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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
  May 23, 2012  
                                NUCLEAR REGULATORY COMMISSION
                                                REGION II
Mr. David A. Heacock  
                            245 PEACHTREE CENTER AVENUE NE, SUITE 1200
President and Chief Nuclear Officer  
                                      ATLANTA, GEORGIA 30303-1257
Virginia Electric and Power Company  
                                              May 23, 2012
Dominion Nuclear  
Mr. David A. Heacock
Innsbrook Technical Center  
President and Chief Nuclear Officer
5000 Dominion Boulevard  
Virginia Electric and Power Company
Glen Allen, VA 23060-6711  
Dominion Nuclear
SUBJECT: SURRY POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT 05000280/2012011 AND 05000281/2012011)  
Innsbrook Technical Center
Dear Heacock:  
5000 Dominion Boulevard
Glen Allen, VA 23060-6711
SUBJECT:         SURRY POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF TRIENNIAL
                FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT
                05000280/2012011 AND 05000281/2012011)
Dear 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 Surry Power
Station, Units 1 and 2, in July and August 2012. McKenzie Thomas, Senior Reactor Inspector,
will lead the team which will be composed of inspectors from the NRC Region II Office. The
inspection will be conducted in accordance with Inspection Procedure 71111.05T, the NRC=s
triennial fire protection baseline inspection procedure dated October 28, 2011.
The inspection objective will be to evaluate your fire protection program implementation with
emphasis on post-fire safe shutdown capability and the fire protection features provided to
ensure at least one post-fire safe shutdown success path is maintained free of fire damage.
The inspection team will focus their review on the systems and equipment necessary to achieve
and maintain safe shutdown and the fire protection features of selected fire areas.
On May 16, 2012, during a telephone conversation between Mr. Barry Garber, Surry Licensing
Supervisor, and Mrs. LaDonna Suggs, 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:
              *  Information gathering visit: July 10 - 12, 2012
              *  Week 1 of onsite inspection: July 30 - August 3, 2012
              *  Week 2 of onsite inspection: August 13 - 17, 2012


The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
VEPCO                                          2
Region II staff will conduct a triennial fire protection baseline inspection at the Surry Power Station, Units 1 and 2, in July and August 2012. McKenzie Thomas, Senior Reactor Inspector, will lead the team which will be composed of inspectors from the NRC Region II Office. The inspection will be conducted in accordance with Inspection Procedure 71111.05T, the NRC
The purposes of the information gathering visit are to obtain information and documentation
=s triennial fire protection baseline inspection procedure dated October 28, 2011.  
needed to support the inspection, and to become familiar with the Surry Power Station fire
protection program, fire protection features, post-fire shutdown capabilities and plant layout
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); and, as necessary, obtain plant-
specific site access training and badging for unescorted site access. A list of the types of
documents the team may be interested in reviewing, and possibly obtaining, are listed in
Enclosures 1 and 2.
Please contact McKenzie Thomas or Rodney Fanner prior to preparing copies of the materials
listed in the Enclosure. The inspection team will try to minimize your administrative burden by
specifically identifying those documents required for inspection preparation.
During the information gathering visit, the team will also discuss the following administrative
details - office space; specific documents to be made available to the team in its office space;
arrangements for reactor site access (including 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 Surry Power Station fire
protection program, including post-fire safe shutdown capability, be readily accessible to the
team for its review. Of specific interest 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, the 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 Surry 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 teams information or logistical needs, please
contact McKenzie Thomas at (404) 997-4673, Rodney Fanner at (404) 997-4638 or me at
(404) 997-4511.


The inspection objective will be to evaluate your fire protection program implementation with  
VEPCO                                          3
emphasis on post-fire safe shutdown capability and the fire protection features provided to ensure at least one post-fire safe shutdown success path is maintained free of fire damage.  The inspection team will focus their review on the systems and equipment necessary to achieve and maintain safe shutdown and the fire protection features of selected fire areas.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its
On May 16, 2012, during a telephone conversation between Mr. Barry Garber, Surry Licensing Supervisor, and Mrs. LaDonna Suggs, our respective staffs confirmed arrangements for a three-
enclosure will be available electronically for public inspection in the NRC Public Document
day information gathering onsite visit and a two-week onsite inspection.  The schedule for the inspection is:
Room or from the Publicly Available Records (PARS) component of NRCs document system
* Information gathering visit: July 10 - 12, 2012
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
* Week 1 of onsite inspection: July 30 - August 3, 2012
rm/adams.html (the Public Electronic Reading Room).
* Week 2 of onsite inspection: August 13 - 17, 2012 
                                              Sincerely,
VEPCO 2  The purposes of the information gathering visit are to obtain information and documentation needed to support the inspection, and to become familiar with the Surry Power Station fire protection program, fire protection features, post-fire shutdown capabilities and plant layout 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); and, as necessary, obtain plant-specific site access training and badging for unescorted site access. A list of the types of documents the team may be interested in reviewing, and possibly obtaining, are listed in Enclosures 1 and 2. 
                                              /RA/
Please contact McKenzie Thomas or Rodney Fanner prior to preparing copies of the materials
                                              Michael F. King
listed in the Enclosure. The inspection team will try to minimize your administrative burden by specifically identifying those documents required for inspection preparation.
                                              Engineering Branch 2
During the information gathering visit, the team will also discuss the following administrative details - office space; specific documents to be made available to the team in its office space; arrangements for reactor site access (including radiation protection training, security, safety and fitness for duty requirements); and the availability of knowledgeable plant engineering and
                                              Division of Reactor Safety
licensing organization personnel to serve as points of contact during the inspection.  
Docket Nos.: 50-280, 50-281
We request that during the inspection weeks you ensure that copies of analyses, evaluations or documentation regarding the implementation and maintenance of the Surry Power Station fire protection program, including post-fire safe shutdown capability, be readily accessible to the
License Nos.: DPR-32, DPR-37
team for its review. Of specific interest 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, the 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
Enclosures:
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 Surry Power Station fire protection program and its implementation.
1. Triennial Fire Protection Program Supporting Documentation
2. Mitigating Strategies Supporting Documentation
cc w/encls: (See page 4)


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 McKenzie Thomas at (404) 997-4673, Rodney Fanner at (404) 997-4638 or me at 
(404) 997-4511.
 
VEPCO 3  In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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 (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
      Engineering Branch 2      Division of Reactor Safety
Docket Nos.: 50-280, 50-281 License Nos.: DPR-32, DPR-37
Enclosures: 
1. Triennial Fire Protection Program Supporting Documentation 2. Mitigating Strategies Supporting Documentation
cc w/encls:  (See page 4) 


  _ML121450437_______________ x
  _ML121450437_______________             xG SUNSI REVIEW COMPLETE G FORM 665 ATTACHED
G SUNSI REVIEW COMPLETE  
OFFICE             RII:DRS       RII:DRS
G FORM 665 ATTACHED OFFICE RII:DRS RII:DRS     SIGNATURE RA RA     NAME DJONES MKING     DATE 5/23/2012 5/23/2012 5/     /2012 5/     /2012 5/     /2012 5/     /2012 5/     /2012 E-MAIL COPY?    YES NO       YES NO       YES NO       YES NO       YES NO       YES NO       YES NO    
SIGNATURE         RA             RA
VEPCO 4 cc w/encls: Larry Lane Site Vice President Surry Power Station Virginia Electric and Power Company Electronic Mail Distribution  
NAME               DJONES         MKING
DATE                   5/23/2012     5/23/2012   5/   /2012     5/ /2012     5/   /2012     5/ /2012   5/ /2012
E-MAIL COPY?         YES     NO   YES     NO   YES     NO     YES   NO     YES     NO     YES   NO   YES   NO
       
VEPCO                                   4
cc w/encls:                               Michael M. Cline
Larry Lane                                 Director
Site Vice President                       Virginia Department of Emergency Services
Surry Power Station                       Management
Virginia Electric and Power Company       Electronic Mail Distribution
Electronic Mail Distribution
B. L. (Sonny) Stanley
Director, Nuclear Safety and Licensing
Virginia Electric and Power Company
Electronic Mail Distribution
Kenny B. Sloane
Plant Manager
Surry Power Station
Virginia Electric & Power Company
Electronic Mail Distribution
Lillian M. Cuoco, Esq.
Senior Counsel
Dominion Resources Services, Inc.
Electronic Mail Distribution
Tom Huber
Director, Nuclear Licensing & Operations
Support
Innsbrook Technical Center
Electronic Mail Distribution
Ginger L. Rutherford
Virginia Electric and Power Company
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
Surry Power Station
U.S. Nuclear Regulatory Commission
5850 Hog Island Rd
Surry, VA 23883


B. L. (Sonny) Stanley Director, Nuclear  Safety and Licensing Virginia Electric and Power Company Electronic Mail Distribution  
VEPCO                                      5
Letter to David A. Heacock from Michael F. King dated May 23, 2012.
SUBJECT:      SURRY POWER STATION , UNITS 1 AND 2 - NOTIFICATION OF TRIENNIAL
              FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT
              05000280/2012011 AND 05000281/2012011)
Distribution w/encls:
RIDSNRRDIRS
PUBLIC
RidsNrrPMSurry Resource


Kenny B. Sloane Plant Manager Surry Power Station Virginia Electric & Power Company Electronic Mail Distribution
                    Triennial Fire Protection Program Supporting Documentation
Note: This is a broad list of the documents the NRC inspection team may be interested in
Lillian M. Cuoco, Esq. Senior Counsel Dominion Resources Services, Inc. Electronic Mail Distribution
reviewing, and possibly obtaining, during the information gathering site visit. Electronic media is
preferred, if readily available. (The preferred file format on CD-ROM or DVDROM is .pdf).
Tom Huber Director, Nuclear Licensing & Operations Support Innsbrook Technical Center Electronic Mail Distribution
The CD/DVD-ROM should be indexed, hyperlinked, readable, and searchable to facilitate ease
of use. Please provide 5 copies of each CD/DVD-ROM 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 or electronic information.
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 the selected fire
        areas/zones (to be determined during information gathering visit).
4.     Corrective actions for fire-induced circuit failures, both single and multiple spurious
        actuations for the selected fire areas/zones (to be determined during information
        gathering visit).
5.      Cable routing for components and equipment credited for safe shutdown for the selected
        fire areas/zones (to be determined during information gathering visit).
6.      List of protected safe shutdown train equipment for the selected fire areas/zones (to be
        determined during information gathering visit).
7.      Current versions of the fire protection program implementing procedures (e.g.,
        administrative controls, surveillance testing, 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


Ginger L. Rutherford Virginia Electric and Power Company Electronic Mail Distribution
                                              2
15. Plant operating procedures which would be used and describe shutdown from inside
Virginia State Corporation Commission Division of Energy Regulation P.O. Box 1197 Richmond, VA  23209
    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
Attorney General Supreme Court Building 900 East Main Street Richmond, VA  23219
    the event of a fire in the control or cable spreading room.
Senior Resident Inspector Surry Power Station
16. Maintenance and surveillance testing procedures for alternative shutdown capability
U.S. Nuclear Regulatory Commission 5850 Hog Island Rd Surry, VA  23883
    and fire barriers, detectors, pumps and suppression systems.
 
17. Maintenance procedures that routinely verify fuse breaker coordination in accordance
Michael M. Cline Director Virginia Department of Emergency Services Management Electronic Mail Distribution
    with the post-fire safe shutdown coordination analysis.
VEPCO 5  Letter to David A. Heacock from Michael F. King dated May 23, 2012.
18. A list of significant fire protection and post-fire safe shutdown related design change
SUBJECT: SURRY POWER STATION , UNITS 1 AND 2 - NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT 05000280/2012011 AND 05000281/2012011)
    packages and evaluations according to Generic Letter 86-10, Implementation of Fire
    Protection Requirements.
Distribution w/encls:
19. The reactor plant's Individual Plant Examination for External Events (IPEEE), results of
RIDSNRRDIRS PUBLIC RidsNrrPMSurry Resource 
    any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in
 
    response to IPEEE information.
Enclosure 1 Triennial Fire Protection Program Supporting Documentation
21. Organization charts of site personnel (including fire protection staff personnel).
  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.  Electronic media is preferred, if readily available.  (The preferred file format on CD-ROM or DVDROM is ".pdf").  The CD/DVD-ROM should be indexed, hyperlinked, readable, and searchable to facilitate ease
22. If applicable, drawings of potential reactor coolant/recirculation pump lube oil system
of use.  Please provide 5 copies of each CD/DVD-ROM 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 or electronic information.
    leakage points and associated lube oil collection systems.
23. Licensing basis documents for fire protection (safety evaluation reports, pertinent
1.  The current version of the fire protection program and fire hazards analysis.
    sections of the final safety analysis report, exemptions, deviations, letters to/from the
2.  Corrective action closeouts as part of operator manual actions corrective actions.
    NRC regarding fire protection/fire safe shutdown, etc.).
3.  List of identified fire induced circuit failure configurations for the selected fire areas/zones (to be determined during information gathering visit).
24. Procedures/instructions that control the configuration of the plant's fire protection
 
    program, features, and post-fire safe shutdown methodology, and system design.
4. Corrective actions for fire-induced circuit failures, both single and multiple spurious actuations for the selected fire areas/zones (to be determined during information gathering visit).
25. A list of applicable codes and standards related to the design of plant fire protection
5. Cable routing for components and equipment credited for safe shutdown for the selected fire areas/zones (to be determined during information gathering visit).
    features and evaluations of code deviations.
6. List of protected safe shutdown train equipment for the selected fire areas/zones (to be determined during information gathering visit).
26. Procedures/instructions that govern the implementation of plant modifications,
    maintenance, special operations, and their impact on fire protection.
7.  Current versions of the fire protection program implementing procedures (e.g., administrative controls, surveillance testing, fire brigade). 
27. Internal and external self-assessments, audits, peer-assessments or similar reviews
8.  Fire brigade training program and pre-fire plans. 
    related to post-fire safe shutdown capability or the fire protection program completed
    since the previous NRC fire protection triennial inspection.
9.  Post-fire safe shutdown systems and separation analysis. 
28. Recent quality assurance surveillances of fire protection activities.
10.  Post-fire alternative shutdown analysis. 
29. A listing of open and closed fire protection condition reports (problem reports/nuclear
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. 
    condition reports/event analysis reports/problem identification, and resolution reports)
12. Plant layout and equipment drawings which identify the physical plant locations of hot standby and cold shutdown equipment. 
    since the last triennial inspection.
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. 
                                                                                    Enclosure 1
14. Plant layout drawings which identify the general location of the post-fire emergency lighting.
 
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.
16. Maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, pumps and suppression systems.  
17. Maintenance procedures that 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.  
21. Organization charts of site personnel (including fire protection staff personnel).  
22. If applicable, drawings of potential reactor coolant/recirculation pump lube oil system leakage points and associated lube oil collection systems.  
23. 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.).  
24. Procedures/instructions that control the configuration of the plant's fire protection program, features, and post-fire safe shutdown methodology, and system design.  
25. A list of applicable codes and standards related to the design of plant fire protection features and evaluations of code deviations.  
26. Procedures/instructions that govern the implementation of plant modifications, maintenance, special operations, and their impact on fire protection.  
27. 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.  
28. Recent quality assurance surveillances of fire protection activities.  
29. 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 on CD-ROM or DVDROM is ".pdf").  The CD/DVD-ROM should be indexed, hyperlinked, readable, and searchable to facilitate ease of use.  Please provide 5 copies of each CD/DVD-ROM submitted.  The lead inspector will discuss specific information needs with the licensee staff and may request additional documents or electronic information.


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).  
                          Mitigating Strategies Supporting Documentation
Note: This is a broad list of the documents the NRC inspection team may be interested in
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.  
reviewing, and possibly obtaining, during the information gathering site visit. The current
version of these documents is expected unless specified otherwise. Electronic media is
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.  
preferred, if readily available. (The preferred file format on CD-ROM or DVDROM is .pdf).
The CD/DVD-ROM should be indexed, hyperlinked, readable, and searchable to facilitate ease
4. Engineering evaluations/calculations that were used to verify engineering bases for the mitigation strategies.  
of use. Please provide 5 copies of each CD/DVD-ROM submitted. The lead inspector will
5. Piping and instrumentation diagram for systems relied upon in the mitigation strategies. These could be of the type used for training.  
discuss specific information needs with the licensee staff and may request additional documents
6. A list of modification packages or simplified drawings or descriptions of modifications that were made to plant systems to implement the mitigation strategies.  
or electronic information.
7. Copies of procedures used to inventory equipment (hoses, fittings, pumps, etc.) required to implement the mitigation strategies.  
1.       A list of all modifications to regulatory commitments made to meet the requirements of
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.  
        Section B.5.b of NRC Order, EA-02-026, Order for NRC Interim Safeguards and
9. A copy of site general arrangement drawing(s) that show the majority of buildings/areas referenced in B.5.b documents.  
        Security Compensatory Measures, dated February 25, 2002, the subsequently
10. Training records, training matrix, and lesson plans related to B.5.b.  
        imposed license conditions, and Title 10 of the Code of Federal Regulations (10 CFR)
11. Copies of Memoranda of Understanding (MOUs) (e.g., with local fire departments) required to implement any mitigating strategies.
        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 (MOUs) (e.g., with local fire departments)
        required to implement any mitigating strategies.
                                                                                          Enclosure 2
}}
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Revision as of 03:14, 12 November 2019

Notification of Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000280-12-011 and 05000281-12-011)
ML121450437
Person / Time
Site: Surry  Dominion icon.png
Issue date: 05/23/2012
From: Mark King
Division of Nuclear Materials Safety II, NRC/RGN-II/DRS/EB2
To: Heacock D
Virginia Electric & Power Co (VEPCO)
References
IR-12-011
Download: ML121450437 (9)
v • d • e


See also: IR 05000280/2012011

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

May 23, 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: SURRY POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF TRIENNIAL

FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT

05000280/2012011 AND 05000281/2012011)

Dear 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 Surry Power

Station, Units 1 and 2, in July and August 2012. McKenzie Thomas, Senior Reactor Inspector,

will lead the team which will be composed of inspectors from the NRC Region II Office. The

inspection will be conducted in accordance with Inspection Procedure 71111.05T, the NRC=s

triennial fire protection baseline inspection procedure dated October 28, 2011.

The inspection objective will be to evaluate your fire protection program implementation with

emphasis on post-fire safe shutdown capability and the fire protection features provided to

ensure at least one post-fire safe shutdown success path is maintained free of fire damage.

The inspection team will focus their review on the systems and equipment necessary to achieve

and maintain safe shutdown and the fire protection features of selected fire areas.

On May 16, 2012, during a telephone conversation between Mr. Barry Garber, Surry Licensing

Supervisor, and Mrs. LaDonna Suggs, 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:

  • Information gathering visit: July 10 - 12, 2012
  • Week 1 of onsite inspection: July 30 - August 3, 2012
  • Week 2 of onsite inspection: August 13 - 17, 2012

VEPCO 2

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

needed to support the inspection, and to become familiar with the Surry Power Station fire

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

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); and, as necessary, obtain plant-

specific site access training and badging for unescorted site access. A list of the types of

documents the team may be interested in reviewing, and possibly obtaining, are listed in

Enclosures 1 and 2.

Please contact McKenzie Thomas or Rodney Fanner prior to preparing copies of the materials

listed in the Enclosure. The inspection team will try to minimize your administrative burden by

specifically identifying those documents required for inspection preparation.

During the information gathering visit, the team will also discuss the following administrative

details - office space; specific documents to be made available to the team in its office space;

arrangements for reactor site access (including 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 Surry Power Station fire

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

team for its review. Of specific interest 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, the 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 Surry 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 teams information or logistical needs, please

contact McKenzie Thomas at (404) 997-4673, Rodney Fanner at (404) 997-4638 or me at

(404) 997-4511.

VEPCO 3

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its

enclosure 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

(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

Engineering Branch 2

Division of Reactor Safety

Docket Nos.: 50-280, 50-281

License Nos.: DPR-32, DPR-37

Enclosures:

1. Triennial Fire Protection Program Supporting Documentation

2. Mitigating Strategies Supporting Documentation

cc w/encls: (See page 4)

_ML121450437_______________ xG SUNSI REVIEW COMPLETE G FORM 665 ATTACHED

OFFICE RII:DRS RII:DRS

SIGNATURE RA RA

NAME DJONES MKING

DATE 5/23/2012 5/23/2012 5/ /2012 5/ /2012 5/ /2012 5/ /2012 5/ /2012

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

VEPCO 4

cc w/encls: Michael M. Cline

Larry Lane Director

Site Vice President Virginia Department of Emergency Services

Surry Power Station Management

Virginia Electric and Power Company Electronic Mail Distribution

Electronic Mail Distribution

B. L. (Sonny) Stanley

Director, Nuclear Safety and Licensing

Virginia Electric and Power Company

Electronic Mail Distribution

Kenny B. Sloane

Plant Manager

Surry Power Station

Virginia Electric & Power Company

Electronic Mail Distribution

Lillian M. Cuoco, Esq.

Senior Counsel

Dominion Resources Services, Inc.

Electronic Mail Distribution

Tom Huber

Director, Nuclear Licensing & Operations

Support

Innsbrook Technical Center

Electronic Mail Distribution

Ginger L. Rutherford

Virginia Electric and Power Company

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

Surry Power Station

U.S. Nuclear Regulatory Commission

5850 Hog Island Rd

Surry, VA 23883

VEPCO 5

Letter to David A. Heacock from Michael F. King dated May 23, 2012.

SUBJECT: SURRY POWER STATION , UNITS 1 AND 2 - NOTIFICATION OF TRIENNIAL

FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT

05000280/2012011 AND 05000281/2012011)

Distribution w/encls:

RIDSNRRDIRS

PUBLIC

RidsNrrPMSurry 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. Electronic media is

preferred, if readily available. (The preferred file format on CD-ROM or DVDROM is .pdf).

The CD/DVD-ROM should be indexed, hyperlinked, readable, and searchable to facilitate ease

of use. Please provide 5 copies of each CD/DVD-ROM 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 or electronic information.

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 the selected fire

areas/zones (to be determined during information gathering visit).

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

actuations for the selected fire areas/zones (to be determined during information

gathering visit).

5. Cable routing for components and equipment credited for safe shutdown for the selected

fire areas/zones (to be determined during information gathering visit).

6. List of protected safe shutdown train equipment for the selected fire areas/zones (to be

determined during information gathering visit).

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

administrative controls, surveillance testing, 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 that 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.

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

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

leakage points and associated lube oil collection systems.

23. 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.).

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

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

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

features and evaluations of code deviations.

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

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

27. 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.

28. Recent quality assurance surveillances of fire protection activities.

29. 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 on CD-ROM or DVDROM is .pdf).

The CD/DVD-ROM should be indexed, hyperlinked, readable, and searchable to facilitate ease

of use. Please provide 5 copies of each CD/DVD-ROM submitted. The lead inspector will

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

or electronic information.

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 (MOUs) (e.g., with local fire departments)

required to implement any mitigating strategies.

Enclosure 2

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