ML073480241
| ML073480241 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/10/2007 |
| From: | Payne D NRC/RGN-II/DRS/EB2 |
| To: | Jerrica Johnson Southern Nuclear Operating Co |
| References | |
| IR-08-006 | |
| Download: ML073480241 (8) | |
See also: IR 05000348/2008006
Text
December 10, 2007
Southern Nuclear Operating Company, Inc.
ATTN: Mr. J. Randy Johnson
Vice President - Farley
Joseph M. Farley Nuclear Plant
7388 North State Highway 95
Columbia, AL 36319
SUBJECT: NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
(NRC INSPECTION REPORT 05000348/2008006 AND 05000364/2008006)
Dear Mr. Johnson:
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 Joseph M. Farley
Nuclear Plant, Units 1 and 2, in March and April 2008. The inspection team will be led by Mr.
Norman Merriweather, NRC Senior Reactor Inspector, of the Region II Office. The team will be
composed of personnel from the NRC Region II Office. The inspection will be conducted in
accordance with the NRCs baseline fire protection inspection procedure 71111.05T.
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 separation of the systems and equipment
necessary to achieve and maintain safe shutdown and the fire protection features of selected
fire areas.
On December 3, 2007, during a telephone conversation between Mr. Doug McKinney,
Licensing Supervisor, and Mr. Merriweather, 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: February 26 - 28, 2008
- Week 1 of onsite inspection: March 17 - 21, 2008
- Week 2 of onsite inspection: March 31 - April 4, 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 Farley Nuclear Plant fire
protection program, fire protection features, post-fire safe 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. Merriweather 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.
SNC 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 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 Farley Nuclear 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 Farley Nuclear 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 team's information or logistical needs, please
contact Mr. Merriweather at (404) 562-4627, or me at (404) 562-4669.
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
(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/
D. Charles Payne, Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos.: 50-348 and 50-364
Enclosure: Triennial Fire Protection Inspection Support Documentation
cc w/encl:
Mr. B. D. McKinney, Licensing Manager
Southern Nuclear Operating
Company, Inc.
Electronic Mail Distribution
(cc w/encl contd - See next page)
SNC 3
(cc w/encl contd)
Mr. Jeffrey T. Gasser
Executive Vice President
Southern Nuclear Operating
Company, Inc.
Electronic Mail Distribution
Mr. M. Stanford Blanton
Balch and Bingham Law Firm
Electronic Mail Distribution
Dr. D. E. Williamson
State Health Officer
Alabama Department of Public Health
Electronic Mail Distribution
Mr. William D. Oldfield, SAER Supervisor
Joseph M. Farley Nuclear Plant
Electronic Mail Distribution
Mr. Mark Culver, Chairman
Houston County Commission
P. O. Box 6406
Dothan, AL 36302
David H. Jones
Vice President - Engineering
Southern Nuclear Operating Company, Inc.
P.O. Box 1295
Birmingham, AL 35201-1295
Moanica Caston
Southern Nuclear Operating Company, Inc.
Bin B-022
P. O. Box 1295
Birmingham, AL 35201-1295
L. M. Stinson, Vice President,
Fleet Operations Support
Southern Nuclear Operating Company, Inc.
11028 Hatch Parkway North
Baxley, GA 31513
Distribution w/encl: (See next page)
SNC 4
Distribution w/encl:
K. Cotton, NRR
RIDSNRRDIRS
PUBLIC
NRC Resident Inspector
U.S. Nuclear Regulatory Commission
7388 N State Hwy 95
Columbia, AL 36319
_________________________
OFFICE RII:DRS RII:DRP
NAME MERRIWEATHER SHAFFER
DATE 12/05/2007 12/10/2007 12/ /2007 12/ /2007 12/ /2007 12/ /2007 12/ /2007
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
SNC 3
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 a 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 used to, and describing, shutdown from inside the control
room with a postulated fire occurring in any plant area outside the control room.
Enclosure
3
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 reports/problem investigation
reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for the
past three years.
Enclosure
3
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).
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.
Enclosure