ML22271A620

Notification of Shearon Harris Nuclear Power Plant Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2023010

ML22271A620
Person / Time
Site:	Harris
Issue date:	09/29/2022
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Haaf T Duke Energy Progress
References
IR 2023010
Download: ML22271A620 (6)

See also: IR 05000400/2023010

Text

September 29, 2022

Mr. Thomas Haaf

Site Vice President

Duke Energy Progress, LLC

Shearon Harris Nuclear Power Plant

5413 Shearon Harris Road

Mail Code HNP01

New Hill, NC 27562-9300

SUBJECT: NOTIFICATION OF SHEARON HARRIS NUCLEAR POWER PLANT

COMPREHENSIVE ENGINEERING TEAM INSPECTION - U.S. NUCLEAR

REGULATORY COMMISSION INSPECTION REPORT 05000400/2023010

Dear Mr. Haaf:

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

Shearon Harris Nuclear Power Plant during the weeks of January 30 and February 13, 2023.

Mr. Paul Carman, 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). This is a new procedure

that has not been issued yet, but it is anticipated that it will be issued by December 31, 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 telephone conversation on September 26, 2022, with Ms. Sarah McDaniel, 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 December 12, 2022

Onsite weeks: Weeks of January 30 and February 13, 2023

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. Carman 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.

T. Haaf 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, December 2, 2022.

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, January 20, 2023, to support the inspection teams preparation week. During

the information-gathering trip, Mr. Carman 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. Carman at 404-997-4471 or contact

me at 404-997-4506.

Sincerely,

James Baptist, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No. 05000400

License No. NPF-63

Enclosure:

Information Request for Shearon Harris

Nuclear Power Plant Comprehensive

Engineering Team Inspection

cc w/ encl: Distribution via LISTSERV

Signed by Baptist, James

on 09/29/22

ML22271A620

X SUNSI Review X Non-Sensitive X Publicly Available

Sensitive Non-Publicly Available

OFFICE RII/DRS RII/DRS

NAME P. Carman J. Baptist

DATE 9/27/2022 9/29/2022

INFORMATION REQUEST FOR SHEARON HARRIS NUCLEAR POWER PLANT

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 January 1, 2020, 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

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

Enclosure

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 September 30, 2019

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. 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. Response to Generic Letter 89-13 including any regulatory commitments made

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

the risk ranking for each listed heat exchanger.

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

associated design margin and risk ranking

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

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

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

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

30. Index and legend for P&IDs

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

Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures

2

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

inspections

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

preparation for current comprehensive engineering team inspection

34. 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)

3