ML031290362
| ML031290362 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/01/2003 |
| From: | Ogle C NRC/RGN-II/DRS/EB |
| To: | Sumner H Southern Nuclear Operating Co |
| References | |
| IR-03-006 | |
| Download: ML031290362 (7) | |
See also: IR 05000321/2003006
Text
May 1, 2003
Southern Nuclear Operating Company, Inc.
ATTN: Mr. H. L. Sumner, Jr.
Vice President
P. O. Box 1295
Birmingham, AL 35201-1295
SUBJECT:
NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION,
(NRC INSPECTION REPORT NOS. 50-321/03-06 and 50-366/03-06)
Dear Mr. Sumner:
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 Hatch Nuclear
Plant in July 2003. The inspection team will be led by Mr. C. Smith, Senior Reactor Inspector,
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 7111.05.
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 systems and equipment
necessary to achieve and maintain safe shutdown and fire protection features of selected fire
areas.
On April 29, 2003, during a telephone conversation with Mr. Tommy Elton, Licensing
Supervisor, 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 - June 16-18, 2003
Week 1 of onsite inspection - July 7-11, 2003
Week 2 of onsite inspection - July 21-25, 2003
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection; to become familiar with the Plant Hatch 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. Smith 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.
SNOPCO
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 Hatch Nuclear 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 Plant Hatch 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. Smith at (404) 562-4630, or me at (404) 562-4605.
Sincerely,
/RA/
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-321, 50-366
Enclosure: Triennial Fire Protection Inspection
Support Documentation
cc w/encl:
J. D. Woodard
Executive Vice President
Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution
P. H. Wells
General Manager, Plant Hatch
Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution
(cc w/encl contd - See page 3)
SNOPCO
3
(cc w/encl contd)
Raymond D. Baker
Manager Licensing - Hatch
Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution
Ernest L. Blake, Esq.
Shaw, Pittman, Potts and
Trowbridge
2300 N Street, NW
Washington, D. C. 20037
Office of Planning and Budget
Room 610
270 Washington Street, SW
Atlanta, GA 30334
Director
Department of Natural Resources
205 Butler Street, SE, Suite 1252
Atlanta, GA 30334
Manager, Radioactive Materials Program
Department of Natural Resources
Electronic Mail Distribution
Chairman
Appling County Commissioners
County Courthouse
Baxley, GA 31513
Resident Manager
Oglethorpe Power Corporation
Edwin I. Hatch Nuclear Plant
Electronic Mail Distribution
Charles A. Patrizia, Esq.
Paul, Hastings, Janofsky & Walker
10th Floor
1299 Pennsylvania Avenue
Washington, D. C. 20004-9500
Senior Engineer - Power Supply
Municipal Electric Authority
of Georgia
Electronic Mail Distribution
(cc w/encl contd - See page 4)
SNOPCO
4
(cc w/encl contd)
Reece McAlister
Executive Secretary
Georgia Public Service Commission
244 Washington Street, SW
Atlanta, GA 30334
Distribution w/encl:
S. Bloom, NRR
RIDSNRRDIPMLIPB
PUBLIC
(See previous page for concurrences)
OFFICE
RII:DRS
RII:DRP
RII:DRS
RII:DRS
SIGNATURE
RA
RA
NAME
CSMITH
BONSER
PAYNE
OGLE
DATE
4/30/2003
5/1/2003
5/1/2003
5/1/2003
5/ /2003
5/ /2003
5/ /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\\ML031290362.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,
procedures which would be used to implement alternative shutdown capability in the
event of a fire in either the control or cable spreading room.
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.