ML023260353
| ML023260353 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/21/2002 |
| From: | Ogle C Division of Reactor Safety II |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| References | |
| IR-03-005 | |
| Download: ML023260353 (6) | |
See also: IR 05000280/2003005
Text
NOVEMBER 21, 2002
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. 50-280, 281/2003-005)
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 Surry Power
Station in January and February 2003. The inspection team will be led by Mr. Charles Payne,
Fire Protection Team Leader, of the Region II Office. The team will be composed of personnel
from the NRC Region II Office and 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 of the separation of the systems and equipment
necessary to achieve and maintain safe shutdown and fire protection features of selected fire
areas.
On November 21, 2002, during a telephone conversation with Mr. Barry Garber, 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 - January 7 - 9, 2003
Week 1 of onsite inspection - January 27 - 31, 2003
Week 2 of onsite inspection - February 10 - 14, 2003
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection; to become familiar with the Surry 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. Payne 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 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 Surry Power Station 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 Surry 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. Payne at (404) 562-4669, or me at (404) 562-4605.
Sincerely,
/RA/
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-280, 50-281
Enclosure: Triennial Fire Protection Inspection
Support Documentation
cc w/encl:
Stephen P. Sarver, Director
Nuclear Licensing and
Operations Support
Virginia Electric & Power Company
Electronic Mail Distribution
(cc w/encl contd - See page 3)
3
(cc w/encl contd)
Richard H. Blount, II
Site Vice President
Surry Power Station
Virginia Electric & Power Company
Electronic Mail Distribution
Virginia State Corporation Commission
Division of Energy Regulation
P. O. Box 1197
Richmond, VA 23209
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:
G. Edison, NRR
RIDSNRRDIPMLIPB
PUBLIC
OFFICE
RII:DRS
RII:DRP
RII:DRS
SIGNATURE
PAYNE
LANDIS
OGLE
NAME
PAYNE
LANDIS
OGLE
DATE
11/ 21/2002
11/21/2002
11/21/2002
11/ /2002
11/ /2002
11/ /2002
11/ /2002
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\\ML023260353.wpd
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 (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.
2
Enclosure
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.
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.
A list of the SERs which form the licensing basis for the 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.
A list of applicable codes and standards related to the design of plant fire protection
features and evaluations of code deviations.
21.
Procedures/instructions that govern the implementation of plant modifications,
maintenance, and special operations, and their impact on fire protection.
22.
The three most recent fire protection QA audits and/or fire protection self-assessments.
23.
Recent QA surveillances of fire protection activities.
24.
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].
25.
A list of plant fire protection licensing basis documents.
26.
A list of the NFPA code versions committed to (NFPA codes of record).
27.
A list of plant deviations from code commitments.