ML061230215
| ML061230215 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/03/2006 |
| From: | Ogle C NRC/RGN-II/DRS/EB1 |
| To: | Stinson L Southern Nuclear Operating Co |
| References | |
| IR-06-006 | |
| Download: ML061230215 (5) | |
See also: IR 05000348/2006006
Text
May 3, 2006
Southern Nuclear Operating Company, Inc.
ATTN: Mr. L. M. Stinson
Vice President - Farley Project
P. O. Box 1295
Birmingham, AL 35201-1295
SUBJECT:
NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
05000348/2006006 AND 05000364/2006006
Dear Mr. Stinson:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a component design bases inspection at your Joseph M. Farley
Nuclear Plant during the weeks of July 17-21, 2006, July 31-August 4, 2006, and August 14-18,
2006. The inspection team will be led by Mr. Caudle Julian, a Senior Reactor Inspector from
the NRC's Region II Office. This inspection will be conducted in accordance with the baseline
inspection procedure, Procedure 71111.21, Component Design Bases Inspection, issued
December 2, 2005.
The inspection will evaluate the capability of risk significant / low margin components to function
as designed and support proper system operation. The inspection will also include a review of
selected operator actions, operating experience, and modifications.
During a telephone conversation on May 2, 2006, Mr. Julian confirmed with Mr. John Seay of
your Birmingham staff, arrangements for an information gathering site visit and the three-week
onsite inspection. The schedule is as follows:
Information gathering visit: Week of June 26-30, 2006.
Onsite weeks: July 17-21, 2006, July 31 - August 4, 2006, and August 14-18,
2006.
The purpose of the information gathering visit is to meet with members of your staff to identify
risk-significant components and operator actions. Information and documentation needed to
support the inspection will also be identified. Mr. Walt Rogers, a Region II Senior Reactor
Analyst, may accompany Mr. Julian and the inspection team during the information gathering
visit to review probabilistic risk assessment data and identify risk significant components which
will be examined during the inspection.
The enclosure lists documents that will be needed prior to the information gathering visit.
Please contact Mr. Julian prior to preparing copies of the materials listed in the enclosure.
2
The inspectors will try to minimize your administrative burden by specifically identifying only
those documents required for the inspection preparation.
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: office space, supplemental documents requested to be made
available to the team in the Region II office prior to the inspection preparation week of June 26,
2006; arrangements for site access; and the availability of knowledgeable plant engineering and
licensing personnel to serve as points of contact during the inspection.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter, its
enclosures, and your response (if any) will be available electronically for public inspection in the
NRC Public Document Room or from the Publicly Available Records (PARS) component of the
NRCs 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).
Thank you for your cooperation in this matter. If you have any questions regarding the
information requested or the inspection, please contact Mr. Julian at (404) 562-4603 or me at
(404) 562-4605.
Sincerely,
\\RA Caswell Smith for\\
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-348 & 50-364
Enclosure: Information Request for Farley Nuclear Plant
Component Design Bases Inspection
cc w/enc: (See page 3)
OFFICE
RII:DRS
RII:DRS
RII:DRP
SIGNATURE
/RA/
/RA/
/RA/
NAME
C. Julian
C. Ogle
C. Rapp
DATE
5/ 03 /06
5/ 03 /06
5/ 03 /06
E-MAIL COPY?
YES
YES
NO YES
NO YES
NO
3
cc w/encl:
B. D. McKinney, Licensing Services
Manager, B-031
Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution
J. R. Johnson
General Manager, Farley Plant
Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution
J. T. Gasser
Executive Vice President
Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution
Bentina C. Terry
Southern Nuclear Operating Company, Inc.
Bin B-022
P. O. Box 1295
Birmingham, AL 35201-1295
State Health Officer
Alabama Department of Public Health
RSA Tower - Administration
201 Monroe St., Suite 700
P. O. Box 303017
Montgomery, AL 36130-3017
M. Stanford Blanton
Balch and Bingham Law Firm
P. O. Box 306
1710 Sixth Avenue North
Birmingham, AL 35201
William D. Oldfield
Quality Assurance Supervisor
Southern Nuclear Operating Company
Electronic Mail Distribution
Distribution (See page 2)
Enclosure
INFORMATION REQUEST FOR FARLEY NUCLEAR PLANT
COMPONENT DESIGN BASES INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of use.
Information in lists should contain enough information to be easily understood by someone
who has a knowledge of pressurized water reactor technology.
1.
Risk ranking of components from your site specific probabilistic safety analysis (PSA)
sorted by Risk Achievement Worth (RAW) and sorted separately by Birnbaum
Importance. If possible, please provide a correlation between actual plant
components in plain language, and RAW values.
2.
Provide a list of the top 500 cutsets from your PSA.
3.
Risk ranking of operator actions from your site specific PSA sorted by RAW. Provide
copies of your human reliability worksheets for these items.
4.
If you have an External Event or Fire PSA Model, provide the information requested in
Items 1 and 2 for external events and fire.
5.
Any pre-existing evaluation or list of components and calculations with low design
margins (i.e., pumps closest to the design limit for flow or pressure, diesel generator
close to design required output, heat exchangers close to rated design heat removal,
MOV risk-margin rankings, etc.).
6.
A list of the last two years of operating experience evaluations, modifications, and
corrective actions sorted by component or system.
7.
Information of any common cause failure of components experienced in the last 5
years at your facility.