ML18190A478

Notification of North Anna Power Station, Units 1 & 2 Design Bases Assurance Inspection (Team) - U.S. Nuclear Regulatory Commission Inspection Report 05000338/2018010 and 05000339/2018010

ML18190A478
Person / Time
Site:	North Anna
Issue date:	07/09/2018
From:	Marvin Sykes NRC/RGN-II/DRS/EB1
To:	Stoddard D Virginia Electric & Power Co (VEPCO)
References
IR 2018010
Download: ML18190A478 (6)

See also: IR 05000338/2018010

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

July 9, 2018

Mr. Daniel G. Stoddard

Senior Vice President and

Chief Nuclear Officer

Innsbrook Technical Center

5000 Dominion Boulevard

Glen Allen, VA 23060-6711

SUBJECT: NOTIFICATION OF NORTH ANNA POWER STATION, UNITS 1 & 2 DESIGN

BASES ASSURANCE INSPECTION (TEAM) - U.S. NUCLEAR REGULATORY

COMMISSION INSPECTION REPORT 05000338/2018010 AND

05000339/2018010

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 North Anna

Power Station, Units 1 & 2 during the weeks of October 29 and November 26, 2018.

Mr. Geoffrey Ottenberg, 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 (Team), dated December 8, 2016 (ADAMS

ML16340B000).

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 28, 2018, with Mr. Donald Taylor, 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 September 4- 7, 2018

• Onsite weeks: Weeks of October 29- November 2, 2018 and November 26- 30, 2018

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. George Macdonald, a Region II Senior Risk Analyst, will support Mr. Ottenberg during the

information-gathering visit to review probabilistic risk assessment data and identify components

to be examined during the inspection. Additionally, during the onsite weeks, 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 August 24, 2018.

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 October 19, 2018, to support the inspection teams preparation week. During the

information-gathering trip, Mr. Ottenberg 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.

This letter, its enclosure, and your response (if any) will be made available for public inspection

and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document

Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for

Withholding.

Thank you for your cooperation in this matter. If you have any questions, regarding the

information requested or the inspection, please contact Mr. Ottenberg at 404-997-4658 or

contact me at 404-997-4639.

Sincerely,

/RA/

Marvin D. Sykes, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-338, 50-339

License Nos.: NPF-4, NPF-7

Enclosure:

Notification of North Anna Power Station, units 1 & 2,

Design Bases Assurance Inspection (Team)

cc: Distribution via Listserv

______________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED

OFFICE RII:DRS RII:DRS

SIGNATURE GKO MDS EMAIL

NAME OTTENBERG SYKES

DATE 7/9/2018 6/29/2018

E-MAIL COPY? YES NO YES NO

INFORMATION REQUEST FOR NORTH ANNA POWER STATION, UNITS 1 & 2

DESIGN BASES ASSURANCE INSPECTION (TEAM)

Please provide the information electronically in .pdf files, Excel, or other searchable format on

file sharing website, if utilized (ex. FTP site, SharePoint, etc.) or CDROM. The website (or

CDROM) should be indexed and hyperlinked to facilitate ease of use. The requested items

below, identified with an asterisk (*), should have a date range from April 1, 2015, until

present.

1. *List and brief description of permanent and field work completed 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 as

described in NRC Inspection Manual Chapter 0326, issued November 20, 2017

Enclosure

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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

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 procedures addressing the following: 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.

22. List of motor operated valves and air operated valves in the valve program, and their

associated design margin and risk ranking

23. Primary AC and DC calculations for safety-related buses

24. One-line diagram of electrical plant (Electronic only)

25. Index and legend for electrical plant one-line diagrams

26. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)

27. Index and legend for P&IDs

28. Index (procedure number, title, and current revision) of station Emergency Operating

Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures

29. Copies of corrective action documents generated from previous CDBI

30. Copy of any self-assessments performed, and corrective action documents generated, in

preparation for current DBAI

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31. 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)