IR 05000275/2024012
| ML24213A074 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/31/2024 |
| From: | Nick Taylor NRC/RGN-IV/DORS/EB2 |
| To: | Peck A Pacific Gas & Electric Co |
| Smith W | |
| References | |
| IR 2024012 | |
| Download: ML24213A074 (8) | |
Text
July 31, 2024
SUBJECT:
DIABLO CANYON POWER PLANT, UNITS 1 AND 2 - LICENSE RENEWAL REPORT 05000275/2024012 AND 05000323/2024012
Dear Adam Peck:
On June 20, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Diablo Canyon Power Plant, Units 1 and 2 and discussed the results of this inspection with Philippe Soenen, Director Strategic Initiatives, 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 Nos. 05000275, 05000323 License Nos. DPR-80, DPR-82
Enclosure:
As stated
Inspection Report
Docket Nos.
05000275 and 05000323
License Nos.
Report Nos.
05000275/2024012 and 05000323/2024012
Enterprise Identifier:
I-2024-012-0005
Licensee:
Pacific Gas and Electric Company
Facility:
Diablo Canyon Power Plant, Units 1 and 2
Location:
Avila Beach, CA
Inspection Dates:
June 17 to 20, 2024
Inspectors:
P. Cooper, Senior Reactor Inspector
G. Pick, Senior Reactor Inspector
A. Siwy, Senior Project Manager
C. Smith, Senior Reactor Inspector
Approved By:
Nicholas H. Taylor, Chief
Engineering Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a license renewal at Diablo Canyon Power Plant, Units 1 and 2, 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
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
===71002 - License Renewal Inspection On November 17, 2010, the NRC issued an inspection report for the withdrawn license renewal application (ADAMS No. ML103220205). This previous inspection was performed using Inspection Procedure 71002, and evaluated the licensees aging management programs, the structures, systems, and components in the scope of license renewal, and the application itself.
This inspection report documents the first in a series of inspections that will review the licensees recent preparations for the current license renewal application, specifically focused on evaluating the differences between the original license renewal application and the application currently under review (ADAMS No. ML23311A154).
The inspectors performed this partial inspection to evaluate whether aging management programs will be capable of managing identified aging effects in an appropriate manner. This in-office review allowed the inspectors to familiarize themselves with their assigned aging management programs and to assess the progress of the licensee implementation activities.
The inspectors reviewed the aging management program basis documents and compared them to NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Revision 2 and appendices A and B of the licensee's license renewal application. The inspectors also reviewed selected implementing documents. The inspectors verified that aging management programs reflected the planned updated final safety analysis report supplement, verified the programs included industry and site-specific operating experience, and assessed site-specific information when designing the aging management programs described in the basis documents.
The inspectors will complete the review of aging management implementation activities during planned inspections for Unit 1 in August, 2024 and for Unit 2 in February, 2025, and potentially other future inspections if the need arises. These additional inspections will review the aging management program implementation, work orders, commitment changes, and other associated implementation activities. Additionally, the inspectors will perform the onsite scoping and screening objectives of the inspection procedure, perform walkdowns, review the annual license renewal application update, and document those results in future inspections reports.
The inspectors determined that the aging management program basis document for the programs listed below accurately reflected the license renewal application appendices A and B and the generic aging lessons learned report.
The inspectors reviewed the program procedure and determined that the licensee had not yet included any commitments or references to license renewal.
License Renewal Inspection===
- (1) A.2.1.1 Fatigue Monitoring
- (2) A.2.1.2 Environmental Qualification (EQ) of Electric Components
- (3) A.2.2.1 ASME Section XI Inservice Inspection, Subsections IWB, IWC and IWD
- (4) A.2.2.2 Water Chemistry
- (5) A.2.2.3 Reactor Head Closure Stud Bolting
- (6) A.2.2.4 Boric Acid Corrosion
- (7) A.2.2.5 Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in Reactor Coolant Pressure Boundary Components
- (8) A.2.2.6 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel
- (9) A.2.2.7 PWR Vessel Internals
- (10) A.2.2.8 Flow-Accelerated Corrosion
- (11) A.2.2.9 Bolting Integrity
- (12) A.2.2.10 Steam Generators
- (13) A.2.2.11 Open Cycle Cooling Water
- (14) A.2.2.12 Closed Treated Water Systems
- (15) A.2.2.13 Inspection of Overhead Heavy Load and Light Load (Related to Refueling)
Handling Systems
- (16) A.2.2.14 Fire Protection
- (17) A.2.2.15 Fire Water Program
- (18) A.2.2.16 Aboveground Metallic Tanks
- (19) A.2.2.17 Fuel Oil Chemistry
- (20) A.2.2.18 Reactor Vessel Surveillance
- (21) A.2.2.19 One-Time Inspection
- (22) A.2.2.20 Selective Leaching
- (23) A.2.2.21 One-time Inspection of ASME Code Class 1 Small Bore-Piping
- (24) A.2.2.22 External Surfaces Monitoring of Mechanical Components
- (25) A.2.2.23 Flux Thimble Tube Inspection
- (26) A.2.2.24 Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components
- (27) A.2.2.25 Lubricating Oil Analysis
- (28) A.2.2.26 Buried and Underground Piping and Tanks
- (29) A.2.2.27 Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks
- (31) A.2.2.29 ASME Section IWL
- (32) A.2.2.30 ASME Section IWF
- (33) A.2.2.31 10 CFR Part 50, Appendix J
- (34) A.2.2.32 Masonry Walls
- (35) A.2.2.33 Structures Monitoring
- (36) A.2.2.34 RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants
- (37) A.2.2.35 Protective Coating Monitoring and Maintenance
- (38) A.2.2.36 Insulation Material for Electric Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements
- (39) A.2.2.37 Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits
- (40) A.2.2.38 Inaccessible Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements
- (41) A.2.2.39 Metal Enclosed Bus
- (42) A.2.2.40 Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements
- (43) A.2.2.41 Periodic Inspections for Selective Leaching (Plant Specific)
- (44) A.2.2.42 Transmission Conductor and Connections, Switchyard Bus and Connections, and High-Voltage Insulators (Plant Specific)
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On June 20, 2024, the inspectors presented the license renewal results to Philippe Soenen, Director Strategic Initiatives, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
9000041674
Buried Piping and Tanks Program Asset Management
Program
Corrective Action
Documents
Resulting from
Inspection
SAPN
222131-20
Drawings
438145, sheet 1
Civil Plan - Firewater System Power Block Perimeter
AWP E-016
Inspection Guide - Maintenance Rule Structural Monitoring
Programs - Civil
CY1.ID2
Closed Cooling Water Chemistry Program
MA1.ID20
Testing/Inspections for Aux Saltwater System NRC Generic Letter 89-13 Compliance
TS1.DC2
Selective Leaching Aging Management Program
TS1.ID11
Reactor Internals Aging Management Program
TS1.ID4
Saltwater Systems Aging Management Program
TS1.ID6
Reactor Pressure Vessel Embrittlement Management
Program
TS5.ID1
System Engineering Program
71002
Procedures
TS5.ID3
Buried Piping and Tanks Program
8