ML13234A385: Difference between revisions
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Calvert Cliffs Nuclear Power Plant | Calvert Cliffs Nuclear Power Plant | ||
~ | ~ | ||
- ~.,....~- NFPA80S | - ~.,....~- NFPA80S | ||
~:~ | ~:~ | ||
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'7 | '7 | ||
"'-:'-~- | "'-:'-~- | ||
~- " ---..> | ~- " ---..> | ||
_ ............... License Amendment Request | _ ............... License Amendment Request | ||
~<).~ | ~<).~ | ||
Pre-Application Meeting with NRC Staff August 19, 2013 | Pre-Application Meeting with NRC Staff August 19, 2013 | ||
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~- -c-: --- - ~ | ~- -c-: --- - ~ | ||
=.wE "'" | =.wE "'" | ||
I)~: ~::. - -- ':.*~ eDF 2 | I)~: ~::. - -- ':.*~ eDF 2 | ||
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<'"" .- . . .."-~- | <'"" .- . . .."-~- | ||
J~.- " -.,. | J~.- " -.,. | ||
~f " eOF 4 | |||
~f " eOF | |||
4 | |||
Current Fire Protection Licensing Basis | Current Fire Protection Licensing Basis | ||
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&.w ..*..eDF | &.w ..*..eDF | ||
~~ | ~~ | ||
6 | 6 | ||
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- Reviewed existing exemptions | - Reviewed existing exemptions | ||
- Three exemptions will be credited post-NFPA 805 transition | - Three exemptions will be credited post-NFPA 805 transition | ||
~. | ~. | ||
_ 19".:-" | _ 19".:-" | ||
,~- | ,~- | ||
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CENG_ | CENG_ | ||
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lOinI\llllltura af- ~ | |||
- ".~eDf | - ".~eDf | ||
~'" | ~'" | ||
I | I | ||
.'. 7 | .'. 7 | ||
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* Recommendations to manage Fire Risk ci:~' | * Recommendations to manage Fire Risk ci:~' | ||
CENGw I | CENGw I | ||
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~. - | ~. - | ||
Line 193: | Line 173: | ||
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Line 228: | Line 206: | ||
- Recovery actions listed in LAR Attachment G | - Recovery actions listed in LAR Attachment G | ||
- There was over 85% reduction in operator recovery actions | - There was over 85% reduction in operator recovery actions | ||
:;; | :;; | ||
;J#Z7- | ;J#Z7- | ||
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1-~- -__ | 1-~- -__ | ||
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CENG. | CENG. | ||
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eDF | eDF | ||
~-" , . | ~-" , . | ||
12 | 12 | ||
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CENG~ | CENG~ | ||
8~1~~ofl __________, | 8~1~~ofl __________, | ||
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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. | 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. | ||
CENG.. 1 | CENG.. 1 | ||
_.... ~;.I*7~~ | _.... ~;.I*7~~ | ||
~- 1I)oont wrdUre 01'- - - - - , | ~- 1I)oont wrdUre 01'- - - - - , | ||
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.~" .:?~. -- -"'~ | .~" .:?~. -- -"'~ | ||
"i ~ - - -- - - | "i ~ - - -- - - | ||
"*~eOF | "*~eOF | ||
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1"-'+*-" ':"-' | 1"-'+*-" ':"-' | ||
CENG. | CENG. | ||
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01- - - - -, | |||
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I 16 | I 16 | ||
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AOPs/recovery actions, etc. | AOPs/recovery actions, etc. | ||
,::- - ~ | ,::- - ~ | ||
1 | 1 | ||
_r~' | _r~' | ||
-~- - | -~- - | ||
-c;- - - -~' | -c;- - - -~' | ||
CENG.. | CENG.. | ||
.;..; | .;..; | ||
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* Cable replacement and lighting transformer protection | * Cable replacement and lighting transformer protection | ||
- .-~..:- CENG. ..,. WI'"' | - .-~..:- CENG. ..,. WI'"' | ||
I | I | ||
_.eo L | _.eo L | ||
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CENG. . -, | CENG. . -, | ||
~-"- . | ~-"- . | ||
-' .¢;~ ---:-~'. 8 jcont 1IeI1tuJ8 01'-------, | -' .¢;~ ---:-~'. 8 jcont 1IeI1tuJ8 01'-------, | ||
'i~:--- ' -- - | 'i~:--- ' -- - |
Revision as of 03:18, 6 February 2020
ML13234A385 | |
Person / Time | |
---|---|
Site: | Calvert Cliffs ![]() |
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) | |
Text
CENG~
a joint venture of------__.
Constellation ..* ~ eDF Energy' ~,.
Calvert Cliffs Nuclear Power Plant
~
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_ ............... License Amendment Request
~<).~
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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CENG..
a )CIn1-nure 01._ _ _ _ __ ~-:-l-
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Agenda Overview of CCN PP
- Current Fire Protection Licensing Basis
- NFPA 805 Transition Project Overview
- Compliance with NFPA 805
- Probabilistic Risk Assessment Development/Results
- Implementation Overview Summary
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CENG.. I a joont ventum o f - -_ _ _,
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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
- Fire Protection Program License Condition
- 10 CFR 50.48(a) and (b)
- 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
- Fire Protection Program Transition
- 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:~'
CENGw I
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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
- 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.
CENG.. 1
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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),
AOPs/recovery actions, etc.
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CENG..
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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. ..,. WI'"'
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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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