ML033640109
| ML033640109 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 12/18/2003 |
| From: | Ogle C NRC/RGN-II/DRS/EB |
| To: | Scalice J Tennessee Valley Authority |
| References | |
| IR-04-006 | |
| Download: ML033640109 (7) | |
See also: IR 05000390/2004006
Text
December 18, 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 WATTS BAR NUCLEAR PLANT - TRIENNIAL FIRE
PROTECTION BASELINE INSPECTION - NRC INSPECTION REPORT
05000390/2004006 AND 05000391/2004006
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 1 and 2 at the
Watts Bar Nuclear Plant in March and April, 2004. The inspection team will be led by
Mr. Norman Merriweather, 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 71111.05.
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 December 18, 2003, during a telephone conversation with Mr. Paul Pace, Licensing
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:
C Information gathering onsite visit - March 1-5, 2004
C Week 1 of onsite inspection - March 22-26, 2004
C Week 2 of onsite inspection - April 5-9, 2004
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, and to become familiar with the Watts Bar 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. Merriweather 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.
TVA 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 Watts Bar 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 Watts Bar 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. Merriweather at (404) 562-4627, or me at (404) 562-4605.
Sincerely,
/RA/
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-390, 50-391
License No.: NPF-90 and Construction
Permit No. CPPR-92
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)
TVA 3
(cc w/encl contd)
James E. Maddox, Vice President
Engineering and Technical Services
Tennessee Valley Authority
Electronic Mail Distribution
William R. Lagergren
Site Vice President
Watts Bar Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
General Counsel
Tennessee Valley Authority
Electronic Mail Distribution
Michael J. Fecht, Acting General Manager
Nuclear Assurance
Tennessee Valley Authority
Electronic Mail Distribution
Mark J. Burzynski, Manager
Nuclear Licensing
Tennessee Valley Authority
Electronic Mail Distribution
Paul L. Pace, Manager
Licensing and Industry Affairs
Watts Bar Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
Larry S. Bryant, Plant Manager
Watts Bar Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
County Executive
Rhea County Courthouse
375 Church Street, Suite 215
Dayton, TN 37321-1300
County Executive
Meigs County Courthouse
Decatur, TN 37322
(cc w/encl contd - See page 4)
TVA 4
(cc w/encl contd)
Lawrence E. Nanney, Director
TN Dept. of Environment & Conservation
Division of Radiological Health
Electronic Mail Distribution
Ann Harris
341 Swing Loop
Rockwood, TN 37854
James H. Bassham, Director
Tennessee Emergency Management Agency
Electronic Mail Distribution
Distribution w/encl:
M. Chernoff, NRR
RIDSNRRDIPMLIPB
PUBLIC
OFFICE RII:DRS RII:DRP RII:DRS RII:DRS
NAME MERRIWEATHER CAHILL OGLE ODONOHUE
DATE 12/ /2003 12/18/2003 12/18/2003 12/18/2003
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\ML033640109.wpd
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
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.
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
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
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.