ML081550578
| ML081550578 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/03/2008 |
| From: | Sandra Walker NRC/RGN-II/DRS/EB2 |
| To: | Duncan R Carolina Power & Light Co |
| References | |
| IR-08-008 | |
| Download: ML081550578 (7) | |
See also: IR 05000400/2008008
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
SAM NUNN ATLANTA FEDERAL CENTER
61 FORSYTH STREET, SW, SUITE 23T85
ATLANTA, GEORGIA 30303-8931
June 3, 2008
Carolina Power and Light Company
ATTN: Mr. R. J. Duncan, II
Vice President - Harris Plant
Shearon Harris Nuclear Power Plant
P. O. Box 165, Mail Code: Zone 1
New Hill, North Carolina 27562-0165
SUBJECT: NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
WHILE TRANSITION TO 10 CFR PART 50.48(c) IS IN PROGRESS
(NRC INSPECTION REPORT 05000400/2008008)
Dear Mr. Duncan:
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 Shearon Harris
Nuclear Power Plant, Unit 1 in September and October 2008. The inspection will be led by
Mr. McKenzie Thomas, NRC Senior Reactor Inspector, of the Region II Office. The team will be
composed of personnel from the NRC Region II Office and a contractor. The inspection will be
conducted in accordance with Inspection Procedure 71111.05TTP, the NRCs baseline fire
protection inspection procedure for plants in the process of implementing 10 CFR 50.48(c) and
National Fire Protection Association Standard (NFPA) 805. The inspection guidance is different
from the regular triennial inspections in that the inspectors will concentrate on the fire protection
program infrastructure and the adequacy of compensatory measures implemented for identified
departures from code requirements. Inspection of circuit analysis is not included in the
inspection procedure; however, electrical topics will be addressed by the team.
On May 30, 2008, during a telephone conversation, between Mr. Dave Corlett, of your staff, and
Mr. Necota Staples, of the NRC Region II Office, 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:
September 09 - 11, 2008
Week 1 of onsite inspection: September 22 - 26, 2008
Week 2 of onsite inspection: October 06 - 10, 2008
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, and to become familiar with the Shearon Harris Nuclear
Power Plant fire protection program, fire protection features, post-fire shutdown capabilities and
plant layout. The types of documents the team will be interested in reviewing, and possibly
obtaining, are listed in the Enclosure. Please contact Mr. Thomas 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.
2
During the information gathering visit, the team will also discuss the following administrative
details - office space; specific documents to be made available to the team in its office space;
arrangements for reactor site access (including radiation protection training, security, safety and
fitness for duty requirements); and the availability of knowledgeable plant engineering and
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 Shearon Harris Nuclear
Power Plant 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. 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 Shearon Harris Nuclear Power Plant fire protection
program and its implementation.
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 Mr. Thomas at (404) 562-4673, or me at (404) 562-4639.
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/
Shakur Walker, Acting Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos.: 50-400
License Nos.: NPF-63
Enclosure: Triennial Fire Protection Inspection Support Documentation
cc w/encl: (See page 3)
3
cc w/encl:
Paul Fulford
Manager
Performance Evaluation and Regulatory
Affairs PEB5
Carolina Power & Light Company
Electronic Mail Distribution
Chris L. Burton
Director Site Operations
Carolina Power & Light Company
Shearon Harris Nuclear Power Plant
Electronic Mail Distribution
J. Wayne Guganious
Training Manager
Harris
Progress Energy Carolinas, Inc.
Electronic Mail Distribution
Phyllis N. Mentel
(Acting) Manager
Support Services
Shearon Harris Nuclear Power Plant
Electronic Mail Distribution
David H. Corlett
Supervisor
Licensing/Regulatory Programs
Carolina Power & Light Company
Electronic Mail Distribution
David T. Conley
Associate General Counsel
Legal Dept.
Progress Energy Service Company, LLC
Electronic Mail Distribution
John H. O'Neill, Jr.
Shaw, Pittman, Potts & Trowbridge
2300 N. Street, NW
Washington, DC 20037-1128
Beverly O. Hall
Chief, Radiation Protection Section
Department of Environmental Health
N.C. Department of Environment and
Natural Resources
Electronic Mail Distribution
Public Service Commission
State of South Carolina
P.O. Box 11649
Columbia, SC 29211
Chairman
North Carolina Utilities Commission
Electronic Mail Distribution
Robert P. Gruber
Executive Director
Public Staff - NCUC
4326 Mail Service Center
Raleigh, NC 27699-4326
Herb Council
Chair
Board of County Commissioners of Wake
County
P.O. Box 550
Raleigh, NC 27602
Tommy Emerson
Chair
Board of County Commissioners of
Chatham County
186 Emerson Road
Siler City, NC 27344
Kelvin Henderson
Plant General Manager
Carolina Power and Light Company
Shearon Harris Nuclear Power Plant
Electronic Mail Distribution
Senior Resident Inspector
Carolina Power and Light Company
Shearon Harris Nuclear Power Plant
U.S. NRC
5421 Shearon Harris Rd
New Hill, NC 27562-9998
_________________________
OFFICE
RII:DRS
RII:DRS
RII:DRP
SIGNATURE
NAME
M. THOMAS
S. WALKER
R. MUSSER
DATE
6/2/2008
6/3/2008
6/3/2008
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
Enclosure
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 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 Fire Protection Program document and the Fire Hazards Analysis.
2.
The Fire Protection Program implementing procedures (e.g., administrative controls,
surveillance testing, fire brigade).
3.
The fire brigade training program document and the pre-fire plans for the selected fire
areas/zones (to be determined during information gathering visit).
4.
The post-fire safe shutdown analysis, including system and separation analyses.
5.
The alternative shutdown analysis.
6.
Piping and instrumentation (flow) diagrams for the fire suppression systems.
7.
Piping and instrumentation (flow) diagrams for the systems and components used to
achieve and maintain hot standby, and cold shutdown, for fires involving shutdown from
the control room.
8.
Piping and instrumentation (flow) diagrams for the systems and components used to
achieve and maintain hot standby, and cold shutdown, for fires in areas requiring
alternative or dedicated shutdown capability.
9.
Plant layout and equipment drawings which identify the physical plant locations of hot
standby and cold shutdown equipment.
10.
Plant layout drawings which identify plant fire area and/or fire zone delineation, areas
protected by automatic fire suppression and detection, and the locations of fire
protection equipment for the selected fire areas/zones (to be determined during
information gathering visit).
11.
Plant layout drawings which identify the general location of the post-fire emergency
lighting units.
12.
Plant operating procedures that describe and are used to shutdown from inside the
control room with a postulated fire occurring in any plant area outside the control room.
Enclosure
2
13.
Plant operating procedures used to implement the alternative shutdown capability from
outside the control room with a fire in either the control or cable spreading room (or any
other alternative shutdown area).
14.
Maintenance and surveillance testing procedures for alternative shutdown capability
(including Appendix R emergency lights and communication systems) and fire barriers,
detectors, fire pumps and fire suppression systems.
15.
Calculations and/or justifications that verify fuse/breaker coordination for the selected fire
areas/zones (to be determined during information gathering visit) that are fed off the
same electrical buses as components in the protected train. Also, a list of the
maintenance procedures used to routinely verify fuse/breaker coordination in
accordance with the post-fire safe shutdown coordination analysis.
16.
A list of the significant fire protection and post-fire safe shutdown design change
descriptions (including their associated 10 CFR 50.59 evaluations) and Generic Letter
(GL) 86-10 evaluations.
17.
A list of the protection methodologies (as identified in 10 CFR Part 50, Appendix R,
Section III.G) used to achieve regulatory compliance for the selected fire areas/zones (to
be determined during information gathering visit). That is, please specify whether 3-hour
rated fire barriers (Section III.G.2.a), 20-foot separation along with detection and
suppression (Section III.G.2.b), 1-hour rated fire barriers with detection and suppression
(Section III.G.2.c), or alternative shutdown capability (Section III.G.3) is used for the
selected fire areas/zones.
18.
Procedures or instructions that govern the implementation of plant modifications,
temporary modifications, maintenance, and special operations, and their impact on fire
protection.
19.
Organization chart(s) of site personnel down to the level of the fire protection staff.
20.
Procedures or instructions that control the configuration of the fire protection program,
features, and post-fire safe shutdown methodology and system design.
21.
A list of applicable codes and standards related to the design of plant fire protection
features and evaluations of code deviations (i.e., a listing of the NFPA code editions
committed to (Code of Record)).
22.
The three most recent fire protection QA audits and/or fire protection self-assessments.
23.
A list of open and closed fire protection problem identification and resolution reports
[also known as action reports/condition reports/problem investigation
reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for the
past three years.
24.
A list of plant fire protection licensing basis documents (i.e., a list of the SERs and
change evaluations which form the licensing basis for the facilitys post-fire safe
shutdown configuration).
Enclosure
3
25.
A list of fire protection or Appendix R calculations.
26.
A list of fire impairments identified during the previous year.
27.
A list of abbreviations/designators for plant systems.