ML070050302
| ML070050302 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/05/2007 |
| From: | Ogle C Division of Reactor Safety II |
| To: | Tynan T Southern Nuclear Operating Co |
| References | |
| IR-07-006 | |
| Download: ML070050302 (6) | |
See also: IR 05000424/2007006
Text
2
January 5, 2007
Southern Nuclear Operating Company, Inc.
ATTN:
Mr. T E. Tynan
Site Vice President
7821 River Road
Waynesboro, GA 30830
SUBJECT:
NOTIFICATION OF VOGTLE NUCLEAR POWER PLANT- COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
05000424/2007006, 05000425/2007006
Dear Mr. Tynan:
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 Vogtle Nuclear Power
Plant during the weeks of April 23-27, 2007, May 7-11, 2007, and May 21-25, 2007. The
inspection team will be led by Mike Cain, 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 June 22, 2006.
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 January 03, 2007, Mr. Cain confirmed with Mr. M. Sharma
of your staff, arrangements for an information gathering site visit and the three-week onsite
inspection. The schedule is as follows:
Information gathering visit: Week of April 9-13, 2007.
Onsite weeks: April 23-27, 2007, May 7-11, 2007, and May 21-25, 2007.
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. Cain 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. Cain prior to preparing copies of the materials listed in the enclosure.
The inspectors will try to minimize your administrative burden by specifically identifying only
those documents required for the inspection preparation.
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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 April 16,
2007; 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 NRC's "Rules of Practice," a copy of this letter and its
enclosure will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRC's 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. Cain at (404) 562-4876 or me at
(404) 562-4601.
Sincerely,
/RA/
Charles R. Ogle, Acting Deputy Director
Division of Reactor Safety
Docket Nos: 50-424, 50-425
Enclosure: Information Request for Component Design Basis Inspection
cc w/encl: (See page 3)
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J. T. Gasser
Executive Vice President
Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution
N. J. Stringfellow
Manager-Licensing
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
Director, Consumers' Utility Counsel
Division
Governor's Office of Consumer Affairs
2 M. L. King, Jr. Drive
Plaza Level East; Suite 356
Atlanta, GA 30334-4600
Office of the County Commissioner
Burke County Commission
Waynesboro, GA 30830
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
Attorney General
Law Department
132 Judicial Building
Atlanta, GA 30334
Laurence Bergen
Oglethorpe Power Corporation
Electronic Mail Distribution
Resident Manager
Oglethorpe Power Corporation
Alvin W. Vogtle Nuclear Plant
Electronic Mail Distribution
Arthur H. Domby, Esq.
Troutman Sanders
Electronic Mail Distributioin
Senior Engineer - Power Supply
Municipal Electric Authority
of Georgia
Electronic Mail Distribution
Reece McAlister
Executive Secretary
Georgia Public Service Commission
244 Washington Street, SW
Atlanta, GA 30334
_________________________
OFFICE
RII:DRP
RII:DRS
SIGNATURE
/RA/
/RA/
NAME
S. Shaeffer
L.Cain
DATE
01/05/2007
01/05/2007
1/ /2007
1/ /2007
1/ /2007
1/ /2007
1/ /2007
E-MAIL COPY?
NO YES
YES
NO YES
NO YES
NO YES
NO YES
NO
Enclosure
INFORMATION REQUEST FOR VOGTLE NUCLEAR POWER 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. Lists
should contain enough information to be easily understood to someone who has a knowledge
of pressurized water reactor technology.
1.
From your most-recent probabilistic safety analysis (PSA) excluding external events and
fires:
a.
Two risk rankings of components from your site-specific probabilistic safety analysis
(PSA): one sorted by Risk Achievement Worth (RAW), and the other sorted by
Birnbaum Importance.
b.
A list of the top 500 cutsets.
c.
A risk ranking of all operator actions, sorted by RAW.
2.
From your most-recent probabilistic safety analysis (PSA) including external events and
fires:
a.
Two risk rankings of components from your site-specific probabilistic safety analysis
(PSA): one sorted by Risk Achievement Worth (RAW), and the other sorted by
Birnbaum Importance.
b.
A list of the top 500 cutsets.
c.
A risk ranking of all operator actions, sorted by RAW.
3.
Human reliability worksheets for the operator actions included in your PSA model.
4.
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.).
5.
A list of operating experience evaluations completed within the last two years, sorted by
associated component and/or system.
6.
A list of design modifications implemented within the last two years, sorted by affected
system.
7.
A list of corrective-action evaluations that involved plant equipment and were completed
within the last two years, sorted by involved component or system.
8.
A list of common-cause failure of components that have occurred at Vogtle and have been
identified within the last five years.
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Enclosure
9.
A list of operability evaluations completed within the last two years, sorted by associated
component or system.
10. Contact information for a person to discuss PRA information prior to information gathering
trip: name, title, phone number, and e-mail address.
11. List of equipment currently on the sites Station Equipment Reliability Issues List, including
a description of the reason(s) why each component is on that list and summaries (if
available) of your plans to address those reasons.
12. List of equipment currently in RIS-05-020 (Formerly GL 91-18) status.
13. List of equipment currently in MR (a)(1) status.