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| number = ML121450437
| number = ML121450437
| issue date = 05/23/2012
| issue date = 05/23/2012
| title = Surry Power Station, Units 1 and 2 - Notification of Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000280-12-011 and 05000281-12-011)
| title = Notification of Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000280-12-011 and 05000281-12-011)
| author name = King M F
| author name = King M
| author affiliation = NRC/RGN-II/DNMS, NRC/RGN-II/DRS/EB2
| author affiliation = NRC/RGN-II/DNMS, NRC/RGN-II/DRS/EB2
| addressee name = Heacock D A
| addressee name = Heacock D
| addressee affiliation = Virginia Electric & Power Co (VEPCO)
| addressee affiliation = Virginia Electric & Power Co (VEPCO)
| docket = 05000280, 05000281
| docket = 05000280, 05000281
Line 14: Line 14:
| page count = 9
| page count = 9
}}
}}
See also: [[followed by::IR 05000280/2012011]]
See also: [[see also::IR 05000280/2012011]]


=Text=
=Text=
{{#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  
245 PEACHTREE CENTER AVENUE NE, SUITE 1200  
ATLANTA, GEORGIA  30303-1257  
May 23, 2012  
   
   
Mr. David A. Heacock  
Mr. David A. Heacock  
Line 27: Line 32:
5000 Dominion Boulevard  
5000 Dominion Boulevard  
Glen Allen, VA 23060-6711  
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:  
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
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
2  
=s triennial fire protection baseline inspection procedure dated October 28, 2011.
   
 
   
The inspection objective will be to evaluate your fire protection program implementation with
The purposes of the information gathering visit are to obtain information and documentation  
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.
needed to support the inspection, and to become familiar with the Surry Power Station fire  
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-
protection program, fire protection features, post-fire shutdown capabilities and plant layout  
day information gathering onsite visit and a two-week onsite inspection.  The schedule for the inspection is:
mitigating strategies to address Section B.5.b of NRC Order EA-02-026, Order for Interim  
  * Information gathering visit: July 10 - 12, 2012
Safeguards and Security Compensatory Measures, dated February 25, 2002, and Title 10 of  
* Week 1 of onsite inspection: July 30 - August 3, 2012
the Code of Federal Regulations (10 CFR) 50.54(hh)(2); and, as necessary, obtain plant-
* Week 2 of onsite inspection: August 13 - 17, 2012  
specific site access training and badging for unescorted site access.  A list of the types of  
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.   
documents the team may be interested in reviewing, and possibly obtaining, are listed in  
  Please contact McKenzie Thomas or Rodney Fanner prior to preparing copies of the materials  
Enclosures 1 and 2.   
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  
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.  
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  
We request that during the inspection weeks you ensure that copies of analyses, evaluations or  
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.  
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  
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  
team for its review.  Of specific interest are those documents which establish that your fire  
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   
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.  
(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
VEPCO
G SUNSI REVIEW COMPLETE
3
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: Larry Lane Site Vice President Surry Power Station Virginia Electric and Power Company Electronic Mail Distribution
   
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) 


  B. L. (Sonny) Stanley Director, Nuclear Safety and Licensing Virginia Electric and Power Company Electronic Mail Distribution
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


  Kenny B. Sloane Plant Manager Surry Power Station Virginia Electric & Power Company Electronic Mail Distribution  
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  
   
   
Lillian M. Cuoco, Esq. Senior Counsel Dominion Resources Services, Inc. Electronic Mail Distribution  
Kenny B. Sloane
Plant Manager
Surry Power Station
Virginia Electric & Power Company
Electronic Mail Distribution  
   
   
Tom Huber Director, Nuclear Licensing & Operations Support Innsbrook Technical Center 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


Ginger L. Rutherford Virginia Electric and Power Company Electronic Mail Distribution
VEPCO
5
   
   
Virginia State Corporation Commission Division of Energy Regulation P.O. Box 1197 Richmond, VA  23209
Letter to David A. Heacock from Michael F. King dated May 23, 2012.
   
   
Attorney General Supreme Court Building 900 East Main Street Richmond, VA  23219
SUBJECT:
  Senior Resident Inspector Surry Power Station
SURRY POWER STATION , UNITS 1 AND 2 - NOTIFICATION OF TRIENNIAL
U.S. Nuclear Regulatory Commission 5850 Hog Island Rd Surry, VA  23883
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).
    
    
  Michael M. Cline Director Virginia Department of Emergency Services Management Electronic Mail Distribution
4.
VEPCO 5 Letter to David A. Heacock from Michael F. King dated May 23, 2012.  
Corrective actions for fire-induced circuit failures, both single and multiple spurious
  SUBJECT: SURRY POWER STATION , UNITS 1 AND 2 - NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT 05000280/2012011 AND 05000281/2012011)  
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.).
   
   
Distribution w/encls:
24.
RIDSNRRDIRS PUBLIC RidsNrrPMSurry Resource 
Procedures/instructions that control the configuration of the plant's fire protection
 
program, features, and post-fire safe shutdown methodology, and system design.  
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.
25.  
2.  Corrective action closeouts as part of operator manual actions corrective actions.
A list of applicable codes and standards related to the design of plant fire protection
3.  List of identified fire induced circuit failure configurations for the selected fire areas/zones (to be determined during information gathering visit).
features and evaluations of code deviations.  
 
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). 
26.  
8.  Fire brigade training program and pre-fire plans.
Procedures/instructions that govern the implementation of plant modifications,  
maintenance, special operations, and their impact on fire protection.  
   
   
9.   Post-fire safe shutdown systems and separation analysis. 
27.  
10.  Post-fire alternative shutdown analysis. 
Internal and external self-assessments, audits, peer-assessments or similar reviews
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. 
related to post-fire safe shutdown capability or the fire protection program completed
12. Plant layout and equipment drawings which identify the physical plant locations of hot standby and cold shutdown equipment. 
since the previous NRC fire protection 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. 
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."
28.  
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.
  Recent quality assurance surveillances of fire protection activities.  
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.
29.  
25. A list of applicable codes and standards related to the design of plant fire protection features and evaluations of code deviations.
A listing of open and closed fire protection condition reports (problem reports/nuclear  
26. Procedures/instructions that govern the implementation of plant modifications, maintenance, special operations, and their impact on fire protection.  
condition reports/event analysis reports/problem identification, and resolution reports)  
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.  
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.  
Enclosure 2
  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.  
Mitigating Strategies Supporting Documentation
  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.  
Note: This is a broad list of the documents the NRC inspection team may be interested in
  9.  A copy of site general arrangement drawing(s) that show the majority of buildings/areas referenced in B.5.b documents.  
reviewing, and possibly obtaining, during the information gathering site visit.  The current
  10. Training records, training matrix, and lesson plans related to B.5.b.  
version of these documents is expected unless specified otherwise.  Electronic media is
  11. Copies of Memoranda of Understanding (MOUs) (e.g., with local fire departments) required to implement any mitigating strategies.
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.
}}
}}

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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