Text

Biennial Problem Identification and Resolution Inspection Report 05000321/2021010 and 05000366/2021010
	ML21309A011
Person / Time
Site:	Hatch
Issue date:	11/04/2021
From:	Alan Blamey; NRC/RGN-II/DRP/RPB2
To:	Gayheart C; Southern Nuclear Company
References
	EPID I-2021-010-0006 IR 2021010
	Download: ML21309A011 (15)
	v • d • e

November 4, 2021

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000321/2021010 AND 05000366/2021010

Dear Ms. Gayheart:

On October 1, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Edwin I. Hatch Nuclear Plant. On September 30, 2021, the NRC inspectors discussed the results of this inspection with Mr. Sonny Dean and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.

The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.

Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.

Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment.

Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.

No findings or violations of more than minor significance were identified during this inspection.

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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects

Docket Nos. 05000321 and 05000366 License Nos. DPR-57 and NPF-5

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000321 and 05000366

License Numbers:

DPR-57 and NPF-5

Report Numbers:

05000321/2021010 and 05000366/2021010

Enterprise Identifier: I-2021-010-0006

Licensee:

Southern Nuclear Company

Facility:

Edwin I. Hatch Nuclear Plant

Location:

Baxley, GA

Inspection Dates:

September 13, 2021 to October 01, 2021

Inspectors:

T. Beck, General Engineer NRAN

D. Hardage, Senior Resident Inspector

S. Mendez-Gonzalez, Allegations Specialist

R. Smith, Senior Resident Inspector

N. Staples, Senior Project Engineer

Approved By:

Alan J. Blamey, Chief

Reactor Projects Branch 2

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at Edwin I. Hatch Nuclear Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

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 a 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 inspections documented below met the objectives and requirements for completion of the IP.

OTHER ACTIVITIES - BASELINE

71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)

Main article: IP 71152

(1) The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment (SCWE).

Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted an in-depth Corrective Action Program (CAP) review of the 600V Switchgear, 4160VAC/250DC Switchgear, and Reactor Pressure Vessel Isolation system.

Operating Experience: The inspectors assessed the effectiveness of the stations processes for use of operating experience.

Self-Assessments and Audits: The inspectors assessed the effectiveness of the licensee's self-assessments and audits.

Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.

INSPECTION RESULTS

Assessment 71152B

1. Corrective Action Program Effectiveness

Problem Identification: The team determined that the licensee was effective in identifying problems and entering them into the corrective action program and that there was a low threshold for entering issues into the corrective action program. This conclusion was based on a review of the requirements for initiating condition reports as described in licensee procedures NMP-GM-002, "Corrective Action Program," NMP-GM-002-001, "Corrective Action Program Instructions," NMP-GM-002-002, "Effectiveness Review Instructions," and managements expectation that employees were encouraged to initiate condition reports. Additionally, site management was actively involved in the corrective action program and focused appropriate attention on significant plant issues.

Problem Prioritization and Evaluation: Based on the review of condition reports, the team concluded that problems were prioritized and evaluated in accordance with the condition report significance determination guidance in procedure NMP-GM-002. The team determined that adequate consideration was given to system or component operability and associated plant risk. The team determined that plant personnel had conducted cause evaluations in compliance with the licensees corrective action program procedures and that cause determinations were appropriate, and considered the significance of the issues being evaluated.

Corrective Actions: Based on a review of corrective action documents, interviews with licensee staff, and verification of completed corrective actions, the team determined that corrective actions were mostly timely, commensurate with the safety significance of the issues, and effective, in that conditions adverse to quality were corrected. For significant conditions adverse to quality, the corrective actions directly addressed the cause and generally prevented recurrence. The team reviewed condition reports and effectiveness reviews to verify that the significant conditions adverse to quality had not recurred. Effectiveness reviews for corrective actions to prevent recurrence were mostly sufficient to ensure corrective actions were properly implemented and were effective.

Based on the samples reviewed, the team determined that the licensees corrective action program complied with regulatory requirements and self-imposed standards. The licensees implementation of the corrective action program adequately supported nuclear safety.

2. Operating Experience

The team determined that the station's processes for the use of industry and NRC operating experience information and for the performance of audits and self-assessments were effective and complied with all regulatory requirements and licensee standards. The implementation of these programs adequately supported nuclear safety. The team concluded that operating experience was adequately evaluated for applicability and that appropriate actions were implemented to address lessons learned as needed.

3. Self-Assessments and Audits

The team determined that the licensee effectively performed self-assessments and audits to identify issues at a low level, properly evaluated those issues, and resolved them commensurate with their safety significance.

Self-assessments were generally detailed and critical. The team verified that condition reports (CRs) were created to document areas for improvement and findings resulting from self-assessments and verified that actions had been completed consistent with those recommendations. Audits of the quality assurance program appropriately assessed performance and identified areas for improvement. Generally, the licensee performed evaluations that were technically accurate.

4. Safety Conscious Work Environment

Based on interviews with plant staff and reviews of the latest safety culture survey results to assess the safety conscious work environment on site, the team found no evidence of challenges to the safety conscious work environment. Employees appeared willing to raise nuclear safety concerns through at least one of the several means available.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On September 30, 2021, the inspectors presented the biennial problem identification and resolution inspection results to Mr. Sonny Dean and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or Date

v t e Inspection Report - Hatch - 2021010
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \| 25 \|
2021 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 10(0) 11(0) Security 401(0) 402(0) Operator Exams 302(0) Emergency Planning Other

IR 05000321/2021010