ML053010217
| ML053010217 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/28/2005 |
| From: | Ogle C NRC/RGN-II/DRS/EB1 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| References | |
| IR-05-005 | |
| Download: ML053010217 (4) | |
See also: IR 05000280/2005005
Text
October 28, 2005
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 SURRY NUCLEAR STATION INTEGRATED DESIGN AND
COMPONENT CAPABILITY INSPECTION - NRC INSPECTION REPORT
05000280/2005005 AND 05000281/2005005
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 an integrated design and component capability inspection at your
Surry Nuclear Station during the weeks of January 9-13, 2006, January 23-27, 2006, and
February 6-10, 2006. The inspection team will be led by Mr. Caswell Smith, a Senior Reactor
Inspector from the NRC's Region II Office. This inspection will be conducted in accordance
with the soon to be issued baseline inspection Procedure 71111.21, Integrated Design and
Component Capability Inspection. (This inspection procedure has not been issued yet.)
As currently planned, 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 October 18, 2005, Mr. Smith of my staff, and Mr. Barry
Garber of your staff, confirmed arrangements for an information gathering site visit and the
three-week onsite inspection. The schedule is as follows:
Information gathering visit: Week of December 12, 2005
Onsite weeks: January 9, 2006; January 23, 2006; and February 6, 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. Walter Rogers, a Region II Senior Reactor
Analyst, will accompany Mr. Smith 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. Please contact Mr. Smith 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 inspection preparation.
2
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: office space; specific documents requested to be made
available to the team in their office space and prior to the inspection preparation week of
January 2, 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 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 Publically Available Records (PARS) component of 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. 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.: 50-280, and 50-281
License Nos.: DPR - 32 and DPR - 37
cc: w/o encl: (See page 3)
3
cc w/encl:
Chris L. Funderburk, Director
Nuclear Licensing and
Operations Support
Virginia Electric & Power Company
Electronic Mail Distribution
Donald E. Jernigan
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 Counsel
Dominion Resources Services, Inc.
Electronic Mail Distribution
Attorney General
Supreme Court Building
900 East Main Street
Richmond, VA 23219
_________________________
OFFICE
RII:DRS
RII:DRP
RII:DRS
SIGNATURE
/RA/
/RA/
/RA/
/RA/
NAME
C. Ogle
KLandis
C. Smith
L.Mellen
DATE
10/28/2005
10/27/2005
10/19/2005
10/19/2005
10/ /2005
10/ /2005
10/ /2005
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
Enclosure
INFORMATION REQUEST FOR SURRY NUCLEAR STATION -- INTEGRATED DESIGN AND
COMPONENT CAPABILITY 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.
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 Events 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
etc.)
6.
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.