ML061530239

Notification of Triennial Fire Protection Baseline Inspection (NRC IR 05000260-06-014 and 05000296-06-014) and Unit 1 Recovery Inspection

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

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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