ML111400367
| ML111400367 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/19/2011 |
| From: | Binoy Desai NRC/RGN-II/DRS/EB1 |
| To: | Heacock D Virginia Electric & Power Co (VEPCO) |
| References | |
| IR-11-011 | |
| Download: ML111400367 (6) | |
See also: IR 05000280/2011011
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
May 19, 2011
Mr. David A. Heacock
President and Chief Nuclear Officer
Virginia Electric and Power Company
Innsbrook Technical Center
5000 Dominion Boulevard
Glen Allen, VA 23060-6711
SUBJECT:
NOTIFICATION OF SURRY POWER STATION - COMPONENT DESIGN
BASES INSPECTION - NRC INSPECTION REPORT 05000280, 281/2011011
Dear Mr. Heacock:
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 Surry Power Station
during the weeks of November 14 - 18, November 28 - December 2, and December 12 - 16,
2011. The inspection team will be led by Shane Sandal, 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 6, 2010.
The inspection will evaluate the capability of risk significant / low margin components to function
as designed and to 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 4, 2011, Mr. Sandal confirmed with Mr. Garber 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 October 24 - 28, 2011
Onsite weeks: November 14 - 18, November 28 - December 2, and December 12 - 16,
2011
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. George MacDonald, a Region II Senior
Reactor Analyst, will accompany Mr. Sandal 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 provide the referenced information to the Region II office by October 17, 2011. Contact
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Mr. Sandal with any questions concerning the requested information. The inspectors will try to
minimize your administrative burden by specifically identifying only those documents required
for inspection preparation.
Additional documents will be requested during the information gathering visit. The additional
information will need to be made available to the team in the Region II office prior to the
inspection teams preparation week of November 7. Mr. Sandal, will also discuss the following
inspection support administrative details: availability of knowledgeable plant engineering and
licensing personnel to serve as points of contact during the inspection; method of tracking
inspector requests during the inspection; licensee computer access; working space;
arrangements for site access; and other applicable information.
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. Sandal at (404) 997-4513 or me at
(404) 997-4519.
Sincerely,
/RA.
Binoy B. Desai, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-280, 50-281
Enclosure: INFORMATION REQUEST FOR SURRY POWER STATION - COMPONENT
DESIGN BASES INSPECTION
cc w/enc/: (See page 3)
3
cc w/encl:
Gerald T. Bischof
Site Vice President
Surry Power Station
Virginia Electric and Power Company
Electronic Mail Distribution
B. L. (Sonny) Stanley
Director, Nuclear Safety and Licensing
Virginia Electric and Power Company
Electronic Mail Distribution
Lillian M. Cuoco, Esq.
Senior Counsel
Dominion Resources Services, Inc.
Electronic Mail Distribution
Chris L. Funderburk
Director, Nuclear Licensing & Operations Support
Virginia Electric and Power Company
Electronic Mail Distribution
Ginger L. Melton
Virginia Electric and Power Company
Electronic Mail Distribution
Virginia State Corporation Commission
Division of Energy Regulation
P.O. Box 1197
Richmond, VA 23209
Attorney General
Supreme Court Building
900 East Main Street
Richmond, VA 23219
Senior Resident Inspector
Surry Power Station
U.S. Nuclear Regulatory Commission
5850 Hog Island Rd
Surry, VA 23883
Michael M. Cline
Director
Virginia Department of Emergency Services Management
Electronic Mail Distribution
ML111400367_ XG SUNSI REVIEW COMPLETE XG FORM 665 ATTACHED
OFFICE
RII:DRS
RII:DRS
SIGNATURE
NAME
SSANDEL
BDESAI
DATE
5/ 18 /2011
5/ 19 /2011
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
Enclosure
INFORMATION REQUEST FOR SURRY POWER STATION
COMPONENT DESIGN BASES INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM (or FTP site, Sharepoint, etc.) The CDROM (or website) should be indexed and
hyperlinked to facilitate ease of use.
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
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
3.
Risk ranking of operator actions from your site specific PSA sorted by RAW. Provide
human reliability worksheets for these items
4.
List of time critical operator actions with a brief description of each action
5.
List of Emergency and Abnormal Operating Procedures revised (significant) since April 1,
2008 with a brief description of each revision
6.
List of components 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.) and associated evaluations or
calculations
7. List of station operating experience evaluations/reviews performed and documented in the
stations corrective action program for industry events and safety related equipment
failures/vulnerabilities [as communicated by NRC generic communications, industry
communications, 10 CFR part 21 notifications, etc.] since April 1, 2008
8.
List and brief description of safety related SSC design modifications implemented since
April 1, 2008
9.
List and brief description of common-cause component failures that have occurred since
April 1, 2008
10. List and brief description of operability evaluations completed since April 1, 2008
11. List of equipment 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 the issue(s)
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Enclosure
12. List and brief description of equipment currently in degraded or nonconforming status as
described in RIS 05-020
13. List and reason for equipment classified in maintenance rule (a)(1) status since April 1,
2008 to present
14. Copies of System Descriptions (or the like design basis documents) for Safety-Related
Systems
15. Copy of UFSAR(s)
16. Copy of Technical Specification(s)
17. Copy of Technical Specifications Bases
18. Copy of Technical Requirements Manual(s)
19. List and brief description of Root Cause Evaluations that have been performed since April
1, 2008
20. In-service Testing Program Procedure(s)
21. Corrective Action Program Procedure(s)
22. One line diagram of electrical plant (electronic and full size - hard copy week of October
24)
23. Index and legend for electrical plant one-line diagrams
24. Primary AC calculation(s) for safety-related buses
25. Primary DC calculation(s) for safety-related buses
26. PI&Ds for ECCS systems (electronic and 1/2 size - hard copy week of October 24)
27. Index and Legend for PI&Ds
28. Copy of design bases documents for ECCS systems
29. Copy of Operability determination procedure(s)
30. Copies of condition reports associated with findings from previous CDBI (if applicable)
31. Index (procedure number, titles, and current revision) of station Emergency Operating
Procedures (EOPs), Abnormal Operating Procedures (AOPs), and Annunciator Response
Procedures (ARPs)
32. Contact information for a person to discuss PRA information prior to the information
gathering trip (name, title, phone number, and e-mail address)