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


Text

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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

  • Project NFPA Consultants

- Mark Crompton EPM, NFPA 805 Project Manager

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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,t ion Project Overview

- License Condition being revised

- 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

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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

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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 CENG* ~-~- f

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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

- Fire PRA followed guidance in NUREG/CR 6850 as supplemented by FAQs.

- 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

  • No un-reviewed methods used

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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.

Tornad oes/H igh 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

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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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