ML030380215
| ML030380215 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/06/2003 |
| From: | Ogle C NRC/RGN-II/DRS/EB |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| References | |
| IR-03-006 | |
| Download: ML030380215 (5) | |
See also: IR 05000338/2003006
Text
February 6, 2003
Virginia Electric and Power Company
ATTN: Mr. David A. Christian
Senior Vice President and
Chief Nuclear Officer
Innsbrook Technical Center
5000 Dominion Boulevard
Glen Allen, VA 23060
SUBJECT: NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION,
(NRC INSPECTION REPORT NOS. 50-338, 339/2003-006)
Dear Mr. Christian:
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 North Anna
Power Station in May 2003. The inspection team will be led by Mr. Gerry Wiseman, Senior
Reactor Inspector - Fire Protection, 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 its 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 January 29, 2003, during a telephone conversation with Mr. Jay Leberstien, Licensing
Engineer, 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 - April 22 - 24, 2003
Week 1 of onsite inspection - May 5 - 9, 2003
Week 2 of onsite inspection - May 19 - 23, 2003
VEPCO 2
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection; to become familiar with the North Anna fire protection
program, fire protection features, post-fire safe shutdown capabilities and plant layout; and, as
necessary, to obtain plant specific site access training and badging for unescorted site access.
The types of documents the team will be interested in reviewing, and possibly obtaining, are
listed in the Enclosure. Please contact Mr. Wiseman 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 requested to be made available to the
team in their office spaces; 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 North Anna Power Station
fire protection program, including post-fire safe shutdown capability, be readily accessible to the
team for 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 North Anna 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. Wiseman at (404) 562-4542, or me at (404) 562-4605.
Sincerely,
/RA: D. Charles Payne for:/
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-338, 50-339
Enclosure: Triennial Fire Protection Inspection
Support Documentation
cc w/encl: (See page 3)
VEPCO 3
cc w/encl:
Chris L. Funderburk, Director
Nuclear Licensing and
Operations Support
Virginia Electric and Power Company
Electronic Mail Distribution
D. A. Heacock
Site Vice President
North Anna Power Station
Electronic Mail Distribution
Executive Vice President
Old Dominion Electric Cooperative
Electronic Mail Distribution
County Administrator
Louisa County
P. O. Box 160
Louisa, VA 23093
Lillian M. Cuoco, Esq.
Senior Nuclear Counsel
Dominion Nuclear Connecticut, Inc.
Electronic Mail Distribution
Attorney General
Supreme Court Building
900 East Main Street
Richmond, VA 23219
Distribution w/encl:
N. Kalyanam, NRR
L. Slack, RII EICS
RIDSNRRDIPMLIPB
PUBLIC
OFFICE RII:DRS RII:DRS RII:DRS RII:DRP
SIGNATURE WISEMAN PAYNE PAYNE FOR LANDIS
NAME WISEMAN PAYNE OGLE LANDIS
DATE 02/05/2003 02/05/2003 02/06/2002 02/06/2003 2/ /2003 2/ /2003 2/ /2003
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
OFFICIAL RECORD COPY DOCUMENT NAME: C:\ORPCheckout\FileNET\ML030380215.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 (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.]
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. The fire brigade training program and pre-fire plans.
4. Post-fire safe shutdown systems and separation analysis.
5. Post-fire alternative shutdown analysis.
6. Piping and instrumentation (flow) diagrams showing those systems and components
used to achieve and maintain hot standby and cold shutdown for fires outside the
control room and those components used for those areas requiring alternative shutdown
capability.
7. Plant layout and equipment drawings which identify the physical plant locations of hot
standby and cold shutdown equipment.
8. Plant layout drawings which identify plant fire area delineation, areas protected by
automatic fire suppression and detection, and the locations of fire protection equipment.
9. Plant layout drawings which identify the general location of the post-fire emergency
lighting units.
10. Plant operating procedures which would be used and describe shutdown from inside the
control room with a postulated fire occurring in any plant area outside the control room
and procedures which would be used to implement alternative shutdown capability in the
event of a fire in the control, the cable spreading room or any other Appendix R, Section
III.G.3 designated fire area.
11. Maintenance and surveillance testing procedures for alternative shutdown capability and
fire barriers, detectors, pumps and suppression systems.
12. Maintenance procedures which routinely verify fuse breaker coordination in accordance
with the post-fire safe shutdown coordination analysis.
13. A sample of significant fire protection and post-fire safe shutdown related design change
packages and Generic Letter 86-10 evaluations for the past 3 year period.
ENCLOSURE
2
14. The reactor plants IPEEE, results of any post-IPEEE reviews, and a list of actions taken
or plant modifications conducted in response to IPEEE information.
15. Temporary modification procedure(s).
16. Current organization charts of site personnel down to the level of fire protection staff
personnel.
17. If applicable, layout/arrangement drawings of potential reactor coolant pump lube oil
system leakage points and associated lube oil collection systems.
18. Copies of the SERs which form the licensing basis for the Fire Protection Program and
post-fire safe shutdown configuration.
19. Procedures/instructions that control the configuration of the fire protection program,
features, and post-fire safe shutdown methodology and system design.
20. Procedures/instructions that govern the implementation of plant modifications,
maintenance, and special operations, and their impact on fire protection.
21. The three most recent fire protection QA audits and/or fire protection self-assessments.
22. Recent QA surveillances of fire protection activities.
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] for the past 3 year period.
24. A list of the plant Fire Protection Program licensing basis documents.
25. A list of the applicable NFPA code versions committed to (NFPA codes of record)
related to the design of plant fire protection features.
26. A list of plant code deviations from NFPA code commitments and any evaluations of
these code deviations.
ENCLOSURE