ML21013A411

Notification of Edwin I. Hatch Nuclear Plant Design Bases Assurance Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000321/2021010 and 05000366/2021010

ML21013A411
Person / Time
Site:	Hatch
Issue date:	01/13/2021
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Dean E Southern Nuclear Operating Co
References
IR 2021010
Download: ML21013A411 (5)

See also: IR 05000321/2021010

Text

January 13, 2021

Mr. Edwin (Sonny) Dean

Site Vice President

Edwin I. Hatch Nuclear Plant

Southern Nuclear Operating Company, Inc.

11028 Hatch Parkway North

Baxley, GA 31513

SUBJECT: NOTIFICATION OF EDWIN I. HATCH NUCLEAR PLANT DESIGN BASES

ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION

INSPECTION REPORT 05000321/2021010 AND 05000366/2021010

Dear Mr. Dean:

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 plant Hatch

during the weeks of April 26, 2021 and May 10, 2021. Mr. Mark Schwieg, a 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 January 1, 2017 (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 January 11, 2021, with James Love 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 April 12, 2021

• Onsite weeks: Weeks of April 26 and May 10, 2021

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.

Shane Sandal, a Region II Senior Risk Analyst, will support Mr. Mark Schwieg 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.

S. Dean 2

Starting on March 20, 2020, in response to the National Emergency declared by the President

of the United States on the public health risks of the coronavirus (COVID-19), inspectors were

directed to begin telework. In addition, regional baseline inspections were evaluated to

determine if all or portion of the objectives and requirements stated in the IP could be performed

remotely. If the inspections could be performed remotely, they were conducted per the

applicable IP. In some cases, portions of an IP were completed remotely and on site.

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 April 12, 2021. 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

April 19, 2021, to support the inspection teams preparation week. During the information-

gathering trip, Mr. Schwieg 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. Schwieg at 404-997-4631 or contact

me at 404-997-4506.

Sincerely,

/RA/

James Baptist, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-321, 50-366

License Nos.: DPR-57 and NPF-5

Enclosure:

Notification of Hatch,

Design Bases Assurance Inspection (Teams)

cc: Distribution via Listserv

S. Dean 3

SUBJECT: NOTIFICATION OF EDWIN I. HATCH NUCLEAR PLANT DESIGN BASES

ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION

INSPECTION REPORT 05000321/2021010 AND 05000366/2021010

Dated January 13, 2021

DISTRIBUION:

M. Schwieg, RII

J. Baptist, RII

RIDNrrPMHATCH

RIDSNrrDRO Resource

ADAMS ACCESION NUMBER: ML21013A411_

OFFICE RII:DRS RII:DRS

NAME M. Schwieg J. Baptist

DATE 01/13/2021 01/13/2021

E-MAIL COPY? YES NO YES NO

OFFICIAL RECORD COPY

INFORMATION REQUEST FOR HATCH

DESIGN BASES ASSURANCE INSPECTION (TEAMS)

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 March 31, 2018, 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 December 3, 2015

10. *List and brief description of Operability Determinations and Functionality Assessments

Enclosure

2

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

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)