ML080940510
| ML080940510 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/03/2008 |
| From: | Sandra Walker NRC/RGN-II/DRS/EB2 |
| To: | Campbell W Tennessee Valley Authority |
| References | |
| IR-08-006 | |
| Download: ML080940510 (8) | |
See also: IR 05000327/2008006
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
SAM NUNN ATLANTA FEDERAL CENTER
61 FORSYTH STREET, SW, SUITE 23T85
ATLANTA, GEORGIA 30303-8931
April 3, 2008
Tennessee Valley Authority
ATTN: Mr. William R. Campbell, Jr.
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 05000327/2008006 AND 05000328/2008006)
Dear Mr. Campbell Jr.:
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 Sequoyah
Nuclear Plant, in June 2007. The inspection will be led by Mr. Paul J. Fillion, NRC Senior
Reactor Inspector, of the Region II Office. The team will be composed of personnel from the
NRC Region II Office and a consultant. The inspection will be conducted in accordance with the
NRCs baseline fire protection 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 January 24, 2008, during a telephone conversation between Mr. Jim Smith, Sequoyah
Licensing Manager, and Mr. Fillion, 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:
Information gathering visit:
April 29 - May 1, 2008
Week 1 of onsite inspection: June 9 - 13, 2008
Week 2 of onsite inspection: June 23 - 27, 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 Sequoyah Nuclear Plant fire
protection program, fire protection features, post-fire shutdown capabilities and plant layout.
The types of documents the team will be interested in reviewing, and possibly obtaining, are
listed in the Enclosure.
2
Please contact Mr. Fillion 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 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 Sequoyah 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 Sequoyah 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 teams information or logistical needs, please
contact Mr. Fillion at (404) 562-4623, or Mr. Shakur Walker at (404) 562-4639.
In accordance with 10 CFR 2.390 of the NRCs 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: McKenzie Thomas for/
Shakur Walker, Acting Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos.: 50-327, 50-328
Enclosure: Triennial Fire Protection Inspection Support Documentation
cc w/encl: (See page 3)
3
cc w/encl:
Ashok S. Bhatnagar
Senior Vice President
Nuclear Generation Development and Construction
Tennessee Valley Authority
Electronic Mail Distribution
William R. Campbell, Jr.
Chief Nuclear Officer and Executive Vice President
Tennessee Valley Authority
6A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
Christopher R. Church
Plant Manager
Sequoyah Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
H. Rick Rogers
Vice President
Nuclear Engineering and Technical Services
Tennessee Valley Authority
Electronic Mail Distribution
Timothy P. Cleary
Site Vice President
Sequoyah Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
John C. Fornicola
General Manager
Nuclear Assurance
Tennessee Valley Authority
Electronic Mail Distribution
General Counsel
Tennessee Valley Authority
Electronic Mail Distribution
Beth A. Wetzel
Manager
Corporate Nuclear Licensing and Industry Affairs
Tennessee Valley Authority
Electronic Mail Distribution
(cc w/encl contd - See page 4)
4
(cc w/encl contd)
James D. Smith
Manager
Licensing and Industry Affairs
Tennessee Valley Authority
Electronic Mail Distribution
Lawrence E. Nanney
Director
TN Dept. of Environment & Conservation
Electronic Mail Distribution
Larry E. Nicholson
General Manager
Performance Improvement
Tennessee Valley Authority
3R Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
Michael A. Purcell
Senior Technical Advisor
Nuclear Power Group
Tennessee Valley Authority
4X Blue Ridge
1101 Market Street
Chattanooga, TN 37402-2801
Ann Harris
341 Swing Loop
Rockwood, TN 37854
Senior Resident Inspector
Sequoyah Nuclear Plant
U.S. NRC
2600 Igou Ferry Road
Soddy Daisy, TN 37379-3624
5
Letter to Mr. William R. Campbell, Jr. from Shakur Walker dated April 3, 2008
SUBJECT: NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
(NRC INSPECTION REPORT 05000327/2008006 AND 05000328/2008006)
Distribution w/encl:
Bob Pascarelli, NRR
B. Moroney, NRR
RIDSNRRDIRS
PUBLIC
G PUBLICLY AVAILABLE
G NON-PUBLICLY AVAILABLE
G SENSITIVE
G NON-SENSITIVE
ADAMS: G Yes
ACCESSION NUMBER:_________________________
OFFICE
RII:DRS
RII:DRS
RII:DRP
SIGNATURE
RA *
Mthomas for
NAME
P. FILLION
S. WALKER
R. NEASE
DATE
3/31/20084/
/2008
4/3/2008
4/2/2008
4/ /2008
4/ /2008
4/ /2008
4/ /2008
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
OFFICIAL
RECORD
COPY DOCUMENT
NAME:
S:\\DRS\\ENG
BRANCH
2\\NOTIFICATION
LETTERS\\SEQNOTLTRPJF.DOC
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 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
2
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.
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).
Enclosure
3
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.