ML13234A385

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NFPA 805 License Amendment Request Pre-Application Meeting with NRC Staff
ML13234A385
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 08/19/2013
From:
Calvert Cliffs, Constellation Energy Nuclear Group, EDF Group
To:
Office of Nuclear Reactor Regulation
Morgan N
References
Download: ML13234A385 (19)
v • d • e


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License Amendment Request

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Pre-Application Meeting with NRC Staff August 19, 2013

Introd uctions

  • CENG Representatives Elliott Flick Gen'l Manager, Fleet Engineering Dave Dellario Manager, Engineering Services Jim McQuighan Project Manager, NFPA 805 Paul Darby Principal Engineer, NFPA 805 Pat Furio Principal Engineer, Licensing Jeff Stone Supervisor, PRA Jim Landale Principal Engineer, PRA Bret Colby Supervisor, Engineering Ch ris Dobry Principal Engineer, Engineering

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Agenda Overview of CCN PP

  • Current Fire Protection Licensing Basis
  • Implementation Overview Summary

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Overview of CCNPP

  • Two PWRs, each rated @ 2737 MWth
  • Combustion Engineering NSSS Commercial operations began in 1975/1977
  • Renewed Operating License issued - expires in 2034/2036

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Current Fire Protection Licensing Basis

  • Branch Technical Position APCSB 9.5-1, Appendix A
  • Current exemptions

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NFPA 805 Transition Project Overview

  • License Amendment Request (LAR) committed submittal date - September 30, 2013
  • Using the Nuclear Energy Institute (NEI) LAR template
  • Web portal will be established to support NRC review

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NFPA 805 Transi,tion Project Overview

- Technical Specifications being revised Reviewed existing exemptions

- Three exemptions will be credited post-NFPA 805 transition

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Compliance with NFPA 80S NFPA 805 Chapter 3 Compliance Review performed using NEI 04-02, Revision 2 guidance as supplemented by FAQ 07-0036 Review documented in B-1 Table (Attachment A of LAR)

Results of review

- 3 Code compliance modifications

- 7 sections are addressed via Attachment L of LAR.

- 96 Sections/sub-sections comply

- 43 Comply with clarifications/EEEEs/required actions 16 Comply by previous NRC approval I ".

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Compliance with NFPA 805

  • Non-Power Operations Review performed using NEI 04-02, Revision 2 guidance as supplemented by FAQ 07-0040 Fire modeling not used to eliminate or reduce pinch points Recovery actions are not credited Results of review
  • All success paths identified
  • Pinch points identified
  • Component list associated with maintaining Key Safety Functions
  • Recommendations to manage Fire Risk ci:~'

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Compliance with NFPA 805

  • Radioactive Release Review performed using NEI 04-02, Revision 2 guidance as supplemented by FAQ 09-0056 Plant evaluated on a room by room basis Credit engineering controls and CENG offsite dose calculation for gaseous and liquid effluents Reviewed Pre-Fire Plan and training materials to clarify monitoring and control requirements
  • Minor Pre-Fire Plan/procedure changes and training program revisions in progress.

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Compliance with NFPA-80S

  • Nuclear Safety Capability Assessment Review performed using NEI 04-02, Revision 2 guidance as supplemented by FAQ 08-0054 Safe and Stable defined as Hot Standby Common Enclosure review (Protection)

Common Power Supply review (Coordination)

Fire Area review Multiple Spurious Operations review Effects of suppression activities review Results of review

  • 21 Fire Areas to be transitioned deterministically
  • 46 Fire Areas to be transitioned using Fire Risk Evaluations
  • All VFDRs addressed I

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Compliance with NFPA 805 Recovery Actions Feasibility Assessment Review performed using NEI 04-02, Revision 2 guidance as supplemented by FAQ 07-0030 Primary Control Station (Other than main Control Room)

  • Alternate Shutdown Panels 1(2)C43 Recovery actions listed in LAR Attachment G

- There was over 85% reduction in operator recovery actions

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Compliance with NFPA 805

  • Monitoring Program Following FAQ 10-0059, Revision 5 guidance NSCA and Fire PRA components

- If any new functions, will be added to Maintenance Rule Program Non-Power Operation components, radioactive release systems, Fire Protection program components

- To be included in normal system and program health monitoring Fire Protection systems and features Low Safety Significant - normal system/program health monitoring High Safety Significant - NFPA 805 specific monitoring program that uses the Maintenance Rule program software

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PRA Development/Results

  • Internal Events PRA Fire PRA built on a quality Internal Events model Full Internal Events peer review to RG 1.200, Revision 2 in 2010

Full peer review to RG 1.200, Revision 2 in January 2012 Total of 41 Facts & Observations (F&Os) 17 Findings 23 Suggestions 1 Best Practice All F&Os subsequently dispositioned

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PRA Development/Results

  • Overall Plant Risk Post-NFPA 805 Transition Sufficient margin to account for non-quantified hazards Unit 1

.JL Unit 2 Comments CoF LERF CoF LERF Fire PRA quantification with NFPA 3.2E-OS 3.0E-06 3.6E-OS 4.2E-06 80S modifications credited.

Internal Events PRA quantification 1.3E-OS 1.3E-06 1.0E-OS 1.3E~06 with NFPA 80S modifications credited.

IPEEE for COF. Estimate for LERF 1.7E-06 1.SE-OS 2.0E-06 based on 13% of CoF.

Tornadoes/High IPEEE for CoF. Estimate for LERF 4.4E-06 S.7E-07 4.4E-06 S.7E-07 Winds based on 13% of CoF.

Plant-Level Total 6.2E-OS 6.6E-06 6.SE-OS 8.1E-06 Overall risk meets Reg. Guide 1.174 guidance for total plant risk of CDF < 1E-4 / year and LERF < 1E-S / year.

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PRA Development/Results

  • Risk improvement from NFPA 805 modifications Total delta risk for B.65E-6/ryr 6.39E-7/ryr B.B7E-6/ryr 9.0BE-7/ryr plant fire scenarios Internal Events risk 1.74E-6/ryr 2.10E-B/ryr 2.26E-6/ryr 4.60E-B/ryr improvement from modifications Plant delta risk with 6.91E-6/ryr 6.1BE-7/ryr 6.61E-6/ryr B.62E-7/ryr plant modifications Total risk increases <lE-S for CDF and <lE-6 for LERF Delta risk meets criteria for RG 1.174 and NFPA 805 application

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Implementation Overview

  • Modifications Planned 15 Fire PRA related modifications 3 NFPA Code compliance modifications
  • Process/Procedure Changes Fire Brigade response Design change process

- Training Operations alarm procedures, Fire Fighting Strategy Manual, hot work, lower mode (refueling outage),

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Modifications

  • RCP Loss of Seal Cooling alarm and local 13 kV trip of RCPs Electrical modifications: (hot short, grounds, etc)

Reactor vessel head and Pressurizer vents Main Steam Isolation Valve control Steam Generator blowdown control valves Normal sump motor operated valves Hydrogen purge valves Component cooling water heat exchanger flow control valve Pressurizer Power Operated Relief Valves Auxiliary Feedwater steam admission valves Reactor Coolant Pump breaker control 4kV breaker control Cable Spreading Room dampers

  • Cable replacement and lighting transformer protection CENG.

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Summary

  • Complete LAR to be submitted on or before September 30, 2013
  • No un-reviewed methods or deviations from approved Fire PRA methods
  • Modifications will be required and are being planned
  • Transition Schedule Assumes 2 year NRC review Consistent with other submittals Implement procedure/process changes 6 months after SER Completion of modifications for both units following SER approval-April 2018

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