ML24115A195

Notification of Surry Power Station Comprehensive Engineering Team Inspection - U.S. NRC Inspection Report 05000280/2024011 and 05000281/2024011

ML24115A195
Person / Time
Site:	Surry
Issue date:	04/24/2024
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Carr E Virginia Electric & Power Co (VEPCO)
References
IR 2024011
Download: ML24115A195 (6)

See also: IR 05000280/2024011

Text

Eric S. Carr

President -Nuclear Operations

And Chief Nuclear Officer

Virginia Electric and Power Company

Innsbrook Technical Center

500 Dominion Blvd

Glenn Allen, VA 23060-6711

SUBJECT: NOTIFICATION OF SURRY POWER STATION COMPREHENSIVE

ENGINEERING TEAM INSPECTION - U.S. NRC INSPECTION REPORT

05000280/2024011 AND 05000281/2024011

Dear Mr. Carr:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region II staff will conduct a Comprehensive Engineering Team Inspection (CETI) at your Surry

Power Station during the weeks of July 15 and July 29, 2024. Mr. Steven Downey, 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, Comprehensive

Engineering Team Inspection (CETI), issued October 7, 2022.

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, and operating

experience, and modifications.

During a conversation while on site at Surry Power Station on April 18th, 2024, with Mr. Samuel

Baker, 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 June 3, 2024

• Onsite weeks: Weeks of July 15 and July 29, 2024

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 Reactor Analyst, will support Mr. Downey 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 may be

needed on the plant-referenced simulator to facilitate the development of operator action-based

scenarios. April 24, 2024

E. Carr 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 Tuesday, May 28, 2024.

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 Friday, July 5, 2024, to support the inspection teams preparation week. During the

information-gathering trip, Mr. Downey 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. Downey at 404-997-4830 or contact

me at 404-997-4506.

Sincerely,

James Baptist, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos. 05000280 and 05000281

License Nos. DPR-32 and DPR-37

Enclosure:

Information Request for Surry Power Station Comprehensive

Engineering Team Inspection

cc w/ encl: Distribution via LISTSERV

Signed by Baptist, James

on 04/24/24

ML241154A195

SUNSI Review x Non-Sensitive x Publicly Available

x Sensitive Non-Publicly Available

OFFICE R2/DRS/EB1 R2/DRS/EB3

NAME J. Downey J. Baptist

DATE 4//24/2024 4/24/2024

INFORMATION REQUEST FOR SURRY POWER STATION COMPREHENSIVE

ENGINEERING TEAM 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. The requested items below, identified with an asterisk (*),

should have a date range from July 1, 2021, until present.

1. *List of modifications to systems, structures or components (SSCs) that are permanent

and field work completed. (For the purpose of this inspection, modifications include

permanent: plant changes, design changes, calculation changes, procedure changes, and

set point changes.)

The list should contain the number of the modification, a short description, affected system

and unit. If multiple categories/stages of modifications exist, provide a description of the

types relative to the coding scheme in your transmittal. Additionally, the list should be

categorized by quality level (i.e., safety or non-safety) as well as whether accompanied by

a screening or 10 CFR 50.59 evaluation. A query report return-field-set might look like:

Identifier Unit System1 Description Type2 Status3 QA Condition4 50.595

1 e.g. If systems are provided with some type of number or acronym designation,

define the systems designation on a separate list or document

2 e.g. Engineering Design/Document Change, Design Change Notice, Test,

Experiment, etc.

3 e.g. Closed, Returned to Operation, Void, Partially Completed, Released for

Installation, Phase 1 Completed, etc.

4 e.g. Safety Related or Non-Safety Related

5 e.g. Screened Out or Full 10 CFR 50.59 Evaluation

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 with applicable

administrative procedures used to maintain them

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

Enclosure

2

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 Generic Letter 91-18, Revision 1

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 Selected Licensee Commitments (SLC)

18. Copy of the Quality Assurance Program Document

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. Copy of procedures addressing the following: loss of service water system or ultimate heat

sink (UHS); controls to prevent clogging due to macrofouling; and performance, testing,

and inspection requirements for service water system and UHS

23. List of heat exchangers or equipment cooled by service water directly or indirectly. Include

the risk ranking for each listed heat exchanger.

24. List of motor operated valves and air operated valves in valve programs, and their

associated design margin and risk ranking

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

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

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

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

29. Index and legend for P&IDs

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

Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures

31. Copies of corrective action documents generated from previous design bases assurance

inspections

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

preparation for current comprehensive engineering team inspection

33. 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)

34. List of system acronyms