presented at sc-2 2006-2 - ieee web hosting · 2017. 6. 23. · these guys? (10 cfr part 52 pra)...
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Company
LOGO
Risk-Informed Performance Based Regulations, Models,Issues, and Implications for
Qualification Standards to Existing Plants and Future Plants
Presented atSC-2 2006-2
James F. Gleason, P.E.
James F. Gleason. P.E.Chairman SC 2.1
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R RESTRICTEDUNDER 17 REQUIRES
ACCOMPANINGPARENT OR GUADIAN
James F. Gleason, P.E.
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The Future
The Doomed
James F. Gleason, P.E.
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Proof of Performance
The use of ASME NOG-1, ASME B&PVC,IEEE Nuclear Standards,ASME, and ACI codes and standards alone, are not sufficient proof of Performance in Risk-informed Performance based Regulation
James F. Gleason, P.E.
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What else is needed?
Answer: Reliability estimate of the code or standard
James F. Gleason, P.E.
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Who will provide this?
Answer: The Standards Committees.
James F. Gleason, P.E.
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Reliability Estimates
Reliability Estimates are needed for a Risk-informed, Performance Based LicenseReliability data needs to be related to the design basis criteria of the SSCs credited with prevention or mitigation of an event sequence.
James F. Gleason, P.E.
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Performance Requirements
Reliability information for SSCs (active and passive) is needed to demonstrate compliance with the performance requirements.
Reliability Estimate of Steel
James F. Gleason, P.E.
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Risk Continuum
00.20.40.60.8
1
ExistingNuclearPlants
Advanced /PassiveNuclearPlants
NewDesigns
Risk Continuum
Hey, What about These Guys?
(10 CFR Part 52 PRA)
And These Guys?(10 CFR Part 50.69
andRisk Based Part 50)
Nuclear Codes and Standards Not Good
Enough for Risk Informed 10 CFR Part 50
James F. Gleason, P.E.
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Burden for Predictable Performance
I once said that for the nuclear power sector: “there is no credible industry without a credible regulator, and there is no credible regulator without a credible industry.” I will add to it that: “there is no predictable industry without a predictable regulator, and there is no predictable regulator without a predictable industry.”Burden for predictable performance is broadly distributed.
Center for Business Intelligence Nuclear Power Outlook 2004Chairman Nils J. Diaz,
U.S. Nuclear Regulatory Commission
Center for Business Intelligence Nuclear Power Outlook 2004Chairman Nils J. Diaz,
U.S. Nuclear Regulatory Commission
James F. Gleason, P.E.
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Predictable
The performance based portion of a regulatory framework must
be able to be complete have a definite end be predictable
James F. Gleason, P.E.
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Nuclear Codes and Standards
Nuclear codes and standards are unique. They have proven their worth. They have been maintained, are current, and are required to be periodically updated.
IEEE Nuclear Standards
James F. Gleason, P.E.
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Framework RI 10CFR50
The Protective Systems objective is to ensure that the systems that mitigate initiating events are adequately designed, and perform adequately, in terms of reliability and capability
James F. Gleason, P.E.
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Framework RI 10CFR50
Establishing reliability goals for protective systemsRedundancy, the use of more than a minimum number of sets of equipment to fulfill a given safety function, is an important design principle
James F. Gleason, P.E.
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Framework RI 10CFR50
The PRA will provide a means of assessing the importance of common cause failures and provide the designer the ability to ameliorate the potential for these failures through selection of diverse materials, components, and manufacturing processes.
AmeliorateImprove Revolutionize Remodel Rearrange Restore Amend
Or: Minimize Diminish Lessen Curtail Eliminate through Equipment Qualification?
James F. Gleason, P.E.
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Framework RI 10CFR50
It is worth noting that the current treatment of common cause failures is often data-driven, i.e., historical data is use to determine which common cause eventsare most likely and, hence, should be incorporated into the PRA.
ShiIShiIShiI happensEarthq
uake
James F. Gleason, P.E.
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Framework RI 10CFR50
Protection against common-cause failures has been, and will continue to be important as these types of failures can be expected to dominate the unreliability of systems with some degree of built in redundancy.
Amock
a frenzy that has traditionally been regarded as occurring in certain cultures
James F. Gleason, P.E.
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Framework RI 10CFR50
Verification of the functionality of the SSC under the required conditions is demonstrated via a reliability assurance program.
James F. Gleason, P.E.
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Framework RI 10CFR50
0102030405060708090
Reliability Qualification EQ Seismic
Final Score: 87 to 7Final Score: 87 to 7
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Demonstrated Performance
Qualification Reliability Estimate
1. Applies to Actual Installed Equipment YES No
2. Performance under Normal Conditions YES YES
3. Performance under Off Normal Conditions YES No
4. Performance under Design Basis Event Conditions
YES No
5. Performance under Post Accident Conditions
YES No
6. Performance under Seismic Conditions YES No
7. Performance under Radiation Conditions YES No
8. Performance under Aging Effects YES No
9. Performance due to maintenance YES No
10. Performance due to periodic testing YES No
11. Performance of replacement parts YES No
James F. Gleason, P.E.
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Call to Action
IEEE SC-2World’s Nuclear PedigreeStep up Leadership RoleNeed to ensure Predictability in RIPB
James F. Gleason, P.E.
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Agenda
1. Risk Informed Regulation
2. IEEE Std 323 Working Group
3. Hazards, Risks, Requirements
4. Potential Risk Informed 323
James F. Gleason, P.E.
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The Future
James F. Gleason, P.E.
Risk-Inform IEEE STD 323
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James F. Gleason, P.E.
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Cycle Diagram
NuclearStandards
NRCCommission
Staff
DesignConstruction
Hazards
Risk
James F. Gleason, P.E.
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Progress Diagram
ProbabilisticCapacity
ProbabilisticDemand
Hazards Analysis
Phase 1 Phase 2 Phase 3
ProbabilisticDemand<
ProbabilisticCapacity
= License
James F. Gleason, P.E.
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EQ Progress Diagram
Probability ofExceedence
SEISMIC HAZARD CURVE
DBA
Qualification is
Demonstrationof Compliance to
Requirements
Riskis
function ofRequirements
Risk Qualification License
James F. Gleason, P.E.
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Probability of Exceedence
James F. Gleason, P.E.
Probability of ExceedenceSeismic Demand
SSE SEISMIC HAZARD CURVE.
ANSI / ANS 2.27 and 2.29ASCE 43-5Not RG 1.165
DBA DemandDBA HAZARD LOCA, MSLB, HELB, Other AccidentRadiation Exposure
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Risk Based Demand
James F. Gleason, P.E.
Risk Based DemandProbability of Exceeding Demand
Typically < 1E-6Seismic Demand
SSEDBA Demand
LOCA, MSLB, HELB, Other AccidentRadiation Consequence
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State of the Art
Demand NEINew Plants
Standards
Applying technical
analysis to very low
probability events
Unintended Consequences
Problematic in practical application
Resolutions
James F. Gleason, P.E.
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Extreme Value Distributionvery low probability seismic events
0.5g
2g
8g
1E-3 1E-41E-2 1E-5
16g
James F. Gleason, P.E.
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EQ Graded Approach
EQ Risk D
EQ Risk C
EQ Risk B
EQ Risk A
SafetySignificant
Yes Yes Yes Yes
Safety Related Yes Yes Yes YesHarsh No No Yes YesHarsh
PerformanceNo No Early During/
AfterSeismic No Yes Yes Yes
James F. Gleason, P.E.
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Graded Approach
Graded ApproachSafety Significant and/or Safety Related
EQ Risk D, UnchallengedMild Environment, Low Seismic Significance
Equipment can be maintained during Design Basis Events DBEs (Includes DBAs and Safe Shutdown Earthquake)
Low expectation of redundant failures during DBE (For mild environment - Safe Shutdown Earthquake Only)
EQ Risk C, Seismic OnlyMild Environment, Seismic significant
Equipment can be maintained during DBELow expectation of redundant failures during DBEExpectation of redundant failures during earthquake
James F. Gleason, P.E.
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Graded Approach
Graded Approach (Continued)EQ Risk B, Early Event Equipment
Harsh Environment - Seismic SignificantEarly Event Equipment function onlyLow expectation of exposure to significant radiation
EQ Risk A, DBE EquipmentHarsh Environment - Seismic Significant
Safety Related function performed during and/or after DBE
Expectation of exposure to significant radiation
James F. Gleason, P.E.
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Proposed IEEE Std 323
Demand/Capacity
Aging
Seismic
DBAReport
Plan
James F. Gleason, P.E.
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Proposed IEEE Std 323
Risk Informed
CapacityPeer
ReviewDemand QA
James F. Gleason, P.E.