ML052090357
| ML052090357 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/28/2005 |
| From: | Payne D Division of Reactor Safety II |
| To: | Singer K Tennessee Valley Authority |
| References | |
| IR-05-011 | |
| Download: ML052090357 (9) | |
See also: IR 05000327/2005011
Text
July 28, 2005
Tennessee Valley Authority
ATTN:
Mr. K. W. Singer
Chief Nuclear Officer and
Executive Vice President
6A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
SUBJECT: SEQUOYAH NUCLEAR POWER PLANT - NOTIFICATION OF TRIENNIAL FIRE
PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT
05000327/2005011 AND 05000328/2005011)
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 of the Sequoyah
Nuclear Power Plant in October and November 2005. The inspection team will be led by
Mr. Robert Schin, 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 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 fire protection features of selected fire
areas.
On July 27, 2005, during a telephone conversation between Mr. Paul Pace, Licensing and
Industry Affairs Manager for Sequoyah and Watts Bar, and Mr. Schin, our respective staffs
confirmed arrangements for a three-day information gathering site visit and a two-week onsite
inspection. The schedule for the inspection is as follows:
C
Information gathering visit:
Week of October 3-7, 2005
C
Week 1 of onsite inspection:
October 31 - November 4, 2005
Week 2 of onsite inspection:
November 14-18, 2005
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 Power
Plant fire protection program 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. Schin 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 requested to be made available to the
team in their 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, operations, and licensing organization personnel to serve as
points of contact during the inspection.
We request that during the onsite inspection weeks you ensure that copies of analyses,
evaluations, or documentation regarding the implementation and maintenance of the Sequoyah
Nuclear Power Plant fire protection program, including post-fire safe shutdown capability, be
readily accessible to the team for their 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 Power 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 team's information or logistical needs, please
contact Mr. Schin at (404) 562-4629, or me at (404) 562-4669.
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).
Should you have any questions concerning this letter, please contact us.
Sincerely,
/RA/
D. Charles Payne, Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos.:
50-327, 50-328
License Nos.:
Enclosure: Triennial Fire Protection Inspection Support Documentation
cc w/encl: (See page 3)
3
cc w/encl:
Ashok S. Bhatnagar
Senior Vice President
Nuclear Operations
Tennessee Valley Authority
Electronic Mail Distribution
Larry S. Bryant, General Manager
Nuclear Engineering
Tennessee Valley Authority
Electronic Mail Distribution
Randy Douet
Site Vice President
Sequoyah Nuclear Plant
Electronic Mail Distribution
General Counsel
Tennessee Valley Authority
Electronic Mail Distribution
John C. Fornicola, Manager
Nuclear Assurance and Licensing
Tennessee Valley Authority
Electronic Mail Distribution
Glenn W. Morris, Manager
Corporate Nuclear Licensing and
Industry Affairs
Tennessee Valley Authority
Electronic Mail Distribution
Paul L. Pace, Manager
Licensing and Industry Affairs
ATTN: James D. Smith
Sequoyah Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
David A. Kulisek, Plant Manager
Sequoyah Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
Lawrence E. Nanney, Director
TN Dept. of Environment & Conservation
Division of Radiological Health
Electronic Mail Distribution
County Mayor
Hamilton County Courthouse
Chattanooga, TN 37402-2801
Ann Harris
341 Swing Loop
Rockwood, TN 37854
James H. Bassham, Director
Tennessee Emergency Management
Agency
Electronic Mail Distribution
_________________________
OFFICE
RII:DRS
RII:DRS
RII:DRP
SIGNATURE
/RA/
/RA/
/RA/
NAME
R.Schin
P.Fillion
S.Cahill
DATE
7/27/2005
7/27/2005
7/27/2005
7/ /2005
7/ /2005
7/ /2005
7/ /2005
E-MAIL COPY?
YES
NO
NO YES
NO YES
NO YES
NO YES
NO
1
Enclosure
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 and the Fire Hazards Analysis.
2.
The fire protection program implementing procedures (e.g., administrative controls,
surveillance testing, fire brigade).
3.
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. Also, simplified (training) flow diagrams of the systems, if available.
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. Also, simplified (training) flow diagrams of
the systems, if available.
9.
Electrical one-line drawings showing AC power distribution (4KV, 480V, and 120V vital
power) and 125V/240V DC power distribution. Also, include lists of loads supplied from
each switchgear, motor control center, and distribution panel.
10.
Plant layout and equipment drawings which identify the physical plant locations of hot
standby and cold shutdown equipment.
11.
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).
2
Enclosure
12.
Plant layout drawings which identify the general location of the post-fire emergency
lighting units and the related post-fire safe shutdown local actions plus access and
egress routes.
13.
Plant operating procedures used for, and describing, shutdown from inside the control
room with a postulated fire occurring in any plant area outside the control room.
14.
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).
15.
Operator training for post-fire safe shutdown, including lesson plans, simulator
scenarios, and job performance measures (JPMs).
16.
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.
17.
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 safety shutdown coordination analysis.
18.
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 in the last three years.
19.
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 dedicated shutdown capability (Section III.G.3) is used
for the selected fire areas/zones.
20.
Procedures or instructions that govern the implementation of plant modifications,
temporary modifications, maintenance, and special operations, and their impact on fire
protection.
21.
Organization chart(s) of site personnel down to the level of the fire protection staff.
22.
Procedures or instructions that control the configuration of the fire protection program,
features, and post-fire safe shutdown methodology and system design.
3
23.
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)).
24.
Fire protection QA audits and/or fire protection self-assessments in the last three years.
25.
A list of open and closed fire protection problem identification and resolution reports
[also know as action requests/condition reports/problem reports/problem investigation
reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for the
past three years.
26.
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).
27.
A list of fire protection or Appendix R calculations.
28.
A list of fire impairments identified during the previous year.
29.
A list of abbreviations/designators for plant systems.