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 Programg NFPA 805 National Fire Protection Association NFPA 805 Pre-LAR Application for CNS, MNS, RNP Jeffery Ertman Ertman, David Goforth - NFPA 805 Project Managers April 18, 2013

Agenda

• NFPA 805 Transition Project j Overview

• License Amendment Request Overview

• Fire PRA Overview 2

Participants

• Jeffery Ertman - NFPA 805 Project Manager

• D id G David Goforth f th - NFPA 805 Project P j t Manager M

• Donna Alexander - Manager Fleet Regulatory Affairs

• Bob Rishel - PRA Manager

• Jeff Robertson - Manager Regulatory Affairs

• Julius Bryant y - Regulatory g y Affairs

• Sarah Chisholm - PRA Engineer

• Kelly Lavin - Site Technical Lead

• Al Maysam - Regulatory Affairs

• Jamie McCrory - PRA Engineer

• B di W Brandi Weaver - PRA Engineer E i 3

Acronyms

• AFW - Alternate Feed Water

• MNS - McGuire Nuclear Station

• CNS - Catawba Nuclear Station

• MOV - Motor Operated Valve

• CPT - Control Power Transformer

• NEI - Nuclear Energy Institute

• CSR - Cable Spreading Room

• NRC - Nuclear Regulatory Commission

• FAQ - Frequently Asked Question

• OE - Operating Experience

• FPRA - Fire Probabilistic Risk Assessment

• PORV - Power Operated Relief Valve

• FRE - Fire Risk Evaluation

• RAI - Request for Additional Information

• FSA - Fire Safety Analysis

• RCP - Reactor Coolant Pump

• F&O - Facts F t and d Ob Observations ti

• RNP - Robinson R bi N Nuclear l Pl Plantt

• HEAF - High Energy Arcing Fault

• SSA - Safe Shutdown Analysis

• HRR - Heat Release Rate

• TDEFWP - Turbine Driven Emergency

• LAR - License Amendment Request Feedwater Pump

• LERF - Large Early Release Frequency

• UAM - Un-reviewed Analytical Method

• LOOP - Loss of Offsite Power

• VFDR - Variance From Deterministic Requirements 4

Fleet Transition to NFPA 805 Milestones CNS MNS RNP LAR 09/30/2013 09/30/2013 09/30/2013 Safety Evaluation 09/30/2015 09/30/2015 09/30/2015 NFPA 805 Program Implementation 03/31/2016 03/31/2016 03/31/2016 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 RAIs

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

Catawba Nuclear Station 7

Catawba Project Status

• Traditional Fire Protection Elements

- Attachment L - NFPA 805 Chapter 3 Requirements for Approval (10 CFR 50.48(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 f Complete l

• 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 Feedwater Flow 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 modification

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

• Completed Modifications

- 4 Breaker Coordination modifications 9

Catawba PRA

• Internal 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

• Performed to RG 1.200 1 200 Revision 1

- LAR technical adequacy statement will address any deltas to RG 1.200 Revision 2

- Focused LERF Peer Review in December 2012 (NEI 05-04) 05 04)

- F&Os from these reviews will be dispositioned in 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 Methods

• Credit for administrative controls (transients)

• Credit for hot short duration failure probabilities for DC circuits 12

Catawba Fire PRA Sensitivities Sensitivity FPRA CDF/LERF VFDR Risk Credit for Admin Controls (Transients) Yes Yes Ignition Frequency (FAQ-48) Yes Yes Hot Short Duration (DC) Yes No1

1) 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

- Attachment L - NFPA 805 Chapter 3 Requirements for Approval (10 CFR 50.48(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 Complete

• MNS meets the requirements of acceptability for RG-1.174

- FRE Defense-in-Depth review complete

- Recoveryy Action

• Local Trip of Reactor Coolant Pumps

• Local throttling of Emergency Feedwater Flow

• Local operation of the Pressurizer Heaters 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

• Completed Modifications

- Current Transformer Modification

- Pressurizer Heater Modification 17

McGuire PRA

• Internal 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

• Performed to RG 1.200 1 200 Revision 1

- LAR technical adequacy statement will address any deltas to RG 1.200 Revision 2

- Focused LERF Peer Review in December 2012 (NEI 05-04) 05 04)

- F&Os from these reviews will be dispositioned in 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 Methods

• Credit for hot short duration failure probabilities for DC circuits i i 20

McGuire Fire PRA Sensitivities Sensitivity FPRA CDF/LERF VFDR Risk Hot Short Duration (DC) Yes No1 Ignition Frequency (FAQ-48)

( ) Yes Yes

1) 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

- Attachment L - NFPA 805 Chapter 3 Requirements for Approval (10 CFR 50.48(c)(2)(vii)

• Approval for existing wiring above control room ceiling

- No Attachment T requests q - Clarification of Prior NRC Approvals pp

• FSA development starting in late April

- FRE is performed as part of FSA development

- Defense-in-Depth actions in review

- FPRA Quantification Revision in Process

• RNP meets the requirements of acceptability for RG-1.174

• 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 4th Train of AFW

• Credit Westinghouse RCP Shutdown Seal

• Credit the Diesel Generators on the Deepwell Pumps 25

Robinson Completed Modifications Auto Start/Auto Load of Dedicated Shutdown Diesel Generator on Loss of All AC Power Auto Reload of Battery Chargers on a LOOP Backup Instrument Air for Charging Pumps Speed Control Pressurizer PORV & Chargingg g Pumpp Make-upp Modification Replacement of Hemyc Fire Barrier Wrap Emergency Lighting Modifications Evaluation and Modifications of the MOVs for IN 92-18 Installation of Fire Walls Between Transformers and Between Transformers And Turbine Building Keyy Locked Isolation Switch in Control Room to Isolate DC Electrical Power to Keyy Auxiliary 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&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)

• Credit taken for Flame Retardant Coatingg

- Intumastic Installed on Thermoplastic Cable

• Unit 2 Cable Spread Room (CSR)

• E1/E2

/ 2 SSwitchgear i h Room

• Incipient Detection

- In-Cabinet In Cabinet Installation - Credit per FAQ 08-0046 08 0046

• Main Control Boards

• I & C Racks

• Safeguards Cabinets

- Area Wide - Normal Detection Credit

• Unit 2 Cable Spread Room 29

RNP Deviations from NRC-Accepted FPRA Methods

• For closed-cabinet MCCs:

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

- HRR severity factors are treated independently, 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 att RNP 30

Robinson Fire PRA Sensitivities Sensitivity FPRA CDF/LERF VFDR Risk CPT credit for spurious failures Yes Yes I iti Ignition F Frequency (FAQ (FAQ-48)

48) Y Yes Y Yes Incipient Detection (FAQ-46) Yes Yes 31

Robinson PRA Considerations

• Re-evaluate treatment of 480V Switchgear

- Amptectors are used at RNP on E1/E2 Switchgears

- Reviewing HEAF data for 480V Switchgear

- Not a generic iss issuee 32

Robinson Project Summary

• Developing committed modifications final scope and scheduling h d li

• Appendix R non-compliances identified

- Compensatory actions implemented l d as needed d d

• Completed NRC Fire Protection Triennial Inspection

- November N b 2012

- No significant findings 33

Questions 34