IR 05000280/2020010
| ML20171A348 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/19/2020 |
| From: | James Baptist NRC/RGN-II/DRS/EB1 |
| To: | Stoddard D Virginia Electric & Power Co (VEPCO) |
| References | |
| IR 2020010 | |
| Download: ML20171A348 (6) | |
Text
une 19, 2020
SUBJECT:
NOTIFICATION OF SURRY POWER STATION DESIGN BASES ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT 05000280/2020010 AND 05000281/2020010
Dear Mr. Stoddard:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a Design Bases Assurance Inspection (DBAI) at your Surry Power Station during the weeks of September 14-18, 2020, and September 28-October 2, 2020.
Mr. Theo Fanelli, a Senior Reactor Inspector from the NRCs Region II office, will lead the inspection team. The inspection will be conducted in accordance with Inspection Procedure 71111.21M, Design Bases Assurance Inspection (Teams), dated December 8, 2016 (ADAMS ML16238A320).
The inspection will evaluate the capability of components that have been modified and 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 June 15, 2020, with Mr. Steve Newman, we confirmed arrangements for an information-gathering site visit and the two-week onsite inspection. The schedule is as follows:
- Information-gathering visit: Week of August 24, 2020
- Onsite weeks: Weeks of September 14 and September 28, 2020 The purpose of the information-gathering visit is to meet with members of your staff to identify components that have been modified, risk-significant components and operator actions.
Information and documentation needed to support the inspection will also be identified.
Mr. Andy Rosebrook, a Region II Senior Risk Analyst, will support Mr. Fanelli during the information-gathering visit to review probabilistic risk assessment data and identify components to be examined during the inspection. Additionally, during the first onsite week, time will be needed on the plant-referenced simulator in order to facilitate the development of operator action-based scenarios. 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 Friday, August 14, 2020.
Additional documents will be requested following 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 be needed in the Region II office by Wednesday, September 2, 2020, to support the inspection teams preparation week.
During the information-gathering trip, Mr. Fanelli 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 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 Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website 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. Fanelli at 404-997-4433 or contact me at 404-997-4506.
Sincerely, James Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-280, 50-281 License Nos.: DPR-32, DPR-37 Enclosure:
Notification of Surry Power Station Design Bases Assurance Inspection (Teams)
cc: Distribution via Listserv
ML20171A348 OFFICE RII:DRS RII:DRS SIGNATURE EJS2 TNF1 FOR JBB1 NAME T. Fanelli J. Baptist DATE 6/15/2020 6/15/2020
INFORMATION REQUEST FOR SURRY POWER STATION DESIGN BASES ASSURANCE INSPECTION (TEAMS)
Please provide the information electronically in .pdf files, Excel, or other searchable format on CDROM (or Certrec, FTP site, SharePoint, etc.). The CDROM (or website) should be indexed and hyperlinked to facilitate ease of use. The requested items below, identified with an asterisk (*), should have a date range from February 1, 2017, until present.
1. *List and brief description of permanent plant modifications including permanent plant changes, design changes, set point changes, procedure changes, equivalency evaluations, suitability analyses, calculations, and commercial grade dedications. Include an index of systems (system numbers/designators and corresponding names), the safety classification for each modification, and type of modification.
2. 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 cut-sets c. A list of the top 500 LERF contributors 3. 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 cut-sets 4. Risk ranking of operator actions from your site-specific PSA sorted by RAW and human reliability worksheets for these items 5. List of time-critical operator actions with a brief description of each action 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 and brief description of Root Cause Evaluations performed 8. *List and brief description of common-cause component failures that have occurred 9. List and brief description of equipment currently in degraded or nonconforming status.
10. *List and brief description of Operability Determinations and Functionality Assessments 11. *List and reason for equipment that has been classified in maintenance rule (a)(1) status Enclosure
12. *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) along with dates added or removed from the issues list 13. List of current operator work arounds/burdens 14. Copy of Updated Final Safety Analysis Report 15. Copy of Technical Specification(s)
16. Copy of Technical Specifications Bases 17. Copy of Technical Requirements Manual(s)
18. Copy of the Quality Assurance Program Manual 19. Copy of Corrective Action Program Procedure(s)
20. Copy of Operability Determination Procedure(s)
21. Copy of Original SER with all Supplements 22. Copy of procedures addressing the following: Corrective Action Program (CAP),
Modifications, design changes, set point changes, equivalency evaluations or suitability analyses, commercial grade dedications, post-modifications testing, 10 CFR 50.59 screenings and evaluations, and UFSAR updates.
23. List of motor operated valves and air operated valves in valve programs, and their associated design margin and risk ranking (Please Note JOG program commitments for MOVs and AOVs).
24. Primary AC and DC calculations for safety-related buses 25. One-line diagram of electrical plant (Electronic only)
26. Index and legend for electrical plant one-line diagrams 27. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
28. Index and legend for P&IDs 29. Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures 30. Copies of corrective action documents generated from previous CDBI / DBAI 31. Copy of any self-assessments performed, and corrective action documents generated, in preparation for current DBAI
32. Contact information for a person to discuss PSA information prior to and during the information-gathering trip (Name, title, phone number, and e-mail address)