ML20171A348

Notification of Surry Power Station Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000280/2020010 and 05000281/2020010

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)

See also: IR 05000280/2020010

Text

June 19, 2020

Mr. Daniel G. Stoddard

Senior Vice President and

Chief Nuclear Officer

Innsbrook Technical Center

5000 Dominion Blvd.

Glen Allen, VA 23060-6711

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.

D. Stoddard

2

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

Enclosure

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

2

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

3

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)