IR 05000528/2023011
| ML23349A079 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/18/2023 |
| From: | Nick Taylor NRC/RGN-IV/DORS/EB2 |
| To: | Heflin A Arizona Public Service Co |
| References | |
| IR 2023001 | |
| Download: ML23349A079 (18) | |
Text
December 18, 2023
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION - LICENSE RENEWAL INSPECTION REPORT 05000528/2023011
Dear Adam Heflin:
On November 7, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station and discussed the results of this inspection with Cary Harbor, Vice President, Nuclear Regulatory & Oversight 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, Nicholas H. Taylor, Chief Engineering Branch 2 Division of Operating Reactor Safety Docket No. 05000528 License No. NPF-41
Enclosure:
As stated
Inspection Report
Docket Number:
05000528
License Number:
Report Number:
Enterprise Identifier:
I-2023-011-0003
Licensee:
Arizona Public Service
Facility:
Palo Verde Nuclear Generating Station
Location:
Tonopah, AZ
Inspection Dates:
October 23, 2023 to October 27, 2023
Inspectors:
S. Makor, Senior Reactor Inspector, Team Lead
M. Davis, Senior Transportation and Storage Safety Inspector
N. Okonkwo, Reactor Inspector
Approved By:
Nicholas H. Taylor, Chief
Engineering Branch 2
Division of Operating Reactor Safety
Enclosure 2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a License Renewal Inspection at Palo Verde Nuclear Generating 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 The inspectors evaluated the material condition of Palo Verde Nuclear Generating Station (PVNGS) in October 2023 while the plant was shut down for Refueling Outage 1R24. This allowed the inspectors to evaluate the material condition of inaccessible areas prior to entry into the period of extended operation and to evaluate the licensees implementation of aging management activities. The period of extended operation is the additional 20 years beyond the original 40-year licensed term and begins after midnight on June 1, 2025.
In addition, the inspectors evaluated whether the licensee:
- (1) completed the necessary actions to comply with the license condition and commitments related to aging management; and
- (2) implemented programs that agreed with those approved in the safety evaluation report and described in the updated final safety analysis report. NRC issued the safety evaluation report in NUREG-1915, Safety Evaluation Report Related to the License Renewal of Palo Verde Nuclear Generating Station, Unit 1, 2, and 3 (ML11095A011). Specific activities evaluated during this inspection are described in the following paragraphs.
Post-Approval Site Inspection for License Renewal===
- (1) The inspectors evaluated the aging management programs and commitments described below and walked down selected areas of the facility while performing this phase 1 license renewal inspection.
A0 Updating USAR Chapter 19 and Commitment No. 1 The commitment to update the USAR Chapter 19 is an ongoing activity and will be incorporated in the Updated Final Safety Analysis Report for PVNGS Units 1, 2, and 3 in the next update required by 10 CFR 50.71(e) following issuance of the renewed operating licenses.
Commitment No. 1 specified:
The summary descriptions of aging management programs, time-limited aging analyses, and license renewal commitments contained in LRA Appendix A, Updated Final Safety Analysis Supplement, as required by 10 CFR 54.21(d), will be incorporated in the Updated Final Safety Analysis Report for PVNGS Units 1, 2, and 3 in the next update required by 10 CFR 50.71(e) following the issuance of the renewed operating licenses.
The inspectors interviewed the program owner and sampled revisions to procedures listed in the controlled documents list in the references and reviewed by the License Renewal Group for any effect in the license renewal application.
Based on our review of the actions completed, we conclude the program will continue to effectively manage the effects of aging through the period or extended operations and conclude that the licensee met the conditions of Commitment 1. This commitment is ongoing but considered closed for this inspection.
A1.2 Water Chemistry and Commitment No. 4 This is an existing program, consistent with the Generic Aging Lessons Learned (GALL) report. The water chemistry program manages cracking, denting, loss of material, reduction in heat transfer, and wall thinning in the primary and secondary water systems. The licensee credits an existing water chemistry program for license renewal that uses current industry standards.
Commitment No. 4 specified:
The existing water chemistry program is credited for license renewal.
The inspectors reviewed this program to ensure that the licensee would continue to manage the effects of aging during the period of extended operation. The inspectors verified that the licensee uses their current program with no additional enhancements and no exceptions. The inspectors identified no issues as a part of this review of the aging management program and considered the evaluation of this aging management program complete.
Based on the review of the actions implemented related to the water chemistry program, we concluded that the program would continue to effectively manage the effects of aging through the period of extended operation and the licensee met the conditions of Commitment 4. This commitment is considered closed.
A1.4 Boric Acid Corrosion and Commitment No. 6 This was an existing program, consistent with the GALL report. The program is credited with managing loss of material and increased resistance of connections due to borated water or reactor coolant leakage. The program includes provisions to identify leakage through inspection and examination. When leakage is identified, an inspection is performed that includes identification of the leakage path, visual inspections of adjacent structures, components and supports, and cleaning of the leakage and evaluation. Components identified with boric acid leakage are cleaned when possible and entered into the database for monitoring. Monitoring is provided by tracking and trending the existing and repaired leaks, and the establishment of a component-based visual history of leakage. The principal industry guidance document used is WCAP-15988-NP, "Generic Guidance for an Effective Boric Acid Inspection Program for Pressurized Water Reactors." The program relies, in part, on implementing recommendations in NRC Generic Letter 88-05, "Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants."
Additionally, the program includes examinations conducted during ISI pressure tests performed in accordance with ASME Section XI requirements.
Commitment No. 6 specified:
The existing boric acid corrosion program is credited for license renewal.
The inspectors reviewed the UFSAR supplemental, work documents, the Program Evaluation and tracking Report document, as well as revised Procedures 73DP-9ZC01, Boric Acid Corrosion Control Program, Revision 11, which contained procedural steps implemented, in part, to satisfy License Renewal Commitment No.
6. The inspector also reviewed procedure, 670TI-9ZC01, Boric Acid Walkdown Leak
Detection, Revision 27, which provides the instructions for walkdown of systems that contain reactor coolant or borated water inside and outside of the containment. The inspectors performed walkdowns of the boric acid corrosion program on unit 1 containment and high-pressure safety injection (HPSI) system to observe material conditions and program implementation. The inspectors reviewed corrective actions, work orders, and held discussion with boric acid corrosion program owners to go over inspection program health and trends. No issues of concern were identified.
Based on the review of the actions implemented related to the boric acid corrosion program, we concluded the program will continue to effectively manage the effects of aging through the period of extended operation and the licensee met the conditions of Commitment No. 6. This commitment is considered closed.
A1.6 - Flow Accelerated Corrosion and Commitment No. 8 The flow-accelerated corrosion (FAC) program is an existing program that manages wall thinning due to FAC and various erosion mechanisms on the internal surfaces of piping, elbows, reducers, expanders, and valve bodies containing two-phase and single-phase fluids. The program has the objective of Identifying system components susceptible to FAC, performing analysis to determine critical locations for inspection and evaluation. Those components determined not to be acceptable for continued service, based on the wear rates and minimum acceptable thickness, are repaired, or replaced. The FAC program methodology is based on EPRI guidelines in the Nuclear Safety Analysis Center (NSAC)-202L-R3 to detect, measure, monitor, predict and mitigate component wall thinning due to flow-accelerated corrosion on the internal surface of carbon and low alloy steel components.
Commitment No. 8 specified:
The existing FAC program is credited for license renewal, and prior to the period of extended operation, the program procedure will be enhanced to clarify the guidance for susceptible small-bore piping components and to verify the trace chromium content of the carbon steel pipe replacement The inspectors reviewed the UFSAR supplemental work documents, the Program Evaluation Report document, as well as revised Procedure 81DP-0RA02, Flow Accelerated Corrosion (FAC) Program Detail, Revision 20, which contained procedural steps to control FAC, in part, to satisfy License Renewal Commitment No.
8. The inspectors performed walkdowns of the containment to review the section of
the piping replaced due to the FAC program. The inspectors interviewed the program owner and reviewed procedures, work orders, licensing documents, and condition reports related to FAC assessments.
Based on the review of the actions implemented related to the FAC program, we concluded the program will continue to effectively manage the effects of aging through the period of extended operation and concluded the licensee met the conditions of Commitment No. 8. This commitment is considered closed.
A1.14 Fuel Oil Chemistry and Commitment No. 16 The fuel oil chemistry program is an existing program credited for license renewal that manages loss of material and mitigates corrosion on the internal surface of components in the emergency diesel generator (EDG) fuel oil storage and transfer system, diesel fire pump oil system, and station blackout generator (SBOG) system.
Commitment No. 16 specified:
The existing fuel oil chemistry program is credited for license renewal, and prior to the period of extended operation,
- Procedures will be enhanced to extend the scope of the program to include the SBOG fuel oil storage tank and SBOG skid fuel tanks,
- Procedures will be enhanced to include ten-year periodic draining, cleaning, and inspections on the diesel-driven fire pump day tanks, the SBOG fuel oil storage tank, and SBOG skid fuel tanks, and
- Ultrasonic testing (UT) or pulsed eddy current (PEC) thickness examination will be conducted to detect corrosion-related wall thinning if degradation is found during the visual inspections and once on the tank bottoms for the EDG fuel oil storage tanks, EDG fuel oil day tanks, diesel-driven fire pump day tanks, SBOG fuel oil storage tank, and SBOG skid fuel tanks. The one-time UT or PEC examination on the tank bottoms will be performed before the period of extended operation.
The inspectors interviewed the program owner and reviewed the UFSAR supplement, work documents, condition reports, and procedure basis document 74DP-9DF01, Diesel Fuel Oil Testing Program, Revision 15a that supports the implementation of the Chemistry Program. The inspectors reviewed and observed the performance of 31ST-9DF02, Diesel Fuel Oil Tank Condensate Removal, Revision 13a for sampling and removal of any condensate accumulated in the bottom of the diesel fuel oil storage tanks (DFOST).
Based on the review of the actions implemented related to the fuel oil chemistry program, we concluded the program will continue to effectively manage the effects of aging through the period of extended operation and the licensee will meet the conditions of Commitment No. 16 when required enhancements are completed. This commitment remains open.
A1.12 Fire Protection and Commitment No. 14 This was an existing program credited with managing loss of material for fire-rated barriers including fire rated doors, fire dampers, Halon system and the aging effects on all actuation signals, valves, nozzles, and discharges of the Halon and CO2 system. The program is also credited with managing concrete cracking, spalling, and loss of material for fire barrier walls, ceilings and floors and increased hardness, shrinkage, and loss of strength of fire barrier penetration seals. The program credits periodic visual inspections of fire barrier penetration seals, fire dampers, and structural fire barriers (walls, ceilings, and floors), drop tests of fire dampers and functional tests on fire-rated doors to ensure they can perform their intended functions. The program also includes periodic visual inspection and functional testing of the Halon and CO2 system.
Commitment No. 14 specified:
The existing fire protection program is credited for license renewal, and prior to the period of extended operation procedures will be enhanced to perform the testing of the electro-thermal links (ETLs) and functional testing of the halon and CO2 dampers every 18 months or at the frequency specified in the current licensing basis in effect upon entry into the period of extended operation.
The inspectors reviewed the UFSAR supplemental, the Program Evaluation Report document for the fire protection program, as well as revised Procedure 14DP-0FP44, Fire Protection Test Program Requirement," Revision 7, which contains enhancements and inspections credited, in part, with meeting the requirements of the fire protection aging management program, including the requirements of Commitment No. 14.
The procedure enhancements include:
- Stating trending requirements for the diesel-driven fire pump.
- Visual inspection of the fuel supply line to detect degradation.
- Inspecting for mechanical damage, corrosion, and loss of material of the Halon discharge pipe header and the CO2 system discharge nozzles.
(completed)
- Stating the qualification requirements for inspecting penetration seals, fire rated doors, fire barrier walls, ceilings, and floors
- The inspectors reviewed completed work documents and periodic test results performed to ensure fire protection program equipment continues to be able to perform intended functions.
The inspector reviewed procedures to ensure all enhancements are reflected to satisfy Commitment No. 14. No issues of concern were identified.
Based on our review of the actions implemented related to the fire protection program, we concluded the program will continue to effectively manage the effects of aging through the period of extended operation and concluded that the licensee met the conditions of Commitment No.14. This commitment is considered closed.
A1.13 Fire Water System and Commitment No. 15 The fire water system program is an existing that manages the aging of piping (including water-based piping that is normally drained), piping components, pump casings, sprinkler heads, tanks, and hydrants. The program focuses on the loss of material due to general, pitting, crevice, and galvanic corrosion, microbiological corrosion, or biofouling of carbon steel, stainless steel, cast-iron, copper, bronze, brass, galvanized, and ductile iron components in the water-based fire protection systems, including water-based piping that is normally drained. Components within the scope of water-based fire protection systems include items such as sprinklers, nozzles, fittings, valve bodies, fire pump casings, hydrants, hose stations, fire water storage tanks, fire service mains, and standpipes. Periodic fire water component inspections, tests and fire main flushing, sprinkler inspections, and flow tests are performed in accordance with National Fire Protection Association (NFPA) 25 2002 Edition to ensure that the water-based fire protection systems are capable of performing their intended function.
Commitment No. 15 specified:
The existing fire water system program is credited for license renewal, and prior to the period of extended operation, the following enhancements will be implemented:
- Specific procedures will be enhanced to include review and approval requirements under the Nuclear Administrative Technical Manual (NATM).
- Procedures will be enhanced to be consistent with the current code of record or NFPA 25 2002 Edition.
- Procedures will be enhanced to field service test a representative sample or replace sprinklers prior to 50 years in service and test thereafter every 10 years to ensure that signs of degradation are detected in a timely manner.
- Procedures will be enhanced to be consistent with NFPA 25 Section 7.3.2.1, 7.3.2.2, 7.3.2.3, and 7.3.2. 4..
The inspectors reviewed the UFSAR supplemental-program evaluation report, implementing procedures describing required tests and inspections, Work orders, as well as some corrective actions associated with some fire water component failures. The inspectors had discussions with the program owner and compared the content to the guidance in license renewal interim staff guidance LR-ISG-2012-02, noting some enhancements from the guidance. Flow tests to confirm the fire water system is functional are yet to be verified, to ensure the capability of the system to deliver water to fire suppression systems at required pressures and flow rates. The work under WO 5570252 for the non-draining section associated with 1PFPNV675**VALVEX, the pre-action valve for lower cable spreading room, has not been completed and tested. The effectiveness of the fire protection water supply is demonstrated by conducting flow testing of the fire water loops once per year.
Based on our review of the actions implemented related to the fire water system program, and the subsequent tests yet to be performed and verified from the enhancements, we concluded the fire water system program remains open and will be reinspected during a future license renewal inspection.
A1.23 Lubricating Oil Analysis and Commitment 25 The lubricating oil analysis program manages loss of material and reduction of heat transfer for components within the scope of license renewal that are exposed to lubricating and hydraulic oil. The effectiveness if the program is verified under the one-time Inspection program.
Commitment No. 25 specified:
The existing lubricating oil analysis program is credited for license renewal.
The inspectors reviewed the program basis documentation, UFSAR supplement, work orders, aging management review documents, and existing procedures. The inspectors interviewed the system owner and verified that the applicant performed adequate historic reviews of plant specific experience to determine aging effects.
The inspector reviewed 73DP-9EE05, One-Time Inspection Program, 8, that provided directions for implementing the one-time inspection program for OTIs. The inspector reviewed the work order 5080635 for the one-time inspection on the DG Diesel system, where it required that a thickness measurement of the lower portion of a representative sample of RCP lubricating oil collection tanks shall be taken and evaluated for meeting minimum wall thickness and a tank inspection is required and
should count as the total population for the material/environment group of carbon steel in lube oil.
The inspectors identified no issues during the review of this aging management program and determined, through review of documentation that the licensees current program was sufficient to manage the aging effects as described in the safety evaluation report and the updated final safety evaluation report.
Based on the review of the actions implemented related to the lubricating oil analysis program, we concluded the program will continue to effectively manage the effects of aging through the period of extended operation and the licensee met the conditions of Commitment No. 25. This commitment is ongoing and considered closed.
Inservice Inspection (ISI) Program and Commitment No. 29 (IWE Only)
The ASME Section XI, Inservice Inspection, Subsection IWE program manages loss of material and loss of sealing of the steel liner of the concrete containment building.
The licensee performs the Containment Inservice inspections in accordance with the 2001 Edition of ASME Section XI, Subsection IWE (with the 2002 and 2003 addenda), supplemented with the applicable requirements of 10 CFR 50.55a(b)(2)(ix). The licensee performs the Containment Inservice inspections using their existing inservice program to identify and manage any containment liner degradation due to loss of material that could result in loss of intended function including the containment liner plate and its integral attachments, such as piping and electrical penetrations, access hatches, the fuel transfer tube, and pressure retaining bolting. The acceptance criteria for components subject to the IWE exam requirements are specified in Article IWE-3000.
Commitment 29, specified:
The existing ASME Section XI, Subsection IWE program is credited for license renewal.
The inspectors reviewed this program to ensure that the licensee would continue to manage the effects of aging during the period of extended operation. The inspectors walkdown the Unit 1 containment and observed multiple aging mechanisms. The inspectors wanted to understand how the licensee was managing the identified aging degradation and if the licensee captured these issues within their aging management program. The inspectors verified that the licensee captured these items and gave a presentation that included summaries and pictures that the inspectors identified during the walkdown.
Based on review of the actions implemented related to the IWE Program, the inspectors determined that the licensee will have met their commitments once they implement corrective actions. The inspectors determined that reasonable assurance exists that this program will manage the effects of aging during the period of extended operation. No further review of this aging management program for Unit 1.
Based on the review of the actions implemented related to the IWE Program, the inspectors determined that the licensee is managing the aging effects of the IWE Program and have met their commitments. The inspectors noted that the licensee entered observed aging mechanisms in their corrective action program. The inspectors determined that reasonable assurance exits that this program will manage
the effects of aging during the period of extended operation.
A1.30 Appendix J and Commitment No. 32 The 10 CFR 50, Appendix J program manages loss of material, loss of leak tightness, and loss of sealing. The program assures leakage through the primary containment and systems and components penetrating the primary containment do not exceed allowable leakage rate limits specified in the Technical Specifications. The 10 CFR 50 Appendix J program does not prevent degradation due to aging effects but provides measures for monitoring to detect the degradation prior to the loss of intended function. The program consists of tests performed in accordance with the regulations and guidance provided in 10 CFR Part 50, Appendix J, Option B; NEI 94-01, Industry Guideline for Implementing Performance-Based Options of 10 CFR Part 50, Appendix J, and ANSI/ANS 56.8, Containment System Leakage Testing Requirements.
Commitment No. 32 specified:
The existing 10CFR 50, Appendix J program is credited for license renewal.
The licensee performed three types of tests at frequencies specified in 10 CFR Part 50, Appendix J, Option B. Type A integrated leak rate tests that demonstrate the leak-tightness and structural integrity of the containment. Type B and type C containment local leakage rate tests detect local leaks across each pressure containing or leakage-limiting boundary of containment penetrations.
The inspectors reviewed this program to ensure that the licensee would continue to manage the effects of aging during the period of extended operation. Additionally, the inspectors observed the performance of an appendix J program surveillance for penetration 61. The inspectors verified that the licensee uses their current program with no additional enhancements and no exceptions. The inspectors identified no issues as a part of the review of this aging management program and considered the evaluation of this aging management program complete.
Based on the review of the actions implemented related to the Appendix J program, we concluded the program will continue to effectively manage the effects of aging through the period of extended operation and the licensee met the conditions of Commitment No. 32. This commitment is ongoing and considered closed for the purposes of this inspection.
A1.36 Metal Enclosed Bus and Commitment No. 38 The metal enclosed bus (MEB) program is a new program that manages the effects of loose connections, embrittlement, cracking, melting, swelling, chipping or discoloration of insulation, loss of material of bus enclosure assemblies, hardening of boots, gaskets, and sealants, and cracking of internal bus supports to ensure that metal-enclosed buses within the scope of license renewal are capable of performing their intended function. The metal enclosed buses within the scope of this program are those used during station blackout recovery.
Commitment No. 38 Specified:
The metal enclosed bus program is a new program and will be completed before the period of extended operation and once every 10 years thereafter. Industry and plant-specific operating experience will be evaluated in the development and implementation of this program.
The inspectors reviewed the UFSAR supplemental, work documents, the program evaluation report document, as well as revised Procedure 82DP-0EE01, Electrical Aging Management Revision 7, which contained procedural steps on how to inspect metal enclosed bus sections to satisfy License Renewal Commitment No. 38. The inspectors reviewed condition reports, work orders and procedures. The inspector also performed walkdowns of the externals of the non-seg-bus ducts sections, inspected and tested under work order 5087628, to observe the material conditions of the bus duct. The inspector held discussion with the system owner to review the work performed, recorded data during the cleaning and inspection of the bus duct and the completed work within the scope of pre-PEO credited MEB inspections and tests, as described in report APSROLI~00011-REPT-004. The inspector noted that some sections of the bus duct within the scope of license renewal are yet to be inspected and tested.
Based on our review of the actions implemented for the metal enclosed bus system program and the subsequent tests yet to be performed and verified, we concluded your program remains open.
High Pressure Safety Injection (HPSI) Piping Cavitation Erosion and Commitment No. 59 The HPSI piping and cavitation erosion program is the result of a commitment change and supplemental response to RAI 4.3-6. The licensee identified some components and associated piping in each unit that was potentially susceptible to cavitation under design basis maximum flow conditions. Based on the review of internal operating experience, the licensee confirmed one location on each unit that was susceptible to cavitation erosion, the HPSI recirculation piping downstream of a throttle valve.
Initially, the licensee established a 7.5-year time-based replacement schedule but changed to a six-cycle (9 years) condition-based monitoring plan in accordance with their preventive maintenance program (including the program defined grace period) to address the condition.
Commitment No. 59 specified:
One location in each unit, the HPSI recirculating piping downstream throttle valve JSIBUV0667 on piping PSIBL112, several inches past the first 90-degree elbow, is susceptible to cavitation erosion. A 6-cycle condition-based monitoring plan will be established in accordance with the preventative maintenance program to address this condition.
The inspectors reviewed the condition-based monitoring plan to ensure that the licensee would continue to manage the effects of aging during the period of extended operation. The inspectors walkdown the susceptible area in Unit 1 and reviewed the ultrasonic test (UT) results that measures the thickness of the piping. The inspectors noted that the UT measurement for the susceptible area was taken prior to what causes the erosion to occur and wanted to assess the condition monitoring during subsequent license renewal inspections.
Based on the review of the actions implemented related to the HPSI piping cavitation erosion, the inspectors concluded that Commitment 59 is being managed through the licensees preventive maintenance program, however the NRC staff will assess the condition monitoring program for the HPSI system during subsequent license renewal
inspections. Therefore, Commitment No. 59 remains open.
Plant Condition Monitoring Walkdowns The inspectors walked down general containment areas, areas where outage activities that overlapped with license renewal commitments, and normally inaccessible areas of the facility looking at the structure, systems, and components for signs of aging, such as corrosion on piping and supports, corrosion of cable trays, water intrusion, cracking, and spalling of concrete.
Specific structures, systems, and components walked down and evaluated during this inspection included:
- Containment - ALL elevations o
Steam Generator (FAC) (S008-08-17 and S011-08-14)
- Diesel Fuel Oil Storage Tank (Inaccessible Area/Confined Space)
- Fire Protection (Damper, panel issues, fire water piping w/corrosion)
- A Spray Pond Vault cement walls (inaccessible area)
- High Pressure Safety Injection (HPSI) Cavitation
- Metal Enclosed Bus Duct
- Boric Acid Corrosion Program, Unit 1 Containment plant areas
- One Time Inspection, Secondary Chemistry, SCN-VM-53 During the walk down of the areas, the inspectors did not identify any signs of aging that affected the structures, systems, or components beyond those already described in the licensees application.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report
- On November 7, 2023, the inspectors presented the License Renewal Inspection results to Cary Harbor, Vice President, Nuclear Regulatory & Oversight and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71003
Corrective Action
Documents
CR-
20-08302, 23-07689, 23-10537, 23-07603, 23-09928, 23-
07305, 22-03758, 19-04391, 23-10986, 22-08401, 23-09638,
23-08006, 22-10117, 23-10529
71003
Corrective Action
Documents
Resulting from
Inspection
CR-
23-11131, 23-11132, 23-11133, 23-11185, 23-11186, 23-
11538
71003
Drawings
13-C-ZVA-011
Fire Protection General Arrangement
71003
Drawings
13-E-MMA-001
Main Single Line Diagram
71003
Drawings
13-E-ZAC-050
Conduit and Tray Notes, Symbols & Details
71003
Drawings
13-E-ZYP-015,
Sh.6
Non-Segregated Bus Arrangement Plan & Section
71003
Miscellaneous
13-LS-A104
PVGS Aging Management Program Evaluation Report -
Boric Acid Corrosion - B2.1.4, NUREG 1801 Program
XI.M10
71003
Miscellaneous
13-LS-A106
PVGS Aging Management Program Evaluation Report -
Flow-Accelerated Corrosion - B2.1.6, NUREG 1801 Program
XI.M17
71003
Miscellaneous
13-LS-A112
PVGS Aging Management Program Evaluation Report - Fire
Protection - B2.1.12, NUREG 1801 Program XI.M26
71003
Miscellaneous
13-LS-A124
PVGS Aging Management Program Evaluation Report -
Electrical Cables and Connections Not Subject to 10 CFR 50.49 EQ Requirements - B2.1.24, NUREG 1801 Program
XI.E1
13-LS-A136
PVGS Aging Management Program Evaluation Report -
Aging Management Program for Metal Enclosed Bus -
B2.1.36, NUREG 1801 Program XI.E4
13-MS-B089
Cavitation in the Safety Injection System
71003
Miscellaneous
16-VT-1027
1R19 IWE Exams Report
71003
Miscellaneous
10/16/2023
71003
Miscellaneous
FAC Report -23EC-548
10/15/2023
14
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71003
Miscellaneous
APSROLI-00011-
REPT-004
Metal Enclosed Bus Program [NUREG-1801 Program XI.E4
Pre-PEO Credited MEB Inspections and Tests
71003
Miscellaneous
Commitment _6
Notebook
PVGS License Renewal Commitment Notebook Boric Acid
Corrosion Program (XI.M10)
N/A
71003
Miscellaneous
Commitment _8
Notebook
PVGS License Renewal Commitment Notebook Flow-
Accelerated Corrosion Program (XI.M17)
N/A
71003
Miscellaneous
CRDR 2325095
CRDR Document the Results of NDE Testing on FP Piping
9/29/2000
71003
Miscellaneous
DCID
1ENBNA01 -
ELECON
Non-Seg Phase Bus Duct ATXFMER E-NBN-X01
01/01/1986
71003
Miscellaneous
DCID
1PSGEL008 -
PIPEXX
Feedwater Header St GENTO RCEE01A
04/13/1998
71003
Miscellaneous
ENG WO #: 23-
07305-005
Evaluate minimum wall thickness for lines APFPNL209-12in,
APDSNL046-6in AND APDFNL057-2in.
71003
Miscellaneous
FAC U1R24
N/A
71003
Miscellaneous
Fire Water AMP
presentation
Fire Water AMP 13-LS-A113 AMP Evaluation Report
10/26/2023
71003
Miscellaneous
LR ISG 2012-01
LR ISG 2012-01 Wall Thinning Due to Erosion
N/A
71003
Miscellaneous
N/A
1R24 Boric acid leaks summary
N/A
71003
Miscellaneous
RCTSAI -
247244
New UFSAR Chapter 19 for License Renewal
11/07/2008
71003
Miscellaneous
RCTSAI -
247220
RCTSAI 3247220 - Unit 2 MEB RCTSAI
11/07/2008
71003
Miscellaneous
RCTSAI 3246893
RCTSAI 3246893 - Commitment 6 - Existing Boric Acid
Corrosion program
11/06/2008
71003
Miscellaneous
RCTSAI 3246895
RCTSAI 3246895 - Commitment 8 for Flow-Accelerated
Corrosion program
11/06/2008
71003
Miscellaneous
RCTSAI 3246901
RCTSAI for RCTSAI for Fire Protection program
11/06/2028
71003
Miscellaneous
RCTSAI 3246902
246902 -RCTSAI for Fire Water System program
11/06/2008
71003
Miscellaneous
RCTSAI 3246932
RCTSAI 3246932 - Unit 1 MEB RCTSAI
11/06/2008
71003
Miscellaneous
RCTSAI 3247221
RCTSAI 3247221 - Unit 3 MEB RCTSAI
11/07/2008
71003
Miscellaneous
RCTSAI 3554175
RCTSAI for Fire Protection program
11/02/2010
71003
Miscellaneous
SWMS #23-
U1 NRC 71003 Phase 1 Assessment
10/16/2023
15
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10537-003
71003
Miscellaneous
Generic Guidance for an Effective Boric Acid Inspection
Program for Pressurized Water Reactors
71003
Procedures
13-MC-FP-0318
CFR 50 Appendix R III.G/III.L Compliance Assessment.
71003
Procedures
Fire Protection Test Program Requirement
7a
71003
Procedures
Fire Protection Test Program Requirement
71003
Procedures
Fire Hydrant, Street Key, Flush & Post Indicator Valve
Operational Testing - Unit 1
71003
Procedures
Fire Hydrant, Street Key, Flush & Post Indicator Valve
Operational Testing - Unit 1
2a
71003
Procedures
Diesel Fuel Oil Tank Condensate Removal
71003
Procedures
Inspection/Cleaning of 13.8 KV and 4.16 KV Switchgear.
71003
Procedures
Inspection/Cleaning of 13.8 KV and 4.16 KV Switchgear.
2a
71003
Procedures
Appendix A Fire Damper Surveillance Test
71003
Procedures
Boric Acid Walkdown Leak Detection
71003
Procedures
Boric Acid Walkdown Leak Detection
27a
71003
Procedures
One-Time Inspection Program
71003
Procedures
Boric Acid Corrosion Control Program
Boric Acid Corrosion Control Program.
11a
ASME Section XI Inservice Inspection
Repair/Replacement - ASME Section XI
Qualification and Certification of NDE Personnel
Containment Leakage Type B and C Testing
Containment Ventilation Purge Isolation Valves Penetration
and 79
71003
Procedures
Visual Examination of Welds, Bolting, and Components
71003
Procedures
Erosion / Corrosion Monitoring
14a
71003
Procedures
Erosion / Corrosion Monitoring.
71003
Procedures
Ultrasonic Thickness Measurement
14a
71003
Procedures
Ultrasonic Thickness Measurement
71003
Procedures
Diesel Fuel Oil Testing Program
15a
71003
Procedures
Plant Numbering.
71003
Procedures
Flow Accelerated Corrosion (FAC) Program Detail
16
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedure.
71003
Procedures
Flow Accelerated Corrosion (FAC) Program Detail
Procedure.
20a
71003
Procedures
Electrical Aging Management
07a
71003
Procedures
Electrical Aging Management
71003
Procedures
Regulatory Commitment Tracking
08a
71003
Procedures
Regulatory Commitment Tracking
71003
Work Orders
WO 5069361, 6069361, 5149326, 5458502, 5314233, 5466656,
5080635, 5087628, 5550883, 5434987, 5573124, 5459176,
5456843, 5456372, 5080575