IR 05000369/2020011

Biennial Problem Identification and Resolution Inspection Report 05000369/2020011 and 05000370/2020011

ML20262H120
Person / Time
Site:	McGuire, Mcguire
Issue date:	09/18/2020
From:	Jared Nadel NRC/RGN-II
To:	Teresa Ray Duke Energy Carolinas
References
IR 2020011
Download: ML20262H120 (15)

Text

September 18, 2020

SUBJECT:

MCGUIRE NUCLEAR STATION - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000369/2020011 AND 05000370/2020011

Dear Mr. Ray:

On August 27, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your McGuire Nuclear Station. On August 28, 2020 the NRC inspectors discussed the results of this inspection with you 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/

Jared H. Nadel, Acting Chief Reactor Projects Br #1 Div of Reactor Projects

Docket Nos. 05000369 and 05000370 License Nos. NPF-17 and NPF-9

Enclosure:

IR 05000369/2020011 and 05000370/2020011

Inspection Report

Docket Numbers:

05000369 and 05000370

License Numbers:

NPF-9 and NPF-17

Report Numbers:

05000369/2020011 and 05000370/2020011

Licensee:

Duke Energy Carolinas, LLC

Facility:

McGuire Nuclear Station

Location:

Huntersville, North Carolina

Inspection Dates:

August 10, 2020 to August 28, 2020

Inspectors:

R. Cureton, Resident Inspector

B. Griman, Resident Inspector

D. Mas-Penaranda, Project Engineer, team lead

A. Wilson, Project Engineer

Approved By:

Jared H. Nadel, Acting Chief

Reactor Projects Br #1

Div 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 McGuire Nuclear Station, 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.

OTHER ACTIVITIES - BASELINE

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

(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.

• Corrective Action Program (CAP) Effectiveness: The inspectors assessed the licensee's CAP effectiveness in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted an in-depth CAP review of the emergency diesel generators, Nuclear Service Water and Auxiliary Feedwater system.

• Operating Experience: The inspectors assessed the effectiveness of the licensees processes for the 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 (SCWE): The inspectors assessed the effectiveness of the licensees programs to establish and maintain a safety conscious work environment.

INSPECTION RESULTS

Assessment 71152B

1. Corrective Action Program Effectiveness

Problem Identification: The inspectors determined that the licensee was effective in identifying problems and entering them into the corrective action program and 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 procedure AD-PI-ALL-0100, "Corrective Action Program,"

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 inspectors concluded that problems were prioritized and evaluated in accordance with the condition report significance determination guidance in procedure AD-PI-ALL-0100. The inspectors determined that adequate consideration was given to system or component operability and associated plant risk. The inspectors determined that plant personnel had conducted cause evaluations in compliance with the licensees corrective action program procedures and 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 inspectors determined that corrective actions were 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 effectively prevented recurrence. The inspectors reviewed condition reports and effectiveness reviews to verify that the significant conditions adverse to quality had not recurred. Effectiveness reviews for corrective actions to preclude repetition (CAPRs) were 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 inspectors 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 inspectors 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 inspectors determined that the licensee was effective at performing 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 inspectors 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 inspectors 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.

Observation: Corrective Action Program Effectiveness 71152B Centralized Screening Team (CST) Meeting

In accordance with the corrective action procedure, AD-PI-ALL-0100, "Corrective Action Program," Revision 23, the CST meeting is a cross-functional team that determines screening decisions for undesired conditions, including but not limited to Conditions Adverse to Quality (CAQ), classifications, cause evaluation types, action plans, and Industry Reporting and Information System (IRIS) experience posting decisions. Screening recommendations made by the CST are reviewed and approved by the corrective action review meeting.

While observing the biweekly CST meeting, on August 18, 2020, the team noted that quorum was not met due to there being no Operations or Maintenance representation. The meeting was carried out without all quorum participants present. The team noted that although there is a requirement for quorum on the CST meeting, in reality it is not enforced. AD-PI-ALL-0100 Section 5.5, highlights the members that are required to meet the quorum requirements at a CST meeting, which includes representation from Nuclear Support Services, Operations, Engineering and Maintenance. When the team inquired about what actions are taken when the quorum is not met, the licensee responded that no actions are required when quorum is not met, and they can continue with the meeting as is. Also, the licensee pointed out that, under Section 5.5.1(a) of AD-PI-ALL-0100, NCRs can be screened outside of the bi-weekly meeting if no cross-functional input is needed.

The team observed that the main purpose of this meeting is to gather a cross-functional team that determines screening decisions for undesired conditions. The purpose of the meeting is defeated by allowing individuals to perform screenings outside the meeting and by not enforcing the quorum requirements for the meeting. The licensee entered the observation into their corrective action program under Action Request

EXIT MEETINGS AND DEBRIEFS

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

• On August 28, 2020, the inspectors presented the biennial problem identification and resolution inspection results to Tom Ray and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Calculations

MCC -1381.05-

00-0374

CA Terminal Voltage Calculation for CA ODBN

Revision 0

Corrective Action

Documents

2130857,

207726,

218867,

228009,

236093,

264517,

294641,

2316204,

2336066,

2197977,

210772,

215743,

218213,

224159,

224300,

226546,

230343,

230862,

232988,

233181,

233686,

233772,

233857,

235526,

250253,

252058,

252273,

267532,

267849,

269771,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

271563,

272261,

274520,

276550,

2317889,

2319018,

2322379,

219858,

212556,

213275,

243803,

2318612,

2198325,

225779,

228278,

272566,

275884,

275731,

279528,

287066,

205631,

214233,

214234,

231437,

268919,

2323090,

219858,

212556,

213275,

243803,

2300664,

2303853,

2308644,

206941,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

237110,

2316299,

223373,

299081,

2335556,

219832,

258327,

291420,

2305855,

2176763,

264663,

01901941,

2306768,

245518,

210227,

234012,

235724,

245518,

283611,

2185267,

217854,

216062,

01901517,

2051245,

211048,

217854,

225402,

232463,

284692,

285755,

298259,

2198421,

230362,

267114,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

271862,

276056,

282589,

284574,

284692,

289219,

2301104,

2324644,

2322671,

232555,

2327355,

2325160,

236093,

226857,

236093,

241291,

2325744,

2331283,

2331340,

2305412,

2189388,

228073,

2313755,

279737,

297177,

248993,

203713,

208074,

209067,

209493,

213515,

235850,

253446,

260247,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

277240,

2314416,

2315942,

2321770,

2321961,

2324680,

2326181,

2329879,

2330989,

208993,

208963,

294081,

2331189,

212333,

2336066,

201540,

206986,

211035,

242479,

268652,

270056,

286582,

292779,

299217,

2306284,

2321569,

2328812,

2333415,

211035,

2328812,

200750,

214716,

226111,

227856,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

231045,

232367,

237375,

240387,

253472,

261587,

263501,

269176,

285073,

293248,

2321628,

2321673,

2322873,

2334646,

237056,

269707

Root Cause

Evaluation Report

268471-04

1B Feedwater Pump Turbine Damage During Overspeed

Trip Test

4/14/2019

Corrective Action

Documents

Resulting from

Inspection

2345431

Miscellaneous

McGuire Nuclear Safety Culture Assessment

June 2018

Procedures

AD-PI-ALL-0106

Cause Investigation Checklists

Revision 4

AD-PI-ALL-0300

Self-Assessment and Benchmark Programs

Revision 4

AD-PI-ALL-0400

Operating Experience Program

Revision 8

AD-EG-ALL-1202

Preventive Maintenance and Surveillance Testing

Administration

Revision 9

AD-EG-ALL-1207

Plant Health Process

Revision 9

AD-EG-ALL-1209

System Health and Notebooks

Revision 8

AD-EG-ALL-1210

Maintenance Rule Program

Revision 2

AD-NO-ALL-0202

Employee Concerns Program

Revision 3

AD-OP-ALL-0105

Operability Determinations [and Functionality Assessments]

Revision 6

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AD-PI-ALL-0100

Corrective Action Program

Revision 23

AD-PI-ALL-0401

Significant Operating Experience Program

Revision 8

AD-PI-ALL-101

Root Cause Evaluation

Revision 7

AD-QC-ALL-1000

CONDUCT OF NUCLEAR OVERSIGHT QUALITY

CONTROL

Revision 9

Self-Assessments 2019-FLEET-

CAP-LSA-01

NUCLEAR OVERSIGHT - FLEET AUDIT PLAN PACKAGE

CORRECTIVE ACTION PROGRAM LIMITED SCOPE

AUDIT

Revision 0

MNS-SEC- 1497.02-2019-3

Security MNS Performance Trending Report

September

2019

Work Orders

Work Orders:

20323367,

20326269,

26643701,

26643801,

26643901,

26644001,

26669901,

26670001,

26670101,

20361031

Work Request:

20156793,

20113549,

20113550,

20113551,

20113552,

20156896,

20125780