ML13127A080

Fleet Fire Protection Program NFPA 805 National Fire Protection Association NFPA 805 Pre-LAR Application for CNS, MNS, Rnp

ML13127A080
Person / Time
Site:	Mcguire, Catawba, Robinson, McGuire
Issue date:	04/18/2013
From:	Ertman J, Goforth D Duke Energy Corp
To:	Billoch-Colon A Plant Licensing Branch II
Billoch-Colon A
Shared Package
ML13127A050	List: ML13127A080
References
TAC MF0956
Download: ML13127A080 (34)

Text

Fleet Fire Protection Pro gram gNFPA 805National Fire Protection AssociationNFPA 805 Pre-LAR Application for CNS, MNS, RNPJefferyErtmanDavidGoforth

-NFPA805ProjectManagersJeffery Ertman , David Goforth -NFPA 805 Project ManagersApril 18, 2013 Agenda*NFPA 805 Transition Pro ject Overview j*License Amendment Request Overview

• Fire PRA Overview 2

Participants

• Jeffery Ertman-NFPA 805 Project ManagerDidGfthNFPA805PjtM

• D av id G o f or th -NFPA 805 P ro j ec t Manager*Donna Alexander -Manager Fleet Regulatory Affairs

• BobRishel-PRAManager Bob Rishel PRA Manager*Jeff Robertson -Manager Regulatory Affairs

• Julius Br yant -Re gulator y Affairs y gy*Sarah Chisholm -PRA Engineer

• Kelly Lavin -Site Technical Lead

• Al Maysam

-Regulatory Affairs

• Jamie McCrory -PRA EngineerBdiWPRAEi*Bran di Weaver -PRA E ng i neer 3 Acronyms*AFW -Alternate Feed Water

• CNS-CatawbaNuclearStation

• MNS -McGuire Nuclear Station

• MOV-MotorOperatedValve CNS Catawba Nuclear Station*CPT -Control Power Transformer

• CSR -Cable Spreading Room

• FAQ -Frequently Asked QuestionMOV Motor Operated Valve*NEI -Nuclear Energy Institute

• NRC -Nuclear Regulatory Commission

• OE -Operating Experience

• FPRA -Fire Probabilistic Risk Assessment

• FRE -Fire Risk Evaluation

• FSA -Fire Safety Analysis F&OFtdObti*PORV -Power Operated Relief Valve

• RAI -Request for Additional Information

• RCP -Reactor Coolant Pump RNPRbiNlPlt*F&O -F ac t s an d Observa ti ons*HEAF -High Energy Arcing Fault

• HRR -Heat Release Rate

• LAR-LicenseAmendmentRequest

• RNP -R o bi nson N uc l ear Pl an t*SSA -Safe Shutdown Analysis

• TDEFWP -Turbine Driven Emergency FeedwaterPump LAR License Amendment Request*LERF -Large Early Release Frequency

• LOOP -Loss of Offsite Power

• UAM -Un-reviewed Analytical Method

• VFDR -Variance From Deterministic Requirements 4

Fleet Transition to NFPA 805MilestonesCNSMNSRNP LAR09/30/201309/30/201309/30/2013SafetyEvaluation09/30/201509/30/201509/30/2015NFPA 805 Program Implementation03/31/201603/31/201603/31/2016 5

LAR Document Submittal

• Using Current Industry LAR Template

-NEI Incorporating Generic RAIs

• Incorporating Lessons Learned

-Current Generic RAIs

-Current Industry NFPA 805 LAR Submittals and RAIsInternalOEfrompreviousplantsubmittalsreviewsand

-Internal OE from previous plant submittals , reviews , and implementation 6

Catawba Nuclear Station 7

Catawba Project Status

• Traditional Fire Protection Elements

-AttachmentL

-NFPA805Chapter3RequirementsforApprovalAttachment L NFPA 805 Chapter 3 Requirements for Approval (10CFR50.48(c)(2)(vii)

• Approval for existing wiring above the control room ceiling

• ReactorCoolantPumpOilMistingReactor Coolant Pump Oil Misting-No Attachment T requests -Clarification of Prior NRC Approvals

• FRE status fl-FPRA Quanti fication Comp lete*CNS meets the requirements of acceptability for RG-1.174

-Defense-in-Depth actions in review

-Recovery Action

• Local Trip of Reactor Coolant Pumps

• Local throttling of Emergency FeedwaterFlow 8

Catawba Project Status (continued)

• LAR development started

• Proposed Modifications

-Breaker Coordination modifications

-Inverter cable re-route

-VCT Outlet Valve spurious closure issue resolved by modificationmodification

-Additional modifications may result from FRE DID review or Chapter 3 required systems code review

• Completed Modifications

-4 Breaker Coordination modifications 9

Catawba PRA

• InternalEventsInternal Events-NEI 00-02 Internal Events Peer Review March 2002

-Internal Gap Assessment to ASME/ANS PRA Standard as endorsed by RG 1.200

• Performed in 2008

• PerformedtoRG1200Revision1

• Performed to RG 1.200 Revision 1-LAR technical adequacy statement will address any deltas to RG 1.200 Revision 2FocusedLERFPeerReviewinDecember2012(NEI05 04)-Focused LERF Peer Review in December 2012 (NEI 05-04)-F&Os from these reviews will be dispositionedin the LAR for Fire PRA impact 10 Catawba Fire PRA

• Full Scope Peer Review in 2010

• F&Os will be addressed in LAR

• NR/CR-6850/ EPRI 108239 methods used

• Fire Modeling methods per NR/CR-6850/ EPRI 108239 *Removed credit for electrical cabinet treatment refinement

• Well sealed Motor Control Centers 11 CNS Deviations from NRC-Accepted FPRA MethodsMethods*Credit for administrative controls (transients)

• Credit for hot short duration failure probabilities for DC circuits 12 Catawba Fire PRA SensitivitiesSensitivityFPRA CDF/LERFVFDR RiskCredit for Admin Controls (Transients)YesYesIgnition Frequency (FAQ-48)YesYesHot Short Duration (DC)YesNo

11) It is not practical to vary the hot short duration credit for the deterministic variant and deterministic compliant case for each fire area; however, the impact on VFDR Risk may be estimated from the overall impact on FPRA CDF/LERF and the scope of VFDRs.

13 Catawba Project Summary

• NUREG-0800 non-compliances identified

-Compensatory actions implemented as needed

• NRC Fire Protection Triennial Inspection

-Scheduled for April 2013 14 McGuire Nuclear Station 15 McGuire Project Status

• Traditional Fire Protection Elements

-AttachmentL

-NFPA805Chapter3RequirementsforApprovalAttachment L NFPA 805 Chapter 3 Requirements for Approval (10CFR50.48(c)(2)(vii)

• Approval for existing wiring above the control room ceiling

• Reactor Coolant Pump Oil Misting

-No Attachment T requests -Clarification of Prior NRC Approvals

• FRE status

-FPRA Quantification CompleteFPRAQuantificationComplete

• MNS meets the requirements of acceptability for RG-1.174

-FRE Defense-in-Depth review complete

-Recover y Action y*Local Trip of Reactor Coolant Pumps

• Local throttling of Emergency FeedwaterFlow

• Local operation of the PressurizerHeaters 16 McGuire Project Status (continued)

• LAR development in progress

• Proposed Modifications

-Eliminate spurious operation of TDEFWP Suction Valve

-Modify condensate drain from containment to improve overall LERF

• CompletedModifications

• Completed Modifications

-Current Transformer Modification

-PressurizerHeaterModificationPressurizerHeater Modification 17 McGuire PRA

• InternalEventsInternal Events-NEI 00-02 Internal Events Peer Review October 2000

-Internal Gap Assessment to ASME/ANS PRA standard as endorsed by RG 1.200

• Performed in 2008

• PerformedtoRG1200Revision1

• Performed to RG 1.200 Revision 1-LAR technical adequacy statement will address any deltas to RG 1.200 Revision 2FocusedLERFPeerReviewinDecember2012(NEI05 04)-Focused LERF Peer Review in December 2012 (NEI 05-04)-F&Os from these reviews will be dispositionedin the LAR for fire PRA impact 18 McGuire Fire PRA

• Full Scope Peer Review in 2009

• F&Os will be addressed in LAR

• NR/CR-6850/ EPRI 108239 methods used

• Fire Modeling methods per NR/CR-6850/ EPRI 108239 *Removed credit for electrical cabinet treatment refinement

• Well sealed Motor Control Centers 19 MNS Deviations from NRC-Accepted FPRA MethodsMethods*Credit for hot short duration failure probabilities for DCii DC c ircu i ts 20 McGuire Fire PRA SensitivitiesSensitivityFPRA CDF/LERFVFDR RiskHot Short Duration (DC)YesNo 1 ()Ignition Frequency (FAQ-48)YesYes1) It is not practical to vary the hot short duration credit for the deterministic variant and deterministic compliant case for each fire area; however, the impact on VFDR Risk may be estimated from the overall impact on FPRA CDF/LERF and the scope of VFDRs.

21 McGuire Project Summary

• Appendix R non-compliances identified

-Compensatory actions implemented as needed

• Completed NRC Fire Protection Triennial Inspection

-February 2013

-No significant findings 22 Robinson Nuclear Plant 23 Robinson Project Status

• Traditional Fire protection Elements

-AttachmentL

-NFPA805Chapter3RequirementsforApprovalAttachment L -NFPA 805 Chapter 3 Requirements for Approval (10CFR50.48(c)(2)(vii)

• Approval for existing wiring above control room ceiling

-No Attachment T re quests -Clarification of Prior NRC A pprovals q pp*FSA development starting in late April

-FRE is performed as part of FSA development

-Defense-in-Depthactionsinreview

-Defense-in-Depth actions in review-FPRA Quantification Revision in Process

• RNP meets the requirements of acceptability for RG-1.174

• LARDevelopmentStartinginMay

• LAR Development Starting in May*Modifications

-Potential Modifications Identified

-Final Scope After Fire PRA and FSAs are Completed 24 Robinson Proposed Modifications

• Incipient Detection

• Protect MOVs from IN 92-18 Hot Short Failure

• Electrically Coordinate Power Supplies

• HEAF mitigation modification in E1/E2 Switchgear room*Protect Shutdown Valves

• Credit 4 thTrain of AFW

• Credit Westinghouse RCP Shutdown Seal

• Credit the Diesel Generators on the DeepwellPumps 25 Robinson Completed ModificationsAuto Start/Auto Load of Dedicated Shutdown Diesel Generator on Loss of All AC Power Auto Reload of Battery Chargers on a LOOPBackup Instrument Air for Charging Pumps Speed Control PressurizerPORV & Char g in g Pum p Make-u p Modificationggp pReplacement of HemycFire Barrier Wrap Emergency Lighting Modifications Evaluation and Modifications of the MOVs for IN92-18Installation of Fire Walls Between Transformers and Between Transformers And Turbine Building Ke y Locked Isolation Switch in Control Room to Isolate DC Electrical Power to Ke y yyAuxiliary Panels Protect the E-Bus Incoming Line Breakers from Spurious Operations for a Postulated Fire in the Turbine Bldg. Cable Rerouting to Protect Safe Shutdown Equipment 26 Robinson PRA

• Internal Events

-Full Scope ASME/ANS PRA Standard Peer Review in October 2009

-F&Oswillbe dispositionedintheLARforfirePRAimpact

-F&Os will be dispositioned in the LAR for fire PRA impact 27 Robinson Fire PRA Overview

• Full Scope Peer Review in 2013

• F&Os being addressed in FPRA revision

-Documented in LAR

• NR/CR-6850/ EPRI 108239 methods used 28 Robinson Fire PRA Overview (Continued)(Continued)

• Credit taken for Flame Retardant Coatin g g-IntumasticInstalled on Thermoplastic Cable

• Unit 2 Cable Spread Room (CSR)/2Sih*E1/E 2 S w i tc hgear Room*Incipient Detection InCabinetInstallationCreditperFAQ08 0046-In-Cabinet Installation -Credit per FAQ 08-0046*Main Control Boards

• I & C Racks

• Safeguards Cabinets

-Area Wide -Normal Detection Credit

• Unit2CableSpreadRoom

• Unit 2 Cable Spread Room 29 RNP Deviations from NRC-Accepted FPRAMethods FPRA Methods*For closed-cabinet MCCs:

-A severity factor of 0.1 is applied, where 90% of fires are contained within the MCC

-HRRseverityfactorsaretreatedindependentlysimilarto

-HRR severity factors are treated independently , similar to other cabinets

-Method was used to Address RAI 5-32 for the HNP NFPA 805 Application

• BNP LAR Audit RAIs under evaluation for applicability tRNP a t RNP 30 Robinson Fire PRA SensitivitiesSensitivityFPRA CDF/LERFVFDR RiskCPT credit for spurious failuresYesYesIitiF(FAQ 48)Y Y I gniti on F requency (FAQ-48)Y es Y esIncipient Detection (FAQ-46)YesYes 31 Robinson PRA Considerations

• Re-evaluate treatment of 480V Switchgear

-Amptectorsare used at RNP on E1/E2 Switchgears

-Reviewing HEAF data for 480V SwitchgearNotagenericisse

-Not a generic iss u e 32 Robinson Project Summary

• Developing committed modifications final scope and hdli sc h e d u li ng*Appendix R non-compliances identified lddd-Compensatory actions imp lemente d as nee d e d*Completed NRC Fire Protection Triennial InspectionNb2012-N ovem b er 2012-No significant findings 33 Questions 34