ML14113A181
| ML14113A181 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/23/2014 |
| From: | Nease R NRC/RGN-II/DRS/EB1 |
| To: | Heacock D Virginia Electric & Power Co (VEPCO) |
| References | |
| IR-14-007 | |
| Download: ML14113A181 (6) | |
See also: IR 05000280/2014007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
April 23, 2014
Mr. David A. Heacock
President and Chief Nuclear Officer
Virginia Electric and Power Company
Dominion Nuclear
Innsbrook Technical Center
5000 Dominion Boulevard
Glen Allen, VA 23060-6711
SUBJECT:
NOTIFICATION OF SURRY POWER STATION, UNITS 1 AND 2 COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
05000280/2014007, 05000281/2014007
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 (CDBI) at your Surry Power
Station, Units 1 and 2, during the weeks of August 18 - 22, September 8 - 12, and
September 22 - 26, 2014. Eric Stamm, a Senior Reactor Inspector from the NRCs Region II
Office, will lead the inspection team. This inspection will be conducted in accordance with the
baseline inspection procedure, Procedure 71111.21, Component Design Bases Inspection,
issued November 29, 2013.
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 April 21, 2014, Mr. Stamm confirmed with Mr. Barry 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 July 28 - August 1, 2014
Onsite weeks: August 18 - 22, September 8 - 12, and September 22 - 26, 2014
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 support Mr. Stamm 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 July 14, 2014.
D. Heacock
2
Additional documents will be requested during the information-gathering visit. The inspectors
will try to minimize your administrative burden by specifically identifying only those documents
required for inspection preparation. The additional information will need to be available to the
team in the Region II Office prior to the inspection teams preparation week of August 11, 2014.
Mr. Stamm will also discuss the following inspection support administrative details: (1)
availability of knowledgeable plant engineering and licensing personnel to serve as points of
contact during the inspection, (2) method of tracking inspector requests during the
inspection, (3) licensee computer access, (4) working space, (5) arrangements for site access,
and (6) other applicable information.
In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections,
Exemptions, Requests for Withholding, of the NRCs Rules of Practice, a copy of this letter
and its Enclosure will be available electronically for public inspection in the NRCs Public
Document Room or from the Publicly Available Records (PARS) component of the NRCs
Agencywide Documents Access and Management 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. Stamm at 404-997-4575 or contact
me at 404-997-4530.
Sincerely,
Rebecca L. Nease, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-280, 50-281
Enclosure:
Information Request for Surry Power
Station, Units 1 and 2 Component
Design Bases Inspection
cc: Distribution via Listserv
______________x SUNSI REVIEW COMPLETE FORM 665 ATTACHED
OFFICE
RII:DRS
RII:DRS
SIGNATURE
NAME
E. STAMM
R. NEASE
DATE
4/22/2014
4/22/2014
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
Enclosure
INFORMATION REQUEST FOR SURRY POWER STATION, UNITS 1 AND 2
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 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 PSA including external events and fires:
a. Two risk rankings of components from your site-specific PSA: one sorted by 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
December 1, 2011, 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, and motor-operated valve 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 December 1, 2011.
8.
List and brief description of safety-related structures, systems, or components (SSCs)
design modifications implemented since December 1, 2011.
9.
List and brief description of common-cause component failures that have occurred
since December 1, 2011.
10. List and brief description of operability evaluations completed since December 1, 2011.
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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).
12. List and brief description of equipment currently in degraded or nonconforming status as
described in Regulatory Issue Summary 05-020.
13. List and reason for equipment classified in maintenance rule (a)(1) status from
December 1, 2011, to present.
14. Copies of system descriptions (or the design basis documents) for safety-related systems.
15. Copy of Updated Final Safety Analysis Report.
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 performed since December 1, 2011.
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 July 28, 2014)
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. Piping and instrumentation diagrams (P&IDs) for safety-related systems.
(Electronic and 1/2 size - hard copy week of July 28, 2014)
27. Index and Legend for P&IDs.
28. Copy of Operability Determination procedure(s).
29. Copies of corrective action documents (i.e. condition reports) associated with findings from
previous CDBI. (If applicable)
30. Index (procedure number, title, and current revision) of station Emergency Operating
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.
31. Copy of any self-assessments performed in preparation for this inspection.
3
32. List of any condition reports generated in preparation for this inspection.
33. Copies of condition reports generated from previous CDBI (2011).
34. Contact information for a person to discuss PSA information prior to the information-
gathering trip. (Name, title, phone number, and e-mail address)