IR 05000413/2023010
| ML23283A037 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/11/2023 |
| From: | Binoy Desai Division of Reactor Safety II |
| To: | Flippin N Duke Energy Carolinas |
| References | |
| IR 2023010 | |
| Download: ML23283A037 (1) | |
Text
SUBJECT:
CATAWBA NUCLEAR STATION - NRC INSPECTION REPORT 05000413/2023010 AND 05000414/2023010
Dear Nicole Flippin:
On August 24, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at 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.
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, Binoy B. Desai, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 05000413, 05000414 License Nos. NPF-35, NPF-52
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000413 and 05000414
License Numbers:
Report Numbers:
05000413/2023010 and 05000414/2023010
Enterprise Identifier:
I-2023-010-0040
Licensee:
Duke Energy Carolinas, LLC
Facility:
Catawba Nuclear Station
Location:
York, South Carolina
Inspection Dates:
August 07, 2023, to August 24, 2023
Inspectors:
P. Cooper, Senior Reactor Inspector
J. Copeland, Reactor Inspector
S. Downey, Sr. Reactor Operations Engineer
M. Hagen, Reactor Inspector
A. Hutto, Senior Project Engineer
M. Schwieg, Senior Reactor Inspector
Approved By:
Binoy B. Desai, Chief
Engineering Branch 3
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a NRC 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) 2516, Policy and Guidance for the License Renewal Inspection Program. 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
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
71003 - Post-Approval Site Inspection for License Renewal Post-Approval Site Inspection for License Renewal
71003 - Post-Approval Site Inspection for License Renewal From August 7, 2023, to August 24, 2023, the NRC continued monitoring Duke Energy's performance at Catawba by conducting a Post-Approval Site Inspection for License Renewal - Phase II in accordance with the license renewal inspection program (LRIP).
This inspection took place prior to the period of extended operation (PEO) for Units 1 and 2, which will begin on December 6, 2024, and February 24, 2026, respectively. Per Inspection Manual Chapter 2516, the LRIP is the process used by NRC staff to verify the adequacy of aging management programs (AMPs), Time Limited Aging Analyses (TLAAs), and other activities associated with an applicants request to renew an operating license of a commercial nuclear power plant beyond the initial licensing period under 10 CFR Part 54, Requirements for the Renewal of Operating Licenses for Nuclear Power Plants.
Post-Approval Site Inspection for License Renewal
- (1) Implementation of License Conditions and Commitments, including Aging Management Programs A total of 27 license renewal action items were reviewed linked to the renewed operating license for Catawba Nuclear Plant Units 1 and 2, issued on December 15, 2003, which include the following: 22 commitments to enhance existing or new AMPs and 5 TLAAs. The inspectors reviewed a majority (greater than 70%) of regulatory commitments and associated AMPs and TLAAs in order to assess the adequacy and effectiveness of the license renewal program. For each item selected in the sample, the inspectors reviewed the applicable license renewal program documents and conducted interviews with licensee staff to verify that the licensee completed the actions necessary to comply with the conditions listed in the renewed facility operating license.
For those license renewal action items that were not completed at the time of this inspection, the inspectors verified, where possible, that there was reasonable assurance that such action items were on track for completion prior to the PEO or in accordance with an established implementation schedule consistent with the license renewal application (LRA), the NRC safety evaluation report (SER), and the Updated Final Safety Analysis Report (UFSAR) supplement. Commitment Items with pending actions requiring further inspection by the NRC are described in the Inspection Results section of this report. The regulatory commitments selected for the inspection sample are listed below along with the completion status of the item at the time of the inspection. The full description of each commitment is available in the UFSAR supplement for license renewal, as revised, and Appendix A of the NRC SER issued as NUREG-1772 dated March 2003.
- Commitment 2: Complete the Borated Water Systems Stainless Steel Inspection.
Status: Complete
- Commitment 4: Implement enhancements to the Fire Protection Program to provide surveillances for sprinkler branch lines, main fire pump strainer, jockey pump, strainer, tank and connected piping, and turbine building manual hose stations. Status: Complete
- Commitment 5: Complete the Galvanic Susceptibility Inspection. Status:
Complete
- Commitment 6: Implement the Inaccessible Non-EQ Medium Voltage Cables Aging Management Program. Status: Complete
- Commitment 7: Implement enhancements to the In-service Inspection Plan to provide surveillances for small bore piping. Status: Complete
- Commitment 8: Implement enhancements to the Inspection Program for Civil Engineering Structures and Components to provide surveillances for exposed external surfaces of mechanical components. Status: Incomplete. At the time of the inspection, the Inspection Program for Civil Engineering Structures and Components had not established a baseline inspection for all accessible structures and components. Additionally, administrative controls were not in place to demonstrate the remaining activities would be completed. To ensure the timely and technically acceptable completion of the remaining activities, Commitment 8 will remain open, and is subject to further NRC inspection.
- Commitment 9: Complete the Liquid Waste System Inspection. Status:
Complete
- Commitment 11: Implement the Non-EQ Insulated Cables and Connections Aging Management. Status: Complete
- Commitment 12: If necessary, following the results of the McGuire Unit 1 examination, complete the Pressurizer Spray Head Examination. Status: This commitment was deleted as part of the licensees transition to a performance-based fire protection program under National Fire Protection Association Standard 805. The change in licensing bases associated with this transition removed the component level intended function of the pressurizer spray head, which eliminated the need for the Pressurizer Spray Head Examination Program. The inspectors verified that the licensee properly evaluated the commitment change in accordance with 10 CFR 50.59, as required by License Condition 2.C.(3). The inspectors also verified that the FSAR was updated accordingly, as required by 10 CFR 50.71(e).
- Commitment 13: Complete the Condenser Circulating Water Pump Expansion Joint Inspection. Status: Complete
- Commitment 14: Implement the Reactor Vessel Internals Inspection. Status:
Complete
- Commitment 15: Complete the Selective Leaching Inspection. Status:
Incomplete. The licensee, in accordance with 10 CFR 54.37(b), identified the Turbine Building Strainer Basket as a newly identified SSC requiring inspection for the presence of selective leaching. At the time of the inspection, the strainer baskets had not been inspected and the administrative controls were not in place to ensure completion of this activity. To ensure the timely and technically acceptable completion of the remaining activities Commitment 15 will remain open and is subject to further NRC inspection.
- Commitment 16: Complete the Sump Pump Systems Inspection. Status:
Complete
- Commitment 18 Complete the Ventilation Area Pressure Boundary Sealants Inspection. Status: Complete
- Commitment 19: Complete the Waste Gas System. Status: Incomplete. The inspectors identified a volumetric examination point on the Waste Gas System that was below minimum requirements. At the time of the inspection, there was no engineering evaluation to determine the impacts of aging effects and administrative controls were not in place to ensure completion of this activity. To ensure the timely and technically acceptable completion of the remaining activities Commitment 19 will remain open and is subject to further NRC inspection.
1) Time Limited Aging Analyses (TLAA):
Since the renewed license was issued, the licensee has performed an assessment to identify any structures, systems, and components (SSCs) that would have been subject to an evaluation as a time-limited aging analysis in accordance with 10 CFR 54.21. The inspectors reviewed the following TLAAs:
- Environmental Qualification TLAA. Status: Complete.
- Leak-Before-Break TLAA. Status: Complete.
- Reactor Coolant Pump Flywheel TLAA. Status: Complete.
- Reactor Vessel Neutron Embrittlement TLAA. Status: Complete.
- Standby Nuclear Service Water Pond Volume Program. Status: Complete.
3) Newly Identified Structures, Systems, and Components (SSCs):
For each newly identified SSC, the inspectors determined that the licensee took appropriate actions in accordance with 10 CFR 54.37(b). Specifically, the inspectors verified that the SSCs have been included in the FSAR update required by 10 CFR 50.71(e), and that the FSAR update described how the effects of aging are managed such that the intended function(s) in 10 CFR 54.4(b) will be effectively maintained during the period of extended operation. The inspectors also reviewed a list of plant modifications performed from the time the LRA was submitted to the time the renewed operating license was issued, to identify any potentially new SSCs that would have been subject to aging management review at the time the NRC was reviewing the LRA. Based on this review, the inspectors did not identify any new SSCs that were subject to the provisions of 10 CFR 54.37(b).
- Auxiliary Building floor drain sump pumps
- Turbine Building fire protection strainers 4) Changes to license renewal commitments and the UFSAR supplement for license renewal As part of the review of license renewal commitments, AMPs, and TLAAs described in this report, the inspectors reviewed a sample of license renewal commitment change documents to verify the licensee followed the guidance in NEI 99-04, Guidelines for Managing NRC Commitment Changes, for any change to the commitments, including their elimination.
Except as identified in the Inspection Results section of the report, the inspectors verified that the licensee properly evaluated, reported, and approved where necessary, changes to license renewal commitments listed in the UFSAR in accordance with 10 CFR 50.59, as required by the Renewed Operating License (Section 2.C.(31))
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 24, 2023, the inspectors presented the NRC inspection results to Nicole Flippin and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2A RC pump expansion joint
06/28/2023
Corrective Action
Documents
Door gap/clearance criteria
04/18/2003
Potential ABVES Missed Surveillance
08/07/2023
Unsealed Penetrations in 1B NV and 1B NI Pump Rooms
08/22/2023
23 NRC License Renewal -Concerns regarding UT data
supporting Waste Gas System
8/10/2023
Corrective Action
Documents
Resulting from
Inspection
23 NRC License Renewal - Procedure Non-Compliance
for Missing Information
8/10/2023
Drawings
CN-2609-07.00
Flow Diagram of Diesel Generator Room Sump Pump
System (WN)
B.18 Commitment
PP-19 - Condenser Circulating Water Pump Expansion Joint
Inspection
6/07/2023
B.19 Commitment
PP-15 - Sump Pump Systems Inspection
7/18/2023
B.20 Commitment
PP 18 - Vent Area Pressure Boundary Sealants Inspection
6/20/2023
B.21 Commitment
PP 61 - Thermal Fatigue Management
07/10/2023
B.7 Commitment
PP-2 Borated Water Systems Stainless Steel Inspection
06/01/2023
B.8 Commitment
PP-14 Liquid Waste System Inspection
07/17/2023
Miscellaneous
B.9 Commitment
PP-17 Waste Gas System Inspection
07/03/2023
AD-EG-ALL-1615
Cable Aging Management Program - Implementation
Revision 5
AD-EG-ALL-1911
Reactor Internals Program Implementation
Revision 5
NDE-NE-ALL-
6401
Ultrasonic Thickness Measurement
PT/1/A/4700/020
WL/WN Sump Pumps and Check Valves Inservice Test
Procedures
PT/1/A/4700/020
WL/WN Sump Pumps and Check Valves Inservice Test
251997
2RC MJ 0007: TECH SUPPORT INSPECT 2A RC
EXPANSION JOINT MONTHLY
07/13/2023
257253 05
1WG TK-08, Inspection of the bottom of waste gas decay
11/3/2021
257253 05
1WG VA-18 UT Inspection
4/5/2020
20564436 01
1&2 RC PP SYS: PUMP EXPANSION JOINT INSPECTION
(EXTERNAL)
10/18/2022
71003
Work Orders
20618422 01
PT/0/A/4450/04A VA 1A PERFORMANCE TEST
08/08/2023
7