IR 05000413/2022011
| ML22343A232 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/15/2022 |
| From: | Eric Stamm NRC/RGN-II/DRP/RPB1 |
| To: | Simril T Duke Energy Carolinas |
| References | |
| IR 2022011 | |
| Download: ML22343A232 (12) | |
Text
SUBJECT:
CATAWBA NUCLEAR STATION - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000413/2022011 AND 05000414/2022011
Dear Tom Simril:
On November 17, 2022, 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 problem identification and resolution 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 problem identification and resolution 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.
December 15, 2022 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, Eric J. Stamm, Chief Reactor Projects Branch 1 Division 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:
Report Numbers:
05000413/2022011 and 05000414/2022011
Enterprise Identifier:
I-2022-011-0028
Licensee:
Duke Energy Carolinas, LLC
Facility:
Catawba Nuclear Station
Location:
York, South Carolina
Inspection Dates:
October 31, 2022, to November 17, 2022
Inspectors:
M. Checkle, Senior Allegations Coordinator
D. Jackson, Senior Project Engineer
N. Lacy, Operations Engineer
D. Rivard, Resident Inspector
E. Robinson, Project Engineer
Approved By:
Eric J. Stamm, Chief
Reactor Projects Branch 1
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 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
Type Issue Number Title Report Section Status LER 05000414/2022-001-00 LER 2022-001-00 for Catawba Nuclear Station,
Unit 2, Manual Reactor Trip and Auxiliary Feedwater Start due to Misaligned Control Rods 71153 Closed
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 03.04)
- (1) The inspectors performed a biennial assessment of the effectiveness of the licensees Problem Identification and Resolution program, use of operating experience, self-assessments and audits, and safety conscious work environment.
Problem Identification and Resolution Effectiveness: The inspectors assessed the effectiveness of the licensees Problem Identification and Resolution (PI&R) program in identifying, prioritizing, evaluating, and correcting problems.
The inspectors conducted an in-depth corrective action program review of the following systems/components or portions thereof: auxiliary feedwater, emergency diesel generators, nuclear service water, standby shutdown facility. The inspectors also conducted a five-year review of equipment aging issues.
Operating Experience: The inspectors assessed the effectiveness of the licensees processes for use of operating experience.
Self-Assessments and Audits: The inspectors assessed the effectiveness of the licensees identification and correction of problems identified through 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.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event report (LER):
- (1) LER 05000414/2022-001-00, Catawba Nuclear Station, Unit 2, Manual Reactor Trip and Auxiliary Feedwater Start due to Misaligned Control Rods (ADAMS Accession No. ML22173A172). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.
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 (which includes the work management system), 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. 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, work orders, and work requests, the inspectors concluded that problems were prioritized and evaluated in accordance with licensee guidance. The inspectors determined that adequate consideration was given to system or component operability and associated plant risk. The inspectors determined that, in general, 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, generally, corrective actions were timely, commensurate with the safety significance of the issues, and effective, in that conditions adverse to quality were corrected. The team determined that the licensee was generally effective in developing corrective actions that were appropriately focused.
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 stations processes for the use of industry and NRC operating experience information were effective and complied with 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 in accordance with applicable procedures.
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. The self-assessments and audits were adequately self-critical and performance-related issues were being appropriately identified. The inspectors verified that action requests were created to document areas for improvement and findings, and verified that actions generally had been completed consistent with those recommendations.
However, the inspectors noted that during the licensees 2020 PI&R readiness self-assessment, the licensee identified that both the work order backlog biennial assessment, and the annual work order and work request backlog review, had not been completed for 2019 and 2020, respectively, as required by AD-WC-ALL-0200, On-line Work Management. Along with other corrective actions, the licensee completed the assessment in November 2020. During the 2022 PI&R readiness self-assessment, the licensee identified that the 2022 work order backlog biennial assessment had not been scheduled for 2022 (although it was required to be scheduled by December 31, 2021, and was due November 2022). Additionally, the licensee identified that the annual work order and work request backlog review had not been performed for 2021. This led the licensee to deem the corrective actions from the 2020 PI&R readiness self-assessment, ineffective. The licensee initiated additional corrective actions to further address the concerns (nuclear condition report 2431519).
4) Safety-Conscious Work Environment Employees interviewed appeared willing to raise nuclear safety concerns through at least one of the several means available. Based on interviews with plant staff and reviews of the latest safety culture survey results, the team found no evidence of challenges to a safety conscious work environment.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On November 17, 2022, the inspectors presented the biennial problem identification and resolution inspection results to Tom Simril and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2143837
2176144
2181760
266064
2300974
2302626
2302634
2302706
2302707
2303887
2305356
2342017
2344352
2347098
2347364
2350950
2351187
2351615
2354956
2356199
2356298
2356772
2356974
2357189
2358529
2359785
2359991
2359993
2362709
2363667
2363831
2364311
2364647
2367070
2367367
2367381
2367457
2367459
2367784
2368553
2371723
2373019
2373374
2375740
2375813
2375996
2376022
2379984
2383078
2383228
2385280
2388798
2389432
2390261
2393718
2393733
2396503
2397351
2397949
2398462
2398745
2398921
2399490
2401326
2401560
2401927
2402459
2402479
2402590
2402710
2405297
2406502
2407902
2408205
2409314
2409746
2410295
2412065
2414079
2414669
2415834
2415837
2415847
2416012
2416660
2418051
2418833
2419020
2419447
2419894
2419921
20233
21239
21877
22817
23905
23924
24201
24572
25057
25058
25552
25952
26694
26696
26981
27097
27164
27166
27202
27313
27521
27709
28747
28876
29628
29958
2430385
2430551
2431369
2431604
2431876
2432589
2433334
2434704
2435040
2436428
2437364
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2438983
2439872
2440019
2441971
2442864
2446617
2446695
2446709
2449795
AD-EG-PWR-1611
Boric Acid Corrosion Control Program - Implementation
AD-MN-ALL-0005
Nuclear Planning
AD-MN-ALL-0006
Fluid Leak Management
AD-PI-ALL-0100
Corrective Action Program
AD-PI-ALL-0106
Cause Investigation Checklists
AD-PI-ALL-0300
Self Assessment and Benchmark Programs
AD-PI-ALL-0400
Operating Experience Program
AD-RP-All-5004
Vendor Cask Manuals
AD-SY-ALL-0150
Reporting Safeguards, Security, and Fitness for Duty Events
AD-WC-ALL-0200
On-line Work Management
AD-WC-ALL-0210
Work Request Initiation, Screening, Prioritization, and
Classification
PD-EG-PWR-1611
Boric Acid Corrosion Control Program
Procedures
PY-NO-ALL-0200
Safety Conscious Work Environment
Work Orders
20185290
20185319
200107
205433
207878
209822
217938
218885
218957
221948
224290
224292
224775
224800
227008
232203
235665
235730
235752
235764
20433802
20437028
20454103
20454285
20454439
20455267
20458094
20462695
20468790
20469906
20475234
20475243
20475246
20484562
20499660
20503389
20503499
20519244
20526623
20531056
20534464
20559079
20431816
20434005
20454439
20459965
20485842
20495382
20499660
20503389
20531056
20534464
Corrective Action
Documents
Resulting from
Inspection
2449795
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
24761