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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257
{{#Wiki_filter:UNITED STATES
  August 17, 2012  
                                NUCLEAR REGULATORY COMMISSION
Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Dominion Nuclear  
                                                REGION II
Innsbrook Technical Center  
                            245 PEACHTREE CENTER AVENUE NE, SUITE 1200
5000 Dominion Boulevard  
                                      ATLANTA, GEORGIA 30303-1257
Glen Allen, VA 23060-6711  
                                            August 17, 2012
SUBJECT: NORTH ANNA POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT NOS. 05000338/2012012 AND 05000339/2012012)  
Mr. David A. Heacock
President and Chief Nuclear Officer
Dear Mr. Heacock:
Virginia Electric and Power Company
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC) Region II staff will conduct a triennial fire protection baseline inspection at the North Anna Power Station, Units 1 and 2, in November and December 2012. The inspection team will be led by Mr. McKenzie Thomas, a Senior Reactor Inspector from the NRC Region II Office. The team will be composed of personnel from the Region II Office. The inspection will be conducted  
Dominion Nuclear
in accordance with Inspection Procedure 71111.05T, the NRC's triennial fire protection baseline inspection procedure, dated October 28, 2011. Inspection of circuit analysis is included in the inspection procedure.
Innsbrook Technical Center
On August 15, 2012, during a telephone conversation between Mr. Donald Taylor, North Anna  
5000 Dominion Boulevard
Licensing Supervisor, and Mr. Thomas, our respective staffs confirmed arrangements for a three-day information gathering onsite visit and a two-week onsite inspection. The schedule for the inspection is as follows:  
Glen Allen, VA 23060-6711
* Information gathering visit: November 6-8, 2012  
SUBJECT:       NORTH ANNA POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF
* Week 1 of onsite inspection: November 26-30, 2012  
                CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
* Week 2 of onsite inspection: December 10-14, 2012
                (NRC INSPECTION REPORT NOS. 05000338/2012012 AND
The purposes of the information gathering visit are to obtain information and documentation needed to support the inspection, to become familiar with the North Anna Power Station fire protection program, fire protection features, post-fire safe shutdown capabilities, plant layout,  
                05000339/2012012)
and mitigating strategies to address Section B.5.b of NRC Order EA-02-026, "Order for Interim Safeguards and Security Compensatory Measures," dated February 25, 2002, and Title 10 of the Code of Federal Regulations (10 CFR) 50.54(hh)(2). The types of documents the team will be interested in reviewing, and possibly obtaining, are listed in Enclosures 1 and 2. Please contact Mr. Thomas at (404) 997-4673 prior to preparing copies of the materials listed in the  
Dear Mr. Heacock:
Enclosures. The inspection team will try to minimize your administrative burden by specifically identifying those documents required for inspection preparation.  
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
D. Heacock 2
Region II staff will conduct a triennial fire protection baseline inspection at the North Anna
During the information gathering visit, the team will also discuss the following inspection support administrative details: office space; specific documents to be made available to the team in their office space; arrangements for unescorted site access (including, as necessary, radiation protection training, security, safety and fitness for duty requirements); and the availability of knowledgeable plant engineering and licensing organization personnel to serve as points of contact during the inspection. 
Power Station, Units 1 and 2, in November and December 2012. The inspection team will be
led by Mr. McKenzie Thomas, a Senior Reactor Inspector from the NRC Region II Office. The
team will be composed of personnel from the Region II Office. The inspection will be conducted
in accordance with Inspection Procedure 71111.05T, the NRCs triennial fire protection baseline
inspection procedure, dated October 28, 2011. Inspection of circuit analysis is included in the
inspection procedure.
On August 15, 2012, during a telephone conversation between Mr. Donald Taylor, North Anna
Licensing Supervisor, and Mr. Thomas, our respective staffs confirmed arrangements for a
three-day information gathering onsite visit and a two-week onsite inspection. The schedule for
the inspection is as follows:
    *   Information gathering visit: November 6-8, 2012
    *   Week 1 of onsite inspection: November 26-30, 2012
    *   Week 2 of onsite inspection: December 10-14, 2012
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, to become familiar with the North Anna Power Station fire
protection program, fire protection features, post-fire safe shutdown capabilities, plant layout,
and mitigating strategies to address Section B.5.b of NRC Order EA-02-026, Order for Interim
Safeguards and Security Compensatory Measures, dated February 25, 2002, and Title 10 of
the Code of Federal Regulations (10 CFR) 50.54(hh)(2). The types of documents the team will
be interested in reviewing, and possibly obtaining, are listed in Enclosures 1 and 2. Please
contact Mr. Thomas at (404) 997-4673 prior to preparing copies of the materials listed in the
Enclosures. The inspection team will try to minimize your administrative burden by specifically
identifying those documents required for inspection preparation.


We request that during the inspection weeks you ensure that copies of analyses, evaluations or documentation regarding the implementation and maintenance of the North Anna Power Station fire protection program, including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest for the fire protection portion of the inspection are  
D. Heacock                                        2
those documents which establish that your fire protection program satisfies NRC regulatory requirements and conforms to applicable NRC and industry fire protection guidance. For the B.5.b portion of the inspection, those documents implementing your mitigating strategies and demonstrating the management of your commitments for the strategies are of specific interest. Also, personnel should be available at the site during the inspection who are knowledgeable regarding those plant systems required to achieve and maintain safe shutdown conditions from inside and outside the control room (including the electrical aspects of the relevant post-fire safe  
During the information gathering visit, the team will also discuss the following inspection support
shutdown analyses), reactor plant fire protection systems and features, and the North Anna Power Station fire protection program and its implementation.
administrative details: office space; specific documents to be made available to the team in their
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection  
office space; arrangements for unescorted site access (including, as necessary, radiation
requirements were approved by the Office of Management and Budget, under control number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
protection training, security, safety and fitness for duty requirements); and the availability of
knowledgeable plant engineering and licensing organization personnel to serve as points of
Your cooperation and support during this inspection will be appreciated. If you have questions concerning this inspection, or the inspection team's information or logistical needs, please contact Mr. Thomas at (404) 997-4673, or me at (404) 997-4511.
contact during the inspection.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its  
We request that during the inspection weeks you ensure that copies of analyses, evaluations or
enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system  
documentation regarding the implementation and maintenance of the North Anna Power Station
 
fire protection program, including post-fire safe shutdown capability, be readily accessible to the
D. Heacock 3
team for their review. Of specific interest for the fire protection portion of the inspection are
(ADAMS).  ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html
those documents which establish that your fire protection program satisfies NRC regulatory
  (the Public Electronic Reading Room).
requirements and conforms to applicable NRC and industry fire protection guidance. For the
Sincerely, 
B.5.b portion of the inspection, those documents implementing your mitigating strategies and
/RA/  Michael F. King, Chief Engineering Branch 2 Division of Reactor Safety 
demonstrating the management of your commitments for the strategies are of specific interest.
Docket Nos.: 50-338, 50-339 License Nos.: NPF-4, NPF-7 
Also, personnel should be available at the site during the inspection who are knowledgeable
Enclosures: 1. Triennial Fire Protection Inspection Support Documentation    2. Mitigating Strategies Support Documentation 
regarding those plant systems required to achieve and maintain safe shutdown conditions from
inside and outside the control room (including the electrical aspects of the relevant post-fire safe
cc w/encls:  (See page 4)
shutdown analyses), reactor plant fire protection systems and features, and the North Anna
Power Station fire protection program and its implementation.
This letter does not contain new or amended information collection requirements subject to the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
requirements were approved by the Office of Management and Budget, under control number
3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to,
a request for information or an information collection requirement unless the requesting
document displays a currently valid Office of Management and Budget control number.
Your cooperation and support during this inspection will be appreciated. If you have questions
concerning this inspection, or the inspection team's information or logistical needs, please
contact Mr. Thomas at (404) 997-4673, or me at (404) 997-4511.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosures will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRCs document system


_________________________  x
D. Heacock                                      3
G SUNSI REVIEW COMPLETE
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
G FORM 665 ATTACHED OFFICE RII:DRS RII:DRS      SIGNATURE RA RA      NAME MTHOMAS MKING      DATE 8/17/2012 8/17/2012 8/     /2012 8/      /2012 8/      /2012 8/      /2012 8/      /2012 E-MAIL COPY?    YES NO      YES NO      YES NO      YES NO      YES NO      YES NO      YES NO     
rm/adams.html (the Public Electronic Reading Room).
D. Heacock 4  
                                            Sincerely,
cc w/encls: Mr. Gerald T. Bischof Site Vice President North Anna Power Station Virginia Electric & Power Company Electronic Mail Distribution
                                            /RA/
                                            Michael F. King, Chief
                                            Engineering Branch 2
                                            Division of Reactor Safety
Docket Nos.: 50-338, 50-339
License Nos.: NPF-4, NPF-7
Enclosures:  1. Triennial Fire Protection Inspection Support Documentation
              2. Mitigating Strategies Support Documentation
cc w/encls: (See page 4)


Fred Mladen Director, Station Safety & Licensing Virginia Electric and Power Company Electronic Mail Distribution


  Michael Crist Plant Manager North Anna Power Station Virginia Electric & Power Company Electronic Mail Distribution  
_________________________                xG SUNSI REVIEW COMPLETE G FORM 665 ATTACHED
  OFFICE            RII:DRS        RII:DRS
Lillian M. Cuoco, Esq. Senior Counsel Dominion Resources Services, Inc. Electronic Mail Distribution  
SIGNATURE          RA              RA
NAME              MTHOMAS        MKING
Tom Huber Director, Nuclear Licensing & Operations Support Inssbrook Technical Center Electronic Mail Distribution  
DATE                  8/17/2012      8/17/2012    8/  /2012    8/  /2012    8/    /2012      8/  /2012    8/ /2012
E-MAIL COPY?        YES    NO    YES      NO  YES    NO    YES    NO    YES      NO      YES    NO    YES  NO
       
D. Heacock                              4
cc w/encls:                                Michael M. Cline
Mr. Gerald T. Bischof                      Director
Site Vice President                        Virginia Department of Emergency Services
North Anna Power Station                  Management
Virginia Electric & Power Company          Electronic Mail Distribution
Electronic Mail Distribution
                                          Executive Vice President
Fred Mladen                                Old Dominion Electric Cooperative
Director, Station Safety & Licensing      Electronic Mail Distribution
Virginia Electric and Power Company
Electronic Mail Distribution              County Administrator
                                          Louisa County
Michael Crist                             P.O. Box 160
Plant Manager                             Louisa, VA 23093
North Anna Power Station
Virginia Electric & Power Company         Doug Smith
Electronic Mail Distribution               President
                                          (Public Correspondence Only)
Lillian M. Cuoco, Esq.                     Lake Anna Civil Association
Senior Counsel                             Electronic Mail Distribution
Dominion Resources Services, Inc.
Electronic Mail Distribution
Tom Huber
Director, Nuclear Licensing & Operations
Support
Inssbrook Technical Center
Electronic Mail Distribution
Virginia State Corporation Commission
Division of Energy Regulation
P.O. Box 1197
Richmond, VA 23209
Attorney General
Supreme Court Building
900 East Main Street
Richmond, VA 23219
Senior Resident Inspector
North Anna Power Station
U.S. Nuclear Regulatory Commission
P.O. Box 490
Mineral, VA 23117
Donald R. Taylor
Licensing Supervisor
North Anna Power Station
P. O. Box 402
Mineral, VA 23117-0402


Virginia State Corporation Commission Division of Energy Regulation P.O. Box 1197 Richmond, VA  23209
D. Heacock                                    5
Letter to David A. Heacock from Michael F. King dated August 17, 2012.
SUBJECT:      NORTH ANNA POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF
              CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
              (NRC INSPECTION REPORT NOS. 05000338/2012012 AND
              05000339/2012012)
Distribution w/encls:
RIDSNRRDIRS
PUBLIC
RidsNrrPMNorthAnna Resource


Attorney General Supreme Court Building 900 East Main Street Richmond, VA  23219
                    Triennial Fire Protection Program Supporting Documentation
Note: This is a broad list of the documents the NRC inspection team may be interested in
reviewing, and possibly obtaining, during the information-gathering site visit. The current
version of these documents is expected unless specified otherwise. Electronic media is
preferred, if readily available. (The preferred file format is searchable .pdf files on CDROM.
The CDROM should be indexed and hyperlinked to facilitate ease of use. Please provide
5 copies of each CDROM submitted.) Information in lists should contain enough information to
be easily understood by someone who has knowledge of the technology. The lead inspector
will discuss specific information needs with the licensee staff and may request additional
documents.
1.      The current version of the fire protection program and fire hazards analysis.
2.      Corrective action closeouts as part of operator manual actions corrective actions.
3.      List of identified fire induced circuit failure configurations for select fire areas.
4.      Corrective actions for fire-induced circuit failures, both single and multiple spurious
        actuations for select fire areas.
5.      Cable routing for components and equipment credited for safe shutdown for select fire
        areas.
6.      List of protected safe shutdown train equipment for select fire areas.
7.      Current versions of the fire protection program implementing procedures (e.g.,
        administrative controls, surveillance testing, and fire brigade).
8.      Fire brigade training program and pre-fire plans.
9.      Post-fire safe shutdown systems and separation analysis.
10.      Post-fire alternative shutdown analysis.
11.      Piping and instrumentation diagrams showing the components used to achieve and
        maintain hot standby and cold shutdown for fires outside the control room and those
        components used for those areas requiring alternative shutdown capability.
12.      Plant layout and equipment drawings which identify the physical plant locations of hot
        standby and cold shutdown equipment.
13.      Plant layout drawings which identify plant fire area delineation, areas protected by
        automatic fire suppression and detection, and the locations of fire protection equipment.
14.      Plant layout drawings which identify the general location of the post-fire emergency
        lighting.
                                                                                            Enclosure 1


  Senior Resident Inspector North Anna Power Station U.S. Nuclear Regulatory Commission P.O. Box 490 Mineral, VA  23117
                                                2
   
15. Plant operating procedures which would be used and describe shutdown from inside
Donald R. Taylor Licensing Supervisor North Anna Power Station P. O. Box 402 Mineral, VA  23117-0402
    the control room with a postulated fire occurring in any plant area outside the control
    room, procedures which would be used to implement alternative shutdown capability in
    the event of a fire in the control or cable spreading room.
16. Maintenance and surveillance testing procedures for alternative shutdown capability
    and fire barriers, detectors, pumps, and suppression systems.
17.  Maintenance procedures which routinely verify fuse breaker coordination in accordance
    with the post-fire safe shutdown coordination analysis.
18.  A list of significant fire protection and post-fire safe shutdown related design change
    packages and evaluations according to Generic Letter 86-10, Implementation of Fire
    Protection Requirements.
19.  The reactor plant's Individual Plant Examination for External Events (IPEEE), results of
    any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in
    response to IPEEE information.
20.  Organization charts of site personnel (including fire protection staff personnel).
21. If applicable, drawings of potential reactor coolant/recirculation pump lube oil system
    leakage points and associated lube oil collection systems.
22.  Licensing basis documents for fire protection (safety evaluation reports, pertinent
    sections of the final safety analysis report, exemptions, deviations, letters to/from the
    NRC regarding fire protection/fire safe shutdown, etc.).
23. Procedures/instructions that control the configuration of the plant's fire protection
    program, features, and post-fire safe shutdown methodology and system design.
24.  A list of applicable codes and standards related to the design of plant fire protection
    features and evaluations of code deviations.
25.  Procedures/instructions that govern the implementation of plant modifications,
    maintenance, and special operations, and their impact on fire protection.
26.  Internal and external self-assessments, audits, peer-assessments or similar reviews
    related to post-fire safe shutdown capability or the fire protection program completed
    since the previous NRC fire protection triennial inspection.
27.  Recent quality assurance surveillances of fire protection activities.
28. A listing of open and closed fire protection condition reports (problem reports/nuclear
    condition reports/event analysis reports/problem identification and resolution reports)
    since the last triennial inspection.
                                                                                      Enclosure 1


Michael M. Cline Director Virginia Department of Emergency Services Management Electronic Mail Distribution
                            Mitigating Strategies Supporting Documentation
Note: This is a broad list of the documents the NRC inspection team may be interested in
Executive Vice President Old Dominion Electric Cooperative Electronic Mail Distribution
reviewing, and possibly obtaining, during the information gathering site visit. The current
County Administrator
version of these documents is expected unless specified otherwise. Electronic media is
Louisa County P.O. Box 160 Louisa, VA  23093
preferred, if readily available. (The preferred file format is searchable .pdf files on CDROM.
Doug Smith President (Public Correspondence Only)
The CDROM should be indexed and hyperlinked to facilitate ease of use. Please provide 5
Lake Anna Civil Association Electronic Mail Distribution 
copies of each CDROM submitted.) Information in lists should contain enough information to
D. Heacock 5
be easily understood by someone who has knowledge of the technology. The lead inspector
Letter to David A. Heacock from Michael F. King dated August 17, 2012.
will discuss specific information needs with the licensee staff and may request additional
SUBJECT: NORTH ANNA POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT NOS. 05000338/2012012 AND 05000339/2012012)
documents.
Distribution w/encls:
1.       A list of all modifications to regulatory commitments made to meet the requirements of
RIDSNRRDIRS PUBLIC RidsNrrPMNorthAnna Resource 
          Section B.5.b of NRC Order, EA-02-026, Order for NRC Interim Safeguards and
  Enclosure 1
          Security Compensatory Measures, dated February 25, 2002, the subsequently
Triennial Fire Protection Program Supporting Documentation
          imposed license conditions, and Title 10 of the Code of Federal Regulations (10 CFR)
Note: This is a broad list of the documents the NRC inspection team may be interested in reviewing, and possibly obtaining, during the information-gathering site visit.  The current version of these documents is expected unless specified otherwise.  Electronic media is preferred, if readily available.  (The preferred file format is searchable ".pdf" files on CDROM.  The CDROM should be indexed and hyperlinked to facilitate ease of use.  Please provide  5 copies of each CDROM submitted.)  Information in "lists" should contain enough information to
          50.54(hh)(2).
be easily understood by someone who has knowledge of the technology.  The lead inspector will discuss specific information needs with the licensee staff and may request additional documents.
2.       Lists of procedures/guidelines that were revised or generated to implement the
  1.  The current version of the fire protection program and fire hazards analysis.
          mitigation strategies. These could be extensive damage mitigation guidelines
          (EDMGs), severe accident management guidelines (SAMGs), emergency operating
2.  Corrective action closeouts as part of operator manual actions corrective actions.
          procedures (EOPs), abnormal operating procedures (AOPs), etc.
3.  List of identified fire induced circuit failure configurations for select fire areas. 
3.       A matrix that shows the correlation between the mitigation strategies identified in
4.  Corrective actions for fire-induced circuit failures, both single and multiple spurious actuations for select fire areas. 
          Nuclear Energy Institute 06-12, Revision 2, B.5.b Phase 2 & 3 Submittal Guideline,
5.  Cable routing for components and equipment credited for safe shutdown for select fire areas. 
          issued December 2006, and the site-specific procedures or guidelines used to
6.  List of protected safe shutdown train equipment for select fire areas.
          implement each strategy.
7.  Current versions of the fire protection program implementing procedures (e.g., administrative controls, surveillance testing, and fire brigade). 
4.       Engineering evaluations/calculations that were used to verify engineering bases for the
          mitigation strategies.
8.  Fire brigade training program and pre-fire plans. 
5.       Piping and instrumentation diagram for systems relied upon in the mitigation strategies.
9.  Post-fire safe shutdown systems and separation analysis. 
          These could be of the type used for training.
10.  Post-fire alternative shutdown analysis. 
6.       A list of modification packages or simplified drawings or descriptions of modifications
 
          that were made to plant systems to implement the mitigation strategies.
11. Piping and instrumentation diagrams showing the components used to achieve and maintain hot standby and cold shutdown for fires outside the control room and those components used for those areas requiring alternative shutdown capability. 
7.       Copies of procedures used to inventory equipment (hoses, fittings, pumps, etc.)
12. Plant layout and equipment drawings which identify the physical plant locations of hot standby and cold shutdown equipment. 
          required to implement the mitigation strategies.
13. Plant layout drawings which identify plant fire area delineation, areas protected by automatic fire suppression and detection, and the locations of fire protection equipment. 
8.       A list of B.5.b strategies, if any, that have implementing details that differ from those
14. Plant layout drawings which identify the general location of the post-fire emergency lighting.
          documented in the submittals and the safety evaluation report.
2  Enclosure 1 15. Plant operating procedures which would be used and describe shutdown from inside the control room with a postulated fire occurring in any plant area outside the control room, procedures which would be used to implement alternative shutdown capability in the event of a fire in the control or cable spreading room. 
9.       A copy of site general arrangement drawing(s) that show the majority of buildings/areas
16. Maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, pumps, and suppression systems.
          referenced in B.5.b documents.
17. Maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis. 
10.       Training records, training matrix, and lesson plans related to B.5.b.
11.     Copies of memoranda of understanding (e.g., with local fire departments) required to
18. A list of significant fire protection and post-fire safe shutdown related design change packages and evaluations according to Generic Letter 86-10, "Implementation of Fire Protection Requirements."
        implement any mitigating strategies.
19. The reactor plant's Individual Plant Examination for External Events (IPEEE), results of any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in response to IPEEE information.
                                                                                            Enclosure 2
20.  Organization charts of site personnel (including fire protection staff personnel).
21. If applicable, drawings of potential reactor coolant/recirculation pump lube oil system leakage points and associated lube oil collection systems.
22. Licensing basis documents for fire protection (safety evaluation reports, pertinent sections of the final safety analysis report, exemptions, deviations, letters to/from the NRC regarding fire protection/fire safe shutdown, etc.).
23. Procedures/instructions that control the configuration of the plant's fire protection program, features, and post-fire safe shutdown methodology and system design.
24. A list of applicable codes and standards related to the design of plant fire protection features and evaluations of code deviations.
25. Procedures/instructions that govern the implementation of plant modifications, maintenance, and special operations, and their impact on fire protection.
26. Internal and external self-assessments, audits, peer-assessments or similar reviews related to post-fire safe shutdown capability or the fire protection program completed since the previous NRC fire protection triennial inspection.
27.  Recent quality assurance surveillances of fire protection activities. 
28. A listing of open and closed fire protection condition reports (problem reports/nuclear condition reports/event analysis reports/problem identification and resolution reports)
since the last triennial inspection. 
  Enclosure 2 Mitigating Strategies Supporting Documentation  
Note: This is a broad list of the documents the NRC inspection team may be interested in reviewing, and possibly obtaining, during the information gathering site visit. The current version of these documents is expected unless specified otherwise. Electronic media is preferred, if readily available. (The preferred file format is searchable ".pdf" files on CDROM.
The CDROM should be indexed and hyperlinked to facilitate ease of use. Please provide 5 copies of each CDROM submitted.) Information in "lists" should contain enough information to be easily understood by someone who has knowledge of the technology. The lead inspector will discuss specific information needs with the licensee staff and may request additional documents.  
 
1. A list of all modifications to regulatory commitments made to meet the requirements of Section B.5.b of NRC Order, EA-02-026, "Order for NRC Interim Safeguards and Security Compensatory Measures," dated February 25, 2002, the subsequently imposed license conditions, and Title 10 of the Code of Federal Regulations (10 CFR) 50.54(hh)(2).  
2. Lists of procedures/guidelines that were revised or generated to implement the mitigation strategies. These could be extensive damage mitigation guidelines (EDMGs), severe accident management guidelines (SAMGs), emergency operating procedures (EOPs), abnormal operating procedures (AOPs), etc.  
3. A matrix that shows the correlation between the mitigation strategies identified in Nuclear Energy Institute 06-12, Revision 2, "B.5.b Phase 2 & 3 Submittal Guideline," issued December 2006, and the site-specific procedures or guidelines used to implement each strategy.  
4. Engineering evaluations/calculations that were used to verify engineering bases for the mitigation strategies.  
5. Piping and instrumentation diagram for systems relied upon in the mitigation strategies. These could be of the type used for training.  
6. A list of modification packages or simplified drawings or descriptions of modifications that were made to plant systems to implement the mitigation strategies.  
7. Copies of procedures used to inventory equipment (hoses, fittings, pumps, etc.) required to implement the mitigation strategies.  
8. A list of B.5.b strategies, if any, that have implementing details that differ from those documented in the submittals and the safety evaluation report.  
9. A copy of site general arrangement drawing(s) that show the majority of buildings/areas referenced in B.5.b documents.  
10. Training records, training matrix, and lesson plans related to B.5.b.  
11. Copies of memoranda of understanding (e.g., with local fire departments) required to implement any mitigating strategies.
}}
}}

Revision as of 23:29, 11 November 2019

IR 05000338-12-012, 05000339-12-012, on 10/28/2011, North Anna Power Station, Units 1 & 2 - Notification of Conduct of a Triennial Fire Protection Baseline Inspection
ML12235A291
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 08/17/2012
From: Mark King
NRC/RGN-II/DRS/EB2
To: Heacock D
Virginia Electric & Power Co (VEPCO)
References
IR-12-012
Download: ML12235A291 (9)
v • d • e


See also: IR 05000338/2012012

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

August 17, 2012

Mr. David A. Heacock

President and Chief Nuclear Officer

Virginia Electric and Power Company

Dominion Nuclear

Innsbrook Technical Center

5000 Dominion Boulevard

Glen Allen, VA 23060-6711

SUBJECT: NORTH ANNA POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF

CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

(NRC INSPECTION REPORT NOS. 05000338/2012012 AND

05000339/2012012)

Dear Mr. Heacock:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region II staff will conduct a triennial fire protection baseline inspection at the North Anna

Power Station, Units 1 and 2, in November and December 2012. The inspection team will be

led by Mr. McKenzie Thomas, a Senior Reactor Inspector from the NRC Region II Office. The

team will be composed of personnel from the Region II Office. The inspection will be conducted

in accordance with Inspection Procedure 71111.05T, the NRCs triennial fire protection baseline

inspection procedure, dated October 28, 2011. Inspection of circuit analysis is included in the

inspection procedure.

On August 15, 2012, during a telephone conversation between Mr. Donald Taylor, North Anna

Licensing Supervisor, and Mr. Thomas, our respective staffs confirmed arrangements for a

three-day information gathering onsite visit and a two-week onsite inspection. The schedule for

the inspection is as follows:

  • Information gathering visit: November 6-8, 2012
  • Week 1 of onsite inspection: November 26-30, 2012
  • Week 2 of onsite inspection: December 10-14, 2012

The purposes of the information gathering visit are to obtain information and documentation

needed to support the inspection, to become familiar with the North Anna Power Station fire

protection program, fire protection features, post-fire safe shutdown capabilities, plant layout,

and mitigating strategies to address Section B.5.b of NRC Order EA-02-026, Order for Interim

Safeguards and Security Compensatory Measures, dated February 25, 2002, and Title 10 of

the Code of Federal Regulations (10 CFR) 50.54(hh)(2). The types of documents the team will

be interested in reviewing, and possibly obtaining, are listed in Enclosures 1 and 2. Please

contact Mr. Thomas at (404) 997-4673 prior to preparing copies of the materials listed in the

Enclosures. The inspection team will try to minimize your administrative burden by specifically

identifying those documents required for inspection preparation.

D. Heacock 2

During the information gathering visit, the team will also discuss the following inspection support

administrative details: office space; specific documents to be made available to the team in their

office space; arrangements for unescorted site access (including, as necessary, radiation

protection training, security, safety and fitness for duty requirements); and the availability of

knowledgeable plant engineering and licensing organization personnel to serve as points of

contact during the inspection.

We request that during the inspection weeks you ensure that copies of analyses, evaluations or

documentation regarding the implementation and maintenance of the North Anna Power Station

fire protection program, including post-fire safe shutdown capability, be readily accessible to the

team for their review. Of specific interest for the fire protection portion of the inspection are

those documents which establish that your fire protection program satisfies NRC regulatory

requirements and conforms to applicable NRC and industry fire protection guidance. For the

B.5.b portion of the inspection, those documents implementing your mitigating strategies and

demonstrating the management of your commitments for the strategies are of specific interest.

Also, personnel should be available at the site during the inspection who are knowledgeable

regarding those plant systems required to achieve and maintain safe shutdown conditions from

inside and outside the control room (including the electrical aspects of the relevant post-fire safe

shutdown analyses), reactor plant fire protection systems and features, and the North Anna

Power Station fire protection program and its implementation.

This letter does not contain new or amended information collection requirements subject to the

Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection

requirements were approved by the Office of Management and Budget, under control number

3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to,

a request for information or an information collection requirement unless the requesting

document displays a currently valid Office of Management and Budget control number.

Your cooperation and support during this inspection will be appreciated. If you have questions

concerning this inspection, or the inspection team's information or logistical needs, please

contact Mr. Thomas at (404) 997-4673, or me at (404) 997-4511.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its

enclosures will be available electronically for public inspection in the NRC Public Document

Room or from the Publicly Available Records (PARS) component of NRCs document system

D. Heacock 3

(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-

rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Michael F. King, Chief

Engineering Branch 2

Division of Reactor Safety

Docket Nos.: 50-338, 50-339

License Nos.: NPF-4, NPF-7

Enclosures: 1. Triennial Fire Protection Inspection Support Documentation

2. Mitigating Strategies Support Documentation

cc w/encls: (See page 4)

_________________________ xG SUNSI REVIEW COMPLETE G FORM 665 ATTACHED

OFFICE RII:DRS RII:DRS

SIGNATURE RA RA

NAME MTHOMAS MKING

DATE 8/17/2012 8/17/2012 8/ /2012 8/ /2012 8/ /2012 8/ /2012 8/ /2012

E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

D. Heacock 4

cc w/encls: Michael M. Cline

Mr. Gerald T. Bischof Director

Site Vice President Virginia Department of Emergency Services

North Anna Power Station Management

Virginia Electric & Power Company Electronic Mail Distribution

Electronic Mail Distribution

Executive Vice President

Fred Mladen Old Dominion Electric Cooperative

Director, Station Safety & Licensing Electronic Mail Distribution

Virginia Electric and Power Company

Electronic Mail Distribution County Administrator

Louisa County

Michael Crist P.O. Box 160

Plant Manager Louisa, VA 23093

North Anna Power Station

Virginia Electric & Power Company Doug Smith

Electronic Mail Distribution President

(Public Correspondence Only)

Lillian M. Cuoco, Esq. Lake Anna Civil Association

Senior Counsel Electronic Mail Distribution

Dominion Resources Services, Inc.

Electronic Mail Distribution

Tom Huber

Director, Nuclear Licensing & Operations

Support

Inssbrook Technical Center

Electronic Mail Distribution

Virginia State Corporation Commission

Division of Energy Regulation

P.O. Box 1197

Richmond, VA 23209

Attorney General

Supreme Court Building

900 East Main Street

Richmond, VA 23219

Senior Resident Inspector

North Anna Power Station

U.S. Nuclear Regulatory Commission

P.O. Box 490

Mineral, VA 23117

Donald R. Taylor

Licensing Supervisor

North Anna Power Station

P. O. Box 402

Mineral, VA 23117-0402

D. Heacock 5

Letter to David A. Heacock from Michael F. King dated August 17, 2012.

SUBJECT: NORTH ANNA POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF

CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

(NRC INSPECTION REPORT NOS. 05000338/2012012 AND

05000339/2012012)

Distribution w/encls:

RIDSNRRDIRS

PUBLIC

RidsNrrPMNorthAnna Resource

Triennial Fire Protection Program Supporting Documentation

Note: This is a broad list of the documents the NRC inspection team may be interested in

reviewing, and possibly obtaining, during the information-gathering site visit. The current

version of these documents is expected unless specified otherwise. Electronic media is

preferred, if readily available. (The preferred file format is searchable .pdf files on CDROM.

The CDROM should be indexed and hyperlinked to facilitate ease of use. Please provide

5 copies of each CDROM submitted.) Information in lists should contain enough information to

be easily understood by someone who has knowledge of the technology. The lead inspector

will discuss specific information needs with the licensee staff and may request additional

documents.

1. The current version of the fire protection program and fire hazards analysis.

2. Corrective action closeouts as part of operator manual actions corrective actions.

3. List of identified fire induced circuit failure configurations for select fire areas.

4. Corrective actions for fire-induced circuit failures, both single and multiple spurious

actuations for select fire areas.

5. Cable routing for components and equipment credited for safe shutdown for select fire

areas.

6. List of protected safe shutdown train equipment for select fire areas.

7. Current versions of the fire protection program implementing procedures (e.g.,

administrative controls, surveillance testing, and fire brigade).

8. Fire brigade training program and pre-fire plans.

9. Post-fire safe shutdown systems and separation analysis.

10. Post-fire alternative shutdown analysis.

11. Piping and instrumentation diagrams showing the components used to achieve and

maintain hot standby and cold shutdown for fires outside the control room and those

components used for those areas requiring alternative shutdown capability.

12. Plant layout and equipment drawings which identify the physical plant locations of hot

standby and cold shutdown equipment.

13. Plant layout drawings which identify plant fire area delineation, areas protected by

automatic fire suppression and detection, and the locations of fire protection equipment.

14. Plant layout drawings which identify the general location of the post-fire emergency

lighting.

Enclosure 1

2

15. Plant operating procedures which would be used and describe shutdown from inside

the control room with a postulated fire occurring in any plant area outside the control

room, procedures which would be used to implement alternative shutdown capability in

the event of a fire in the control or cable spreading room.

16. Maintenance and surveillance testing procedures for alternative shutdown capability

and fire barriers, detectors, pumps, and suppression systems.

17. Maintenance procedures which routinely verify fuse breaker coordination in accordance

with the post-fire safe shutdown coordination analysis.

18. A list of significant fire protection and post-fire safe shutdown related design change

packages and evaluations according to Generic Letter 86-10, Implementation of Fire

Protection Requirements.

19. The reactor plant's Individual Plant Examination for External Events (IPEEE), results of

any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in

response to IPEEE information.

20. Organization charts of site personnel (including fire protection staff personnel).

21. If applicable, drawings of potential reactor coolant/recirculation pump lube oil system

leakage points and associated lube oil collection systems.

22. Licensing basis documents for fire protection (safety evaluation reports, pertinent

sections of the final safety analysis report, exemptions, deviations, letters to/from the

NRC regarding fire protection/fire safe shutdown, etc.).

23. Procedures/instructions that control the configuration of the plant's fire protection

program, features, and post-fire safe shutdown methodology and system design.

24. A list of applicable codes and standards related to the design of plant fire protection

features and evaluations of code deviations.

25. Procedures/instructions that govern the implementation of plant modifications,

maintenance, and special operations, and their impact on fire protection.

26. Internal and external self-assessments, audits, peer-assessments or similar reviews

related to post-fire safe shutdown capability or the fire protection program completed

since the previous NRC fire protection triennial inspection.

27. Recent quality assurance surveillances of fire protection activities.

28. A listing of open and closed fire protection condition reports (problem reports/nuclear

condition reports/event analysis reports/problem identification and resolution reports)

since the last triennial inspection.

Enclosure 1

Mitigating Strategies Supporting Documentation

Note: This is a broad list of the documents the NRC inspection team may be interested in

reviewing, and possibly obtaining, during the information gathering site visit. The current

version of these documents is expected unless specified otherwise. Electronic media is

preferred, if readily available. (The preferred file format is searchable .pdf files on CDROM.

The CDROM should be indexed and hyperlinked to facilitate ease of use. Please provide 5

copies of each CDROM submitted.) Information in lists should contain enough information to

be easily understood by someone who has knowledge of the technology. The lead inspector

will discuss specific information needs with the licensee staff and may request additional

documents.

1. A list of all modifications to regulatory commitments made to meet the requirements of

Section B.5.b of NRC Order, EA-02-026, Order for NRC Interim Safeguards and

Security Compensatory Measures, dated February 25, 2002, the subsequently

imposed license conditions, and Title 10 of the Code of Federal Regulations (10 CFR)

50.54(hh)(2).

2. Lists of procedures/guidelines that were revised or generated to implement the

mitigation strategies. These could be extensive damage mitigation guidelines

(EDMGs), severe accident management guidelines (SAMGs), emergency operating

procedures (EOPs), abnormal operating procedures (AOPs), etc.

3. A matrix that shows the correlation between the mitigation strategies identified in

Nuclear Energy Institute 06-12, Revision 2, B.5.b Phase 2 & 3 Submittal Guideline,

issued December 2006, and the site-specific procedures or guidelines used to

implement each strategy.

4. Engineering evaluations/calculations that were used to verify engineering bases for the

mitigation strategies.

5. Piping and instrumentation diagram for systems relied upon in the mitigation strategies.

These could be of the type used for training.

6. A list of modification packages or simplified drawings or descriptions of modifications

that were made to plant systems to implement the mitigation strategies.

7. Copies of procedures used to inventory equipment (hoses, fittings, pumps, etc.)

required to implement the mitigation strategies.

8. A list of B.5.b strategies, if any, that have implementing details that differ from those

documented in the submittals and the safety evaluation report.

9. A copy of site general arrangement drawing(s) that show the majority of buildings/areas

referenced in B.5.b documents.

10. Training records, training matrix, and lesson plans related to B.5.b.

11. Copies of memoranda of understanding (e.g., with local fire departments) required to

implement any mitigating strategies.

Enclosure 2

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