compliance No. 1031 82-55 Amendment No. 7

Page 109: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Note: For fuel assembly average burn up greater than 45 GWd/MTU, cool time tables have been revised to account for a 5% margin in heat load.

Table 82-20 Loading Table for PWR Fuel- 876 W/Assembly

45 < Assembly Average Burnup ::;; 46 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1::;; E < 2.3 2.3::;; E < 2.5 2.5::; E < 2.7 2.7::; E < 2.9 7.1 7.4 9.2 9.8 2.9::; E < 3.1 7.0 7.3 9.0 9.6 3.1::; E < 3.3 6.9 7.1 8.8 3.3::; E < 3.5 6.8 7.0 8.6 3.5::; E < 3.7 6.7 6.9 3.7::; E < 3.9 6.6 6.8 3.9::; E < 4.1 6.5 6.7 4.1::; E < 4.3 6.4 6.6 4.3 ::; E < 4.5 6.3 6.6 4.5::; E < 4.7 6.2 6.5 4.7::; E < 4.9 6.2 7.9

E ~4.9 6.1 7.9

Certificate of Compliance No. 1031 82-56 Amendment No. 7

Page 110: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-20 Loading Table for PWR Fuel - 876 W/Assembly (continued)

46 <Assembly Average Burnup ~ 47 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 23su E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1 ::; E < 2.3 2.3 ::; E < 2.5 2.5::; E < 2.7 2.7::; E < 2.9 7.5 7.8 9.8 2.9 ::; E < 3.1 7.4 7.7 9.6 3.1 ::; E < 3.3 7.2 7.5 9.3 3.3 ::; E < 3.5 7.1 7.4 9.1 3.5::; E < 3.7 7.0 7.2 9.0 3.7::; E < 3.9 6.9 7.1 8.8 3.9::; E < 4.1 6.8 7.0 4.1 ::; E < 4.3 6.7 6.9 4.3 ::; E < 4.5 6.6 6.9 4.5::; E < 4.7 6.5 6.8 4.7::; E < 4.9 6.5 6.7

E 2:: 4.9 6.4

Initial Assembly Avg. Enrichment B&W

17x17 17x17

10.5 11.3 9.2 10.7 10.6 10.2 11.1 9.0 10.4 10.3

7.9 10.0 10.8 8.8 10.1 10.1 7.8 9.7 10.5 8.7 9.9 9.9 7.6 9.6 10.3 8.5 9.7 9.7 7.5 9.4 10.1 8.4 9.5 9.5 7.4 9.2 9.9 8.2 9.4 9.4 7.3 9.0 9.7 8.1 9.2 9.2 7.2 8.9 9.6 8.0 9.1 9.1 7.1 8.8 9.5 7.9 9.0 9.0

4.7::; E < 4.9 7.0 8.7 9.4 7.8 8.9 8.9 E 2:: 4.9 6.7 6.9 8.6 9.2 7.7 8.8 8.8

Certificate of Compliance No. 1031 82-57 Amendment No. 7

Page 111: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-20 Loading Table for PWR Fuel - 876 W/Assembly (continued)

48 < Assembly Average Burnup ~ 49 GWd/MTU Initial Assembly 1---~---M~in_i_m_um~C_oo_l_in....__Ti~m_e.......__e_ar~s'----~--Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235LJ E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1::; E < 2.3 2.3 ::; E < 2.5 2.5::; E < 2.7 2.7::; E < 2.9 2.9 ::; E < 3.1 3.1::; E < 3.3 3.3 ::; E < 3.5 3.5::; E < 3.7 3.7::; E < 3.9 3.9 ::; E < 4.1 4.1 ::; E < 4.3 4.3 ::; E < 4.5 4.5::; E < 4.7 4.7::; E < 4.9

E 2".4.9

8.4 8.2 8.0 7.8 7.7 7.6 7.4 7.3 7.2 7.1 7.0 6.9

8.8 8.6 8.4 8.2 8.0 7.9 7.8 7.7 7.6 7.5 7.4

Initial Assembly1-----,;;,~------.-+---~~....__~-"'--...'----~-­Avg. Enrichment

.9 11.8 8.7 11.5 8.5 11.2 8.4 11.0

7.9 8.2 10.7 7.8 8.0 10.5 7.7 7.9 10.3 7.6 7.8 10.1 7.5 7.7 9.9

4.7::; E < 4.9 7.4 7.6 9.8 E 2".4.9 7.3 7.6 9.7

Certificate of Compliance No. 1031 82-58

B&W 15x15 16x16 17x17 17x17

12.7 10.2 11.9 11.9 12.4 10.0 11.7 11.6 12.1 9.8 11.4 11.4 11.8 9.6 11.2 11.1 11.6 9.4 10.9 10.9 11.4 9.2 10.7 10.7 11.2 9.0 10.5 10.5 11.0 8.9 10.4 10.3 10.9 8.8 10.2 10.1 10.7 8.7 10.0 10.0 10.5 8.6 9.9 9.9

Amendment No. 7

Page 112: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-20 Loading Table for PWR Fuel - 876 W/Assembly (continued)

50 < Assembly Average Burnup::; 51 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1::; E < 2.3 2.3::; E < 2.5 2.5::; E < 2.7 2.7::; E < 2.9 2.9::; E < 3.1 8.9 9.5 12.6 13.7 3.1 ::; E < 3.3 8.7 9.3 12.2 13.3 3.3 ::; E < 3.5 8.5 9.0 11.9 13.0 3.5::; E < 3.7 8.4 8.8 11.7 3.7::; E < 3.9 8.2 8.7 11.5 3.9::;E<4.1 8.0 8.5 11.2 4.1::; E < 4.3 7.9 8.4 4.3 ::; E < 4.5 7.8 8.2 4.5::; E < 4.7 7.7 8.1 4.7::; E < 4.9 7.6 8.0

E;::: 4.9 7.5

Initial Assembly Avg. Enrichment ,.t~' B&W

wt% 235U E 14~ ~i~'4';,% 15x15 16x16 17x17 17x17 "'• 7 2.1 ::; E < 2.3 (: ;~ 2.3 ::; E < 2.5 2.5::; E < 2.7

\ .... 1 2.7::;~~~ _,

2.9tt:... < 3.1)':1', ~~~:;f0.1 13.5 14.3 11.7 13.7 13.7 <'')._ i itlQ:;?,,, 9.8 13.2 13.9 11.5 13.4 13.4 3.1~;~~ \'.''' '.,.

03"3 < E~'* 3 5 9~0'" 9.6 12.8 13.6 11.2 13.1 13.0 '4''' ··kit\ ~~

8.8 9.4 12.5 13.3 10.9 12.8 12.7 ·~·' 3. '"~ E <'3':,~ ' "\;;\?'_,

8.7 9.2 12.2 13.0 10.7 12.5 12.4 3 E < 3.~~ 111t!~~ <E<41 8.5 9.0 12.0 12.8 10.4 12.2 12.2

~*;' '$:~ I - I

11.8 12.5 10.2 12.0 11.9 '4>1::; E < 4.3 8.3 8.9 4~~E < 4.5 8.2 8.7 11.6 12.3 10.0 11.8 11.8 4.5::; E < 4.7 8.1 8.6 11.4 12.1 9.9 11.6 11.6 4.7::; E < 4.9 8.0 8.5 11.2 11.9 9.8 11.5 11.5

E;::: 4.9 7.9 8.3 11.1 11.8 9.6 11.3 11.3

Certificate of Compliance No. 1031 82-59 Amendment No. 7

Page 113: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-20 Loading Table for PWR Fuel - 876 W/Assembly (continued)

52 <Assembly Average Burnup ~ 53 GWd/MTU

Initial Assembly Minimum Coolin Time ears

Avg. Enrichment CE WE WE B&W CE WE B&W wt%23su E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 2.7 ~ E < 2.9 2.9 ~ E < 3.1 10.1 10.9 15.3 3.1~E<3.3 9.8 10.5 14.9 3.3 ~ E < 3.5 9.6 10.2 14.6 •' -l-~,;;

3.5 ~ E < 3.7 9.3 10.0 14.2 1·~r6 3.7 ~ E < 3.9 9.1 9.9 13.3 3.9~E<4.1 8.9 9.6 13.1 4.1~E<4.3 8.8 9.4 12.8 4.3 ~ E < 4.5 8.7 9.2 12.6 4.5 ~ E < 4.7 8.5 9.0 12.4 4.7 ~ E < 4.9 8.4 8.9 12.2

E~4.9 8.3 12.0

Initial Assembly Avg. Enrichment B&W

wt% 23su E 15x15 16x16 17x17 17x17 2.1~E<2.3

.6 15.1 16.4 13.5 15.7 15.6 11.3 14.6 15.9 13.1 15.3 15.3 11.0 14.2 15.6 12.7 14.9 14.9 10.7 13.9 15.2 12.4 14.6 14.6 10.4 13.6 14.9 12.1 14.3 14.2 10.2 13.4 14.6 11.9 14.0 14.0 9.9 13.1 14.3 11.7 13.7 13.7 9.8 12.9 14.0 11.5 13.5 13.5 9.6 12.6 13.8 11.3 13.3 13.3

4.7 ~ E < 4.9 9.5 12.4 13.6 11.1 13.1 13.1 E~4.9 8.7 9.6 12.2 13.4 10.9 12.9 12.9

Certificate of Compliance No. 1031 82-60 Amendment No. 7

Page 114: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-20 Loading Table for PWR Fuel - 876 W/Assembly (continued)

54 <Assembly Average Burnup :::;; 55 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1:::;; E < 2.3 2.3:::;; E < 2.5 2.5:::;; E < 2.7 2.7:::;; E < 2.9 2.9:::;E<3.1 3.1 :::;; E < 3.3 11.2 12.0 15.6 3.3:::;; E < 3.5 10.9 11.7 15.2 3.5:::;; E < 3.7 10.6 11.4 14.9 3.7:::;E<3.9 10.3 11.2 14.5 3.9:::;; E < 4.1 10.0 10.9 14.2 4.1:::;; E < 4.3 9.9 10.7 4.3:::;; E < 4.5 9.7 10.5 4.5:::;; E < 4.7 9.5 10.2 4.7:::;; E < 4.9 9.3 10.0

E~4.9 9.2 13.7

Initial Assembly Avg. Enrichment CE B&W

wt% 235U E 15x15 16x16 17x17 17x17 2.1:::; E < 2.3 2.3:::; E < 2.5

12.8 16.6 18.1 14.5 17.4 17.3 12.5 16.2 17.6 14.1 17.0 16.9 12.1 15.8 17.3 13.7 16.6 16.6 11.8 15.5 17.0 13.4 16.3 16.2 11.6 15.2 16.6 13.2 15.9 15.9

10.5 11.3 14.9 16.3 12.9 15.7 15.6 10.2 11.1 14.6 16.0 12.6 15.4 15.3 10.0 10.9 14.3 15.8 12.4 15.2 15.1

4.7:::; E < 4.9 9.9 10.7 14.1 15.6 12.2 14.9 14.9 E~4.9 9.7 10.5 13.9 15.3 12.0 14.7 14.6

Certificate of Compliance No. 1031 82-61 Amendment No. 7

Page 115: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-20 Loading Table for PWR Fuel - 876 W/Assembly (continued)

56 <Assembly Average Burn up~ 57 GWd/MTU Initial Assembly 1----~--~M_in_im_u_m_C~o_o_lin_.,__T~im_e_lL_e_a~rs_,__ ___ _ Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 2.7 ~ E < 2.9 2.9 ~ E < 3.1 3.1~E<3.3 12.6 3.3 ~ E < 3.5 12.3 3.5 ~ E < 3.7 11.9 3.7 ~ E < 3.9 11.7 3.9 ~ E < 4.1 11.4 4.1 ~ E < 4.3 11.2 4.3 ~ E < 4.5 10.9 4.5 ~ E < 4.7 10.7 4.7 ~ E < 4.9 10.5

E ~ 4.9 10.3

14.5 14.1 13.8 13.4 13.1 12.9 12.6 12.3 12.1 11.9

Certificate of Compliance No. 1031

18.7 18.3 17.9 17.5 17.2 16.9 16.5 16.3 16.0 15.8

82-62

20.1 16.4 19.5 19.4 19.8 15.9 19.1 19.0 19.4 15.6 18.7 18.7 19.0 15.3 18.4 18.3 18.7 14.9 18.0 18.0 18.4 14.6 17.7 17.7 18.1 14.3 17.4 17.4 17.8 14.0 17.2 17.1 17.5 13.8 16.9 16.8 17.3 13.6 16.7 16.6

Amendment No. 7

Page 116: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-20 Loading Table for PWR Fuel - 876 W/Assembly (continued)

58 <Assembly Average Burnup ~ 59 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235LJ E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1::; E < 2.3 2.3 ::; E < 2.5 2.5::; E < 2.7 2.7::; E < 2.9 2.9::;E<3.1 3.1 ::; E < 3.3 14.3 15.4 19.7 3.3 ::; E < 3.5 13.9 15.0 19.3 3.5::; E < 3.7 13.5 14.7 18.9 3.7::; E < 3.9 13.2 14.3 18.5 3.9::; E < 4.1 12.9 14.0 4.1::; E < 4.3 12.6 13.7 4.3 ::; E < 4.5 12.2 13.4 4.5::; E < 4.7 12.0 13.1 4.7::; E < 4.9 11.8 12.9

E~4.9 11.6

Initial Assembly Avg. Enrichment CE B&W

wt% 235LJ E 15x15 15x15 16x16 17x17 17x17 2.1::; E < 2.3 2.3::; E < 2.5 2.5::; E < 2.7

2.77~· -2.~t'.~I • < 3. ~~ '"" >,. "'

~~ 3.1~ ~~v3::~ ~'!;; '}?: '\'l.&l~~\ifk~-~~ ... ~ --~ "•1~:7 15.9 20.2 21.9 17.9 20.7 20.6 ~~~::; &'§\·3.5 .IT ··"·\ ""··· 14.3 15.6 19.9 21.5 17.5 20.3 :: 3.5z~ E < 20.2 """~ 3 ;/j E < 3. 13.9 15.2 19.5 21.1 17.1 19.9 19.9 ~\,.#(}~I;'.?/

13.6 14.9 19.2 20.8 16.8 19.6 19.5 •·"'::?J3~9 ::; E < 4.1

~~E<4.3 13.3 14.5 18.8 20.5 16.4 19.3 19.2 4.S~E <4.5 13.1 14.2 18.5 20.2 16.1 18.9 18.9 4.5::; E < 4.7 12.8 13.9 18.2 19.9 15.8 18.7 18.6 4.7 ::; E < 4.9 12.5 13.7 18.0 19.6 15.6 18.4 18.3

E~4.9 12.3 13.5 17.7 19.4 15.4 18.2 18.1

Certificate of Compliance No. 1031 82-63 Amendment No. 7

Page 117: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-21 Loading Table for PWR Fuel - 800 W/Assembly

30 <Assembly Average Burn up:::; 32.5 GWd/MTU Initial Assembly r-------.------.--M_in_im_u_m---,C_o_ol_in_.....__T,...im_e---"<-e_a_rs+-----.---Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1 ::::; E < 2.3 2.3::::; E < 2.5 2.5::::; E < 2.7 2.7:::; E < 2.9 2.9 ::::; E < 3.1 3.1::::; E < 3.3 3.3::::; E < 3.5 3.5::; E < 3.7 3.7::; E < 3.9 3.9sE<4.1 4.1::; E < 4.3 4.3::; E < 4.5 4.5sE<4.7 4.7::; E < 4.9

E~4.9

4.8 4.7 4.7 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.3

32.~~~~111 ... m~~ag~. $.Hrnup:::; 35 GWd/MTU Initial Assembly ,,tti}Y ~.n\muln<iie_QQlirfvTime ears Avg. Enrichment CE ,,W,E 1'1)WE B&W CE WE B&W

wt% 235U E 14~1t4i':"~~f4.:~Y15x15 15x15 16x16 17x17 17x17

2.1::; E < 2 .. 3 .. ~·'.'·(·{·rr--~ • .. ~<~ -2.3::; E < 2.5 ~5.2 S~~ \Q6.0 6.3 5.7 6.1 2.5::; E < 2.7 '~' . 1 5.2l* 6.0 6.2 5.7 6.0 ~ ~~ /.,•.

2.7::::; E~~~~"l· o!©~~ .. §12 5.9 6.1 5.6 6.0 2.9~E'f3.1 J' 5.~~5.1 5.9 6.0 5.5 5.9 3.1 - 3J~ ~9~ 5.0 5.8 6.0 5.5 5.9

''3:~-.;~\ ·Qrv 4.9~ 5.o 5.8 5.9 5.4 5.8 3.5 5;~!£ < 3".'~ .. 4.9 4.9 5.7 5.9 5.4 5.8 3l~E < 3.9 ··~~ 4.8 4.9 5.7 5.8 5.3 5.8 3f;9"'::; E < 4.1 4.8 4.9 5.6 5.8 5.3 5.7

'\,:i'~· ii~t~ E < 4.3 4.7 4.8 5.6 5.8 5.2 5.7 4.~ < 4.5 4.7 4.8 5.5 5.7 5.2 5.6 4.5::; E < 4.7 4.7 4.8 5.5 5.7 5.2 5.6 4.7::::; E < 4.9 4.6 4.7 5.5 5.7 5.1 5.6

E ~ 4.9 4.6 4.7 5.4 5.6 5.1 5.5

Certificate of Compliance No. 1031 82-64

6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.8 5.7 5.7 5.6 5.6 5.6 5.5

Amendment No. 7

Page 118: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-21 Loading Table for PWR Fuel - 800 W/Assembly (continued)

35 <Assembly Average Burnup::;; 37.5 GWd/MTU Initial Assembly 1---~--~M_in_im_um~Co_o_li_,n .._T_i~m_e_,,,__ea_r~s "----~---Avg. Enrichment CE WE WE B&W CE WE

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 B&W 17x17

2.1:<.:;E<2.3 2.3 :<.:; E < 2.5 2.5 :<.:; E < 2.7 2.7::; E < 2.9 2.9::;; E < 3.1 3.1::;; E < 3.3 3.3 :<.:; E < 3.5 3.5::;; E < 3.7 3.7::;; E < 3.9 3.9:<.:;E<4.1 4.1::; E < 4.3 4.3::; E < 4.5 4.5::; E < 4.7 4.7::;; E < 4.9

E~4.9

5.8 5.7 5.6 5.5 5.5 5.4 5.3 5.3 5.2 5.2 5.1 5.1 5.0 5.0

5.9 6.9 7.1 6.4 6.9 5.8 6.8 7.0 6.3 5.7 6.7 6.9 6.2 5.7 6.6 6.8 6.1 5.6 6.5 6.8 6.0 5.5 6.4 6.7 6.0 5.5 6.3 6.6 5,·,

,.;·

5.4 6.3 6.5 ~i~ 5.4 6.2 6.5 5:8:;,: 5.3 6.1 ~~ 5.8

5.3 6.1 n: ~if77~ 5.2 6.o 6!t~r571 5.2 6,0r'.~J;~6,3 ~.77:~r /'}v ~ ~ ~ .. ,; 5.1 Ai~~ 6)?ii. -~J6 6.1

8.1 8.0 7.8 7.7 7.6 7.5 7.4 7.4 7.3 7.2 7.1 7.1 7.0

7.0 6.9 6.9 6.8 6.7 6.6 6.5 6.5 6.4 6.4 6.3 6.3 6.2

7.8 7.7 7.6 7.4 7.3 7.3 7.2 7.1 7.0 7.0 6.9 6.9 6.8

Certificate of Compliance No. 1031 82-65

B&W 17x17

7.8 7.7 7.6 7.4 7.3 7.2 7.1 7.1 7.0 7.0 6.9 6.9 6.8

Amendment No. 7

Page 119: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-21 Loading Table for PWR Fuel - 800 W/Assembly (continued)

40 <Assembly Average Burnup:::; 41 GWd/MTU Initial Assembly 1---------.-------.M_in_im_u_m_C.-o_o_li_,n .._T--,im,_e .1£..._ea_rs--+-------,----Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1 :::; E < 2.3 2.3 :::::; E < 2.5 2.5:::::; E < 2.7 2.7:::; E < 2.9 2.9::SE<3.1 3.1:::::; E < 3.3 3.3:::; E < 3.5 3.5:::; E < 3.7 3.7:::::; E < 3.9 3.9:::;E<4.1 4.1:::; E < 4.3 4.3:::; E < 4.5 4.5:::; E < 4.7 4.7:::::; E < 4.9

E~4.9

6.6 6.5 6.4 6.3 6.2 6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.7

6.8 8.2 6.7 8.0 6.6 7.9 6.5 7.8 6.4 7.7 6.3 7.6 6.2 7.5 6.1 7.4

8.7 8.5 8.3 8.2 8.0

6.1 7.3 ~ ~1

6.0 7.2 6~~ 6.7 6.0 71'~~~~') ~9, .. 5 9 ~p1; 7·,r:c~4.·.···'.. ,~jt;.~ . .,, .'9<?~ 'ti.

5.9 tp 7.4\~ 6.5 7.2

41 ~1A~~iy~~rag~~Ji~?up:::; 42 GWd/MTU Initial Assembly M1 mum::.~q-g,~n Time ears Avg. Enrichment CE W.E WE B&W CE WE

wt% 235LJ E 14>s2t~·~'."'"1~~ft 15x15 16x16 17x17

8.7 8.6 8.4 8.2 8.1 8.0 7.9 7.8 7.7 7.6 7.6 7.5 7.4

9.3 9.0 8.9 8.7 8.6 8.5 8.3 8.2 8.1 8.0 8.0 7.9 7.8

7.8 7.7 7.6 7.5 7.3 7.2 7.1 7.1 7.0 6.9 6.9 6.8 6.8

8.8 8.6 8.5 8.3 8.2 8.1 8.0 7.9 7.8 7.8 7.7 7.6 7.6

7.3 7.3 7.2 7.2

B&W 17x17

8.8 8.6 8.5 8.3 8.2 8.1 8.0 7.9 7.8 7.7 7.7 7.6 7.6

Certificate of Compliance No. 1031 82-66 Amendment No. 7

Page 120: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-21 Loading Table for PWR Fuel - 800 W/Assembly (continued)

42 < Assembly Average Burnup::; 43 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 23su E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1 ::; E < 2.3 2.3 ::; E < 2.5 2.5::; E < 2.7 7.3 7.5 9.3 9.9 8.3 2.7::; E < 2.9 7.1 7.4 9.1 9.7 8.1 2.9 ~ E < 3.1 7.0 7.2 8.9 9.5 8.0 3.1~E<3.3 6.9 7.1 8.8 9.3 7.9"~ >

" 3.3 ~ E < 3.5 6.8 7.0 8.6 9.2 <7t:8 .. ~/ 6.7 6.9 8.5 9.0

,'!JI'

,8.6 ~6 3.5 ~ E < 3.7 ~~ 3.7 ~ E < 3.9 6.6 6.8 8.4 8~ ~7.~ 8.5~ ~ 8.5 6.5 8,·sr ~ 8 4:"" ~ 3.9~E<4.1 6.8 8.2 . 7.5 ' ···~·· 8.4

I Cf

~ ~'·' 4.1 ::; E < 4.3 6.5 6.7 8.1 8~7 .r3 8.3

~:· '

4.3 ~ E < 4.5 6.4 6.6 8.0 8 6" ·if: .'.:' 7 3 ~. 8.2 8.2 .·~'¥ffe

4.5 ~ E < 4.7 6.3 6.6 8!F ~ ~.:; 8.1 8.1 {''

·~ ~;;:,'8J7l!P,v 4.7 ~ E < 4.9 6.2 6.5 ~~19 8.~~l ' 8.0 8.0 E;:::4.9 6.2 6.4 ~:? 8.3 ' 7.1 8.0 8.0

}f'~f'iY~x;~ag~<4~:af~up ::; 44 GWd/MTU Initial Assembly ' MmJmum~0JrGl!rf Time ears Avg. Enrichment ·WE E B&W CE WE B&W

""'>

wt% 23su E 15x15 16x16 17x17 17x17 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 i,.,~,\~ . 7 10.0 10.8 8.8 10.0 10.1 2.7~~<ii~ ~~ 7.§' 9.7 10.5 8.7 9.9 9.8 2.9~~3.1J 7.4 ''" ~ 9.5 10.2 8.5 9.7 9.6 ::::£..-"

3.1~~3;-~f'~ 7J"::7"":;7 7.5 9.3 10.0 8.3 9.5 9.4 £3~3~:$ E"<'3.·f"" 7i~ 7.4 9.2 9.8 8.2 9.3 9.3 .. 1:~·~ ~~~ 7.1 7.3 9.0 9.7 8.0 9.1 9.1 ., ;, ' 3.5 ~!!! < ~7''.:.

3J4i:E < 19~ ' 6.9 7.2 8.9 9.5 8.0 9.0 9.0 ,"'{1;l,_,:Y

· ... a~§7~ E < 4.1 6.8 7.1 8.8 9.4 7.9 8.9 8.9 '!%>~~~ 6.7 7.0 8.7 9.2 7.8 8.8 8.8 ·~~)GE< 4.3 4.~~<4.5 6.7 6.9 8.5 9.1 7.7 8.7 8.7 4.5 ~ E < 4.7 6.6 6.9 8.5 9.0 7.6 8.6 8.6 4.7 ~ E < 4.9 6.6 6.8 8.4 8.9 7.6 8.5 8.5

E;:::4.9 6.5 6.8 8.3 8.9 7.5 8.5 8.4

Certificate of Compliance No. 1031 82-67 Amendment No. 7

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Table 82-21 Loading Table for PWR Fuel - 800 W/Assembly (continued)

44 <Assembly Average Burnup::::; 45 GWd/MTU Initial Assembly 1--------.------.-M_in_im_u_m-.-C_oo_li---'n.._T_i..-m_e-"'--e_ar--js r--------.---Avg. Enrichment CE WE WE B&W CE WE

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 B&W

17x17 2.1 ::::; E < 2.3 2.3 ::::; E < 2.5 2.5::::; E < 2.7 2.7::::; E < 2.9 2.9::::; E < 3.1 3.1::::; E < 3.3 3.3 ::::; E < 3.5 3.5::::; E < 3.7 3.7::::; E < 3.9 3.9 ::::; E < 4.1 4.1 :s;E<4.3 4.3 ::::; E < 4.5 4.5::::; E < 4.7 4.7::::; E < 4.9

E~4.9

7.9 7.8 7.6 7.5 7.3 7.2 7.1 7.0 7.0 6.9 6.8 6.8

8.2 8.1 7.9 7.8 7.7 7.6 7.5 7.4 7.3 7.2 7.1 7.0

Certificate of Compliance No. 1031

10.5 10.2 10.0 9.8 9.6 9.5

82-68 Amendment No. 7

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Note: For fuel assembly average burn up greater than 45 GWd/MTU, cool time tables have been revised to account for a 5% margin in heat load.

Table 82-22 Loading Table for PWR Fuel - 760 W/Assembly

45 < Assembly Average Burnup :::;; 46 GWd/MTU Initial Assembly r------.---M--.i_n_im_u_m_C.--o_o_lin~T-.im_e~_ea_r---rs --~---Avg. Enrichment CE WE WE B&W CE

wt% 235U (E) 14x14 2.1:::;; E < 2.3 2.3:::; E < 2.5 2.5:::; E < 2.7 2.7:::; E < 2.9 2.9:::;E<3.1 3.1 :::; E < 3.3 3.3:::; E < 3.5 3.5:::; E < 3.7 3.7:::;; E < 3.9 3.9:::; E < 4.1 4.1:::;; E < 4.3 4.3:::;; E < 4.5 4.5:::; E < 4.7 4.7:::; E < 4.9

E 2:: 4.9

14x14

Certificate of Compliance No. 1031

15x15 15x15

82-69

16x16

9.5 9.4 9.3

WE 17x17

B&W 17x17

12.1 11.9 11.7 11.5 11.4 11.3 11.1 11.0 10.9

Amendment No. 7

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Table 82-22 Loading Table for PWR Fuel - 760 W/Assembly (continued)

46 <Assembly Average Burnup ~ 47 GWd/MTU Initial Assembly 1-------..c:..:.M=in=im"-'-'u=mc.::.._C.;...co'-'-o=lin-'-"'--T_im_e___,..._e:....::..:a=rs"'--_---Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 2.7 ~ E < 2.9 2.9 ~ E < 3.1 3.1~E<3.3

3.3 ~ E < 3.5 3.5 ~ E < 3.7 3.7 ~ E < 3.9 3.9 ~ E < 4.1 4.1~E<4.3

4.3 ~ E < 4.5 4.5 ~ E < 4.7 4.7 ~ E < 4.9

E~4.9

9.9 9.7 9.4 9.2 9.0 8.9 8.8 8.6 8.5 8.4 8.3 8.2

Certificate of Compliance No. 1031

14.9 16.1 14.5 15.8 14.1 15.5 13.9 15.2 13.6 14.9 13.4 14.6 13.2 14.4 13.0 14.1 12.8 14.0 12.6 13.8 12.4 13.6 12.3 13.5

82-70

B&W

12.9 15.1 15.1 12.5 14.7 14.7 12.2 14.4 14.4 12.0 14.1 14.0 11.8 13.8 13.8 11.6 13.6 13.6 11.4 13.4 13.4 11.2 13.2 13.2 11.1 13.0 13.0 10.9 12.9 12.8 10.8 12.7 12.7 10.7 12.5 12.5

Amendment No. 7

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Table 82-22

Initial Assembly Avg. Enrichment

wt% 235U E 2.1::; E < 2.3 2.3::; E < 2.5 2.5::; E < 2.7 2.7::; E < 2.9 2.9 ::; E < 3.1 3.1::; E < 3.3 3.3 ::; E < 3.5 3.5::; E < 3.7 3.7::; E < 3.9 3.9::; E < 4.1 4.1::; E < 4.3 4.3 ::; E < 4.5 4.5::; E < 4.7 4.7::; E < 4.9

E ~4.9

Loading Table for PWR Fuel - 760 W/Assembly (continued)

CE 14x14

11.4 11.1 10.8 10.6 10.3 10.1 9.9 9.7 9.6 9.5 9.3 9.2

48 < Assembly Average Burnup ~ 49 GWd/MTU Minimum Coolin

WE WE B&W 14x14 15x15 15x15

12.2 16.0 17.3 11.8 15.6 17.0 11.6 15.3 16.6 11.3 14.9 16.3 11.1 14.7 10.9 14.4 10.7 14.1 10.4 13.9 10.2 10.1 9.9

16.8 18.2 16.4 17.8 16.0 17.5 15.7 17.2 15.5 16.9 15.2 16.6 14.9 16.3 14.7 16.1 14.5 15.9

10.5 14.3 15.7 10.3 14.1 15.5

Time ears CE

16x16

13.9

14.5 14.1 13.8 13.6 13.3 13.1 12.9 12.7 12.5 12.3 12.2

WE B&W 17x17 17x17

13.9 13.8 13.6 13.5

B&W 17x17 17x17

17.0 17.0 16.6 16.6 16.3 16.2 16.0 16.0 15.7 15.7 15.5 15.5 15.3 15.2 15.0 15.0 14.9 14.8 14.6 14.6 14.5 14.5

Certificate of Compliance No. 1031 82-71 Amendment No. 7

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Table 82-22 Loading Table for PWR Fuel - 760 W/Assembly (continued)

50 < Assembly Average Burnup::;; 51 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 23su E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1 ::o;E<2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9 2.9sE<3.1 12.4 13.4 17.8 3.1sE<3.3 12.1 13.1 17.5 3.3 s E < 3.5 11.8 12.7 17.2 3.5 s E < 3.7 11.5 12.4 16.8 3.7 s E < 3.9 11.3 12.1 16.5 3.9 s E < 4.1 11.1 11.9 16.2 4.1sE<4.3 10.9 11.7 4.3 s E < 4.5 10.7 11.5 4.5 s E < 4.7 10.5 11.4 4.7 s E < 4.9 10.4 11.2

E 2:4.9 10.2 15.5

Initial Assembly Avg. Enrichment CE B&W

wt% 23su E 15x15 16x16 17x17 17x17 2.1sE<2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7s~~

;_,. •::.·-

;~.3 Lt;- ~· 1 . 19.0 20.1 16.7 19.4 19.3 2.9~~e: < 3.1 ·~ <··;~ ;"

~1,2.,.9 14.0 18.6 19.7 16.3 19.0 18.9 3.1~~<,l&~* . :':"3"3 < '5\ :gf'5 ~~2~6?' 13.6 18.2 19.4 15.9 18.6 18.6 ... 'f..···'£ °'\;;'.'..

'.. 3.Si'~ E ~~'\_ 12.3 13.3 17.9 19.1 15.6 18.3 18.3 '. hifi ~.

12.0 13.1 17.6 18.8 15.3 18.0 17.9 ~'.t~ 3.~'.:~ E < 3.9-V ~~,;E<4.1 11.8 12.8 17.4 18.5 15.0 17.7 17.7

•·!l, '~";;1sE<4.3 11.6 12.5 17.1 18.2 14.8 17.5 17.4 4.3)E <4.5 11.4 12.3 16.8 18.0 14.5 17.3 17.2 4.5sE<4.7 11.2 12.1 16.6 17.7 14.4 17.0 17.0 4.7 s E < 4.9 11.1 11.9 16.4 17.5 14.1 16.8 16.8

E 2:4.9 10.9 11.8 16.2 17.4 13.9 16.6 16.5

Certificate of Compliance No. 1031 82-72 Amendment No. 7

Page 126: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-22 Loading Table for PWR Fuel - 760 W/Assembly (continued)

52 <Assembly Average Burnup:::; 53 GWd/MTU Initial Assemblyf----~--~M_in_im_u_m_C~o_o_lin_,,.__T~im_e----'-"-e_a~rsL.___~ __ Avg. Enrichment CE WE WE B&W CE WE

wt% 235LJ E 14x14 14x14 15x15 15x15 16x16 17x17 B&W 17x17

2.1 :::; E < 2.3 2.3:::; E < 2.5 2.5:::; E < 2.7 2.7:::; E < 2.9 2.9:::; E < 3.1 3.1:::; E < 3.3 3.3:::; E < 3.5 3.5:::; E < 3.7 3.7:::; E < 3.9 3.9:::; E < 4.1 4.1 :::;E<4.3 4.3:::; E < 4.5 4.5:::; E < 4.7 4.7:::;E<4.9

E~4.9

14.2 13.8 13.5 13.1 12.9 12.6 12.3 12.1 11.9 11.8 11.6

Certificate of Compliance No. 1031

20.9 20.4 20.0 19.7 19.4 19.1 18.9 18.6 18.3 18.1 17.9

82-73

22.5 22.1 21.8 21.4 21.1 20.8 20.5 20.3 20.1 19.8 19.6

18.9 18.5 18.1 17.7 17.4 17.2 16.9 16.6 16.4 16.1 15.9

21.7 21.3 21.0 20.6 20.3 20.1 19.8 19.5 19.3 19.0 18.8

21.6 21.3 20.9 20.6 20.3 20.0 19.7 19.5 19.2 19.0 18.8

Amendment No. 7

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Table 82-22 Loading Table for PWR Fuel - 760 W/Assembly (continued)

54 <Assembly Average Burnup ~ 55 GWd/MTU Initial Assembly 1--~---M~in_i_m_um~C_oo_l_in...__Ti~m_e-->L-.e_ar~s,___~---Avg. Enrichment CE WE WE B&W CE WE

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 2.1::; E < 2.3 2.3 ::; E < 2.5 2.5::; E < 2.7 2.7::; E < 2.9 2.9 ::; E < 3.1 3.1 ::; E < 3.3 3.3 ::; E < 3.5 3.5::; E < 3.7 3.7::; E < 3.9 3.9::; E < 4.1 4.1::; E < 4.3 4.3::; E < 4.5 4.5::; E < 4.7 4.7::; E < 4.9

E ~4.9

15.7 15.4 15.0 14.6 14.4 14.1 13.8 13.6 13.4 13.2

5~.~~.p.'iy~~~ag. ~.¢~,:·r~up ~ 56 GWd/MTU

B&W 17x17

Initial Assembly ,1;,y· Mu1J,mum~Cp,:Qhn Time ears Avg. Enrichment CE '<<f~WE i"lWE B&W CE WE B&W

wt% 235U E 14x1t4~ ~1"4j/15x15 15x15 16x16 17x17 17x17

22.31 ! EE : 22.35 ~(:~ ~(~~\ ~ • - • ')!$, 'V

25 <E<27 , ... J -. - ~ ·-~~ 2. 7 ::; l?'<.:2~90 ~.'; ~ .

2.9,1f!~ 3.1f:~ _·s~ 3.1~~,<]f3;~~_0 .. ~ 18.1

.~.3~~ ~~;3~ 16~3 17. 7 3.5k,~ E <~~ 15.9 17.3 3l~E<3.9-$ 15.6 17.0

~0.ef::;E<4.1 15.3 16.7 ...•.. , .,,~4':4 ::; E < 4.3 15.0 16.4 4:~~E<4.5 14.8 16.1 4.5::; E < 4.7 4.7::; E < 4.9

E ~4.9

14.5 14.3 14.0

15.8 15.6 15.4

Certificate of Compliance No. 1031

22.7 22.4 21.9 21.7 21.4 21.0 20.8 20.5 20.3 20.0

82-74

24.4 24.1 23.7 23.4 23.1 22.9 22.6 22.4 22.2 21.9

20.2 19.8 19.5 19.2 18.8 18.5 18.3 17.9 17.8 17.6

23.6 23.3 23.0 22.6 22.4 22.1 21.8 21.6 21.3 21.1

23.6 23.3 22.9 22.6 22.3 22.0 21.8 21.5 21.3 21.1

Amendment No. 7

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Table 82-22 Loading Table for PWR Fuel - 760 W/Assembly (continued)

56 < Assembly Average Burnup ::;; 57 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment CE WE WE B&W CE WE B&W

wt% 23su E 14x14 14x14 15x15 15x15 16x16 17x17 17x17 2.1::;; E < 2.3 2.3::;; E < 2.5 2.5::;; E < 2.7 2.7::;;E<2.9 2.9::;; E < 3.1 3.1::;; E < 3.3 17.7 19.2 23.8 25.6 3.3::;; E < 3.5 17.3 18.8 23.4 25.2 3.5::;; E < 3.7 16.9 18.4 23.1 24.9 3.7::;;E<3.9 16.6 18.1 22.7 3.9::;;E<4.1 16.2 17.7 22.4 4.1::;; E < 4.3 15.9 17.4 4.3::;; E < 4.5 15.7 17.1 4.5::;; E < 4.7 15.4 16.8 22.7 4.7::;; E < 4.9 15.2 16.6 22.5

E~4.9 15.0

Initial Assembly Avg. Enrichment CE B&W

wt% 235U E 14x14 15x15 16x16 17x17 2.1::;; E < 2.3 If~~ ~ 2.3::;; E < 2.5 l :'.~~ 2.5::;; E < 2.7 I< \\

~ ,.,W 2. 7 ::;; E,,~2?9~ '

29->;~1'' '<~ .~~ . ',~'' 6~

3. ,;,M < 3.~\,,i ~ 20.2 24.9 26.7 22.3 25.8 25.8

'?· /';;,;;::"'•'

"'"3.3 :S;{~<i3~ 19.9 24.6 26.3 22.0 25.5 25.5 ,;;, ; ~) ~ :;;_'':'l' (Y-3~6!-f E <(~ 17.9 19.5 24.2 26.0 21.6 25.2 25.2

jJJJ 17.6 19.1 23.9 25.7 21.3 24.9 24.8 3 ~ E < 3. :~-30~f::;; E < 4.1 17.3 18.8 23.6 25.4 20.9 24.6 24.6 '':-:, t#'

'·1/>.li .. 1 ::;; E < 4.3 16.9 18.4 23.3 25.1 20.6 24.4 24.3 ''''"' 24.1 24.0 ti~~~ E < 4.5 16.6 18.1 23.0 24.9 20.4 4.~E<4.7 16.3 17.9 22.8 24.6 20.0 23.8 23.8 4.7::;; E < 4.9 16.1 17.6 22.5 24.4 19.9 23.6 23.6

E~4.9 15.8 17.4 22.3 24.2 19.7 23.4 23.3

Certificate of Compliance No. 1031 82-75 Amendment No. 7

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Table 82-22 Loading Table for PWR Fuel - 760 W/Assembly (continued)

58 <Assembly Average Burn up :::; 59 GWd/MTU Initial Assembly 1-------M~i_ni_m_um_C_oo_l_in""----Ti~m_e--"'-e_ar~s.__ ___ _ Avg. Enrichment CE WE WE B&W CE WE

wt% 235U E 14x14 14x14 15x15 15x15 16x16 17x17 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 2.7 ~ E < 2.9 2.9~E<3.1

3.1~E<3.3

3.3 ~ E < 3.5 3.5 ~ E < 3.7 3.7 ~ E < 3.9 3.9 ~ E < 4.1 4.1~E<4.3

4.3 ~ E < 4.5 4.5 ~ E < 4.7 4.7 ~ E < 4.9

E ;::4.9

19.8 19.3 18.9 18.6 18.2 17.9 17.6 17.3 17.1 16.8

21.3 20.9 20.5 20.2 19.8 19.5 19.2 18.9 18.7

22.0 21.5 21.2 20.8 20.5 20.2 20.0 19.7 19.5

25.9 25.6 25.3 24.9 24.6 24.3

26.7 26.4 26.0 25.7 25.4 25.2 24.9 24.7 24.4

15x15

28.4 28.1 27.8 27.6 27.3 27.1 26.8 26.6 26.4

16x16

24.1 23.7 23.4 23.1 22.7 22.5 22.2 22.0 21.7

WE 17x17

27.2 26.8 26.5 26.2 26.0 25.7 25.5 25.2 25.0

B&W 17x17

24.7 24.4

B&W 17x17

27.1 26.7 26.5 26.2 25.9 25.6 25.4 25.2 24.9

Certificate of Compliance No. 1031 82-76 Amendment No. 7

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Table 82-23 Loading Table for 8WR Fuel - 379 W/Assembly

30 <Assembly Average Burn up::;; 32.5 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt% 235LJ E 2.1 ::; E < 2.3 2.3::; E < 2.5 2.5::; E < 2.7 2.7::; E < 2.9 2.9::; E < 3.1 3.1 ::; E < 3.3 3.3::; E < 3.5 3.5::; E < 3.7 3.7::; E < 3.9 3.9 ::; E < 4.1 4.1 ::; E < 4.3 4.3 ::; E < 4.5 4.5::; E < 4.7 4.7::; E < 4.9

E~4.9

Initial Assembly Avg. Enrichment

7x7 4.3 4.2 4.2 4.1 4.1 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0

BWR/2-3

~'.'' 4.3 ':1:';1~,,3 ~07.

4.2 4.2 4.2 4.1 4.1 4.1

7x7 4.6 4.6 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1

Certificate of Compliance No. 1031

8x8 9x9 9x9 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0

BWR/4-6 9x9 9x9 10x10

4.9 4.0 4.9 4.8 4.8 4.0 4.8 4.7 4.8 4.0 4.7 4.6 4.7 4.0 4.7 4.6 4.7 4.0 4.6 4.5 4.6 4.0 4.6 4.5 4.6 4.0 4.5 4.5 4.5 4.0 4.5 4.4 4.5 4.0 4.5 4.4 4.5 4.0 4.4 4.3 4.4 4.0 4.4 4.3 4.4 4.0 4.4 4.3 4.4 4.0 4.3 4.2 4.3 4.0 4.3 4.2

82-77 Amendment No. 7

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Table 82-23 Loading Table for BWR Fuel - 379 W/Assembly (continued)

35 <Assembly Average Burnup::;; 37 .5 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2·3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt% 235U E 7x7 7x7 8x8 8x8 9x9 9x9 10x10

2.1 s E < 2.3 2.3 s E < 2.5 5.2 5.6 4.7 5.4 2.5 s E < 2.7 5.1 5.5 4.7 2.7 s E < 2.9 5.0 5.4 4.6 2.9 s E < 3.1 4.9 5.4 4.5 3.1 sE<3.3 4.9 5.3 4.5 3.3 s E < 3.5 4.8 5.2 4.4 3.5 s E < 3.7 4.8 5.1 4.4 3.7 s E < 3.9 4.7 5.1 4.3 3.9 s E < 4.1 4.6 5.0 4.3 4.1sE<4.3 4.6 5.0 4.3 4.7 4.3 s E < 4.5 4.6 4.9 4.2 4.7 4.5 s E < 4.7 4.5 4.9 4. 4.7 4.6 4.7 s E < 4.9 4.5 4.9 4.7 4.6

E~4.9 4.5 4.9 4.7 4.6

Initial Assembly Avg. Enrichment BWR/2-3 BWR/4-6 BWR/4-6

wt%235U E 7x7 8x8 9x9 9x9 10x10

2.1sE<2.3 2.3 s E < 2.5

5.2 5.9 4.7 5.9 5.7 5.1 5.8 4.6 5.8 5.7 5.0 5.8 4.6 5.7 5.6 4.9 5.7 4.5 5.6 5.5 4.9 5.6 4.4 5.6 5.4 4.8 5.6 4.4 5.5 5.4 4.7 5.5 4.3 5.4 5.3 4.7 5.4 4.3 5.4 5.2

5.1 4.6 5.4 4.3 5.3 5.2 5.0 5.5 4.6 5.3 4.2 5.3 5.1

4.5 s E < 4.7 5.0 5.5 4.5 5.3 4.2 5.2 5.0 4.7 s E < 4.9 5.0 5.4 4.5 5.2 4.1 5.2 5.0

E ~4.9 4.9 5.4 4.5 5.2 4.1 5.1 5.0

Certificate of Compliance No. 1031 82-78 Amendment No. 7

Page 132: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-23 Loading Table for 8WR Fuel - 379 W/Assembly (continued)

40 <Assembly Average Burnup~ 41 GWd/MTU Initial Assembly f-------~--~M_i_ni_m_um~C_oo_li____cn,._T_i~m_e->L..._ea_rs__,___, ___ ~--Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt% 235LJ E 7x7 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 2.7 ~ E < 2.9 2.9 ~ E < 3.1 3.1~E<3.3

3.3 ~ E < 3.5 3.5 ~ E < 3.7 3.7 ~ E < 3.9 3.9 ~ E < 4.1 4.1~E<4.3

4.3 ~ E < 4.5 4.5 ~ E < 4.7 4.7 ~ E < 4.9

E~4.9

6.0 5.9 5.8 5.7 5.6 5.5 5.5 5.4 5.3 5.3 5.2 5.2 5.1

7x7 8x8 8x8

6.5 5.4 6.2 6.4 5.3 6.1 6.2 5.2 6.0 6.1 5.1 5.9 6.0 5.0 5.9

9x9

4.9 4.8

9x9

6.0 5.0 5.8 5.7 5.9 4.9 5.~~r~ ·. , 51~" 5.9 4.9 ~r 4.~'., ~$6· 5.8 4.8 ~6 ~4~ "'; ~5.5 5.8 4.8 < 1;,,,, 5~6~ ~4.~:~ 5.5

g ~r~~~ .. <~~r ;:: 5.6 Lt. 5:~\i 4:2 5.4

10x10

BWR/4-6 10x10

6.2 6.1 6.0 5.9 5.9 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.4

Certificate of Compliance No. 1031 82-79 Amendment No. 7

Page 133: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-23 Loading Table for 8WR Fuel - 379 W/Assembly (continued)

42 < Assembly Average Burnup ~ 43 GWd/MTU Initial Assembly 1------,-----,-=M=in=im'-'-'u=mc::...C.::....:o:....:o=lin:..:..si.._T:...:.:imc;.::.e.::.....lL.::....:ea=rs::..L..., ___ ~---Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt% 235LJ E 7x7

2.1sE<2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9 2.9 s E < 3.1 3.1sE<3.3 3.3 s E < 3.5 3.5 s E < 3.7 3.7 s E < 3.9 3.9 s E < 4.1 4.1 sE<4.3 4.3 s E < 4.5 4.5 s E < 4.7

6.6 6.5 6.4 6.3 6.1 6.0 6.0 5.9 5.8 5.8 5.7

7x7 8x8 8x8 9x9

7.1 5.9 6.8 7.0 5.8 6.7 6.9 5.7 6.6 6.8 5.6 6.5 6.7 5.5 6.4 6.6 5.4 6.3

~:~ ;:~ ~~) 4.~ r},.

6.3 5.2 6:0 ~~~ll, 6.3 5.1 <;·,j:. ~~V4.~t.' 6 2 5 ~~. ·.· 0~ tl;~n6"'0 . 4 a,., . ,1··· ~· ~l;ly

9x9

5.9 5.9 4.7 s E < 4.9

E 2': 4.9 5.7 5.6

6.1 5f.·lf 5~~:~·~·· .. ' < ilfl~*'~ t;~A . Ci~, •

6.1 5@\ 5.9 'Wl 4.5 5.8 43 ~1'.'A~bly~h\x:rage 13.tl,nup ~ 44 GWd/MTU

Initial Assembly /p M(n\m~~E__::qojjf Time ears Avg. Enrichment BWR/2-3 BV\/Rf\{ JY9·Rf2·3 BWR/4-6 BWR/2-3 BWR/4-6

wt% 235LJ E 7x7 ,.. .. ,,.:::,.,,,7~x7 ~'!;, '7 8x8 8x8 9x9 9x9 2 1 < E < 2 3 - /[,;.~"f'J>~·-~:t:;, "' 2.3 ~ E < 2.5 . -~.:··.···:· - ,,~ 2:5 ~ E < 2:7 7.0t 7.6 ~::11 7.2 5.5 7.1 2.7 s E < 2.9(:11~6:8 '~ .. 7.4 J~+I 7.0 5.4 6.9 2.9 s E <-1~'>Y'~~f ~:'Jfil 5 9 6 9 5 3 6 8 <f:,:;ft_ A"'I . . . .

~:~~~~~~~~"rrr:1~~·~]~ i:6 ;:~ ~:~ ;:~ ~:~ .t:~~,~· 'I:' « ~ ~ )~ ~ ~:~ ;:~ ~:~ ;:~ ~:; 3~9~~t~4.1 6.2 6.7 5.5 6.4 4.9 6.4

~;/'!:<1,''.''"if"

4.1 ~~~~4.3 6.1 6.7 5.5 6.4 4.9 6.3 4.3 s E~~l~ 6.0 6.6 5.4 6.3 4.8 6.2 4.5 s E < 4.7 5.9 6.5 5.3 6.2 4.8 6.1 4.7 s E < 4.9 5.9 6.5 5.3 6.2 4.7 6.1

E 2': 4.9 5.8 6.4 5.2 6.1 4.7 6.0

10x10

5.9 5.8 5.8 5.7 5.7 5.6

BWR/4-6 10x10

6.9 6.7 6.6 6.5 6.4 6.3 6.2 6.1 6.0 6.0 5.9 5.9 5.9

Certificate of Compliance No. 1031 82-80 Amendment No. 7

Page 134: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-23 Loading Table for 8WR Fuel - 379 W/Assembly (continued)

44 < Assembly Average Burnup::;; 45 GWd/MTU Initial Assembly f-------.--------r--'-M-'-in'-'-im_u_m_,C_o_o_li__,n .._T_im:..---:-e -'L...:....ea=r-"-'s -,.--------r--­

Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6 wt% 235LJ E 7x7 7x7 8x8 8x8 9x9 9x9 10x10 2.1~E<2.3

2.3 ~ E < 2.5 2.5 ~ E < 2.7 2.7 ~ E < 2.9 2.9 ~ E < 3.1 3.1~E<3.3

3.3 ~ E < 3.5 3.5 ~ E < 3.7 3.7 ~ E < 3.9 3.9 ~ E < 4.1 4.1~E<4.3

4.3 ~ E < 4.5 4.5 ~ E < 4.7 4.7 ~ E < 4.9

E 24.9

7.2 7.0 6.9 6.8 6.7 6.6 6.5 6.4 6.3 6.3 6.2 6.1

7.9 7.7 7.6 7.4 7.3 7.2 7.1 7.0 6.9 6.8 6.8 6.7

Certificate of Compliance No. 1031

6.3 6.2 6.1 6.0 5.9 5.8

82-81

5:6 ~~1 5.5.:11 ·~2 ~~l 5.~ ?/3~d'.) ~;8 Al'f;?' ''Iii l~ :~ 6 ·',,, :~~6.7

6.6 6.5 6.4 6.3 6.3 6.2 6.1 6.1

Amendment No. 7

Page 135: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Note: For fuel assembly average burnup greater than 45 GWd/MTU, cool time tables have been revised to account for a 5% margin in heat load.

Table 82-24 Loading Table for 8WR Fuel - 360 W/Assembly

45 < Assembly Average Burnup ~ 46 GWd/MTU Initial Assembly r------.-----.--M_i_ni_m_u_m,...C_o_o_lin_,,,_T_im..--e ..lL_ea_r_,s '-,-------.--­Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/2-3

wt% 23su E 2.1:::; E < 2.3 2.3:::; E < 2.5 2.5:::; E < 2.7 2.7:::; E < 2.9 2.9:s;E<3.1 3.1:::; E < 3.3 3.3:::; E < 3.5 3.5:::; E < 3.7 3.7:::; E < 3.9 3.9:::; E < 4.1 4.1:::; E < 4.3 4.3:::; E < 4.5 4.5:::; E < 4.7 4.7:::; E < 4.9

E~4.9

7x7

8.5 8.3 8.1 8.0 7.9 7.7 7.6 7.5 7.4 7.3 7.2 7.1

7x7

9.3 9.0 8.9 8.8 8.6 8.4 8.3 8.2 8.1 8.0

Certificate of Compliance No. 1031

8x8

7.3 7.1 7.0 6.8 6.7

82-82

8x8 9x9

5.6 5.5 5.4

7.4 7.4 7.3

BWR/4-6

7.2 7.1 7.0 7.0

Amendment No. 7

Page 136: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-24 Loading Table for BWR Fuel - 360 W/Assembly (continued)

46 <Assembly Average Burn up:::; 47 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt% 23su E 7x7 7x7 8x8 8x8 9x9 9x9 10x10 2.1 :::; E < 2.3 2.3:::; E < 2.5 2.5:::; E < 2.7 2.7:::; E < 2.9 9.1 10.0 7.7 9.3 2.9:::; E < 3.1 8.9 9.8 7.5 9.1 3.1 :::; E < 3.3 8.7 9.5 7.4 8.9 3.3:::; E < 3.5 8.5 9.3 7.2 8.7 3.5:::; E < 3.7 8.3 9.1 7.0 8.6 3.7:::; E < 3.9 8.2 9.0 7.0 3.9:::; E < 4.1 8.0 8.8 7.8 4.1:::; E < 4.3 7.9 8.7 7.7 4.3:::; E < 4.5 7.8 8.6 7.6 4.5:::; E < 4.7 7.7 8.5 7.5 4.7:::; E < 4.9 7.6 8.4 7.4

E~4.9 7.5 7.4

Initial Assembly Avg. Enrichment BWR/2-3 BWR/2-3 BWR/4-6 BWR/4-6

wt% 23su E 8x8 9x9 9x9 10x10 2.1:::; E < 2.3 2.3:::; E < 2.5 2.5:::; E < 2.7

8.2 9.9 6.9 9.8 9.3 8.0 9.7 6.8 9.5 9.1 7.8 9.5 6.7 9.3 8.9 7.7 9.3 6.6 9.2 8.7 7.5 9.1 6.5 9.0 8.5 7.4 8.9 6.3 8.8 8.4 7.2 8.8 6.2 8.7 8.2 7.1 8.7 6.1 8.6 8.1 7.0 8.6 6.0 8.4 8.0 6.9 8.5 6.0 8.3 7.9 6.9 8.3 5.9 8.2 7.8

7.9 6.8 8.2 5.9 8.1 7.8

Certificate of Compliance No. 1031 82-83 Amendment No. 7

Page 137: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-24 Loading Table for 8WR Fuel - 360 W/Assembly (continued)

48 <Assembly Average Burn up::; 49 GWd/MTU Initial Assembly 1-------.--------.--M_in_im_u_m__,C_o_o_lin__,,._T_im...----e ......___ea_rs--L.......,c-----.----­Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2·3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt% 23su E 7x7 2.1 sE<2.3 2.3::::; E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9 2.9 s E < 3.1 3.1 s E < 3.3 3.3 s E < 3.5 3.5 s E < 3.7 3.7 s E < 3.9 3.9 s E < 4.1 4.1 sE<4.3 4.3 s E < 4.5 4.5 s E < 4.7 4.7 s E < 4.9

E:?: 4.9

10.5 10.2 10.0 9.7 9.5 9.3 9.1 9.0 8.8 8.7 8.6 8.5

7x7 8x8 8x8 9x9 9x9

11.6 8.7 10.8 11.3 8.5 10.4 11.0 8.3 10.1 10.7 8.1 9.9 10.5 7.9 9.7 10.3 7.8 10.1 7.7 9.9 7.5

9.7 7.4 ~~ 9.6 7ir~~9 9.5 ~!~ 8.~ 9.3 7~\ 8.8 )i\ 6.1 8.6

4~~~.b)y~~~a·g··· ~""~~1?up::; 50 GWd/MTU Initial Assembly ~"!Y Mln'1,mum::.€.:_qq~n Time ears Avg. Enrichment BWR/2-3 BWRl:4~ ~~Rl2·3 BWR/4-6 BWR/2-3 BWR/4-6

wt% 235U E 7x7 .. ~z...x~\1\F'!/ 8x8 8x8 9x9 9x9 2.1 s E < 2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9/ 2.9 s E <.a~Y 3.1 sE~~9. 3 3, <"!§"~ 3 ~ ' -;'.';.,-, -<j'!,,'~ I

4Py~~7 3'·7. < E · · 9 ' ~'.~- ~-f?. fg'A'.,, ;:0tc'.} 4.1

4.1 ::::;~ . 4.3 4.3 s E~~'.?5 4.5 s E < 4.7 4.7 s E < 4.9

E :?:4.9

~-' to ,j''J :0:r:~ .J~

~~~ 9.7 9.6 9.4 9.3 9.1 9.0

9.0 11.2 7.6 11.0 11.7 8.8 10.9 7.4 10.7 11.5 8.6 10.7 7.2 10.4 11.3 8.4 10.4 7.0 10.2 11.0 8.2 10.2 7.0 10.0 10.8 8.0 10.0 6.8 9.8 10.6 7.9 9.8 6.7 9.7 10.4 7.8 9.7 6.7 9.5 10.2 7.7 9.5 6.6 9.4 10.1 7.6 9.4 6.5 9.2 10.0 7.5 9.3 6.4 9.1

10x10

8.7 8.6 8.5 8.4 8.3 8.2

BWR/4-6 10x10

10.3 10.1 9.8 9.7 9.5 9.3 9.1 9.0 8.9 8.7 8.6

Certificate of Compliance No. 1031 82-84 Amendment No. 7

Page 138: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-24 Loading Table for 8WR Fuel - 360 W/Assembly (continued)

50 < Assembly Average Burnup ~ 51 GWd/MTU Initial Assembly 1--------.------.----:M=i=ni=m=um:..:..:..,..:.C-=-oo=li=n""---"-"Ti:.:..;.:m=-=-e~ea=r=s ~--~--­Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt% 23su E 7x7 2.1:::; E < 2.3 2.3:::; E < 2.5 2.5:::; E < 2.7 2.7:::; E < 2.9 2.9 :::; E < 3.1 11.8 3.1 :::; E < 3.3 11.5 3.3 :::; E < 3.5 11.2 3.5:::; E < 3.7 10.9 3.7:::; E < 3.9 10.7 3.9:::; E < 4.1 10.4 4.1 :::; E < 4.3 10.3 4.3 :::; E < 4.5 10.0 4.5:::; E < 4.7 9.9 4.7:::; E < 4.9 9.8

E 2 4.9 9.6

7x7 8x8 8x8 9x9 9x9

12.9 9.6 8.0 12.6 9.4 12.3 9.1 11.9 8.9 11.8 8.7 11.6 8.6 11.3 8.4 11.2 8.3 11.0 8.1 10.9 8.0 iO.O 9.8 10.7 7{~\ :~ 9.7

10x10

11.1 .9

:~6 'S''.3

10.0 9.9 9.7 9.6 9.4 9.3 9.1

BWR/4-6 10x10

51 < Asse~'~ly Averag~ B~~~up ~ 52 GWd/MTU Initial Assembly 1--------.---~~~:,,:,~1L~M~.J,.,_m--"'n)~uJ~.llC-'-oo=h_n~~¥-W1:.:..;.:m-=-e-"'( =ea=r-"..!s)~--~---Avg. Enrichment BWR/2-3 BWR/4~6"'" BWR/2~· .~ !5 BWR/2-3 BWR/4-6

wt% 235LJ E 7x7 'fflt( A~B 8x8 9x9 9x9

2.1:::; E < 2.3 2.3:::; E < 2.5 2.5:::; E < 2.7 2.7:::; E < 2.9 2.9 :::; E < 3.1A!! :tJ:' 3.1 ::;E<31:e? 3.3:::; E ~~~ 3.5~-tft~

E\:~9 ~;/~1.5 ~~~ 9 :::; E .< .. ,l1:·~'1 ~~~~'>2

°"1' ,,f~ ·~ 4. \~·t:i.3 11.0 4.3 ~~IE'\< 4.5 10.8 45< E~7 10 6 . - ~\~ . 4.7 :::; E < 4.9 10.5

E 2 4.9 10.2

13.2 12.9 12.6 12.4 12.1 11.8 11.7 11.6 11.4

Certificate of Compliance No. 1031

10.3 12.9 8.4 12.6 11.9 10.0 12.5 8.2 12.3 11.6 9.8 12.1 8.0 11.9 11.3 9.5 11.9 7.9 11.7 11.0 9.3 11.7 7.7 11.4 10.8 9.1 11.5 7.6 11.3 10.5 8.9 11.3 7.4 11.0 10.3 8.8 11.1 7.3 10.9 10.2 8.7 10.9 7.2 10.7 10.0 8.5 10.7 7.1 10.5 9.9 8.4 10.6 7.0 10.4 9.8

82-85 Amendment No. 7

Page 139: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-24 Loading Table for BWR Fuel - 360 W/Assembly (continued)

52 <Assembly Average Burnup ~ 53 GWd/MTU Initial Assembly f------.------.--M_i_ni_m_u_m.-C_oo_l_in,,.__Ti-.-m_e........__e_ar_,s '--,------,---­Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt% 235U E 7x7 2.1 s E < 2.3 2.3 s E < 2.5 2.5 s E < 2.7 2.7 s E < 2.9 2.9 s E < 3.1 3.1sE<3.3 3.3 s E < 3.5 3.5 s E < 3.7 3.7 s E < 3.9 3.9 s E < 4.1 4.1sE<4.3 4.3 s E < 4.5 4.5 s E < 4.7 4.7 s E < 4.9

E~4.9

13.6 13.2 12.8 12.6 12.2 11.9 11.7 11.6 11.4 11.2 11.0

7x7

14.8 14.5 14.1 13.8 13.5 13.2 13.0 12.7 12.5 12.4

8x8 8x8 9x9 9x9 10x10

53 4fA~f y~~~rag~jijt~up ~ 54 GWd/MTU Initial Assembly A7 MlotmumtQ:Q:Q!!D Time ears Avg. Enrichment BWR/2-3 BWRl~t jW:RI2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt%235U E 7x7 1~zx1 '~·;;•f'Sxs 8x8 9x9 9x9 10x10

2.1 s E < 2.3 - .(!-("·. ~~ -2.3 s E < 2.5 -~Ill!· - ~

4~,,

2.5 s E < 2.7 - · - '·

2.7 s E <.·.··.·.2 ... 9~:~·:···.·.,\.... :~ _ - 4iJ 2.9 s E ~~~7 1~15 ~1.5tf'1 3.1 .. s E < .. :::.:.~~.~ A.:e.-.. · .. ~· .. ,,,~:~1~¥ 15.4 3.3~ ~3.5,~~~·~ 15.1

(~ ~ ~~ ~~ :::~ 3~~" t,4.1 12.9 14.1 4.1 - ·i ~.3 12.6 13.9 4.3 s E~~;s 12.4 13.6 4.5sE<4.7 12.1 13.4 4.7sE<4.9 11.9 13.2

E~4.9 11.7 13.1

Certificate of Compliance No. 1031

11.8 11.4 11.1 10.9 10.6 10.4 10.1 9.9 9.7 9.6 9.4

82-86

14.6 14.3 13.9 13.6 13.3 13.1 12.8 12.6 12.3 12.2 12.0

9.5 9.2 8.9 8.7 8.6 8.4 8.2 8.1 7.9 7.9 7.8

14.4 14.0 13.6 13.4 13.1 12.8 12.5 12.3 12.1 11.9 11.7

13.6 13.2 12.8 12.6 12.2 12.0 11.8 11.6 11.4 11.2 11.1

Amendment No. 7

Page 140: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-24 Loading Table for 8WR Fuel - 360 W/Assembly (continued)

54 < Assembly Average Burnup::;; 55 GWd/MTU Initial Assembly Minimum Coolin Time ears Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt% 23su E 2.1 ::;; E < 2.3 2.3::;; E < 2.5 2.5::;; E < 2.7 2.7 ~ E < 2.9 2.9 ~ E < 3.1 3.1~E<3.3

3.3 ~ E < 3.5 3.5 ~ E < 3.7 3.7 ~ E < 3.9 3.9 ~ E < 4.1 4.1~E<4.3

4.3 ~ E < 4.5 4.5 ~ E < 4.7 4.7 ~ E < 4.9

E 2:: 4.9

4.7 ~ E < 4.9 E 2:: 4.9

7x7

15.0 14.7 14.3 13.9 13.6 13.3 13.1 12.9 12.8 12.5

7x7

16.4 16.0 15.7 15.4 15.1 14.7 14.5 14.3 14.1

15.7 15.4 15.2 15.0 14.8

Certificate of Compliance No. 1031

8x8

13.1 12.7 12.3 12.0 11.8 11.5 11.3 11.1 10.9 10.7

82-87

8x8 9x9 9x9 10x10

16.2 10.4 15.9 15.0 15.8 10.1 15.5 14.6 15.5 9.9 15.2 14.3 15.1 9.7 14.8 13.9 14.9 9.4 14.6 13.6 14.5 9.2 14.3 13.4 14.3 9.0 14.0 13.1 14.1 8.8 13.8 12.9 13.9 8.7 13.7 12.8 13.7 8.6 13.4 12.5

Amendment No. 7

Page 141: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-24 Loading Table for 8WR Fuel - 360 W/Assembly (continued)

56 <Assembly Average Burnup::;; 57 GWd/MTU Initial Assembly f-------r------,-=M=in=im=u=m-'-rC.::...co:....::.o=lin~T:..:.:imc;..:.e"---'L.:....:ea=rs:L__, ___ ~---Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt% 235LJ E 7x7 7x7 8x8 2.1:::; E < 2.3 2.3:::; E < 2.5 2.5:::; E < 2.7 2.7:::; E < 2.9 2.9:::; E < 3.1 3.1 :::; E < 3.3 16.8 3.3:::; E < 3.5 16.5 3.5:::; E < 3.7 16.0 3.7:::; E < 3.9 15.7 3.9:::; E < 4.1 15.4 4.1:::; E < 4.3 15.1 4.3:::; E < 4.5 14.8 4.5:::; E < 4.7 14.6 4.7:::; E < 4.9 14.3

E~4.9 14.0

14.8 14.4 14.0 13.6 13.3 13.1 12.8

17.1 12.5 4.7:::; E < 4.9 16.9 12.3

E ~4.9 16.7 12.1

Certificate of Compliance No. 1031 82-88

8x8 9x9

18.2 11.8 17.7 11.5 17.4 11.2 17.0 10.9 16.7 10.6 16.3 10.3 16.1 10.1 15.9 9.9 15.6 9.8 15.4 9.6

9x9

17.8 17.5

. 17.1 16.8 16.4 16.1 15.8 15.5 15.3 15.1

10x10

BWR/4-6 10x10

16.8 16.5 16.1 15.7 15.4 15.1 14.8 14.6 14.4 14.2

Amendment No. 7

Page 142: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-24 Loading Table for 8WR Fuel - 360 W/Assembly (continued)

58 < Assembly Average Burnup::;: 59 GWd/MTU Initial Assembly >----~--~_..:..::..:M=in=im=u=m;:.....cC=--=o'-'-o=lin-'.SL-.C.T_,_im:..::....:e~e:...::.:.a::....::rsL-r------,---­Avg. Enrichment BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt % 235U E 7x7 2.1 s E < 2.3 2.3 s E < 2.5

7x7 8x8 8x8 9x9 9x9 10x10

. . 5J~e1T~1~1~er~g~'-lfr~up::;: 60 GWd/MTU Initial Assembly .(Jf!' IVJ1mmarrl1!§q,~m Time ears Avg. Enrichment BWR/2-3 BV'liRl~i'.~ R§~Rt2-3 BWR/4-6 BWR/2-3 BWR/4-6 BWR/4-6

wt%235U E 7x7 .~7x~\l',17sxa 8x8 9x9 9x9 10x10

;:~~~:;~ r-\ ~ 2.5 s E < 2. 7 "'~\ - 1' -2.7sE<3:9~.,\·1' .. -~JJJ -2.9sE,r3r1 '\.. ~ -

~v"f J~:~ 3.1 s E ~~"0 ·.·. ~ -~·.~'"~~3·''. ; 19.3. 21.0 16.0 19.7 12.9 19.5 18.4

.4?5 s E ~:~.7 J,8.9 20.7 15.6 19.3 12.7 19.1 17.9 ~~{ s /~3.9 18.6 20.3 15.2 19.0 12.3 18.7 17.7

3'!Bj~·f <4.1 18.2 19.9 14.9 18.7 11.9 18.3 17.3 4.1~~4.3 17.9 19.7 14.5 18.3 11.6 17.9 17.0 4.3 s ~t4.5 17.6 19.4 14.2 18.1 11.4 17.7 16.6 4.5sE<4.7 17.3 19.1 14.0 17.7 11.2 17.5 16.4 4.7 s E < 4.9 17.1 18.8 13.8 17.6 11.0 17.2 16.1

E 2 4.9 16.9 18.6 13.6 17.3 10.8 16.9 15.9

Certificate of Compliance No. 1031 82-89 Amendment No. 7

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Table 82-25 Loading Table for PWR Fuel - 959 W/Assembly-WE 14x14 Fuel

Initial Assembly B GWd/MTU

Avg. Enrichment B S10 25< B 30< B wt 323su E S15 S20 S25 S30 S32.5 1.3 :::; E < 1.5 2.5 1.5 :::; E < 1.7 2.5 2.5 1.7$E<1.9 2.5 2.5 2.9 1.9 :::; E < 2.1 2.5 2.5 2.9 2.1 :::; E < 2.3 2.5 2.5 2.8 2.3:::; E < 2.5 2.5 2.5 2.8 2.5 :::; E < 2.7 2.5 2.5 2.8 2.7 :::; E < 2.9 2.5 2.5 2.8 2.9 :::; E < 3.1 2.5 2.5 2.7 3.1 :::; E < 3.3 2.5 2.5 2.7 3.3 :::; E < 3.5 2.5 2.5 2.7 3.5 :::; E < 3.7 2.5 2.5 3.6 3.8 3.7 :::;E<3.9 2.5 2.5 3.6 3.8 3.9 :::;E<4.1 2.5 3.6 3.8 4.1 :::; E < 4.3 2.5 3.1 3.5 3.8 4.3 :::; E < 4.5 2.5 3.0 3.5 3.7 4.5 :::; E < 4.7 3.0 3.5 3.7 4.7 :::; E < 4.9 2.6 3.0 3.5 3.7

E ;:::4,9 2.6 3.0 3.5 3.7

Certificate of Compliance No. 1031 82-90 Amendment No. 7

Page 144: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-25 Loading Table for PWR Fuel - 959 W/Assembly-WE 14x14 Fuel (Continued)

Initial Assembly Avg. Enrichment 41< B 42< B

wt 323su (E) :S35 :S37.5 :S40 :S41 :S42 :S43 1.3 ::; E < 1.5 1.5 :s;E<1.7 1.7 :s;E<1.9 1.9 ::; E < 2.1 2.1 ::; E < 2.3 2.3 ::; E < 2.5 4.4 4.8 2.5 ::; E < 2.7 4.4 4.7 5.8 2.7 ::; E < 2.9 4.3 4.7 5.7 2.9 ::; E < 3.1 4.3 4.6 5.6 3.1 ::; E < 3.3 4.2 4.5 5.6 3.3 ::; E < 3.5 4.2 4.5 5.3 5.5 3.5 ::; E < 3.7 4.1 5.2 5.4 3.7 ::; E < 3.9 4.1 4.9 5.1 5.3 3.9 ::; E < 4.1 4.1 4.9 5.1 5.3 4.1 :s;E<4.3 4.0 4.9 5.0 5.2 4.3 ::; E < 4.5 4.7 4.8 5.0 5.2 4.5 ::; E < 4.7 4.6 4.8 4.9 5.1 4.7 ::; E < 4.9 4.6 4.7 4.9 5.0

E <::4.9 4.5 4.7 4.9 5.0

Certificate of Compliance No. 1031 82-91 Amendment No. 7

Page 145: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-25 Loading Table for PWR Fuel - 959 W/Assembly-WE 14x14 Fuel (Continued)

WE 14x14 Assembly Average Burnup (8)

Initial Assembly ,_ __ G_W_d~/M_T_U __ _ Avg. Enrichment 43< B 44< B

wt % 235U (E S44

1.3 ::;; E < 1.5 1.5 ::;; E < 1.7 1.7::;;E<1.9 1.9 ::;; E < 2.1 2.1 ::;; E < 2.3 2.3 ::;; E < 2.5 2.5 ::;; E < 2.7 6.0 2.7 ::;; E < 2.9 2.9 ::;;E<3.1 3.1 ::;; E < 3.3

5.7 5.4 5.6 5.4 5.6 5.3 5.5 5.3 5.5 5.2 5.4

a Cool times for burnup over 45 GWd/MTU are in Table B2-16

Certificate of Compliance No. 1031 82-92 Amendment No. 7

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Table 82-26 Loading Table for PWR Fuel - 513 W/Assembly-WE 14x14 Fuel

Initial Assembly B GWd/MTU

Avg. Enrichment B :S10 25< B 30< B wt %235U E :S15 :S20 :S25 :S30 :S32.5 1.3 ::; E < 1.5 2.9 1.5 ::; E < 1.7 2.9 3.8 1.7 ::; E < 1.9 2.9 3.7 4.5 1.9 ::; E < 2.1 2.9 3.7 4.5 5.7 2.1 ::; E < 2.3 2.8 3.7 4.5 5.7 2.3 ::; E < 2.5 2.8 3.6 4.4 5.6 2.5 ::; E < 2.7 2.8 3.6 4.4 2.7 ::; E < 2.9 2.8 3.6 4.4 2.9 ::; E < 3.1 2.8 3.5 4.4 3.1 ::; E < 3.3. 2.8 3.5 3.3 ::; E < 3.5 2.8 3.5 8.3 3.5 ::; E < 3.7 2.7 3.5 .0 8.2 3.7 ::; E < 3.9 2.7 3.5 7.0 8.1 3.9 ::; E < 4.1 2.7 6.9 8.1 4.1 ::; E < 4.3 2.7 6.9 8.0 4.3 ::; E < 4.5 2.7 6.8 8.0 4.5 ::; E < 4.7 5.2 6.8 7.9 4.7 ::; E < 4.9 5.2 6.8 7.9

E 2::4.9 5.2 6.8 7.9

Certificate of Compliance No. 1031 82-93 Amendment No. 7

Page 147: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-26 Loading Table for PWR Fuel - 513 W/Assembly-WE 14x14 Fuel

(Continued)

Initial Assembly Avg. Enrichment 41< B 42< B

wt %235U (E) S35 S37.5 S40 S41 S42 :543 1.3 :::; E < 1.5 1.5 :::; E < 1.7 1.7:5E<1.9 1.9 :::; E < 2.1 2.1 :::; E < 2.3 2.3 :::; E < 2.5 10.9 13.7 2.5 :::; E < 2.7 10.7 13.5 16.9 2.7 :::; E < 2.9 10.5 13.3 16.5 2.9 :::; E < 3.1 10.4 13.1 20.6 3.1 :::; E < 3.3 10.2 12.8 20.4 3.3 :::; E < 3.5 10.1 12.7 18.7 20.1 3.5 :::; E < 3.7 10.0 12.5 18.4 19.9 3.7 :::; E < 3.9 9.9 18.2 19.6 3.9 :::; E < 4.1 9.8 18.0 19.5 4.1 :::; E < 4.3 9.8 16.5 17.9 19.3 4.3 ::; E < 4.5 9.7 15.1 16.3 17.7 19.2 4.5 ::; E < 4.7 9/l~" 15.0 16.2 17.6 19.0 ~.r 4.7 :::; E < 4.9 @6 :. 14.9 16.1 17.5 18.8

\r1 '\':'\ E <:: 4.9 9~5 11~18 14.8 16.0 17.3 18.7

•\,~:.' \)):~>ey· ,:~

.,:-\11-,,~~i'V' ~~'·' ·':\"&w,.," · •.

Certificate of Compliance No. 1031 82-94 Amendment No. 7

Page 148: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-26 Loading Table for PWR Fuel - 513 W/Assembly-WE 14x14 Fuel

(Continued)

WE 14x14 Assembly Average Burnup (B)

Initial Assembly 1----__ G_W_d_/M_T_U __ Avg. Enrichment

wt 323su (E

1.3 ::; E < 1.5 1.5 ::; E < 1.7 1.7:5E<1.9 1.9 ::; E < 2.1 2.1 :5E<2.3 2.3 ::; E < 2.5

43< B :S44

2.5 ::; E < 2.7 22.7 2.7 ::; E < 2.9 22.3 2.9 ::; E < 3.1 3.1 ::; E < 3.3 3.3 ::; E < 3.5

Certificate of Compliance No. 1031

20.4 20.3 20.1

82-95

44< B

22.3 22.1 21.9 21.8 21.6 21.5

Amendment No. 7

Page 149: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-27 Loading Table for PWR Fuel-1300 W/Assembly-WE 14x14 Fuel

Initial Assembly B GWd/MTU

Avg. Enrichment B :S10 25< B 30< B wt %235U E :S15 :S20 :S25 :S30 :S32.5 1.3 :s;E<1.5 2.5 1.5 :s; E < 1.7 2.5 2.5 1.7 :s;E<1.9 2.5 2.5 2.5 1.9 :s; E < 2.1 2.5 2.5 2.5 2.7 2.1 :s; E < 2.3 2.5 2.5 2.5 2.6 2.3 :s; E < 2.5 2.5 2.5 2.5 2.6 2.5 :s; E < 2.7 2.5 2.5 2.5 2.7 :s; E < 2.9 2.5 2.5 2.9 :s; E < 3.1 2.5 2.5 3.1 :s; E < 3.3 2.5 2.5 3.0 3.3 :s; E < 3.5 2.5 2.5 3.0 3.5 :s; E < 3.7 2.5 3.0 3.7 :s; E < 3.9 2.5 3.0 3.9 :s; E < 4.1 2.5 2.9 4.1 :s; E < 4.3 2.5 2.9 4.3 :s; E < 4.5 2.5 2.8 2.9 4.5 :s; E < 4.7 2.5 2.5 2.7 2.9 4.7 :s; E < 4.9 2.5 2.5 2.7 2.9

E ;:::4,9 2.5 2.5 2.7 2.8

Certificate of Compliance No. 1031 82-96 Amendment No. 7

Page 150: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-27 Loading Table for PWR Fuel-1300 W/Assembly-WE 14x14 Fuel (Continued)

Initial Assembly 8 GWd/MTU

Avg. Enrichment 41< 8 42< 8 wt 323su E :S35 :S40 :S41 :S42 :S43

1.3 :::; E < 1.5 1.5 :5E<1.7 1.7 :5E<1.9 1.9 :::; E < 2.1 2.1 :::; E < 2.3 2.3 :::; E < 2.5 3.4 3.6 2.5 :::; E < 2.7 3.3 3.6 3.8 2.7 :::; E < 2.9 3.3 3.5 3.8 2.9 :::; E < 3.1 3.3 3.5 3.7 3.1 :::; E < 3.3 3.2 3.4 4.0 3.3 :::; E < 3.5 3.2 3.4 3.8 3.9 3.5 :::; E < 3.7 3.2 3.4 3.8 3.9 3.7 :5E<3.9 3.1 3.8 3.9 3.9 :::; E < 4.1 3.1 3.7 3.8 4.1 :5E<4.3 3.6 3.7 3.8 4.3 :::; E < 4.5 3.6 3.6 3.8 4.5 :::; E < 4.7 3.4 3.5 3.6 3.7 4.7:5E<4.9 3.4 3.5 3.6 3.7

E 2:4.9 3.4 3.5 3.5 3.7

Certificate of Compliance No. 1031 82-97 Amendment No. 7

Page 151: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-27 Loading Table for PWR Fuel -1300 W/Assembly-WE 14x14 Fuel (Continued)

WE 14x14 Assembly Average Burnup (B)

Initial Assembly f---__ G_W_d~/M_T_U __ _ Avg. Enrichment

wt Ofo235U E

1.3 ::;; E < 1.5 1.5:5E<1.7 1.7:5E<1.9 1.9 ::;; E < 2.1 2.1 ::;; E < 2.3 2.3 ::;; E < 2.5 2.5 ::;; E < 2.7 2.7 ::;; E < 2.9 2.9 ::;; E < 3.1 3.1 ::;; E < 3.3 3.3 ::;; E < 3.5

43< B :S44

4.3 4.2

44< B :S45

4.0 4.0

3.8 3.9 3.9 3.9 3.8 3.9 3.8 3.8

Certificate of Compliance No. 1031 82-98 Amendment No. 7

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Table 82-28 Loading Table for PWR Fuel -1800 W/Assembly-WE 14x14 Fuel

Initial Assembly 8 GWd/MTU

Avg. Enrichment 8 S10 25< 8 30< 8 wt %235U E S15 S20 S25 S30 S32.5 1.3 :::; E < 1.5 2.5 1.5 :::; E < 1.7 2.5 2.5 1.7 :::; E < 1.9 2.5 2.5 2.5 1.9 :::; E < 2.1 2.5 2.5 2.5 2.5 2.1 :5E<2.3 2.5 2.5 2.5 2.5 2.3 :::; E < 2.5 2.5 2.5 2.5 2.5 2.5 :::; E < 2.7 2.5 2.5 2.5 2.5 2.§:.: 2.7 :::; E < 2.9 2.5 2.5 2.5 2~ . 2.9 :::; E < 3.1 2.5 2.5 2.5 ~~ ~· ~'~ 3.1 :::; E < 3.3 2.5 2.5 2.5 2.5c ::·«~2.sv 2.5 3.3 :::; E < 3.5 2.5 2.5 2.5 2$,~)·2.5 2.5 3.5 :::; E < 3.7 2.5 2.5 r ~··~¥ 2.~~~-(f 2.5 2.5

'

3.7 :::; E < 3.9 2.5 2.5 .5 ·~1: 5 ' ~'' 2.5 2.5 3.9 :::; E < 4.1 2.5 5 j}o 2.5 2.5 ,;.,,, 4.1 :::; E < 4.3 2.5 ·:. 2,~ .5 2.5 2.5 4.3 :::; E < 4.5 2.5 2.5 ~~:!\.,,: .' .. :· / 2.5 2.5 2.5 4.5 :::; E < 4.7 2.5 2.5 2.5 2.5 4.7 :::; E < 4.9 2.5 2.5 2.5

E ;:::4,9 2.5 2.5 2.5

Certificate of Compliance No. 1031 82-99 Amendment No. 7

Page 153: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-28 Loading Table for PWR Fuel-1800 W/Assembly-WE 14x14 Fuel

(Continued)

Initial Assembly Avg. Enrichment 41< 8 42< 8

wt Ofo235U (E) S35 :S37.5 :S40 :S41 :S42 :S43 1.3 :::; E < 1.5 1.5 :::; E < 1.7 1.7 :::; E < 1.9 1.9 :::; E < 2.1 2.1 :::; E < 2.3 2.3 :::; E < 2.5 2.6 2.7 2.5 :::; E < 2.7 2.5 2.7 2.9 2.7 :::; E < 2.9 2.5 2.7 3.0 2.9 :::; E < 3.1 2.5 2.6 3.0 3.1 :::; E < 3.3 2.5 2.6 3.0 3.3 :::; E < 3.5 2.5 2.6 2.9 2.9 3.5 :::; E < 3.7 2.5 2.8 2.9 3.7 :::; E < 3.9 2.5 2.8 2.9 3.9 :::; E < 4.1 2.5 2.8 2.8 4.1 :::; E < 4.3 2.5 2.8 2.8 4.3 :::; E < 4.5 2.7 2.7 2.8 4.5 :::; E < 4.7 2.6 2.6 2.7 2.8 4.7 :::; E < 4.9 2.5 2.6 2.7 2.7

E;::: 4.9 2.5 2.6 2.6 2.7

Certificate of Compliance No. 1031 82-100 Amendment No. 7

Page 154: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-28 Loading Table for PWR Fuel -1800 W/Assembly-WE 14x14 Fuel

(Continued)

WE 14x14 Assembly Average Burnup (8)

Initial Assembly 1--__ G_W_d~/_M_TU __ _ Avg. Enrichment

wt %235U E

1.3 ::;; E < 1.5 1.5 ::;; E < 1.7 1.7:5E<1.9 1.9 ::;; E < 2.1 2.1 ::;; E < 2.3 2.3 ::;; E < 2.5

43< 8 :S44

44< 8 :S45

2.5 :5E<2.7 3.1 2.7 ::;; E < 2.9 2.9 ::;; E < 3.1 3.1 :5E<3.3

Certificate of Compliance No. 1031

3.0 2.9

2.8 2.9 2.9 2.9 2.8 2.9 2.8 2.8

82-101 Amendment No. 7

Page 155: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-29 Loading Table for PWR Fuel- 830 W/Assembly-WE 14x14 Fuel

Initial Assembly B GWd/MTU

Avg. Enrichment B S10 25< B 30< B wt %235U E S15 S20 S25 S30 S32.5 1.3 ::;;E<1.5 2.5 1.5 ::;; E < 1.7 2.5 2.7 1.7::;;E<1.9 2.5 2.7 3.2 1.9 ::;; E < 2.1 2.5 2.7 3.2 3.8 2.1 ::;; E < 2.3 2.5 2.6 3.1 3.7 2.3 ::;; E < 2.5 2.5 2.6 3.1 2.5 ::;; E < 2.7 2.5 2.6 3.1 2.7 ::;; E < 2.9 2.5 2.6 3.0 2.9 ::;; E < 3.1 2.5 2.5 3.0 3.1 ::;; E < 3.3 2.5 2.5 3.0 3.3 ::;; E < 3.5 2.5 2.5 3.5 ::;; E < 3.7 2.5 2.5 4.4 3.7 ::;; E < 3.9 2.5 2.5 4.4 3.9 ::;; E < 4.1 2.5 2.5 4.0 4.3 4.1 ::;;E<4.3 2.5 4.0 4.3 4.3 ::;; E < 4.5 2.5 4.0 4.3 4.5 ::;; E < 4.7 2.9 3.4 4.0 4.2 4.7 ::;; E < 4.9 2.9 3.4 3.9 4.2

E;;::: 4.9 2.9 3.4 3.9 4.2

Certificate of Compliance No. 1031 82-102 Amendment No. 7

Page 156: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-29 Loading Table for PWR Fuel - 830 W/Assembly - WE 14x14 Fuel

(Continued)

Initial Assembly Avg. Enrichment 41< B 42< B

wt %235LJ (E S35 S37.5 S40 S41 S42 S43 1.3 s; E < 1.5 1.5$E<1.7 1.7 s; E < 1.9 1.9 s;E<2.1 2.1 s; E < 2.3 2.3 s; E < 2.5 5.1 5.6 2.5 s; E < 2.7 5.0 5.6 6.1 2.7 s; E < 2.9 5.0 5.5 2.9 s; E < 3.1 4.9 5.4 3.1 s; E < 3.3 4.9 5.4 6.7 3.3 s; E < 3.5 4.8 5.3 6.3 6.6 3.5 s; E < 3.7 4.8 6.3 6.6 3.7s;E<3.9 4.7 6.2 6.5 3.9 s; E < 4.1 4.7 6.1 6.4 4.1 s;E<4.3 5.8 6.0 6.3 4.3 s; E < 4.5 5.8 6.0 6.2 4.5 s; E < 4.7 5.5 5.7 5.9 6.2 4.7 s; E < 4.9 5.5 5.7 5.9 6.1

E ~4.9 5.4 5.6 5.9 6.0

Certificate of Compliance No. 1031 82-103 Amendment No. 7

Page 157: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-29 Loading Table for PWR Fuel-830 W/Assembly-WE 14x14 Fuel

{Continued)

WE 14x14 Assembly Average Burnup (B)

Initial Assembly ~ __ G_W_d~/M_T_U __ _ Avg. Enrichment 43< B 44< B

wt % 235U E :S44 :S45

1.3 :::; E < 1.5 1.5:::;E<1.7 1.7 :::; E < 1.9 1.9 :::; E < 2.1 2.1 :::; E < 2.3 2.3 :::; E < 2.5 2.5 :::; E < 2.7 7.5 2.7 :::; E < 2.9 2.9 :::; E < 3.1 3.1 :::; E < 3.3

Certificate of Compliance No. 1031

7.0 6.9

6.6 6.8 6.5 6.8 6.4 6.7 6.4 6.7

82-104 Amendment No. 7

Page 158: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Note: For fuel assembly average burn up greater than 45 GWd/MTU, cool time tables have been revised to account for a 5% margin in heat load.

Table 82-30 Loading Table for PWR Fuel - 487 W/Assembly - WE 14x14 Fuel

Initial Assembly Avg. Enrichment 45< B

wt %235U E S46 S47 S48 1.3 :5 E < 1.5 1.5 :5 E < 1.7 1.7 :5E<1.9 1.9 :5 E < 2.1 2.1 :5 E < 2.3 2.3 :5 E < 2.5 2.5 :5 E < 2.7 2.7 :5E<2.9 27.9 29.3 2.9 :5 E < 3.1 27.6 29.0 32.7 33.9 3.1 :5 E < 3.3 27.4 32.4 33.7 3.3 :5 E < 3.5 27.1 32.2 33.6 3.5 :5 E < 3.7 26.9 32.0 33.3 3.7 :5 E < 3.9 31.8 33.1 3.9 :5 E < 4.1 30.8 31.6 32.9 4.1 :5E<4.3 30.6 31.4 33.5

30.3 31.2 32.6 28.8 30.2 31.1 32.4 28.6 30.1 30.9 32.3 28.5 30.0 30.8 32.1

Certificate of Compliance No. 1031 82-105 Amendment No. 7

Page 159: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-30 Loading Table for PWR Fuel -487 W/Assembly-WE 14x14 Fuel

(Continued)

Initial Assembly Avg. Enrichment 51< B 55< B 56< B

wt 323su E S52 S53 S54 S55 S56 S57 1.3 ::;; E < 1.5 1.5 ::;; E < 1.7 1.7:5E<1.9 1.9 ::;; E < 2.1 2.1 ::;; E < 2.3 2.3 ::;; E < 2.5 2.5 ::;; E < 2.7 2.7 :::; E < 2.9 2.9 ::;; E < 3.1 35.2 36.4 3.1 :5E<3.3 35.0 36.2 41.0 3.3 ::;; E < 3.5 34.8 36.0 40.9 3.5 ::;; E < 3.7 34.5 35.9 39.5 40.7 3.7 :::; E < 3.9 34.3 39.4 40.5 3.9 ::;; E < 4.1 34.2 39.2 40.4 4.1 :5E<4.3 34.1 39.2 40.2 4.3 ::;; E < 4.5 39.0 40.2 4.5 ::;; E < 4.7 37.6 38.8 40.0 4.7 :::; E < 4.9 37.4 38.7 39.8

E~4.9 37.3 38.6 39.7

Certificate of Compliance No. 1031 82-106 Amendment No. 7

Page 160: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-30 Loading Table for PWR Fuel - 487 W/Assembly-WE 14x14 Fuel

(Continued)

WE 14x14 Assembly Average

Initial Assembly Burnu 8 GWd/MTU

Avg. Enrichment 57< 8 58< 8 59< 8 wt Ofo235U (E) :S58 :S59 :S60 1.3 ::;; E < 1.5 1.5 ::;; E < 1.7 1.7:5E<1.9 1.9 ::;; E < 2.1 2.1 ::;; E < 2.3 2.3 ::;; E < 2.5 2.5 ::;; E < 2.7 2.7 ::;; E < 2.9 2.9 ::;; E < 3.1 3.1 ::;; E < 3.3 3.3 ::;; E < 3.5 3.5 ::;; E < 3.7

43.8 4.1 :5E"-' 43.7

42.5 43.6 42.4 43.5 42.3 43.4 42.1 43.3

Certificate of Compliance No. 1031 82-107 Amendment No. 7

Page 161: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-31 Loading Table for PWR Fuel -1235 W/Assembly-WE 14x14 Fuel

Initial Assembly B GWd/MTU

Avg. Enrichment 45< B 49< B 50< B wt %235U E S46 S47 S48 S49 S50 S51 1.3 ::;; E < 1.5 1.5:5E<1.7 1.7 :5E<1.9 1.9 :5 E < 2.1 2.1 :5E<2.3 2.3 ::;; E < 2.5 2.5 :5 E < 2.7 2.7 :5 E < 2.9 4.7 4.9 5.0 2.9 :5 E < 3.1 4.6 4.8 4.9 3.1 :5 E < 3.3 4.6 4.7 5.3 3.3 :5 E < 3.5 4.5 4.6 5.2 3.5 :5 E < 3.7 4.5 4.6 5.2 3.7 :5 E < 3.9 4.4 4.5 5.1 3.9 :5 E < 4.1 4.4 4.9 5.0 4.1 :5 E < 4.3 4.3 4.8 4.9 4.3 :5 E < 4.5 4.3 4.8 4.9 4.5 :5 E < 4.7 4.6 4.7 4.8 4.7 :5 E < 4.9 4.6 4.7 4.8

E <::4.9 4.5 4.6 4.7

Certificate of Compliance No. 1031 82-108 Amendment No. 7

Page 162: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-31 Loading Table for PWR Fuel -1235 W/Assembly-WE 14x14 Fuel

(Continued)

Initial Assembly 8 GWd/MTU

Avg. Enrichment 51< 8 55< 8 56< 8 wt %235U (E) S52 S53 S54 S55 S56 S57

1.3 ::;; E < 1.5 1.5 ::;; E < 1.7 1.7:s;E<1.9 1.9 ::;; E < 2.1 2.1 :s;E<2.3 2.3 ::;; E < 2.5 2.5 :s;E<2.7 2.7 ::;; E < 2.9 2.9 ::;; E < 3.1 5.6 5.8 3.1 :s;E<3.3 5.5 5.7 6.7 3.3 ::;; E < 3.5 5.4 5.6 6.5 3.5 ::;; E < 3.7 5.4 6.1 6.4 3.7 ::;; E < 3.9 5.3 6.0 6.3 3.9 ::;; E < 4.1 5.2 5.9 6.1 4.1 ::;; E < 4.3 5.9 6.0 4.3 ::;; E < 4.5 5.8 6.0 4.5 ::;; E < 4.7 5.5 5.7 5.9 4.7 ::;; E < 4.9 5.5 5.6 5.8

E 2::4.9 5.4 5.6 5.7

Certificate of Compliance No. 1031 82-109 Amendment No. 7

Page 163: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-31 Loading Table for PWR Fuel-1235 W/Assembly-WE 14x14 Fuel

(Continued)

WE 14x14 Assembly Average

Initial Assembly Burnu B GWd/MTU

Avg. Enrichment 57< B 58< B 59< B wt 323su (E S58 S59 S60 1.3 :s; E < 1.5 1.5:5E<1.7 1.7 :s; E < 1.9 1.9 :s; E < 2.1 2.1 :s; E < 2.3 2.3 :s; E < 2.5 2.5 :s; E < 2.7 2.7 :s; E < 2.9 2.9 :s; E < 3.1 3.1 :s; E < 3.3 3.3 :s; E < 3.5 3.5 :s; E < 3.7

7.0 6.9 6.8 6.7

6.3 6.6 6.2 6.5 6.1 6.4

Certificate of Compliance No. 1031 82-110 Amendment No. 7

Page 164: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-32 Loading Table for PWR Fuel -1710 W/Assembly-WE 14x14 Fuel

Initial Assembly 8 GWd/MTU

Avg. Enrichment 45< 8 49< 8 50< 8 wt Ofo235U E S46 S47 S48 S49 S50 S51 1.3 ::;; E < 1.5 1.5 ::;; E < 1.7 1.7 ::;;E<1.9 1.9 ::;; E < 2.1 2.1 ::;; E < 2.3 2.3 ::;; E < 2.5 2.5 ::;; E < 2.7 2.7 ::;; E < 2.9 3.4 3.5 3.6 2.9 ::;; E < 3.1 3.4 3.5 3.5 3.1 ::;; E < 3.3 3.3 3.4 3.7 3.3 ::;; E < 3.5 3.3 3.4 3.7 3.5 ::;; E < 3.7 3.3 3.3 3.6 3.7 ::;;E<3.9 3.2 3.3 3.5 3.6 3.9 ::;; E < 4.1 3.2 3.5 3.5 4.1 ::;;E<4.3 3.1 3.4 3.5 4.3 ::;; E < 4.5 3.1 3.4 3.5 4.5 ::;; E < 4.7 3.3 3.4 3.4 4.7 ::;; E < 4.9 3.3 3.4 3.4

E;::: 4.9 3.2 3.3 3.4

Certificate of Compliance No. 1031 82-111 Amendment No. 7

Page 165: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-32 Loading Table for PWR Fuel-1710 W/Assembly-WE 14x14 Fuel

(Continued)

Initial Assembly B GWd/MTU

Avg. Enrichment 51< B 55< B 56< B wt %235U (E) S52 S53 S54 S55 S56 S57 1.3 ::;; E < 1.5 1.5 ::;; E < 1.7 1.7 ::;; E < 1.9 1.9 ::;; E < 2.1 2.1 ::;; E < 2.3 2.3 ::;; E < 2.5 2.5 ::;; E < 2.7 2.7 ::;; E < 2.9 2.9 ::;; E < 3.1 3.9 4.0 3.1 ::;; E < 3.3 3.8 3.9 4.3 3.3 ::;; E < 3.5 3.8 3.9 4.3 3.5=s;E<3.7 3.7 3.8 4.1 4.2 3.7=s;E<3.9 3.7 4.0 4.2 3.9 ::;; E < 4.1 3.6 4.0 4.1 4.1 ::;; E < 4.3 3.6 3.9 4.0 4.3 ::;; E < 4.5 3.8 3.9 4.0 4.5 ::;; E < 4.7 3.8 3.9 3.9 4.7 ::;; E < 4.9 3.7 3.8 3.9

E~4.9 3.7 3.8 3.9

Certificate of Compliance No. 1031 82-112 Amendment No. 7

Page 166: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-32 Loading Table for PWR Fuel-1710 W/Assembly-WE 14x14 Fuel

(Continued)

WE 14x14 Assembly Average

Initial Assembly Burnu B GWd/MTU

Avg. Enrichment 57< 8 58< 8 59< 8 wt 323su (E) :S58 :S59 :S60 1.3 ::; E < 1.5 1.5 ::; E < 1.7 1.7 ::; E < 1.9 1.9 ::; E < 2.1 2.1 ::; E < 2.3 2.3 ::; E < 2.5 2.5 ::; E < 2.7 2.7 ::; E < 2.9 2.9 ::; E < 3.1 3.1 ::; E < 3.3 3.3 ::; E < 3.5

4.5 4.4 4.3 4.3 4.2

4.1 4.2 4.0 4.1

Certificate of Compliance No. 1031 82-113 Amendment No. 7

Page 167: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-33 Loading Table for PWR Fuel - 788 W/Assembly-WE 14x14 Fuel

Initial Assembly 8 GWd/MTU

Avg. Enrichment 45< 8 49< 8 50< 8 wt 323su E S46 S47 S48 S49 S50 S51 1.3 ::; E < 1.5 1.5 ::; E < 1.7 1.7:5E<1.9 1.9 ::; E < 2.1 2.1 ::; E < 2.3 2.3 ::; E < 2.5 2.5 ::; E < 2.7 2.7 :5E<2.9 9.0 9.7 10.4 2.9 ::; E < 3.1 8.9 9.5 10.1 3.1 :5E<3.3 8.7 9.2 9.9 11.9 3.3 ::; E < 3.5 8.5 9.0 11.6 3.5 ::; E < 3.7 8.4 8.9 11.4 3.7 ::; E < 3.9 8.2 8.7 10.4 11.1 3.9 ::; E < 4.1 8.1 8.6 10.2 10.9 4.1 ::; E < 4.3 8.0 10.0 10.7 4.3 ::; E < 4.5 7.9 9.8 10.5 4.5 ::; E < 4.7 7.8 9.3 9.7 10.3 4.7 ::; E < 4.9 8.6 9.1 9.5 10.2

E;::: 4.9 8.5 9.0 9.4 10.0

Certificate of Compliance No. 1031 82-114 Amendment No. 7

Page 168: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-33 Loading Table for PWR Fuel - 788 W/Assembly-WE 14x14 Fuel

(Continued)

Initial Assembly Avg. Enrichment 51< B

wt % 235U (E) :S52

1.3 ::; E < 1.5 1.5 ::o;E<1.7 1.7 ::o;E<1.9 1.9 ::; E < 2.1 2.1 ::o;E<2.3 2.3 ::; E < 2.5 2.5 ::; E < 2.7 2.7 ::; E < 2.9 2.9 ::; E < 3.1 3.1 ::; E < 3.3 3.3 ::; E < 3.5 3.5 ::; E < 3.7 3.7 ::; E < 3.9 3.9 ::; E < 4.1 4.1 ::; E < 4.3 4.3 ::; E < 4.5 4.5 ::; E < 4.7 4.7 ::; E < 4.9

E 2::4.9

13.1 12.8 12.4 12.1 11.9 11.6

:S53

14.0 13.6 13.3 13.0

Certificate of Compliance No. 1031

:S54

82-115

:S55

13.7 13.5 13.3 13.1

B GWd/MTU 55< B 56< B

:S56 :S57

14.7 14.4 14.1 13.9

17.7 17.3 16.9 16.5 16.2 15.9 15.6 15.3 15.1 14.8

Amendment No. 7

Page 169: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-33 Loading Table for PWR Fuel - 788 W/Assembly-WE 14x14 Fuel

(Continued)

WE 14x14 Assembly Average Initial Assembly ,___ __ B_u_r_nu___.____,_B,_G_W_d_/_M_TU __ _ Avg. Enrichment 57< B 58< B 59< B

wt %235U (E) 1.3 ::; E < 1.5 1.5$E<1.7 1.7$E<1.9 1.9 ::; E < 2.1 2.1 ::; E < 2.3 2.3 ::; E < 2.5 2.5 ::; E < 2.7 2.7 ::; E < 2.9 2.9 ::; E < 3.1 3.1 ::; E < 3.3

Certificate of Compliance No. 1031

:S58

82-116

:S59 :S60

19.6 19.2 18.9 18.6 18.3 18.0 17.8

Amendment No. 7

Page 170: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-34 Loading Table for PWR Fuel - 513 W/Assembly- CE 16x16 Fuel

Initial Assembly Assembl

Avg. Enrichment B S10 10< B 30< B wt %235U E S15 S20 S25 S30 S32.5 1.3 :::; E < 1.5 4.0 1.5$E<1.7 4.0 4.0 1.7 :::; E < 1.9 4.0 4.0 4.9 1.9 :::; E < 2.1 4.0 4.0 4.8 6.1 2.1 :::; E < 2.3 4.0 4.0 4.8 2.3 :::; E < 2.5 4.0 4.0 4.7 2.5 :::; E < 2.7 4.0 4.0 4.7 2.7 :::; E < 2.9 4.0 4.0 4.7 2.9 :::; E < 3.1 4.0 4.0 4.6 9.6 3.1 :::; E < 3.3 4.0 4.0 9.5 3.3 :::; E < 3.5 4.0 4.0 9.4 3.5 :::; E < 3.7 4.0 4.0 7.8 9.4 3.7 $E<3.9 4.0 4.0 7.8 9.3 3.9 :::; E < 4.1 4.0 7.7 9.2 4.1 :::; E < 4.3 4.0 7.7 9.2 4.3 :::; E < 4.5 4.0 5.7 7.7 9.2 4.5 :::; E < 4.7 5.7 7.6 9.1 4.7 :::; E < 4.9 4.5 5.7 7.6 9.1

E~4.9 4.5 5.7 7.6 9.0

Certificate of Compliance No. 1031 82-117 Amendment No. 7

Page 171: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

( \ Table 82-34 Loading Table for PWR Fuel- 513 W/Assembly- CE 16x16 Fuel

(Continued)

Initial Assembly Assembl B GWd/MTU

Avg. Enrichment 32.5< B 35< B 41< B 42< B wt 323su E :S35 :S37.5 :S40 :S41 :S42 :S43

1.3 s E < 1.5 1.5 s E < 1.7 1.7SE<1.9 1.9 s E < 2.1 2.1 SE<2.3 2.3 s E < 2.5 12.5 15.8 2.5 s E < 2.7 12.3 15.6 19.2 2.7 s E < 2.9 12.1 15.4 19.0 2.9 s E < 3.1 12.0 15.2 18.8 23.2 3.1 s E < 3.3 11.9 15.0 23.0 3.3 s E < 3.5 11.8 14.8 22.8 3.5 s E < 3.7 11.7 21.1 22.5 3.7 s E < 3.9 11.7 20.9 22.3

( 3.9 s E < 4.1 11.6 20.8 22.2 4.1 s E < 4.3 11.5 20.7 22.1 4.3 s E < 4.5 19.1 20.5 21.9 4.5 s E < 4.7 17.6 19.0 20.4 21.8 4.7 s E < 4.9 17.5 18.9 20.3 21.7

E 2:: 4.9 17.4 18.8 20.2 21.6

Certificate of Compliance No. 1031 82-118 Amendment No. 7

Page 172: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-34 Loading Table for PWR Fuel- 513 W/Assembly- CE 16x16 Fuel

(Continued)

Initial Assembly Avg. Enrichment

wt %235LJ E

1.3 =:; E < 1.5 1.5=:;E<1.7 1.7=:;E<1.9 1.9 =:; E < 2.1 2.1 =:; E < 2.3 2.3 =:; E < 2.5

Assembly Average Burnu B GWd/MTU

43< B 44< B S44 S45

2.5 =:; E < 2.7 25.1 2.7 ::;; E < 2.9 2.9 =:; E < 3.1 3.1 =:; E < 3.3 3.3 =:; E < 3.5

Certificate of Compliance No. 1031

25.0 24.9

23.4 24.8 23.2 24.6 23.1 24.5 23.0 24.4

82-119 Amendment No. 7

Page 173: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-35 Loading Table for PWR Fuel -1300 W/Assembly- CE 16x16 Fuel

Initial Assembly Assembl

Avg. Enrichment B :S10 10< B 30< B wt %235U E :S15 :S20 :S25 :S30 :S32.5 1.3 :5 E < 1.5 4.0 1.5 :5 E < 1.7 4.0 4.0 1.7:5E<1.9 4.0 4.0 4.0 1.9 :5 E < 2.1 4.0 4.0 4.0 4.0 2.1 :5 E < 2.3 4.0 4.0 4.0 2.3 :5 E < 2.5 4.0 4.0 4.0 2.5 :5 E < 2.7 4.0 4.0 4.0 2.7 :5 E < 2.9 4.0 4.0 4.0 2.9 :5 E < 3.1 4.0 4.0 4.0 3.1 :5 E < 3.3 4.0 4.0 4.0 3.3 :5 E < 3.5 4.0 4.0 4.0 3.5 :5 E < 3.7 4.0 4.0 4.0 4.0 3.7 :5 E < 3.9 4.0 4.0 4.0 4.0 3.9 :5 E < 4.1 4.0 4.0 4.0 4.1 :5E<4.3 4.0 4.0 4.0 4.3 :5 E < 4.5 4.0 4.0 4.0 4.0 4.5 :5 E < 4.7 4.0 4.0 4.0 4.7 :5 E < 4.9 4.0 4.0 4.0 4.0

E ~4.9 4.0 4.0 4.0 4.0

Certificate of Compliance No. 1031 82-120 Amendment No. 7

Page 174: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-35 Loading Table for PWR Fuel - 1300 W/Assembly - CE 16x16 Fuel (Continued)

Initial Assembly Assembl B GWd/MTU

Avg. Enrichment 32.5< B 35< B 41< B 42< B wt %235U E :S35 :S37.5 :S40 :S41 :S42 :S43 1.3 :5 E < 1.5 1.5 :SE<1.7 1.7 :SE<1.9 1.9 :::; E < 2.1 2.1 :::; E < 2.3 2.3 :::; E < 2.5 4.0 4.0 2.5 :::; E < 2.7 4.0 4.0 2.7 :::; E < 2.9 4.0 4.0 2.9 :::; E < 3.1 4.0 4.0 4.4 3.1 :::; E < 3.3 4.0 4.0 4.3 3.3 :::; E < 3.5 4.0 4.0 4.1 4.3 3.5 :::; E < 3.7 4.0 4.0 4.1 4.2 3.7 :::; E < 3.9 4.0 4.0 4.2 3.9 :::; E < 4.1 4.0 4.0 4.0 4.1 4.1 :::; E < 4.3 4.0 4.0 4.1 4.3 :::; E < 4.5 4.0 4.0 4.0 4.5 :::; E < 4.7 4.0 4.0 4.0 4.0 4.7 :::; E < 4.9 4.0 4.0 4.0 4.0

E ~4.9 4.0 4.0 4.0 4.0

Certificate of Compliance No. 1031 82-121 Amendment No. 7

Page 175: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-35 Loading Table for PWR Fuel -1300 W/Assembly- CE 16x16 Fuel (Continued)

Initial Assembly Avg. Enrichment

wt 323su E 1.3 ::;; E < 1.5 1.5 ::;; E < 1.7 1.7:s;E<1.9 1.9 ::;; E < 2.1 2.1 ::;; E < 2.3 2.3 ::;; E < 2.5

Assembly Average Burnu B GWd/MTU

43< B 44< B S44 S45

2.5 ::;; E < 2.7 4.6 2.7 ::;; E < 2.9 4.5 2.9 ::;; E < 3.1 3.1 ::;; E < 3.3 3.3 ::;; E < 3.5 3.5 ::;; E < 3.7 3.7 ::;; E < 3.9

3.9~~~~ 4.1~<4.3/1 ' 4.3 4.3 ~~E'>s: 4 o/ 4.2 4.3

~'6' '":/. 4.1 4.2

4.1 4.2 4.0 4.2

Certificate of Compliance No. 1031 82-122 Amendment No. 7

Page 176: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-36 Loading Table for PWR Fuel - 1800 WI Assembly - CE 16x16 Fuel

Initial Assembly Assembl

Avg. Enrichment 8 S10 10< 8 30< 8 wt %235U E S15 S20 S25 S30 S32.5 1.3 ::;; E < 1.5 4.0 1.5$E<1.7 4.0 4.0 1.7 ::;; E < 1.9 4.0 4.0 4.0 1.9 ::;; E < 2.1 4.0 4.0 4.0 4.0 2.1 ::;;E<2.3 4.0 4.0 4.0 4.0 2.3 ::;; E < 2.5 4.0 4.0 4.0 2.5 ::;; E < 2.7 4.0 4.0 4.0 2.7 ::;; E < 2.9 4.0 4.0 4.0 4.0 2.9 ::;; E < 3.1 4.0 4.0 4.0 4.0 3.1 ::;; E < 3.3 4.0 4.0 4.0 3.3 ::;; E < 3.5 4.0 4.0 4.0 4.0 3.5 ::;; E < 3.7 4.0 4.0 4.0 4.0 3.7 ::;; E < 3.9 4.0 4.0 4.0 4.0 3.9 ::;;E<4.1 4.0 4.0 4.0 4.0 4.1 ::;; E < 4.3 4.0 4.0 4.0 4.0 4.3 ::;; E < 4.5 4.0 4.0 4.0 4.0 4.5 ::;; E < 4.7 4.0 4.0 4.0 4.0 4.7 ::;; E < 4.9 4.0 4.0 4.0 4.0

E~4.9 4.0 4.0 4.0 4.0

Certificate of Compliance No. 1031 82-123 Amendment No. 7

Page 177: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-36 Loading Table for PWR Fuel -1800 W/Assembly- CE 16x16 Fuel (Continued)

Initial Assembly Assembl B GWd/MTU

Avg. Enrichment 32.5< B 35< B 41< B 42< B wt 323su E :S35 :S37.5 :S40 :S41 :S42 :S43 1.3 :::; E < 1.5 1.5 :5E<1.7 1.7 :::; E < 1.9 1.9 :::; E < 2.1 2.1 :::; E < 2.3 2.3 :::; E < 2.5 4.0 4.0 2.5 :::; E < 2.7 4.0 4.0 2.7 :::; E < 2.9 4.0 4.0 2.9 :::; E < 3.1 4.0 4.0 4.0 3.1 :::; E < 3.3 4.0 4.0 4. 4.0 3.3 :::; E < 3.5 4.0 4.0

~-4.0 4.0

~ r:.f) 3.5 :::; E < 3.7 4.0 4.0 4.0 4.0 .

3.7 :::; E < 3.9 4.0 .

4.0 4.0 4.0 \ 4.0 ;~¥ • 3.9 :::; E < 4.1 4.0 4.0 (!'. 4.0 4.0 4.0

><\".,:

4.1 :::; E < 4.3 4.0 %4~~£i'" 4.0 4.0 4.0 4.3 :::; E < 4.5 4.0 4.0 4.0 4.0 4.5 :::; E < 4.7 4.0 4.0 4.0 4.0 4.7 :::; E < 4.9 4.0 4.0 4.0 4.0

E2::4.9 4.0 4.0 4.0 4.0

Certificate of Compliance No. 1031 82-124 Amendment No. 7

Page 178: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-36 Loading Table for PWR Fuel -1800 W/Assembly- CE 16x16 Fuel (Continued)

Initial Assembly Avg. Enrichment

wt %235U E 1.3 ::;; E < 1.5 1.5 :s;E<1.7 1.7 ::;; E < 1.9 1.9 ::;; E < 2.1 2.1 ::;; E < 2.3 2.3 ::;; E < 2.5

Assembly Average Burnu 8 GWd/MTU

43< B 44< B S44 S45

2.5 ::;; E < 2.7 4.0 2.7 ::;; E < 2.9 4.0 2.9 ::;; E < 3.1 4.0 3.1 ::;; E < 3.3 3.3 ::;; E < 3.5 3.5 ::;; E < 3.7

Certificate of Compliance No. 1031

4.0 4.0

4.0 4.0 4.0 4.0 4.0 4.0

82-125 Amendment No. 7

Page 179: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-37 Loading Table for PWR Fuel- 830 W/Assembly- CE 16x16 Fuel

Initial Assembly Assembl

Avg. Enrichment B :S10 10< B 30< B wt %235U E :S15 :S20 :S25 :S30 :S32.5 1.3 :::; E < 1.5 4.0 1.5$E<1.7 4.0 4.0 1.7 :::; E < 1.9 4.0 4.0 4.0 1.9 :::; E < 2.1 4.0 4.0 4.0 2.1 :::; E < 2.3 4.0 4.0 4.0 2.3 :::; E < 2.5 4.0 4.0 4.0 2.5 :::; E < 2.7 4.0 4.0 4.0 2.7 :::; E < 2.9 4.0 4.0 4.0 2.9 :::; E < 3.1 4.0 4.0 4.0 4.8 3.1 :::; E < 3.3 4.0 4.0 4.8 3.3 :::; E < 3.5 4.0 4.0 4.7 3.5 :::; E < 3.7 4.0 4.0 4.4 4.7 3.7 :::; E < 3.9 4.0 4.0 4.4 4.7 3.9$E<4.1 4.0 4.3 4.6 4.1 :::; E < 4.3 4.0 4.3 4.6 4.3 :::; E < 4.5 4.0 4.0 4.3 4.6 4.5 :::; E < 4.7 4.0 4.3 4.5 4.7 :::;E<4.9 4.0 4.2 4.5

E~4.9 4.0 4.0 4.2 4.5

Certificate of Compliance No. 1031 82-126 Amendment No. 7

Page 180: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-37 Loading Table for PWR Fuel - 830 W/Assembly- CE 16x16 Fuel (Continued)

Initial Assembly Assembl B GWd/MTU

Avg. Enrichment 32.5< B 35< B 41< B 42< B wt %235U E :S35 :S37.5 :S40 :S41 :S42 :S43 1.3 s; E < 1.5 1.5 s; E < 1.7 1.7 s; E < 1.9 1.9 s; E < 2.1 2.1 s; E < 2.3 2.3 s; E < 2.5 5.5 6.0 2.5 s; E < 2.7 5.4 6.0 2.7 s; E < 2.9 5.4 5.9 7.7 2.9 :sE<3.1 5.3 5.8 7.5 3.1 s; E < 3.3 5.2 5.8 7.4 3.3 s; E < 3.5 5.2 5.7 6.9 7.3 3.5 s; E < 3.7 5.1 5.7 6.8 7.2 3.7 s; E < 3.9 5.1 6.8 7.1 3.9 s; E <4.1 5.0 6.4 6.7 7.0 4.1 s; E < 4.3 5.0 6.4 6.7 6.9 4.3 s; E < 4.5 6.0 6.3 6.6 6.9 4.5 s; E < 4.7 6.0 6.2 6.5 6.8 4.7 :5E<4.9 5.9 6.2 6.5 6.8

E ~4.9 5.9 6.1 6.4 6.7

Certificate of Compliance No. 1031 82-127 Amendment No. 7

Page 181: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-37 Loading Table for PWR Fuel - 830 W/Assembly- CE 16x16 Fuel (Continued)

Initial Assembly Avg. Enrichment

wt Ofo235LJ E 1.3 $ E < 1.5 1.5 $E<1.7 1.7$E<1.9 1.9 $ E < 2.1 2.1 $ E < 2.3 2.3 $ E < 2.5 2.5 $ E < 2.7 2.7 $ E < 2.9 2.9 $ E < 3.1 3.1 $ E < 3.3 3.3 $ E < 3.5 3.5 $ E < 3.7

Assembly Average Burnu B GWd/MTU

43< B S44

8.2 8.0 7.9

44< B S45

7.7 7.2 7.6 7.1 7.5 7.0 7.4 7.0 7.4

Certificate of Compliance No. 1031 82-128 Amendment No. 7

Page 182: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Note: For fuel assembly average burn up greater than 45 GWd/MTU, cool time tables have been revised to account for a 5% margin in heat load.

Table 82-38 Loading Table for PWR Fuel -487 W/Assembly- CE 16x16 Fuel

Initial Assembly Assembl

Avg. Enrichment 45< B 46< B 50< B wt 323su E S46 S47 S48 S49 1.3 :::; E < 1.5 1.5 :5 E < 1.7 1.7 :::; E < 1.9 1.9 :::; E < 2.1 2.1 :::; E < 2.3 2.3 :::; E < 2.5 2.5 :::; E < 2.7 2.7 :::; E < 2.9 30.4 31.8 2.9 :::; E < 3.1 30.1 31.6 35.5 36.8 3.1 :::; E < 3.3 30.0 31.4 35.4 36.7 3.3 :::; E < 3.5 29.8 35.2 36.6 3.5 :::; E < 3.7 29.6 35.1 36.3 3.7 :::; E < 3.9 29.4 34.9 36.3 3.9 :5E<4.1 33.5 34.7 36.1 4.1 :::; E < 4.3 32.0 33.4 34.6 35.9 4.3 :::; E < 4.5 31.9 33.2 34.5 35.9

31.7 33.1 34.4 35.7 31.5 33.0 34.3 35.6 31.4 32.8 34.2 35.4

Certificate of Compliance No. 1031 82-129 Amendment No. 7

Page 183: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-38 Loading Table for PWR Fuel - 487 W/Assembly- CE 16x16 Fuel (Continued)

Initial Assembly Assembl B GWd/MTU

Avg. Enrichment 51< B 52< B 55< B 56< B wt Ofo235LJ E :S52 :S53 :S54 :S55 :S56 :S57

1.3 :5 E < 1.5 1.5 ::; E < 1.7 1.7 :5 E < 1.9 1.9 ::; E < 2.1 2.1 :5 E < 2.3 2.3 :5 E < 2.5 2.5 :5 E < 2.7 2.7 :5 E < 2.9 2.9 ::; E < 3.1 38.1 39.3 3.1 :5 E < 3.3 38.0 39.2 43.1 3.3 :5 E < 3.5 37.8 39.1 41.9 43.1 3.5 :5 E < 3.7 37.6 38.9 41.8 42.9 3.7 ::; E < 3.9 37.6 38.7 41.7 42.8 3.9 ::; E < 4.1 41.6 42.7 4.1 ::; E < 4.3 41.4 42.6 4.3 :5 E < 4.5 41.3 42.5 4.5 :5 E < 4.7 41.2 42.4 4.7 :5 E < 4.9 39.5 40.7 41.0 42.3

E 2::4.9 39.3 40.5 40.9 42.1

Certificate of Compliance No. 1031 82-130 Amendment No. 7

Page 184: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-38 Loading Table for PWR Fuel- 487 W/Assembly- CE 16x16 Fuel (Continued)

Assembly Average Burnup (B) Initial Assembly f----~_G_W_d_/M_T_U ___ _ Avg. Enrichment

wt 323su E

1.3 ::; E < 1.5 1.5:5E<1.7 1.7 ::; E < 1.9 1.9 ::; E < 2.1 2.1 ::; E < 2.3 2.3 ::; E < 2.5 2.5 ::; E < 2.7 2.7 ::; E < 2.9 2.9 ::; E < 3.1 3.1 ::; E < 3.3

57< B S58

58< B S59

59< B S60

Certificate of Compliance No. 1031 82-131 Amendment No. 7

Page 185: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-39 Loading Table for PWR Fuel - 1235 W/Assembly - CE 16x16 Fuel

Initial Assembly Assembl

Avg. Enrichment 45< 8 46< 8 50< 8 wt %235U E S46 S47 S48 S49 S50 S51 1.3 :::; E < 1.5 1.5:s;E<1.7 1.7 :::; E < 1.9 1.9 :::; E < 2.1 2.1 :::; E < 2.3 2.3 :::; E < 2.5 2.5 :::; E < 2.7 2.7 :::; E < 2.9 5.1 5.3 5.5 2.9 :::; E < 3.1 5.0 5.2 5.4 6.0 3.1 :::; E < 3.3 4.9 5.1 5.9 3.3 :::; E < 3.5 4.9 5.0 5.8 3.5 :::; E < 3.7 4.8 5.0 5.5 5.7 3.7 :::; E < 3.9 4.8 4.9 5.4 5.6 3.9 :::; E < 4.1 4.7 5.4 5.6 4.1 :::; E < 4.3 4.7 5.3 5.5 4.3 :::; E < 4.5 4.6 5.0 5.2 5.4 4.5 :::; E < 4.7 5.0 5.1 5.3 4.7 :::; E < 4.9 4.8 4.9 5.1 5.3

E;:::4.9 4.8 4.9 5.0 5.2

Certificate of Compliance No. 1031 82-132 Amendment No. 7

Page 186: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-39 Loading Table for PWR Fuel-1235 W/Assembly- CE 16x16 Fuel (Continued)

Initial Assembly Assembl 8 GWd/MTU

Avg. Enrichment 51< 8 52< 8 55< 8 56< 8 wt 323su E :S52 :S53 :S54 :S55 :S56 :S57 1.3 :5 E < 1.5 1.5 :5 E < 1.7 1.7 :5 E < 1.9 1.9 :5 E < 2.1 2.1 :5 E < 2.3 2.3 :5 E < 2.5 2.5 :5 E < 2.7 2.7 :5 E < 2.9 2.9 :5 E < 3.1 6.2 6.5 6.7 3.1 :5 E < 3.3 6.1 6.3 7.3 3.3 :5 E < 3.5 6.0 6.2 6.9 7.1 3.5 :5 E < 3.7 5.9 6.1 6.7 7.0 3.7 :5E<3.9 5.8 6.6 6.9 3.9 :5 E < 4.1 5.7 6.5 6.8 4.1 :5 E < 4.3 6.4 6.7 4.3 :5 E < 4.5 6.2 6.3 6.6 4.5 :5 E < 4.7 5.9 6.0 6.2 6.4 4.7 :5 E < 4.9 5.8 6.0 6.1 6.4

E~4.9 5.8 5.9 6.0 6.3

Certificate of Compliance No. 1031 82-133 Amendment No. 7

Page 187: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-39 Loading Table for PWR Fuel -1235 W/Assembly- CE 16x16 Fuel (Continued)

Assembly Average Burnup (B) Initial Assembly .___ ____ G_W_d_/M_T_U ___ _ Avg. Enrichment 57< B 58< B 59< B

S60 wt % 235U E S58 S59 1.3 :::; E < 1.5 1.5$;E<1.7 1.7$E<1.9 1.9 :::; E < 2.1 2.1 $; E < 2.3 2.3 :::; E < 2.5 2.5 :::; E < 2.7 2.7 $; E < 2.9 2.9 :s;E<3.1 3.1 $; E < 3.3 3.3 $; E < 3.5 3.5 :::; E < 3.7 3.7 :::; E < 3.9

7.7 7.,'

7.8 7.7 7.5 7.4 7.2

6.9 7.1 6.8 7.0

Certificate of Compliance No. 1031 82-134 Amendment No. 7

Page 188: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-40 Loading Table for PWR Fuel -1710 W/Assembly- CE 16x16 Fuel

Initial Assembly Assembl

Avg. Enrichment 45< 8 46< 8 50< 8 wt Ofo235U E :S46 :S47 :S48 :S49 :S50 :S51 1.3 :5 E < 1.5 1.5:5E<1.7 1.7 :5 E < 1.9 1.9 :5 E < 2.1 2.1 :5E<2.3 2.3 :5 E < 2.5 2.5 :5 E < 2.7 2.7 :5 E < 2.9 4.0 4.0 4.0 2.9 :5 E < 3.1 4.0 4.0 4.0 4.1 3.1 :5 E < 3.3 4.0 4.0 4.1 3.3 :5 E < 3.5 4.0 4.0 4.0 3.5 :5 E < 3.7 4.0 4.0 4.0 4.0 3.7 :5 E < 3.9 4.0 4.0 4.0 3.9 :5 E < 4.1 4.0 4.0 4.0 4.1 :5 E < 4.3 4.0 4.0 4.0 4.3 :5 E < 4.5 4.0 4.0 4.0 4.0 4.5 :5 E < 4.7 4.0 4.0 4.0 4.7 :5E<4.9 4.0 4.0 4.0 4.0

E 2:4.9 4.0 4.0 4.0 4.0

Certificate of Compliance No. 1031 82-135 Amendment No. 7

Page 189: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-40 Loading Table for PWR Fuel-1710 W/Assembly- CE 16x16 Fuel (Continued)

Initial Assembly Assembl B GWd/MTU

Avg. Enrichment 51< B 52<8 55< B 56< B wt %235U E S52 S53 S54 S55 S56 S57 1.3 :::; E < 1.5 1.5:5E<1.7 1.7:5E<1.9 1.9 :::; E < 2.1 2.1 :::; E < 2.3 2.3 :::; E < 2.5 2.5 :::; E < 2.7 2.7 :::; E < 2.9 2.9 :::; E < 3.1 4.2 4.4 3.1 :5E<3.3 4.2 4.3 4.7 3.3 :::; E < 3.5 4.1 4.2 4.5 4.6 3.5 :::; E < 3.7 4.0 4.5 4.6 3.7 :::; E < 3.9 4.0 4.4 4.5 3.9 :::; E < 4.1 4.0 4.3 4.4 4.1 :::; E < 4.3 4.0 4.2 4.3 4.4 4.3 :::; E < 4.5 4.1 4.2 4.2 4.3 4.5 :::; E < 4.7 4.0 4.1 4.2 4.3 4.7 :::; E < 4.9 4.0 4.0 4.1 4.2

E <:: 4.9 4.0 4.0 4.1 4.2

Certificate of Compliance No. 1031 82-136 Amendment No. 7

Page 190: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-40 Loading Table for PWR Fuel -1710 W/Assembly- CE 16x16 Fuel (Continued)

Assembly Average Burnup (8)

Initial Assembly ~-----=-G-'-'W--'-d-'-/M...:....:T....::.U ___ _ Avg. Enrichment 57< B 58< B 59< B

S60 wt % 235U E S58 S59 1.3 :s; E < 1.5 1.5:s;E<1.7 1.7$E<1.9 1.9 :s; E < 2.1 2.1 :s; E < 2.3 2.3 :s; E < 2.5 2.5 :s; E < 2.7 2.7 :s; E < 2.9 2.9 :s; E < 3.1 3.1 :s; E < 3.3 3.3 :s; E < 3.5 3.5 :s; E < 3.7

4.8 4.7

4.5 4.7 4.5 4.6 4.4 4.5 4.4 4.5

Certificate of Compliance No. 1031 82-137 Amendment No. 7

Page 191: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-41 Loading Table for PWR Fuel - 788 W/Assembly- CE 16x16 Fuel

Initial Assembly f-------.---A_s_se_m_b,..I L----"'--.-------'----'--L....,------.-----

Avg. Enrichment 45< B 46< B wt% 23su E :S46 :S47 :S48

1.3 :::; E < 1.5 1.5 :::; E < 1.7 1.7$E<1.9 1.9 :::; E < 2.1 2.1 :s;E<2.3 2.3 :::; E < 2.5 2.5 :::; E < 2.7 2.7 :::; E < 2.9 2.9 :::; E < 3.1 3.1 :::; E < 3.3 3.3 :::; E < 3.5 3.5 :::; E < 3.7 3.7 :::; E < 3.9 3.9 :::; E < 4.1 4.1 :::; E < 4.3 4.3 :::; E < 4.5 4.5 :::; E < 4.7 4.7 :::; E < 4.9

E~4.9

Certificate of Compliance No. 1031 82-138

:S49 :S50

12.6 12.4 12.0 11.9 11.7 11.5 11.4 11.2 11.1

50< B

:S51

14.2 13.9 13.6 13.3 13.0 12.8 12.5 12.3 12.1 12.0 11.8

Amendment No. 7

Page 192: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-41 Loading Table for PWR Fuel- 788 W/Assembly- CE 16x16 Fuel (Continued)

Initial Assembly Avg. Enrichment 51 < B

wt % 23su E ::552

1.3 :::; E < 1.5 1.5$E<1.7 1.7 :::; E < 1.9 1.9 :::; E < 2.1 2.1 :::; E < 2.3 2.3 :::; E < 2.5 2.5 :::; E < 2.7 2.7 :::; E < 2.9 2.9 :::; E < 3.1 3.1 :::; E < 3.3 3.3 :::; E < 3.5 3.5 :::; E < 3.7 3.7 :::; E < 3.9 3.9 :::; E < 4.1 4.1 :::; E < 4.3 4.3 :::; E < 4.5 4.5 :::; E < 4.7 4.7 :::; E < 4.9

E2::4.9

15.2 14.9 14.6 14.2

Assembl

52< B ::553 ::554

16.3 15.9 15.6 15.2

Certificate of Compliance No. 1031 82-139

B GWd/MTU 55< B

::555 ::556

16.4 16.1 15.8 15.7 15.4

17.9 17.5 17.2 16.9 16.7 16.4 16.1 16.0

56< B ::557

19.7 19.3 19.0 18.6 18.2 18.0 17.7 17.4 17.2 17.0

Amendment No. 7

Page 193: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-41 Loading Table for PWR Fuel - 788 WI Assembly - CE 16x16 Fuel (Continued)

Assembly Average Burnup (B)

Initial Assembly 1---~_G_W_d_/M_T_U ___ _ Avg. Enrichment 57< B 58< B

wt % 23su E ::S58 ::S59

1.3 ::; E < 1.5 1.5::;E<1.7 1.7 ::; E < 1.9 1.9 ::; E < 2.1 2.1 ::; E < 2.3 2.3 ::; E < 2.5 2.5 ::; E < 2.7 2.7 ::; E < 2.9 2.9 ::; E < 3.1 3.1 ::; E < 3.3 3.3 ::; E < 3.5 3.5 ::; E < 3.7 3.7 ::; E < 3.9

19.7 19.5 19.2 19.0

59< B

::S60

21.7 21.4 21.1 20.8 20.5 20.2 20.0

Certificate of Compliance No. 1031 82-140 Amendment No. 7

Page 194: (.Modular Advanced generation Nuclear All-purpose STORage) · Certificate of Compliance No. 1031 A1-1 Amendment No. 7 . DAMAGED FUEL Definitions 1.1 SPENT NUCLEAR FUEL (SNF) assembly

Table 82-42 Low SNF Assembly Average 8urnup Enrichment Limits for CE 16x16 Fuel Loaded via the PMTC

Max. Assembly Avg. Min. Assembly Avg. Minimum Cool Time Burn up Initial Enrichment (yrs)

(MWd/MTU) (wt% 235LJ) 10,000 1.3 4.0 15,000 1.5 4.0 20,000 1.7 4.0 25,000 1.9 4.1

2.3 ~ E < 2.5 2.5 ~ E < 2.7

8.9 8.8 14.0 8.6 13.7 19.0 8.5 13.4 18.7 23.5 8.3 13.1 18.2 23.1 8.2 12.9 17.9 22.7 8.1 12.6 17.7 22.4 8.0 12.4 17.4 22.1 7.9 12.2 17.1 21.8 7.8 12.0 16.8 21.5

7.8 11.9 16.6 21.3

7.7 11.8 16.4 21.1

• The minimum cool times for heat loads of 811 W/assy for assembly average burnups less than 45 GWd/MTU and heat loads of 770 W/Assy for burnups greater than 45 GWd/MTU

Certificate of Compliance No. 1031 82-141 Amendment No. 7