ML13127A080
| 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: |
| References | |
| TAC MF0956 | |
| Download: ML13127A080 (34) | |
Text
Fleet Fire Protection Program g
NFPA 805 National Fire Protection Association NFPA 805 Pre-LAR Application for CNS, MNS, RNP Jeffery Ertman David Goforth - NFPA 805 Project Managers Jeffery Ertman, David Goforth - NFPA 805 Project Managers April 18, 2013
Agenda
- NFPA 805 Transition Project Overview j
- License Amendment Request Overview
- Fire PRA Overview 2
Participants
- Jeffery Ertman - NFPA 805 Project Manager D
id G f th NFPA 805 P j
t M
- David Goforth - NFPA 805 Project Manager
- Donna Alexander - Manager Fleet Regulatory Affairs
- Jeff Robertson - Manager Regulatory Affairs
- Julius Bryant - Regulatory Affairs y
g y
- Sarah Chisholm - PRA Engineer
- Kelly Lavin - Site Technical Lead
- Al Maysam - Regulatory Affairs
- Jamie McCrory - PRA Engineer B
di W PRA E i
- Brandi Weaver - PRA Engineer 3
Acronyms AFW - Alternate Feed Water CNS - Catawba Nuclear Station MNS - McGuire Nuclear Station MOV - Motor Operated Valve CNS Catawba Nuclear Station CPT - Control Power Transformer CSR - Cable Spreading Room FAQ - Frequently Asked Question MOV 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&O F
t d Ob ti PORV - Power Operated Relief Valve RAI - Request for Additional Information RCP - Reactor Coolant Pump RNP R bi N
l Pl t
F&O - Facts and Observations HEAF - High Energy Arcing Fault HRR - Heat Release Rate LAR - License Amendment Request RNP - Robinson Nuclear Plant SSA - Safe Shutdown Analysis TDEFWP - Turbine Driven Emergency Feedwater Pump 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 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 reviews and
- Internal OE from previous plant submittals, reviews, and implementation 6
Catawba Nuclear Station 7
Catawba Project Status
- Traditional Fire Protection Elements
- Attachment L - NFPA 805 Chapter 3 Requirements for Approval 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 Reactor Coolant Pump Oil Misting
- No Attachment T requests - Clarification of Prior NRC Approvals
- FRE status f
l
- FPRA Quantification Complete
- 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 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 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 Revision 1
- Performed to RG 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)
- Focused LERF Peer Review in December 2012 (NEI 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 Methods
- Credit for administrative controls (transients)
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 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 FPRA Quantification Complete
- FRE Defense-in-Depth review complete
- Recovery Action y
- 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
- Completed Modifications
- Current Transformer Modification
- Pressurizer Heater Modification Pressurizer Heater Modification 17
McGuire PRA
- Internal Events 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 Revision 1
- Performed to RG 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)
- Focused LERF Peer Review in December 2012 (NEI 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 Methods
DC circuits 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 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 - Clarification of Prior NRC Approvals q
pp
- FSA development starting in late April
- FRE is performed as part of FSA development
- Defense-in-Depth actions in review
- Defense-in-Depth actions in review
- FPRA Quantification Revision in Process
- LAR Development Starting in May
- LAR Development Starting in May
- Modifications
- Potential Modifications Identified
- Final Scope After Fire PRA and FSAs are Completed 24
Robinson Proposed Modifications
- Incipient Detection
- 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 & Charging Pump Make-up Modification g g p
p 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 Key Locked Isolation Switch in Control Room to Isolate DC Electrical Power to Key y
y 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
- 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 Coating
- Intumastic Installed on Thermoplastic Cable
- Unit 2 Cable Spread Room (CSR)
/ 2 S i h
- E1/E2 Switchgear Room
- Incipient Detection In Cabinet Installation Credit per FAQ 08 0046
- In-Cabinet Installation - Credit per FAQ 08-0046
- Main Control Boards
- I & C Racks
- Safeguards Cabinets
- Area Wide - Normal Detection Credit
- Unit 2 Cable Spread Room
- Unit 2 Cable Spread Room 29
RNP Deviations from NRC-Accepted FPRA Methods 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 similar to
- HRR severity factors are treated independently, similar to other cabinets
- Method was used to Address RAI 5-32 for the HNP NFPA 805 Application
Robinson Fire PRA Sensitivities Sensitivity FPRA CDF/LERF VFDR Risk CPT credit for spurious failures Yes Yes I
iti F
(FAQ 48)
Y Y
Ignition Frequency (FAQ-48)
Yes 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 e
- Not a generic issue 32
Robinson Project Summary
- Developing committed modifications final scope and h d li scheduling
- Appendix R non-compliances identified l
d d d
- Compensatory actions implemented as needed
- Completed NRC Fire Protection Triennial Inspection N
b 2012
- November 2012
- No significant findings 33
Questions 34