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{{Adams
#REDIRECT [[IR 05000338/2012012]]
| number = ML12235A291
| issue date = 08/17/2012
| title = IR 05000338-12-012, 05000339-12-012, on 10/28/2011, North Anna Power Station, Units 1 & 2 - Notification of Conduct of a Triennial Fire Protection Baseline Inspection
| author name = King M
| author affiliation = NRC/RGN-II/DRS/EB2
| addressee name = Heacock D
| addressee affiliation = Virginia Electric & Power Co (VEPCO)
| docket = 05000338, 05000339
| license number = NPF-004, NPF-007
| contact person =
| document report number = IR-12-012
| document type = Letter, Inspection Plan
| page count = 9
}}
See also: [[see also::IR 05000338/2012012]]
 
=Text=
{{#Wiki_filter:UNITED STATES
                                NUCLEAR REGULATORY COMMISSION
                                                REGION II
                            245 PEACHTREE CENTER AVENUE NE, SUITE 1200
                                      ATLANTA, GEORGIA 30303-1257
                                            August 17, 2012
Mr. David A. Heacock
President and Chief Nuclear Officer
Virginia Electric and Power Company
Dominion Nuclear
Innsbrook Technical Center
5000 Dominion Boulevard
Glen Allen, VA 23060-6711
SUBJECT:        NORTH ANNA POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF
                CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
                (NRC INSPECTION REPORT NOS. 05000338/2012012 AND
                05000339/2012012)
Dear Mr. Heacock:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a triennial fire protection baseline inspection at the North Anna
Power Station, Units 1 and 2, in November and December 2012. The inspection team will be
led by Mr. McKenzie Thomas, a Senior Reactor Inspector from the NRC Region II Office. The
team will be composed of personnel from the Region II Office. The inspection will be conducted
in accordance with Inspection Procedure 71111.05T, the NRCs triennial fire protection baseline
inspection procedure, dated October 28, 2011. Inspection of circuit analysis is included in the
inspection procedure.
On August 15, 2012, during a telephone conversation between Mr. Donald Taylor, North Anna
Licensing Supervisor, and Mr. Thomas, our respective staffs confirmed arrangements for a
three-day information gathering onsite visit and a two-week onsite inspection. The schedule for
the inspection is as follows:
    *  Information gathering visit: November 6-8, 2012
    *  Week 1 of onsite inspection: November 26-30, 2012
    *  Week 2 of onsite inspection: December 10-14, 2012
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, to become familiar with the North Anna Power Station fire
protection program, fire protection features, post-fire safe shutdown capabilities, plant layout,
and mitigating strategies to address Section B.5.b of NRC Order EA-02-026, Order for Interim
Safeguards and Security Compensatory Measures, dated February 25, 2002, and Title 10 of
the Code of Federal Regulations (10 CFR) 50.54(hh)(2). The types of documents the team will
be interested in reviewing, and possibly obtaining, are listed in Enclosures 1 and 2. Please
contact Mr. Thomas at (404) 997-4673 prior to preparing copies of the materials listed in the
Enclosures. The inspection team will try to minimize your administrative burden by specifically
identifying those documents required for inspection preparation.
 
D. Heacock                                        2
During the information gathering visit, the team will also discuss the following inspection support
administrative details: office space; specific documents to be made available to the team in their
office space; arrangements for unescorted site access (including, as necessary, radiation
protection training, security, safety and fitness for duty requirements); and the availability of
knowledgeable plant engineering and licensing organization personnel to serve as points of
contact during the inspection.
We request that during the inspection weeks you ensure that copies of analyses, evaluations or
documentation regarding the implementation and maintenance of the North Anna Power Station
fire protection program, including post-fire safe shutdown capability, be readily accessible to the
team for their review. Of specific interest for the fire protection portion of the inspection are
those documents which establish that your fire protection program satisfies NRC regulatory
requirements and conforms to applicable NRC and industry fire protection guidance. For the
B.5.b portion of the inspection, those documents implementing your mitigating strategies and
demonstrating the management of your commitments for the strategies are of specific interest.
Also, personnel should be available at the site during the inspection who are knowledgeable
regarding those plant systems required to achieve and maintain safe shutdown conditions from
inside and outside the control room (including the electrical aspects of the relevant post-fire safe
shutdown analyses), reactor plant fire protection systems and features, and the North Anna
Power Station fire protection program and its implementation.
This letter does not contain new or amended information collection requirements subject to the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
requirements were approved by the Office of Management and Budget, under control number
3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to,
a request for information or an information collection requirement unless the requesting
document displays a currently valid Office of Management and Budget control number.
Your cooperation and support during this inspection will be appreciated. If you have questions
concerning this inspection, or the inspection team's information or logistical needs, please
contact Mr. Thomas at (404) 997-4673, or me at (404) 997-4511.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosures will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRCs document system
 
D. Heacock                                      3
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room).
                                            Sincerely,
                                            /RA/
                                            Michael F. King, Chief
                                            Engineering Branch 2
                                            Division of Reactor Safety
Docket Nos.: 50-338, 50-339
License Nos.: NPF-4, NPF-7
Enclosures:  1. Triennial Fire Protection Inspection Support Documentation
              2. Mitigating Strategies Support Documentation
cc w/encls: (See page 4)
 
 
_________________________                xG SUNSI REVIEW COMPLETE G FORM 665 ATTACHED
OFFICE            RII:DRS        RII:DRS
SIGNATURE          RA              RA
NAME              MTHOMAS        MKING
DATE                  8/17/2012      8/17/2012    8/  /2012    8/  /2012    8/    /2012      8/  /2012    8/ /2012
E-MAIL COPY?        YES    NO    YES      NO  YES    NO    YES    NO    YES      NO      YES    NO    YES  NO
       
D. Heacock                              4
cc w/encls:                                Michael M. Cline
Mr. Gerald T. Bischof                      Director
Site Vice President                        Virginia Department of Emergency Services
North Anna Power Station                  Management
Virginia Electric & Power Company          Electronic Mail Distribution
Electronic Mail Distribution
                                          Executive Vice President
Fred Mladen                                Old Dominion Electric Cooperative
Director, Station Safety & Licensing      Electronic Mail Distribution
Virginia Electric and Power Company
Electronic Mail Distribution              County Administrator
                                          Louisa County
Michael Crist                              P.O. Box 160
Plant Manager                              Louisa, VA 23093
North Anna Power Station
Virginia Electric & Power Company          Doug Smith
Electronic Mail Distribution              President
                                          (Public Correspondence Only)
Lillian M. Cuoco, Esq.                    Lake Anna Civil Association
Senior Counsel                            Electronic Mail Distribution
Dominion Resources Services, Inc.
Electronic Mail Distribution
Tom Huber
Director, Nuclear Licensing & Operations
Support
Inssbrook Technical Center
Electronic Mail Distribution
Virginia State Corporation Commission
Division of Energy Regulation
P.O. Box 1197
Richmond, VA 23209
Attorney General
Supreme Court Building
900 East Main Street
Richmond, VA 23219
Senior Resident Inspector
North Anna Power Station
U.S. Nuclear Regulatory Commission
P.O. Box 490
Mineral, VA 23117
Donald R. Taylor
Licensing Supervisor
North Anna Power Station
P. O. Box 402
Mineral, VA 23117-0402
 
D. Heacock                                    5
Letter to David A. Heacock from Michael F. King dated August 17, 2012.
SUBJECT:      NORTH ANNA POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF
              CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
              (NRC INSPECTION REPORT NOS. 05000338/2012012 AND
              05000339/2012012)
Distribution w/encls:
RIDSNRRDIRS
PUBLIC
RidsNrrPMNorthAnna Resource
 
                    Triennial Fire Protection Program Supporting Documentation
Note: This is a broad list of the documents the NRC inspection team may be interested in
reviewing, and possibly obtaining, during the information-gathering site visit. The current
version of these documents is expected unless specified otherwise. Electronic media is
preferred, if readily available. (The preferred file format is searchable .pdf files on CDROM.
The CDROM should be indexed and hyperlinked to facilitate ease of use. Please provide
5 copies of each CDROM submitted.) Information in lists should contain enough information to
be easily understood by someone who has knowledge of the technology. The lead inspector
will discuss specific information needs with the licensee staff and may request additional
documents.
1.      The current version of the fire protection program and fire hazards analysis.
2.      Corrective action closeouts as part of operator manual actions corrective actions.
3.      List of identified fire induced circuit failure configurations for select fire areas.
4.      Corrective actions for fire-induced circuit failures, both single and multiple spurious
        actuations for select fire areas.
5.      Cable routing for components and equipment credited for safe shutdown for select fire
        areas.
6.      List of protected safe shutdown train equipment for select fire areas.
7.      Current versions of the fire protection program implementing procedures (e.g.,
        administrative controls, surveillance testing, and fire brigade).
8.      Fire brigade training program and pre-fire plans.
9.      Post-fire safe shutdown systems and separation analysis.
10.      Post-fire alternative shutdown analysis.
11.      Piping and instrumentation diagrams showing the components used to achieve and
        maintain hot standby and cold shutdown for fires outside the control room and those
        components used for those areas requiring alternative shutdown capability.
12.      Plant layout and equipment drawings which identify the physical plant locations of hot
        standby and cold shutdown equipment.
13.      Plant layout drawings which identify plant fire area delineation, areas protected by
        automatic fire suppression and detection, and the locations of fire protection equipment.
14.      Plant layout drawings which identify the general location of the post-fire emergency
        lighting.
                                                                                            Enclosure 1
 
                                                2
15.  Plant operating procedures which would be used and describe shutdown from inside
    the control room with a postulated fire occurring in any plant area outside the control
    room, procedures which would be used to implement alternative shutdown capability in
    the event of a fire in the control or cable spreading room.
16.  Maintenance and surveillance testing procedures for alternative shutdown capability
    and fire barriers, detectors, pumps, and suppression systems.
17.  Maintenance procedures which routinely verify fuse breaker coordination in accordance
    with the post-fire safe shutdown coordination analysis.
18.  A list of significant fire protection and post-fire safe shutdown related design change
    packages and evaluations according to Generic Letter 86-10, Implementation of Fire
    Protection Requirements.
19.  The reactor plant's Individual Plant Examination for External Events (IPEEE), results of
    any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in
    response to IPEEE information.
20.  Organization charts of site personnel (including fire protection staff personnel).
21.  If applicable, drawings of potential reactor coolant/recirculation pump lube oil system
    leakage points and associated lube oil collection systems.
22.  Licensing basis documents for fire protection (safety evaluation reports, pertinent
    sections of the final safety analysis report, exemptions, deviations, letters to/from the
    NRC regarding fire protection/fire safe shutdown, etc.).
23.  Procedures/instructions that control the configuration of the plant's fire protection
    program, features, and post-fire safe shutdown methodology and system design.
24.  A list of applicable codes and standards related to the design of plant fire protection
    features and evaluations of code deviations.
25.  Procedures/instructions that govern the implementation of plant modifications,
    maintenance, and special operations, and their impact on fire protection.
26.  Internal and external self-assessments, audits, peer-assessments or similar reviews
    related to post-fire safe shutdown capability or the fire protection program completed
    since the previous NRC fire protection triennial inspection.
27.  Recent quality assurance surveillances of fire protection activities.
28. A listing of open and closed fire protection condition reports (problem reports/nuclear
    condition reports/event analysis reports/problem identification and resolution reports)
    since the last triennial inspection.
                                                                                      Enclosure 1
 
                            Mitigating Strategies Supporting Documentation
Note: This is a broad list of the documents the NRC inspection team may be interested in
reviewing, and possibly obtaining, during the information gathering site visit. The current
version of these documents is expected unless specified otherwise. Electronic media is
preferred, if readily available. (The preferred file format is searchable .pdf files on CDROM.
The CDROM should be indexed and hyperlinked to facilitate ease of use. Please provide 5
copies of each CDROM submitted.) Information in lists should contain enough information to
be easily understood by someone who has knowledge of the technology. The lead inspector
will discuss specific information needs with the licensee staff and may request additional
documents.
1.        A list of all modifications to regulatory commitments made to meet the requirements of
          Section B.5.b of NRC Order, EA-02-026, Order for NRC Interim Safeguards and
          Security Compensatory Measures, dated February 25, 2002, the subsequently
          imposed license conditions, and Title 10 of the Code of Federal Regulations (10 CFR)
          50.54(hh)(2).
2.        Lists of procedures/guidelines that were revised or generated to implement the
          mitigation strategies. These could be extensive damage mitigation guidelines
          (EDMGs), severe accident management guidelines (SAMGs), emergency operating
          procedures (EOPs), abnormal operating procedures (AOPs), etc.
3.        A matrix that shows the correlation between the mitigation strategies identified in
          Nuclear Energy Institute 06-12, Revision 2, B.5.b Phase 2 & 3 Submittal Guideline,
          issued December 2006, and the site-specific procedures or guidelines used to
          implement each strategy.
4.        Engineering evaluations/calculations that were used to verify engineering bases for the
          mitigation strategies.
5.        Piping and instrumentation diagram for systems relied upon in the mitigation strategies.
          These could be of the type used for training.
6.        A list of modification packages or simplified drawings or descriptions of modifications
          that were made to plant systems to implement the mitigation strategies.
7.        Copies of procedures used to inventory equipment (hoses, fittings, pumps, etc.)
          required to implement the mitigation strategies.
8.        A list of B.5.b strategies, if any, that have implementing details that differ from those
          documented in the submittals and the safety evaluation report.
9.        A copy of site general arrangement drawing(s) that show the majority of buildings/areas
          referenced in B.5.b documents.
10.      Training records, training matrix, and lesson plans related to B.5.b.
11.      Copies of memoranda of understanding (e.g., with local fire departments) required to
        implement any mitigating strategies.
                                                                                            Enclosure 2
}}

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