ML21207A107

Biennial Problem Identification and Resolution Inspection Report 05000321/2021010 and 05000366/2021010

ML21207A107
Person / Time
Site:	Hatch
Issue date:	07/26/2021
From:	Alan Blamey NRC/RGN-II/DRP/RPB2
To:	Gayheart C Southern Nuclear Operating Co
T Francis
References
IR 2021010
Download: ML21207A107 (8)

See also: IR 05000321/2021010

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

July 26, 2021

Ms. Cheryl A. Gayheart

Regulatory Affairs Director

Southern Nuclear Operating Co., Inc

Edwin I. Hatch Nuclear Plant

3535 Colonnade Parkway

Birmingham, AL 35423

SUBJECT: EDWIN I. HATCH NUCLEAR PLANT UNITS 1 & 2 - BIENNIAL

PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT

05000321/2021010 AND 05000366/2021010

Dear Ms. Gayheart:

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

Region II staff will conduct a problem identification and resolution (PI&R) inspection at your

Edwin I. Hatch Nuclear Plant, Units 1 and 2 during the weeks of September 13, 2021, and

September 27, 2021. The inspection team will be led by Mr. Necota Staples, a Sr. Project

Engineer from the NRCs Region II office. This inspection will be conducted in accordance with

the baseline inspection procedure, 71152, Problem Identification and Resolution, issued

February 26, 2015.

The biennial PI&R inspection and assessment of the licensees Corrective Action Program

(CAP) complements and expands upon the resident baseline inspections of routine daily

screening of all corrective action program issues, quarterly focused issue reviews, and

semiannual trend PI&R reviews.

On July 14, 2021, Mr. Staples confirmed with Mr. Jimmy Collins, Licensing Manager, the details,

and expectations for the two weeks of the inspection.

The enclosure lists documents that will be needed prior to the inspection. Please have the

referenced information available no later than August 23, 2021. Contact Mr. Staples with any

questions concerning the requested information. The inspectors will try to minimize your

administrative burden by specifically identifying only those documents required for inspection

preparation.

If additional documents are needed, they will be requested when identified. Prior to the

inspection, Mr. Staples will discuss, with your staff, the following inspection support

administrative details: availability of knowledgeable plant engineering and licensing personnel to

serve as points of contact during the inspection; method of tracking inspector requests during

the inspection; and other applicable information.

C. Gayheart 2

In response to the COVID-19 coronavirus and updated Federal Government guidance on travel

and social distancing, the NRC inspection team is prepared to conduct this inspection

accordingly. Therefore, in support of this inspection some, or all, of the inspection team may

perform their reviews with minimal onsite staff interaction or remotely as conditions permit.

The NRC inspection team requests that your staff be prepared to support these

efforts. Additionally, the inspection team is open to any suggestions regarding communications

and coordination such that the overall effort from both the NRC inspection team and Hatch

Nuclear Plant support staff may be the most efficient while also prioritizing public health and

safety.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs

Rules of Practice, a copy of this letter will be available electronically for public inspection in the

NRC Public Document Room or from the Publicly Available Records (PARS) component of

NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site 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. Staples at (404) 997-4644.

Sincerely,

/RA/

Alan Blamey, Chief

Reactor Projects Branch 2

Division of Reactor Projects

Docket No. 05000321 and 05000366

License No. NPF-57, NPF-5

Enclosure: Information Request for Hatch Nuclear Plant

Problem Identification and Resolution Inspections

cc Distribution via ListServ

PAPERWORK REDUCTION ACT STATEMENT

This letter does not contain new or amended information collection requirements subject to the

Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements

were approved by the Office of Management and Budget, control number 3150-0011.

PUBLIC PROTECTION NOTIFICATION

C. Gayheart 3

The NRC may not conduct or sponsor, and a person is not required to respond to, a request for

information or an information collection requirement unless the requesting document displays a currently

valid Office of Management and Budget control number.

ML21207A107

OFFICE RII/DRS RII/DRP

NAME N. Staples A. Blamey

DATE 07/20/2021 07/262021

INFORMATION REQUEST FOR EDWIN I. HATCH NUCLEAR PLANT UNITS 1 & 2

PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION

(September 13 - 17, 2021 AND September 27 - October 01, 2021)

Note: Unless otherwise noted, the information requested below corresponds to documents

generated since May 01, 2019. Please provide the requested documents in electronic format.

If the information is not available in electronic format, please contact the inspection team leader

to coordinate other available methods to provide the information.

1. Copies of the corporate and site level procedures and sub-tier procedures associated with

the corrective action program. This should include procedures related to:

a) Corrective action process

b) Cause evaluation

c) Operating experience program

d) Employee concerns program

e) Self-assessment program

f) Maintenance rule program and implementing procedures

g) Operability determination and functionality assessment process

h) Degraded/non-conforming condition process (e.g., RIS 2005-20)

i) System health process or equivalent equipment reliability improvement programs

j) Preventive maintenance deferral process

If any of the procedures requested above were revised after May 01, 2019, please provide

copies of all revisions during the onsite inspection.

2. List of top ten risk-significant systems, top ten risk-significant components for each one of

the top ten risk-significant systems, and top ten risk-significant operator manual actions.

3. List of all Condition Reports (CRs) initiated including the following information for each CR:

a) CR number

b) Brief, but complete problem description

c) Priority or level

d) Affected system

e) Affected component

f) Responsible plant department

g) CR completion status

If possible, provide this list in a format compatible with spreadsheet software (i.e. Excel

example shown below) and ensure the list is searchable and can be filtered by system.

AR # Problem Priority System Component Org Status

CR001 A RHR Pump 2 RHR 2-RHR- ENG Open

failed flow criteria PMP-A

per SR 5.0.5.4

Enclosure

4. List of outstanding corrective actions including the following information for each action:

a) Corrective action number

b) Corrective action type (e.g., corrective action to prevent recurrence, enhancement,

maintenance rule evaluation, etc.)

c) Brief, but complete corrective action description

d) Associated CR number

e) Corrective action initiation date

f) Number of extensions

g) Corrective action due date

h) Completion status

If possible, provide this list in a format compatible with spreadsheet software (i.e. Excel,

example shown below) and ensure the list is searchable and can be filtered by system.

Corrective Type Description AR System Initiation Extensions Due Status

Action # Date Date

001 CAPR Revise CR0058 RHR 04/05/20 2 10/15/20 Awaiting

Procedure CARB

NGK-003-4585 review

5. List of control room deficiencies with a brief description and corresponding CR and/or work

order (WO) number.

6. List of operator workarounds and operator burdens with a brief description and

corresponding CR number, searchable and filtered by system.

7. List of all currently extended or overdue CRs, searchable and filtered by system and sorted

by initiation date, with the following information:

a) CR number

b) Priority or Significance

c) CR title and short description

8. List of all CRs that have been voided, cancelled, or deleted, searchable and filtered by

system. Please provide the following information for each CR:

a) CR number

b) Brief, but complete problem description

c) Reason voided, cancelled, or deleted

9. List of all structures, systems, and components (SSCs) which were classified as (a)(1) in

accordance with the Maintenance Rule since May 01, 2019.

Please include the following information for each system in (a)(1):

a) Date of classification in (a)(1)

b) Reason for being placed in (a)(1)

c) Planned actions and their status

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10. List of Maintenance Preventable Functional Failures (MPFF) of risk-significant systems.

Please include actions completed and current status.

11. List of corrective maintenance work orders and modifications for safety-related (SR)

structures, systems, and components and any work considered high risk. Please include

the following information for each work order:

a) WO number

b) Brief, but complete work description

c) Affected system and components

d) Date of initiation

e) Date of completion (if completed)

f) Associated CR (if applicable)

If possible, provide this list in a format compatible with spreadsheet software (i.e. Excel,

example shown below) and ensure the list is searchable and can be filtered by system.

Work Description System Component Initiation Due Status

Order # Date Date

WO01345 Replace breaker SI 2A-SI-PMP, 01/05/19 05/15/19 Closed

2A-BKR-08-BB4 BKR-08-BB4

for 2A SI Pump.

12. Corrective action closeout packages, including CRs with description of corrective actions, for

all NRC findings and licensee-identified violations (LIVs). Please include a cross-reference

linking NRC finding numbers and LIVs to appropriate CR numbers.

13. Corrective action closeout packages, including CRs with description of corrective actions, for

all licensee event reports (LERs) issued. Please include a cross reference linking LER

number to appropriate CR number.

14. List of all NRC generic communications (e.g., Information Notices, Generic Letters, etc.) and

industry operating experience (OE) documents (e.g., Part 21 reports, vendor information

letters, information from other sites, etc.) evaluated by the site for applicability to the station,

regardless of the determination of applicability. Please include the reference number (e.g.,

CR number) for the documents that evaluated the aforementioned OE information.

15. Copies of all quality assurance audits and/or assessments issued, including the last two

audits/assessments of the corrective action program.

16. Copies of all department self-assessments.

17. Copy of the most recent integrated plant trend report, departmental trend report(s), and

corrective action trend reports, including any human performance and equipment reliability

trends.

18. Copy of the latest Corrective Action Program statistics (if already compiled) such as the

number of CRs initiated by department, human performance errors by department, and

others as may be available.

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19. List of routine meetings involving the CAP to be held while team is onsite.

20. List of CRs related to equipment aging issues in the top ten risk-significant systems since

April 2016 (e.g., system erosion and/or corrosion problems; electronic component aging or

obsolescence of circuit boards, power supplies, relays, etc.; environmental qualification).

Please provide the following information for each AR:

a) CR number

b) Priority

c) CR problem description

21. If performed, please provide any recent self-assessment of the site safety culture

completed.

22. Copies of corrective action program documents related to cross-cutting issues (human

performance, problem identification and resolution, and safety conscious work environment)

identified via trending, self-assessments, safety review committee or other oversight

methods.

23. List of all root cause, apparent cause, common cause and related or similar equipment

cause evaluations with a brief description.

24. Copy of Probabilistic Risk Assessment importance measures report, if available.

25. System health reports, system design basis documents, maintenance rule functions and

status, and system description information for the top ten risk significant systems.

26. Complete list of Operability Determination performed includes Prompt Operability

Determination (PDO) and Immediate Determination Operability (IDO).

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