IR 05000413/2020011
ML20353A066 | |
Person / Time | |
---|---|
Site: | Catawba ![]() |
Issue date: | 12/18/2020 |
From: | Margaret Tobin NRC/RGN-II |
To: | Simril T Duke Energy Carolinas |
References | |
IR 2020011 | |
Download: ML20353A066 (15) | |
Text
December 18, 2020
SUBJECT:
CATAWBA NUCLEAR STATION - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000413/2020011 AND 05000414/2020011
Dear Mr. Simril:
On November 20, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Catawba Nuclear Station and 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/
Margaret C. Tobin, Acting Chief Reactor Projects Br #1 Div of Reactor Projects Docket Nos. 05000413 and 05000414 License Nos. NPF-35 and NPF-52
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000413 and 05000414 License Numbers: NPF-35 and NPF-52 Report Numbers: 05000413/2020011 and 05000414/2020011 Enterprise Identifier: I-2020-011-0023 Licensee: Duke Energy Carolinas, LLC Facility: Catawba Nuclear Station Location: York, SC Inspection Dates: November 02, 2020 to November 20, 2020 Inspectors: R. Cureton, Resident Inspector D. Mas-Penaranda, Project Engineer C. Scott, Resident Inspector, Team Lead J. Worosilo, Senior Project Engineer Approved By: Margaret C. Tobin, 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 Catawba 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 (CAP), use of operating experience, self-assessments and audits, and safety conscious work environment.
- 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 CAP review of the residual heat removal system, chemical volume and control, emergency supplemental power system, and the safety injection system.
- Operating Experience, Self-Assessments and Audits: The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits and self-assessments.
- 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 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: Self-Assessments and Audits 71152B During the inspection, the team reviewed licensee procedure AD-EG- ALL-1002, Conduct of Design Engineering. AD-EG- ALL-1002, Section 5.6 Management of Corrective Action EC Backlog, requires that a review of open engineering changes to correct conditions adverse to quality be performed between the months of June and August each year. The purpose of the review is to confirm that the age and implementation date for the engineering change (EC) is timely and acceptable for addressing the adverse condition at the plant. This review is required to be documented in a self-assessment report and presented to the plant health committee. When the team requested copies of the self-assessments, the licensee discovered that the 2020 self-assessment had not been performed as required by procedure. Catawba entered this issue in the CAP as CR 2358656 and initiated actions to perform a self-assessment of the EC backlog in 2020. The licensee performed a cursory review of the open ECs and verified that the ECs for risk significant equipment were tracked by either a condition adverse to quality (CAQ) work order in the work management system or a CAPR in the CAP program. The team concluded that even though the self-assessment was not performed, the licensee demonstrated that the schedule dates for the open ECs were appropriate for addressing the conditions adverse to quality.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 20, 2020, the inspectors presented the biennial problem identification and resolution inspection results to Tom Simril and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Corrective Action NCRs 1897267
Documents 2161152
205072
23943
24847
26880
29344
29571
230620
233672
235304
236600
239553
244942
245845
246958
247876
249561
256331
256868
257769
264322
265962
270638
271394
275149
278168
279736
280631
280660
288734
288755
Inspection Type Designation Description or Title Revision or
Procedure Date
290100
290319
290522
293014
293228
293620
293759
294307
294574
294614
295296
297177
299143
299984
2300383
2300922
2302424
2302472
2303441
2305450
2308405
2314730
2319066
2319620
20233
29426
2331304
2331792
2337921
2338939
2340429
2348493
2349025
2349344
Inspection Type Designation Description or Title Revision or
Procedure Date
2349784
2351604
27287
275467
24404
2330654
292867
283390
2311992
279376
290855
288606
280118
2309023
252082
2316312
2308530
291848
259146
292063
282910
2319975
2310713
242969
297129
290339
29632
243702
241973
299936
2311354
2334670
2335989
2348355
Inspection Type Designation Description or Title Revision or
Procedure Date
2319532
290528
295170
1496462
2061998
2315936
287546
270638
290522
21754
21302
22033
22346
22499
22579
212222
260624
257482
2303601
2303697
2303851
26580
216962
247837
2338327
296571
247832
284178
2351299
2355996
2350661
214326
277988
2184291
Inspection Type Designation Description or Title Revision or
Procedure Date
22339
29433
292605
29335
278487
292371
292736
244992
249421
26633
2346486
2352344
2342017
2314994
2341330
27594
22339
1945732
29433
237293
2184291
2342917
2315936
275149
2192509
22346
247779
2331304
2346908
295850
247749
231525
250289
28507
Inspection Type Designation Description or Title Revision or
Procedure Date
26532
230608
247603
296571
2335856
Corrective Action NCRs 2358656
Documents
Resulting from
Inspection
Procedures AD-PI-ALL-0400 Operating Experience Program Revision 8
AD-EG-ALL-1202 Preventive Maintenance and Surveillance Testing Revision 9
Administration
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 Revision 3
AD-PI-ALL-0100 Corrective Action Program Revision 24
AD-PI-ALL-0106 Cause Investigation Checklists Rev.4
AD-PI-ALL-0300 Self-Assessment and Benchmark Programs Revision 4
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
IP/0/B/4974/059 Main Generator and Exciter PM Inspection 02,03
MP/0/A/7150/097 Standby Makeup Pump Suction Pulsation Damper 19,20,21
Preventative Maintenance Inspection
TE-MN-ALL-0202 Transformer and Apparatus Testing
Work Orders 20297426
297432
297528
298165
299678
20313089
20313638
Inspection Type Designation Description or Title Revision or
Procedure Date
20325390
20345446
20356110
20162010
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