ML091730506
| ML091730506 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/22/2009 |
| From: | Nease R NRC/RGN-II/DRS/EB2 |
| To: | Swafford P Tennessee Valley Authority |
| References | |
| IR-09-009 | |
| Download: ML091730506 (7) | |
See also: IR 05000259/2009009
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
SAM NUNN ATLANTA FEDERAL CENTER
61 FORSYTH STREET, SW, SUITE 23T85
ATLANTA, GEORGIA 30303-8931
June 22, 2009
Mr. Preston D. Swafford
Chief Nuclear Officer and Executive Vice President
Tennessee Valley Authority
3R Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - NOTIFICATION OF TRIENNIAL FIRE
PROTECTION BASELINE INSPECTION WHILE TRANSITION TO 10 CFR
PART 50.48(c) IS IN PROGRESS (NRC INSPECTION REPORT NO.
05000259/2009009, 05000260/2009009, AND 05000296/2009009)
Dear Mr. Swafford:
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 Browns Ferry Nuclear
Plant, Units 1, 2, and 3 in September and October 2009. The inspection team 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. 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 June 5, 2009, during a telephone conversation between Mr. Russ Godwin (Site Licensing
Manager) of your staff, and Mr. Thomas, 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:
September 1-3, 2009
Week 1 of onsite inspection: September 21-25, 2009
Week 2 of onsite inspection: October 5-9, 2009
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
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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. 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.
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 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. Thomas at (404) 562-4673, or me at (404) 562-4530.
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/
Rebecca L. Nease, 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
cc w/encl. (See page 3)
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cc w/encl:
Ashok S. Bhatnagar
Senior Vice President
Nuclear Generation Development and
Construction
Tennessee Valley Authority
Electronic Mail Distribution
Preston D. Swafford
Chief Nuclear Officer and Executive Vice
President
Tennessee Valley Authority
Electronic Mail Distribution
William R. Campbell
Senior Vice President
Fleet Engineering
Tennessee Valley Authority
6A Lookout Place
1101 Market Place
Chattanooga, TN 37402-2801
Thomas Coutu
Vice President
Nuclear Support
Tennessee Valley Authority
Electronic Mail Distribution
R. G. (Rusty) West
Site Vice President
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
Frederick Russell Godwin
Manager, Licensing and Industry Affairs
Browns Ferry Nuclear Plant
Tennessee Valley Authority
P.O. Box 2000
Decatur, AL 35609
James J. Randich
Plant Manager
Browns Ferry Nuclear Plant
Tennessee Valley Authority
P.O. Box 2000
Decatur, AL 35609
General Counsel
Tennessee Valley Authority
Electronic Mail Distribution
Larry E. Nicholson
General Manager
Performance Improvement
Tennessee Valley Authority
Electronic Mail Distribution
Michael A. Purcell
Senior Licensing Manager
Nuclear Power Group
Tennessee Valley Authority
Electronic Mail Distribution
Michael J. Lorek
Vice President - Nuclear Oversight
Tennessee Valley Authority
Electronic Mail Distribution
Fredrick C. Mashburn
Acting Manager
Corporate Nuclear Licensing and Industry
Affairs
Tennessee Valley Authority
Electronic Mail Distribution
Robert J. Whalen
Tennessee Valley Authority
3R Lookout Place
1101 Market Street
Chattanooga, TN 37402-280
Senior Resident Inspector
Browns Ferry Nuclear Plant
U.S. Nuclear Regulatory Commission
10833 Shaw Road
Athens, AL 35611-6970
Kirksey E. Whatley
Director
Office of Radiation Control
Alabama Dept. of Public Health
Electronic Mail Distribution
Chairman
Limestone County Commission
310 West Washington Street
Athens, AL 35611
Dr. D. E. Williamson
State Health Officer
Alabama Dept. of Public Health
Electronic Mail Distribution
_________________________
XG SUNSI REVIEW COMPLETE by
MT 6/22/2009
OFFICE
RII:DRS
RII:DRP
RII:DRS
SIGNATURE
NAME
MThomas
EGuthrie
RNease
DATE
6/18/2009
6/19/2009
6/22/2009
E-MAIL COPY?
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 CD/DVD-ROM. The CD/DVD-ROM should be indexed and hyperlinked to
facilitate ease of use. Please provide 5 copies of each CD/DVD-ROM 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.
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Enclosure
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/problem
evaluation reports/NCRs] 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).
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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.