ML031910112
| ML031910112 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/08/2003 |
| From: | Ogle C NRC/RGN-II/DRS/EB |
| To: | Scalice J Tennessee Valley Authority |
| References | |
| IR-03-007 | |
| Download: ML031910112 (7) | |
See also: IR 05000260/2003007
Text
July 8, 2003
Tennessee Valley Authority
ATTN: Mr. J. A. Scalice
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 NO. 50-260/03-07, 50-296/03-07)
Dear Mr. Scalice:
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 of Units 2 and 3 at the
Browns Ferry Nuclear Plant in September 2003. The inspection team will be led by Mr. Charles
Payne, Team Leader, of the Region II Office. The team will be composed of personnel from
the NRC Region II Office and a contracted national laboratory. The inspection will be
conducted in accordance with the NRCs baseline fire protection inspection procedure
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 fire protection features of selected fire
areas.
On July 3, 2003, during a telephone conversation with Mr. Tim Abney, Licensing and Industry
Affairs Manager, 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 19-21, 2003
Week 1 of onsite inspection - September 8-12, 2003
Week 2 of onsite inspection - September 22-26, 2003
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 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. Payne 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 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 Browns Ferry 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 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 teams information or logistical needs, please
contact Mr. Payne at (404) 562-4669, or me at (404) 562-4605.
Sincerely,
/RA/
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-260, 50-296
Enclosure: Triennial Fire Protection Inspection
Support Documentation
cc w/encl:
Karl W. Singer
Senior Vice President
Nuclear Operations
Tennessee Valley Authority
Electronic Mail Distribution
(cc w/encl contd - See page 3)
3
(cc w/encl contd)
James E. Maddox, Vice President
Engineering and Technical Services
Tennessee Valley Authority
Electronic Mail Distribution
Ashok S. Bhatnagar
Site Vice President
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
General Counsel
Tennessee Valley Authority
Electronic Mail Distribution
Robert J. Adney, General Manager
Nuclear Assurance
Tennessee Valley Authority
Electronic Mail Distribution
Michael D. Skaggs, Plant Manager
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
Mark J. Burzynski, Manager
Nuclear Licensing
Tennessee Valley Authority
Electronic Mail Distribution
Timothy E. Abney, Manager
Licensing and Industry Affairs
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
State Health Officer
Alabama Dept. of Public Health
RSA Tower - Administration
Suite 1552
P. O. Box 303017
Montgomery, AL 36130-3017
(cc w/encl contd - See page 4)
4
(cc w/encl contd)
Chairman
Limestone County Commission
310 West Washington Street
Athens, AL 35611
Distribution w/encl:
K. Jabbour, NRR
RIDSNRRDIPMLIPB
PUBLIC
OFFICE
RII:DRS
RII:DRP
RII:DRS
RII:DRS
SIGNATURE
PAYNE
CAHILL
NAME
PAYNE
CAHILL
OGLE
DATE
7/7/2003
7/8/2003
7/ /2003
7/ /2003
7/ /2003
7/ /2003
7/ /2003
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
PUBLIC DOCUMENT
YES
NO
OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML031910112.wpd
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 (i.e., on CD-ROM or computer disc). If electronic media is
offered, we request that an index of files or a simple menu be provided. 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
zones/areas (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 outside the control room.
8.
Piping and instrumentation (flow) diagrams for the systems and components used to
achieve and maintain hot standby, and cold shutdown, in areas requiring alternative
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 zones/areas (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.
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).
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Enclosure
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
zones/areas (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 zones/areas (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 zones/areas.
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.
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).
3
Enclosure
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.