ML13234A385: Difference between revisions
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| number = ML13234A385 | | number = ML13234A385 | ||
| issue date = 08/19/2013 | | issue date = 08/19/2013 | ||
| title = | | title = NFPA 805 License Amendment Request Pre-Application Meeting with NRC Staff | ||
| author name = | | author name = | ||
| author affiliation = Calvert Cliffs Nuclear Power Plant, LLC, Constellation Energy Nuclear Group, LLC, EDF Group | | author affiliation = Calvert Cliffs Nuclear Power Plant, LLC, Constellation Energy Nuclear Group, LLC, EDF Group | ||
Line 9: | Line 9: | ||
| docket = 05000317, 05000318 | | docket = 05000317, 05000318 | ||
| license number = | | license number = | ||
| contact person = Morgan N | | contact person = Morgan N | ||
| document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | ||
| page count = 19 | | page count = 19 | ||
| project = | |||
| stage = Meeting | |||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:CENG~ | ||
Constellation Energy' . | a joint venture of------__. | ||
Constellation ..* ~ eDF Energy' ~,. | |||
-Elliott Flick Gen'l Manager, Fleet Engineering | Calvert Cliffs Nuclear Power Plant | ||
-Dave Dellario | ~ | ||
- ~.,....~- NFPA80S | |||
-Jim McQuighan Project Manager, NFPA 805 -Paul Darby Principal | ~:~ | ||
-C-'.II, _~ | |||
'7 | |||
-Jeff Stone Supervisor, PRA -Jim Landale Principal | "'-:'-~- | ||
~- " ---..> | |||
-Ch ris Dobry Principal | _ ............... License Amendment Request | ||
~<).~ | |||
-Mark Crompton EPM, NFPA 805 Project Manager CENG.. a )CIn1-nure 01. | 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 | ||
*k -' | - Paul Darby Principal Engineer, NFPA 805 | ||
- Pat Furio Principal Engineer, Licensing | |||
-License Condition being revised -Technical Specifications being revised -Reviewed existing exemptions | - Jeff Stone Supervisor, PRA | ||
-Three exemptions will be credited post-NFPA 805 transition | - Jim Landale Principal Engineer, PRA | ||
_ 19".:-" | - Bret Colby Supervisor, Engineering | ||
-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 | - Ch ris Dobry Principal Engineer, Engineering | ||
-7 sections are addressed via Attachment L of -96 Sections/sub-sections -43 Comply with clarifications/EEEEs/required | * Project NFPA Consultants | ||
-16 Comply by previous NRC I " . .- | - Mark Crompton EPM, NFPA 805 Project Manager | ||
a joInI venture 01' | ~ -- | ||
-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 | -~ f~~"':: - | ||
-Results of review | CENG.. | ||
a )CIn1-nure 01._ _ _ _ __ ~-:-l- | |||
~- -c-: --- - ~ | |||
=.wE "'" | |||
I)~: ~::. - -- ':.*~ eDF 2 | |||
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 | |||
/;...;7- | |||
<~- | |||
CENG.. I a joont ventum o f - -_ _ _, | |||
~-"- k | |||
~;J ~~ -~ --:~~~- - .r | |||
- "!-'eor: | |||
01' 3 | |||
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 | |||
-'7- | |||
- --~-- | |||
...:>-~ | |||
CENG. | |||
8)oint VEWTlure 011- _ _ _ __ | |||
I | |||
...... -:*t | |||
<'"" .- . . .."-~- | |||
J~.- " -.,. | |||
~f " eOF 4 | |||
Current Fire Protection Licensing Basis | |||
* Fire Protection Program License Condition | |||
* 10 CFR 50.48(a) and (b) | |||
* Draft General Design Criterion 3 10 CFR 50, Appendix R | |||
* Branch Technical Position APCSB 9.5-1, Appendix A | |||
* Current exemptions | |||
.. ~7~ CENG.. I | |||
- --~- ..:..---'*k Iii ~~- - -.' ---- | |||
'. ,,)001II8I'I1U19 "'- - - - - - , | |||
~ | |||
~ ..f"' eDf | |||
~ -" 5 | |||
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 | |||
--~~- | |||
~~7--- CENG_ | |||
a joini venliml 01_ _ __ _ -, | |||
I | |||
~~ - k | |||
'\:.:" ~: --""- ,,~ | |||
~- | |||
.;.' - ' ~. - - | |||
&.w ..*..eDF | |||
~~ | |||
6 | |||
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 | |||
~. | |||
_ 19".:-" | |||
,~- | |||
,~~-.. | |||
s-: | |||
._.~!z,;;. | |||
CENG_ | |||
B lOinI\llllltura af- ~ | |||
- ".~eDf | |||
~'" | |||
I | |||
.'. 7 | |||
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 | |||
. ~-,- - CENG.. I ". | |||
,-::.-'~--- | |||
" -c""': -.~--~-. | |||
a joInI venture 01'_ _ _ _--, ~~-k 1 ~'- ~ . ~ <1-. | |||
- J - .,y ..*.. eDf 8 | |||
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 | * All success paths identified | ||
* Pinch points identified | * Pinch points identified | ||
* Component list associated with maintaining Key Safety Functions | * Component list associated with maintaining Key Safety Functions | ||
* Recommendations to manage Fire Risk | * Recommendations to manage Fire Risk ci:~' | ||
_ ---..' ....eDf -9 | CENGw I | ||
"';.'~- | |||
-Plant evaluated on a room by room -Credit engineering controls and CENG offsite 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. | ~ - -.~ - -.;,.. ajant ventuteo! _ ~ '~-' | ||
* k | |||
-Common Power Supply review (Coordination) | ;~- . - ..' ....eDf | ||
Fire Area review -Multiple Spurious Operations review -Effects of suppression activities Results of | .-~ | ||
9 | |||
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. | |||
4#9:"'::' | |||
-~.,- CENG. ..; . ~-wI | |||
*i~"':~'* | |||
j~.-' | |||
:-c:- * -., -~~ | |||
~ - - | |||
a joint venture of _ ~ | |||
-EI-wY ~'''eDF | |||
-- 4' 10 | |||
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 | * 21 Fire Areas to be transitioned deterministically | ||
* 46 Fire Areas to be transitioned using Fire Risk Evaluations | * 46 Fire Areas to be transitioned using Fire Risk Evaluations | ||
* All VFDRs addressed I '* | * All VFDRs addressed | ||
* Enefn | ..,~~ | ||
-Review performed using NEI 04-02, Revision 2 guidance as supplemented by FAQ 07-0030 -Primary Control Station (Other than main Control Room) | CENG.. I '* | ||
* Alternate Shutdown Panels 1(2)C43 -Recovery actions listed in LAR Attachment G -There was over 85% reduction in operator recovery actions | ~~- | ||
~ --~- | |||
a joht _01,- -___ ~~ - -.t | |||
* Monitoring Program -Following FAQ 10-0059, Revision 5 guidance NSCA and Fire PRA components | ('-., *Cn | ||
-If any new functions, will be added to Maintenance Rule Program Non-Power Operation components, radioactive release systems, Fire Protection program components | * j~-:- _ r Enefn ~~eDF 11 | ||
-To be included in normal system and program health monitoring Fire Protection systems and features | |||
-Low Safety Significant | Compliance with NFPA 805 Recovery Actions Feasibility Assessment | ||
-normal system/program health monitoring | - Review performed using NEI 04-02, Revision 2 guidance as supplemented by FAQ 07-0030 | ||
-High Safety Significant | - Primary Control Station (Other than main Control Room) | ||
-NFPA 805 specific monitoring program that uses the Maintenance Rule program software CENG* | * Alternate Shutdown Panels 1(2)C43 | ||
- Recovery actions listed in LAR Attachment G | |||
- There was over 85% reduction in operator recovery actions | |||
;J#Z7- | |||
-~-,~- | |||
~: | |||
1-~- -__ | |||
~ | |||
CENG. | |||
a pot venture 011- _ _ _---, | |||
~ | |||
~ | |||
-'~ | |||
~~ | |||
eDF | |||
~-" , . | |||
12 | |||
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 | |||
,,~7 __ | |||
--~- a janl..,lUf1l at_ _ _ _ ~ | |||
<. ~ - --~ - .:~- | |||
5 ~:- - ~ -- .r. ....':.-. eoF 13 | |||
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 | * 17 Findings | ||
* 23 Suggestions | * 23 Suggestions | ||
* 1 Best | * 1 Best Practice | ||
-All F&Os subsequently | - All F&Os subsequently dispositioned | ||
* No un-reviewed methods used -- | * No un-reviewed methods used | ||
__________ | - - - -~..:- | ||
'- .::~ ~~. ---'- >. | |||
-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. | CENG~ | ||
Internal Events PRA quantification 1.3E-OS 1.3E-06 1.0E-OS with NFPA 80S modifications credited. | 8~1~~ofl __________, | ||
IPEEE for COF. Estimate for LERF 1.7E-06 1.SE-OS 2.0E-06 based on 13% of | ,..,. -"'-.t J~---::'" - | ||
~ ...*4eDF | |||
-- | -...- J' 14 | ||
----- | |||
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 plant fire 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 | * Overall Plant Risk Post-NFPA 805 Transition | ||
-Total risk increases | - 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. | ||
<lE-S for CDF and <lE-6 for LERF -Delta risk meets criteria for RG 1.174 and NFPA 805 application -- | 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. | |||
-3 NFPA Code compliance modifications Process/Procedure Changes -Fire Brigade response | CENG.. 1 | ||
-Design change process -Training | _.... ~;.I*7~~ | ||
-Operations alarm procedures, Fire Fighting Strategy Manual, hot work, lower mode (refueling outage), | ~- 1I)oont wrdUre 01'- - - - - , | ||
AOPs/recovery | ~ wr't _. | ||
.~" .:?~. -- -"'~ | |||
"i ~ - - -- - - | |||
(hot short, grounds, -Reactor vessel head and Pressurizer -Main Steam Isolation Valve | "*~eOF | ||
-Steam Generator blowdown control -Normal sump motor operated -Hydrogen purge -Component cooling water heat exchanger flow control -Pressurizer Power Operated Relief Auxiliary Feedwater steam admission -Reactor Coolant Pump breaker 4kV breaker | '" 15 | ||
-Cable Spreading Room Cable replacement and lighting transformer protection | |||
..:.-' 18 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 Transition Schedule | PRA Development/Results | ||
-Assumes 2 year NRC review -Consistent with other submittals | * 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 | ||
-Implement procedure/process changes 6 months after SER -Completion of modifications for both units following SER approval-April 2018 CENG-, .- | - Total risk increases <lE-S for CDF and <lE-6 for LERF | ||
8 jcont 1IeI1tuJ8 01'-------, --...*:-eoF | - Delta risk meets criteria for RG 1.174 and NFPA 805 application | ||
~ | |||
~~ | |||
- - ~"""----- | |||
,~"..~~.~ -.-.-~;. .. | |||
1"-'+*-" ':"-' | |||
CENG. | |||
a IC*l1 ..",ture | |||
--..r 01- - - - -, | |||
..* ... eOF | |||
~ ... | |||
I 16 | |||
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. | |||
,::- - ~ | |||
1 | |||
_r~' | |||
-~- - | |||
-c;- - - -~' | |||
CENG.. | |||
I | |||
-" " 17 | |||
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'"' | |||
I | |||
_.eo L | |||
~";'~ ..:.- ~; ------~ | |||
j~.' ' 18 | |||
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 | |||
.;,1; | |||
-z~ | |||
--\.~- ~ | |||
CENG. . -, | |||
~-"- . | |||
-' .¢;~ ---:-~'. 8 jcont 1IeI1tuJ8 01'-------, | |||
'i~:--- ' -- - | |||
- . . .- ...*:-eoF | |||
.6. | |||
19}} |
Latest revision as of 20:07, 25 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
~
- ~.,....~- NFPA80S
~:~
-C-'.II, _~
'7
"'-:'-~-
~- " ---..>
_ ............... 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
~ --
-~ f~~"':: -
CENG..
a )CIn1-nure 01._ _ _ _ __ ~-:-l-
~- -c-: --- - ~
=.wE "'"
I)~: ~::. - -- ':.*~ eDF 2
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
/;...;7-
<~-
CENG.. I a joont ventum o f - -_ _ _,
~-"- k
~;J ~~ -~ --:~~~- - .r
- "!-'eor:
01' 3
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
-'7-
- --~--
...:>-~
CENG.
8)oint VEWTlure 011- _ _ _ __
I
...... -:*t
<'"" .- . . .."-~-
J~.- " -.,.
~f " eOF 4
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
.. ~7~ CENG.. I
- --~- ..:..---'*k Iii ~~- - -.' ----
'. ,,)001II8I'I1U19 "'- - - - - - ,
~
~ ..f"' eDf
~ -" 5
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
--~~-
~~7--- CENG_
a joini venliml 01_ _ __ _ -,
I
~~ - k
'\:.:" ~: --""- ,,~
~-
.;.' - ' ~. - -
&.w ..*..eDF
~~
6
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
~.
_ 19".:-"
,~-
,~~-..
s-:
._.~!z,;;.
CENG_
B lOinI\llllltura af- ~
- ".~eDf
~'"
I
.'. 7
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
. ~-,- - CENG.. I ".
,-::.-'~---
" -c""': -.~--~-.
a joInI venture 01'_ _ _ _--, ~~-k 1 ~'- ~ . ~ <1-.
- J - .,y ..*.. eDf 8
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
"';.'~-
~. -
~ - -.~ - -.;,.. ajant ventuteo! _ ~ '~-'
- k
- ~- . - ..' ....eDf
.-~
9
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.
4#9:"'::'
-~.,- CENG. ..; . ~-wI
- i~"':~'*
j~.-'
- -c:- * -., -~~
~ - -
a joint venture of _ ~
-EI-wY ~eDF
-- 4' 10
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
..,~~
CENG.. I '*
~~-
~ --~-
a joht _01,- -___ ~~ - -.t
('-., *Cn
- j~-:- _ r Enefn ~~eDF 11
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
- J#Z7-
-~-,~-
~:
1-~- -__
~
CENG.
a pot venture 011- _ _ _---,
~
~
-'~
~~
eDF
~-" , .
12
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
,,~7 __
--~- a janl..,lUf1l at_ _ _ _ ~
<. ~ - --~ - .:~-
5 ~:- - ~ -- .r. ....':.-. eoF 13
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.
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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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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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