ML111510959
| ML111510959 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/31/2011 |
| From: | Nease R NRC/RGN-II/DRS/EB2 |
| To: | Burton C Carolina Power & Light Co |
| References | |
| Download: ML111510959 (9) | |
See also: IR 05000400/2011009
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
May 31, 2011
Mr. Christopher L. Burton
Vice President
Carolina Power and Light Company
Shearon Harris Nuclear Power Plant
P. O. Box 165, Mail Code: Zone 1
New Hill, North Carolina 27562-0165
SUBJECT: SHEARON HARRIS NUCLEAR POWER PLANT- NOTIFICATION OF
CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
(NRC INSPECTION REPORT NO. 05000400/2011009)
Dear Mr. Burton:
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 Shearon Harris
Nuclear Power Plant in August and September 2011. The inspection team will be led by Mr.
Reinaldo Rodriguez, NRC Senior Reactor Inspector, of the Region II Office. The team will be
composed of personnel from the NRC Regional and Headquarters Offices. The inspection will
be conducted in accordance with Inspection Procedure 71111.05XT, the NRCs baseline fire
protection inspection procedure for plants implementing 10 CFR 50.48(c) and National Fire
Protection Association Standard (NFPA) 805.
On February 2, 2011, during a telephone conversation between Mr. John Caves (Harris
Licensing Supervisor) of your staff, and Mr. Rodriguez, 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: August 9 - 11, 2011
- Week 1 of onsite inspection: August 29 - September 2, 2011
- Week 2 of onsite inspection: September 19 - 23, 2011
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, to become familiar with the Shearon Harris Nuclear Power
Plant fire protection programs, fire protection features, and post-fire safe shutdown capabilities
and plant layout, mitigating strategies to address Section B.5.b of the Interim Compensatory
Measures Order, EA-02-026, of February 25, 2002/10 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. Rodriguez 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.
CP&L 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 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 Harris 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 that 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 Harris 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, 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. Rodriguez at (404) 997-4498, or me at (404) 997-4503.
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 NRCs document system
CP&L 3
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html http://www.nrc.gov/reading-rm/adams.html(the Public Electronic Reading
Room).
Sincerely,
/RA by Gerald Wiseman Acting For/
Rebecca L. Nease, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No.: 50-400
License Nos.: NPF-63
Enclosures: 1. Triennial Fire Protection Inspection Support Documentation
2. Mitigating Strategies Support Documentation
cc w/encl. (See page 4)
_ML111510959__________ X SUNSI REVIEW COMPLETE G FORM 665 ATTACHED
OFFICE RII:DRS RII:DRS RII:DRP
SIGNATURE RRR1 GWiseman for RAM
NAME RRodriguez RNease RMusser
DATE 05/31/2011 05/31/2011 05/31/2011
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
CP&L 4
cc w/encl: W. Lee Cox, III
Brian C. McCabe Section Chief
Manager, Nuclear Oversight Radiation Protection Section
Shearon Harris Nuclear Power Plant N.C. Department of Environmental
Progress Energy Commerce & Natural Resources
Electronic Mail Distribution Electronic Mail Distribution
Donald L. Griffith Public Service Commission
Training Manager State of South Carolina
Shearon Harris Nuclear Power Plant P.O. Box 11649
Progress Energy Columbia, SC 29211
Electronic Mail Distribution
Chairman
LaQuisha M. Parks North Carolina Utilities Commission
Manager Electronic Mail Distribution
Support Services
Shearon Harris Nuclear Power Plant Robert P. Gruber
Electronic Mail Distribution Executive Director
Public Staff - NCUC
David H. Corlett 4326 Mail Service Center
Supervisor Raleigh, NC 27699-4326
Licensing/Regulatory Programs
Progress Energy Chair
Electronic Mail Distribution Board of County Commissioners of Wake
County
David T. Conley P.O. Box 550
Senior Counsel Raleigh, NC 27602
Legal Department
Progress Energy Ernest J. Kapopoulos Jr.
Electronic Mail Distribution Plant General Manager
Carolina Power and Light Company
Donna B. Alexander Shearon Harris Nuclear Power Plant
Manager, Nuclear Regulatory Affairs Electronic Mail Distribution
(interim)
Progress Energy Chair
Electronic Mail Distribution Board of County Commissioners of
Chatham County
John H. O'Neill, Jr. P.O. Box 1809
Shaw, Pittman, Potts & Trowbridge Pittsboro, NC 27312
2300 N. Street, NW
Washington, DC 20037-1128 Senior Resident Inspector
U.S. Nuclear Regulatory Commission
Joseph W. Donahue Shearon Harris Nuclear Power Plant
Vice President U.S. NRC
Nuclear Oversight 5421 Shearon Harris Rd
Progress Energy New Hill, NC 27562-9998
Electronic Mail Distribution
CP&L 5
Letter to Christopher L. Burton from Rebecca L. Nease dated May 31, 2011.
SUBJECT: SHEARON HARRIS NUCLEAR POWER PLANT- NOTIFICATION OF
CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
(NRC INSPECTION REPORT NO. 05000400/2011009)
Distribution w/encl:
C. Evans, RII EICS
L. Douglas, RII EICS
OE Mail
RIDSNRRDIRS
PUBLIC
RidsNrrPMShearonHarris Resource
Triennial Fire Protection Inspection Support 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 DVD-
ROM 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. Current versions of the fire protection program implementing procedures (e.g.,
administrative controls, surveillance testing, and fire brigade).
3. Fire brigade training program and pre-fire plans.
4. Post-fire nuclear safety capability systems and separation analysis.
5. Analysis supporting achieving and maintaining nuclear safety performance criteria,
including those analyses for areas requiring recovery actions.
6. Piping and instrumentation (flow) diagrams showing the components used to achieve
and maintain nuclear safety performance criteria for fires outside the control room and
other areas requiring recovery actions at other than primary control stations.
7. Plant layout and equipment drawings that identify the physical plant locations of nuclear
safety capability equipment.
8. Plant layout drawings that identify plant fire area delineation, areas protected by
automatic fire suppression and detection, and the locations of fire protection equipment.
9. Plant layout drawings which identify the general location of the emergency lighting units
required to support achieving and maintaining nuclear safety performance criteria.
10. Plant operating procedures for achieving nuclear safety performance criteria from inside
the control room with a postulated fire occurring in any plant area outside the control
room, procedures for achieving nuclear safety performance criteria in the event of a fire
in either the control or cable spreading room, or any area requiring recovery actions to
achieve control from other than the main control room or primary control stations.
11. Maintenance and surveillance testing procedures for nuclear safety capability systems
and equipment, and fire barriers, detectors, pumps and suppression systems.
12. Maintenance procedures that routinely verify fuse breaker coordination in accordance
with the nuclear safety circuit coordination analysis.
Enclosure 1
13. A sample of significant design change packages and engineering equivalency
evaluations related to fire protection and post-fire nuclear safety capability (e.g.,
Generic Letter 86-10 evaluations).
14. The reactor plant's probabilistic risk assessment (PRA), results of any PRA reviews,
and listings of actions taken or plant modifications conducted in response to PRA
information (including NFPA 805, Section 2.4.3, Fire Risk Evaluations, and NFPA 805,
Section 2.4.4, Plant Change Evaluations).
15. Temporary modification procedures.
16. Organization charts of site personnel, including fire protection staff personnel.
17. If applicable, layout or arrangement drawings of potential reactor coolant/recirculation
pump lube oil system leakage points and associated lube oil collection systems.
18. A listing of the safety evaluations that form the licensing basis for the reactor plant's
post-fire nuclear safety capability.
19. Procedures or instructions that control the configuration of the reactor plant's fire
protection program, features, and post-fire nuclear safety capability methodology and
system design.
20. A list of applicable codes and standards related to the design of plant fire protection
features and evaluations of code deviations, including any safety evaluations issued for
deviations from NFPA 805 fundamental fire protection program and design elements
(NFPA 805, Chapter 3).
21. Procedures or instructions that govern the implementation of plant modifications,
maintenance, and special operations, and their impact on fire protection.
22. The three most recent fire protection quality assurance (QA) audits and/or self-
assessments.
23. Recent QA surveillances of fire protection activities.
24. A listing of open and closed fire protection condition reports (problem reports / nuclear
condition reports (NCRs) / event analysis reports (EARs) / problem identification and
resolution reports).
25. Listing of plant fire protection program and licensing basis documents.
26. A listing of the NFPA code versions committed to (NFPA codes of record).
27. A listing of plant deviations from code commitments.
28. Actual copies of engineering equivalency evaluations (e.g., Generic Letter 86-10
evaluations).
Enclosure 1
Mitigating Strategies Support 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 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 the ICM Order, EA-02-026, dated February 25, 2002, the subsequently
imposed license conditions, and 10 CFR 50.54(hh)(2).
2. Copies 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 and the site-specific procedures or guidelines that are
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 (P&ID) or simplified flow diagrams for systems relied
upon in the mitigation strategies. These could be the type used for training.
6. A modification package or simplified drawings/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 be used to implement the mitigation strategies.
8. A list of B.5.b strategies, if any, which have implementing details that differ from that
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/lesson plans related to B.5.b.
11. Copies of Memoranda of Understanding (MOUs) (e.g., with local fire departments)
required to implement any mitigating strategies.
Enclosure 2