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{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES  
                                NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION  
                                                REGION II
REGION II  
                            245 PEACHTREE CENTER AVENUE NE, SUITE 1200
245 PEACHTREE CENTER AVENUE NE, SUITE 1200  
                                      ATLANTA, GEORGIA 30303-1257
ATLANTA, GEORGIA 30303-1257  
                                              May 23, 2012
Mr. David A. Heacock
May 23, 2012  
President and Chief Nuclear Officer
Virginia Electric and Power Company
Mr. David A. Heacock  
Dominion Nuclear
President and Chief Nuclear Officer  
Innsbrook Technical Center
Virginia Electric and Power Company  
5000 Dominion Boulevard
Dominion Nuclear  
Glen Allen, VA 23060-6711
Innsbrook Technical Center  
SUBJECT:         SURRY POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF TRIENNIAL
5000 Dominion Boulevard  
                FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT
Glen Allen, VA 23060-6711  
                05000280/2012011 AND 05000281/2012011)
Dear Heacock:
SUBJECT:  
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
SURRY POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF TRIENNIAL  
Region II staff will conduct a triennial fire protection baseline inspection at the Surry Power
FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT  
Station, Units 1 and 2, in July and August 2012. McKenzie Thomas, Senior Reactor Inspector,
05000280/2012011 AND 05000281/2012011)  
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
Dear Heacock:  
triennial fire protection baseline inspection procedure dated October 28, 2011.
The inspection objective will be to evaluate your fire protection program implementation with
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
emphasis on post-fire safe shutdown capability and the fire protection features provided to
Region II staff will conduct a triennial fire protection baseline inspection at the Surry Power  
ensure at least one post-fire safe shutdown success path is maintained free of fire damage.
Station, Units 1 and 2, in July and August 2012. McKenzie Thomas, Senior Reactor Inspector,  
The inspection team will focus their review on the systems and equipment necessary to achieve
will lead the team which will be composed of inspectors from the NRC Region II Office. The  
and maintain safe shutdown and the fire protection features of selected fire areas.
inspection will be conducted in accordance with Inspection Procedure 71111.05T, the NRC=s  
On May 16, 2012, during a telephone conversation between Mr. Barry Garber, Surry Licensing
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-
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
day information gathering onsite visit and a two-week onsite inspection. The schedule for the  
inspection is:
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
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
VEPCO  
The purposes of the information gathering visit are to obtain information and documentation
2  
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
The purposes of the information gathering visit are to obtain information and documentation  
Safeguards and Security Compensatory Measures, dated February 25, 2002, and Title 10 of
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-
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
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
documents the team may be interested in reviewing, and possibly obtaining, are listed in  
Enclosures 1 and 2.
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
Please contact McKenzie Thomas or Rodney Fanner prior to preparing copies of the materials  
specifically identifying those documents required for inspection preparation.
listed in the Enclosure. The inspection team will try to minimize your administrative burden by  
During the information gathering visit, the team will also discuss the following administrative
specifically identifying those documents required for inspection preparation.  
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
During the information gathering visit, the team will also discuss the following administrative  
fitness for duty requirements); and the availability of knowledgeable plant engineering and
details - office space; specific documents to be made available to the team in its office space;  
licensing organization personnel to serve as points of contact during the inspection.
arrangements for reactor site access (including radiation protection training, security, safety and  
We request that during the inspection weeks you ensure that copies of analyses, evaluations or
fitness for duty requirements); and the availability of knowledgeable plant engineering and  
documentation regarding the implementation and maintenance of the Surry Power Station fire
licensing organization personnel to serve as points of contact during the inspection.  
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
We request that during the inspection weeks you ensure that copies of analyses, evaluations or  
protection program satisfies NRC regulatory requirements and conforms to applicable NRC and
documentation regarding the implementation and maintenance of the Surry Power Station fire  
industry fire protection guidance. For the B.5.b portion of the inspection, the documents
protection program, including post-fire safe shutdown capability, be readily accessible to the  
implementing your mitigating strategies and demonstrating the management of your
team for its review. Of specific interest are those documents which establish that your fire  
commitments for the strategies are of specific interest. Also, personnel should be available at
protection program satisfies NRC regulatory requirements and conforms to applicable NRC and  
the site during the inspection who are knowledgeable regarding those plant systems required to
industry fire protection guidance. For the B.5.b portion of the inspection, the documents  
achieve and maintain safe shutdown conditions from inside and outside the control room
implementing your mitigating strategies and demonstrating the management of your  
(including the electrical aspects of the relevant post-fire safe shutdown analyses), reactor plant
commitments for the strategies are of specific interest. Also, personnel should be available at  
fire protection systems and features, and the Surry Power Station fire protection program and its
the site during the inspection who are knowledgeable regarding those plant systems required to  
implementation.
achieve and maintain safe shutdown conditions from inside and outside the control room  
This letter does not contain new or amended information collection requirements subject to the
(including the electrical aspects of the relevant post-fire safe shutdown analyses), reactor plant  
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
fire protection systems and features, and the Surry Power Station fire protection program and its  
requirements were approved by the Office of Management and Budget, under control
implementation.  
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
This letter does not contain new or amended information collection requirements subject to the  
requesting document displays a currently valid Office of Management and Budget control
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection  
number.
requirements were approved by the Office of Management and Budget, under control  
Your cooperation and support during this inspection will be appreciated. If you have questions
number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to  
concerning this inspection, or the inspection teams information or logistical needs, please
respond to, a request for information or an information collection requirement unless the  
contact McKenzie Thomas at (404) 997-4673, Rodney Fanner at (404) 997-4638 or me at
requesting document displays a currently valid Office of Management and Budget control  
(404) 997-4511.
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
VEPCO  
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its
3  
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-
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its  
rm/adams.html (the Public Electronic Reading Room).
enclosure will be available electronically for public inspection in the NRC Public Document  
                                              Sincerely,
Room or from the Publicly Available Records (PARS) component of NRCs document system  
                                              /RA/
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
                                              Michael F. King
rm/adams.html (the Public Electronic Reading Room).  
                                              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)
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)


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)
xG PUBLICLY AVAILABLE
G NON-PUBLICLY AVAILABLE
G SENSITIVE
xG NON-SENSITIVE
ADAMS: xG Yes
ACCESSION NUMBER: _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   
OFFICIAL
RECORD
COPY          DOCUMENT
NAME:
S:\\DRS\\ENG
BRANCH
2\\REPORTS\\SURRY\\NOTIFICATION
LETTERS\\SUR2012TFPI NOTIFICATION LETTER REV.1.DOCX


  _ML121450437_______________            xG SUNSI REVIEW COMPLETE G FORM 665 ATTACHED
VEPCO
  OFFICE            RII:DRS        RII:DRS
4
  SIGNATURE          RA            RA
   
  NAME              DJONES        MKING
cc w/encls:
  DATE                  5/23/2012      5/23/2012  5/  /2012      5/ /2012    5/    /2012      5/ /2012    5/ /2012
Larry Lane
  E-MAIL COPY?        YES    NO    YES      NO   YES    NO      YES    NO    YES      NO      YES    NO    YES   NO
Site Vice President
       
Surry Power Station
VEPCO                                    4
Virginia Electric and Power Company
cc w/encls:                                Michael M. Cline
Electronic Mail Distribution
Larry Lane                                Director
   
Site Vice President                        Virginia Department of Emergency Services
B. L. (Sonny) Stanley
Surry Power Station                        Management
Director, Nuclear  Safety and Licensing
Virginia Electric and Power Company        Electronic Mail Distribution
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
Michael M. Cline  
Director  
Virginia Department of Emergency Services  
Management  
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
VEPCO  
Letter to David A. Heacock from Michael F. King dated May 23, 2012.
5  
SUBJECT:       SURRY POWER STATION , UNITS 1 AND 2 - NOTIFICATION OF TRIENNIAL
              FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT
Letter to David A. Heacock from Michael F. King dated May 23, 2012.  
              05000280/2012011 AND 05000281/2012011)
Distribution w/encls:
SUBJECT:  
RIDSNRRDIRS
SURRY POWER STATION , UNITS 1 AND 2 - NOTIFICATION OF TRIENNIAL  
PUBLIC
FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT  
RidsNrrPMSurry Resource
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
Enclosure 1
reviewing, and possibly obtaining, during the information gathering site visit. Electronic media is
Triennial Fire Protection Program Supporting Documentation  
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
Note: This is a broad list of the documents the NRC inspection team may be interested in  
of use. Please provide 5 copies of each CD/DVD-ROM submitted. Information in lists should
reviewing, and possibly obtaining, during the information gathering site visit. Electronic media is  
contain enough information to be easily understood by someone who has knowledge of the
preferred, if readily available. (The preferred file format on CD-ROM or DVDROM is .pdf).
technology. The lead inspector will discuss specific information needs with the licensee staff
The CD/DVD-ROM should be indexed, hyperlinked, readable, and searchable to facilitate ease  
and may request additional documents or electronic information.
of use. Please provide 5 copies of each CD/DVD-ROM submitted. Information in lists should  
1.     The current version of the fire protection program and fire hazards analysis.
contain enough information to be easily understood by someone who has knowledge of the  
2.     Corrective action closeouts as part of operator manual actions corrective actions.
technology. The lead inspector will discuss specific information needs with the licensee staff  
3.     List of identified fire induced circuit failure configurations for the selected fire
and may request additional documents or electronic information.  
        areas/zones (to be determined during information gathering visit).
4.     Corrective actions for fire-induced circuit failures, both single and multiple spurious
1.
        actuations for the selected fire areas/zones (to be determined during information
The current version of the fire protection program and fire hazards analysis.  
        gathering visit).
5.     Cable routing for components and equipment credited for safe shutdown for the selected
2.
        fire areas/zones (to be determined during information gathering visit).
Corrective action closeouts as part of operator manual actions corrective actions.  
6.     List of protected safe shutdown train equipment for the selected fire areas/zones (to be
        determined during information gathering visit).
3.
7.       Current versions of the fire protection program implementing procedures (e.g.,
List of identified fire induced circuit failure configurations for the selected fire  
        administrative controls, surveillance testing, fire brigade).
areas/zones (to be determined during information gathering visit).  
8.       Fire brigade training program and pre-fire plans.
 
9.       Post-fire safe shutdown systems and separation analysis.
4.  
10.     Post-fire alternative shutdown analysis.
Corrective actions for fire-induced circuit failures, both single and multiple spurious  
11.     Piping and instrumentation diagrams showing the components used to achieve and
actuations for the selected fire areas/zones (to be determined during information  
        maintain hot standby and cold shutdown for fires outside the control room and those
gathering visit).  
        components used for those areas requiring alternative shutdown capability.
12.     Plant layout and equipment drawings which identify the physical plant locations of hot
5.  
        standby and cold shutdown equipment.
Cable routing for components and equipment credited for safe shutdown for the selected  
13.     Plant layout drawings which identify plant fire area delineation, areas protected by
fire areas/zones (to be determined during information gathering visit).  
        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
6.  
        lighting.
List of protected safe shutdown train equipment for the selected fire areas/zones (to be  
                                                                                            Enclosure 1
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.  


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


                          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
Enclosure 2
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
Mitigating Strategies Supporting Documentation  
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
Note: This is a broad list of the documents the NRC inspection team may be interested in  
or electronic information.
reviewing, and possibly obtaining, during the information gathering site visit. The current  
1.       A list of all modifications to regulatory commitments made to meet the requirements of
version of these documents is expected unless specified otherwise. Electronic media is  
        Section B.5.b of NRC Order, EA-02-026, Order for NRC Interim Safeguards and
preferred, if readily available. (The preferred file format on CD-ROM or DVDROM is .pdf).
        Security Compensatory Measures, dated February 25, 2002, the subsequently
The CD/DVD-ROM should be indexed, hyperlinked, readable, and searchable to facilitate ease  
        imposed license conditions, and Title 10 of the Code of Federal Regulations (10 CFR)
of use. Please provide 5 copies of each CD/DVD-ROM submitted. The lead inspector will  
        50.54(hh)(2).
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
or electronic information.  
        mitigation strategies. These could be extensive damage mitigation guidelines
        (EDMGs), severe accident management guidelines (SAMGs), emergency operating
1.
        procedures (EOPs), abnormal operating procedures (AOPs), etc.
A list of all modifications to regulatory commitments made to meet the requirements of  
3.       A matrix that shows the correlation between the mitigation strategies identified in
Section B.5.b of NRC Order, EA-02-026, Order for NRC Interim Safeguards and  
        Nuclear Energy Institute 06-12, Revision 2, B.5.b Phase 2 & 3 Submittal Guideline,
Security Compensatory Measures, dated February 25, 2002, the subsequently  
        issued December 2006, and the site-specific procedures or guidelines used to
imposed license conditions, and Title 10 of the Code of Federal Regulations (10 CFR)  
        implement each strategy.
50.54(hh)(2).  
4.       Engineering evaluations/calculations that were used to verify engineering bases for the
        mitigation strategies.
2.
5.       Piping and instrumentation diagram for systems relied upon in the mitigation strategies.
Lists of procedures/guidelines that were revised or generated to implement the  
        These could be of the type used for training.
mitigation strategies. These could be extensive damage mitigation guidelines  
6.       A list of modification packages or simplified drawings or descriptions of modifications
(EDMGs), severe accident management guidelines (SAMGs), emergency operating  
        that were made to plant systems to implement the mitigation strategies.
procedures (EOPs), abnormal operating procedures (AOPs), etc.  
7.       Copies of procedures used to inventory equipment (hoses, fittings, pumps, etc.)
        required to implement the mitigation strategies.
3.
8.       A list of B.5.b strategies, if any, that have implementing details that differ from those
A matrix that shows the correlation between the mitigation strategies identified in  
        documented in the submittals and the safety evaluation report.
Nuclear Energy Institute 06-12, Revision 2, B.5.b Phase 2 & 3 Submittal Guideline,  
9.       A copy of site general arrangement drawing(s) that show the majority of buildings/areas
issued December 2006, and the site-specific procedures or guidelines used to  
        referenced in B.5.b documents.
implement each strategy.  
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)
4.
        required to implement any mitigating strategies.
Engineering evaluations/calculations that were used to verify engineering bases for the  
                                                                                          Enclosure 2
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.
}}
}}

Latest revision as of 01:55, 12 January 2025

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)

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)

xG PUBLICLY AVAILABLE

G NON-PUBLICLY AVAILABLE

G SENSITIVE

xG NON-SENSITIVE

ADAMS: xG Yes

ACCESSION NUMBER: _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

OFFICIAL

RECORD

COPY DOCUMENT

NAME:

S:\\DRS\\ENG

BRANCH

2\\REPORTS\\SURRY\\NOTIFICATION

LETTERS\\SUR2012TFPI NOTIFICATION LETTER REV.1.DOCX

VEPCO

4

cc w/encls:

Larry Lane

Site Vice President

Surry Power Station

Virginia Electric and Power Company

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

Michael M. Cline

Director

Virginia Department of Emergency Services

Management

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

Enclosure 1

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.

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).

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.

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