ML120050043
| ML120050043 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/05/2012 |
| From: | Nease R L NRC/RGN-II/DRS/EB1 |
| To: | Heacock D A Dominion Nuclear Connecticut, Virginia Electric & Power Co (VEPCO) |
| References | |
| IR-12-007 | |
| Download: ML120050043 (7) | |
See also: IR 05000338/2012007
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257
January 5, 2012
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 NORTH ANNA POWER STATION
- COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT 05000338, 339/2012007 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 North Anna Power
Station during the weeks of May 21 - 25, June 4 - 8, and June 18 - 22, 2012. 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 January 4, 2012, Mr. Sandal confirmed with Mr. Leberstien
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 30 - May 4, 2012
- Onsite weeks: May 21 - 25, June 4 - 8, and June 18 - 22, 2012
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 April 23, 2012. Contact
VEPCO 2 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 team's preparation week of May 14. 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) 997-4530.
Sincerely,
/RA/ Rebecca Nease, Chief Engineering Branch 1
Division of Reactor Safety
Docket No.: 50-338, 50-339 License No.: NPF-4, NPF-7
Enclosure: Information Request for North Anna Power Station - Component Design Bases Inspection
cc w/enc/: (See page 3)
VEPCO 3 cc w/encl: Larry Lane Site Vice President North Anna Power Station Virginia Electric & Power Company Electronic Mail Distribution
Fred Mladen Director, Station Safety & Licensing Virginia Electric and Power Company Electronic Mail Distribution
Michael Crist Plant Manager North Anna Power Station Virginia Electric & Power Company Electronic Mail Distribution
Lillian M. Cuoco, Esq. Senior Counsel Dominion Resources Services, Inc. Electronic Mail Distribution
Tom Huber Director, Nuclear Licensing & Operations Support Virginia Electric and Power Company Electronic Mail Distribution
Ginger L. Rutherford 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 North Anna Power Station
U.S. Nuclear Regulatory Commission P.O. Box 490 Mineral, VA 23117
Michael M. Cline Director Virginia Department of Emergency Services Management Electronic Mail Distribution
Executive Vice President Old Dominion Electric Cooperative Electronic Mail Distribution
County Administrator Louisa County P.O. Box 160 Louisa, VA 23093
_ML#120050043_______________
X SUNSI REVIEW COMPLETE OFFICE RII:DRS RII:DRS SIGNATURE /RA/ /RA/ NAME S. SANDAL R. NEASE DATE 01/ 4 / 2012 01/ 5 /2012 E-MAIL COPY YES NO YES NOYES NOYES NOYES NO YES NOYES
Enclosure INFORMATION REQUEST FOR NORTH ANNA 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 October 1, 2009 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 station's 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 October 1, 2009
8. List and brief description of safety related SSC design modifications implemented since October 1, 2009
9. List and brief description of common-cause component failures that have occurred since October 1, 2009
2 Enclosure 10. List and brief description of operability evaluations completed since October 1, 2009
11. List of equipment on the site's 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 RIS 05-020
13. List and reason for equipment classified in maintenance rule (a)(1) status since October 1, 2009 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 October 1, 2009
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 April 30)
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&D's for ECCS systems (electronic and 1/2 size - hard copy week of April 30)
27. Index and Legend for PI&Ds
28. Copy of design bases documents for ECCS systems
29. Copy of Operability determination procedure(s)
3 Enclosure 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)