IR 05000369/2020011
| 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 Enterprise Identifier: I-2020-011-0024 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 Enclosure
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 Type Designation Description or Title Revision or
Procedure Date
71152B Calculations MCC -1381.05- CA Terminal Voltage Calculation for CA ODBN Revision 0
00-0374
Corrective Action 02130857,
Documents 02207726,
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 Type Designation Description or Title Revision or
Procedure 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 Type Designation Description or Title Revision or
Procedure 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 Type Designation Description or Title Revision or
Procedure 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 Type Designation Description or Title Revision or
Procedure 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 Type Designation Description or Title Revision or
Procedure Date
231045,
232367,
237375,
240387,
253472,
261587,
263501,
269176,
285073,
293248,
2321628,
2321673,
2322873,
2334646,
237056,
269707
Root Cause 1B Feedwater Pump Turbine Damage During Overspeed 4/14/2019
Evaluation Report Trip Test
268471-04
Corrective Action 02345431
Documents
Resulting from
Inspection
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 Revision 9
Administration
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 Type Designation Description or Title Revision or
Procedure 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 Revision 9
CONTROL
Self-Assessments 2019-FLEET- NUCLEAR OVERSIGHT - FLEET AUDIT PLAN PACKAGE Revision 0
CAP-LSA-01 CORRECTIVE ACTION PROGRAM LIMITED SCOPE
AUDIT
MNS-SEC- Security MNS Performance Trending Report September
1497.02-2019-3 2019
Work Orders Work Orders:
20323367,
20326269,
26643701,
26643801,
26643901,
26644001,
26669901,
26670001,
26670101,
20361031
Work Request:
20156793,
20113549,
20113550,
20113551,
20113552,
20156896,
20125780
2