ML061530239
| ML061530239 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/02/2006 |
| From: | Edwin Lea NRC/RGN-II/DRS/EB2 |
| To: | Singer K Tennessee Valley Authority |
| References | |
| IR-06-014 | |
| Download: ML061530239 (8) | |
See also: IR 05000260/2006014
Text
June 2, 2006
Tennessee Valley Authority
ATTN: Mr. Karl W. Singer
Chief Nuclear Officer and
Executive Vice President
6A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
SUBJECT: NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
(NRC INSPECTION REPORT 05000260/2006014 AND 05000296/2006014)
AND UNIT 1 RECOVERY INSPECTION
Dear Mr. Singer:
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 Browns Ferry
reactor facilities, Units 2 and 3, in August and September 2006. Mr. George MacDonald, NRC
Senior Reactor Inspector, will lead the inspection team, which 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 May 31, 2006, during a telephone conversation between Mr. Jim Davenport, Licensing
Engineer, and Mr. Paul Fillion, Fire protection Team Leader Region II, 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 onsite visit - August 1 - 3, 2006
- Week 1 of onsite inspection - August 28 - September 1, 2006
- Week 2 of onsite inspection - September 11 - 15, 2006
TVA 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 Browns Ferry 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. MacDonald 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 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.
Also discussed during the May 31, 2006 telephone conversation, the inspection team will
conduct a Unit 1 recovery inspection in the area of fire protection during September 25 - 29,
2006. At present, the concept of this inspection will be to review the post-fire safe shutdown
procedures that you are preparing in anticipation of Unit 1 restart and any other issues that may
arise from the baseline inspection on Units 2 and 3 that apply to Unit 1. The report number for
the Unit 1 portion of the inspection has not yet been selected.
We request that during the inspection weeks you ensure that copies of analyses, evaluations or
documentation regarding the implementation and maintenance of the Browns Ferry 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 Browns Ferry 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. MacDonald at (404) 562-4543, or me at (404) 562-4567.
TVA 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 Paul Fillion for/
Edwin Lea., Acting Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos. 50-259, 50-260, 50-296
License Nos. DPR-33, DPR-52, DPR-68
Enclosure: Triennial Fire Protection Inspection Support Documentation
TVA 4
cc w/encl: William D. Crouch, Manager
Ashok S. Bhatnagar Licensing and Industry Affairs
Senior Vice President Browns Ferry Nuclear Plant
Nuclear Operations Tennessee Valley Authority
Tennessee Valley Authority Electronic Mail Distribution
Electronic Mail Distribution
State Health Officer
Larry S. Bryant, Vice President Alabama Dept. of Public Health
Nuclear Engineering & Technical Services RSA Tower - Administration
Tennessee Valley Authority Suite 1552
Electronic Mail Distribution P. O. Box 303017
Montgomery, AL 36130-3017
Brian O'Grady
Site Vice President Chairman
Browns Ferry Nuclear Plant Limestone County Commission
Tennessee Valley Authority 310 West Washington Street
Electronic Mail Distribution Athens, AL 35611
Preston D. Swafford Masoud Bajestani, Vice President
Senior Vice President Browns Ferry Unit 1 Restart
Nuclear Support Browns Ferry Nuclear Plant
Tennessee Valley Authority Tennessee Valley Authority
Electronic Mail Distribution P. O. Box 2000
Decatur, AL 35609
General Counsel
Tennessee Valley Authority Robert G. Jones, General Manager
Electronic Mail Distribution Browns Ferry Site Operations
Browns Ferry Nuclear Plant
John C. Fornicola, Manager Tennessee Valley Authority
Nuclear Assurance and Licensing P. O. Box 2000
Tennessee Valley Authority Decatur, AL 35609
Electronic Mail Distribution
Bruce M. Aukland, Plant Manager
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
Glenn W. Morris, Manager
Corporate Nuclear Licensing
and Industry Affairs
Tennessee Valley Authority
Electronic Mail Distribution
__ML061530239___________
OFFICE RII:DRS RII:DRP
SIGNATURE /RA/ /RA H. Gepford for/
NAME P. Fillion M. Widmann
DATE 6/ /2006 7/ /2006
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
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 shutdown, and cold shutdown, for fires outside the control
room.
8. Piping and instrumentation (flow) diagrams for the systems and components used to
achieve and maintain hot shutdown, and cold shutdown, in areas requiring alternative
shutdown capability.
9. Plant layout and equipment drawings which identify the physical plant locations of hot
shutdown 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
4
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