IR 05000003/1961020
| ML25329A049 | |
| Person / Time | |
|---|---|
| Site: | San Onofre, Indian Point  |
| Issue date: | 12/01/2025 |
| From: | Jeffrey Josey NRC/RGN-IV/DRSS/DIOR |
| To: | Bailly F Southern California Edison Co |
| Dennes C | |
| References | |
| IR 2025005 | |
| Download: ML25329A049 (0) | |
Text
December 01, 2025
SUBJECT:
SAN ONOFRE NUCLEAR GENERATING STATION - NRC INSPECTION REPORT 05000361/2025005; 05000362/2025005
Dear Frederic Bailly:
This letter refers to the U.S. Nuclear Regulatory Commission (NRC) inspection that was conducted from September 15-18, 2025, at your San Onofre Nuclear Generating Station near San Clemente, California. The purpose of the inspection was to conduct a routine review of your compliance with license and regulatory requirements. The inspectors discussed the preliminary inspection results with you and other members of your staff at the conclusion of the onsite inspection. The final inspection results were presented to your staff on November 24, 2025. The results of this inspection are documented in the enclosed report.
This inspection examined activities conducted under your license as they relate to public health and safety, the common defense and security, and to confirm compliance with the Commissions rules and regulations and with the conditions of your licenses. Within these areas, the inspection consisted of selected examination of procedures and representative records, observation of activities, independent measurement of radiation levels, and interviews with personnel. Specifically, the inspectors reviewed decommissioning performance; occupational radiation control; and solid radioactive waste management and transportation of radioactive materials. Within the scope of the inspection, no violations of more than minor significance were identified, and no response to this letter is required.
In accordance with 10 CFR 2.390 of the NRCs Agency Rules of Practice and Procedures, a copy of this letter, its enclosure, and your response if you choose to provide one will be made available electronically for public inspection in the NRC Public Document Room and from the NRCs ADAMS, accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. If you have any questions regarding this inspection report, please contact Eric McManus at (817) 200-1127 or the undersigned at (817) 200-1249.
Sincerely, Jeffrey E. Josey, Chief Decomm., ISFSI and Operating Reactors Branch Division of Radiological Safety and Security Docket Nos. 05000361 and 05000362 License Nos. NPF-10 and NPF-15
Enclosure:
Inspection Report Nos. 05000361/2025005 and 05000362/2025005 w/Attachment: Document request sent to licensee prior to inspection date
Inspection Report
Docket Numbers:
05000361 and 05000362
License Numbers:
Report Numbers:
05000361/2025005 and 05000362/2025005
Enterprise Identifier:
I-2025-005-0060
Licensee:
Southern California Edison Company
Facility:
San Onofre Nuclear Generating Station, Units 2 and 3
Location:
San Clemente, CA
Inspection Dates:
September 15-18, 2025
Inspectors:
R. Evans, Senior Health Physicist
C. Dennes, Health Physicist
E. McManus, Health Physicist
Approved By:
Jeffrey E. Josey, Chief
Decomm., ISFSI and Operating Reactors Branch
Division of Radiological Safety and Security
E-2
SUMMARY
This U.S. Nuclear Regulatory Commission (NRC) inspection was a routine, announced team inspection of activities being conducted at the licensees San Onofre Nuclear Generating Station (SONGS) near San Clemente, California.
List of Findings and Violations
No violations of more than minor significance were identified.
Additional Tracking Items
None.
SITE STATUS Since the previous NRC inspection in July 2025 (ADAMS Accession No. ML25253A269), the licensee continued to conduct major decommissioning activities across Units 2 and 3. Open air demolition work continued in the area around the two containment buildings including the fuel handling buildings, penetration buildings, safety buildings, and tank farms. The demolition work included structural removal, concrete segmentation, and the controlled disposition of embedded pipping and residual components in accordance with the site radiological controls program.
The material handling facility remained fully operational to support the ongoing open-air demolition work and manage waste loading and shipment activities. Radiological air monitoring and dust-suppression measures were observed to be in use during the inspection.
INSPECTION SCOPES
The inspection was conducted using the appropriate portions of the inspection procedures (IPs).
Currently approved IPs are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. 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. The inspection was declared complete when the objectives of the IP were met, consistent with Inspection Manual Chapter (IMC) 2561, Decommissioning Power Reactor Inspection Program.
IP 83801 - Inspection of Remedial and Final Surveys at Permanently Shutdown Reactors Remediation Activities and Final Status Surveys (IP Section 02.01)
The inspectors conducted site tours to observe radiological surveys in progress. The inspectors:
- (1) Observed the licensees survey of an outdoor pipe
- (2) Observed core boring and radiological sampling was conducted per work plan and survey plan requirements
- (3) Reviewed several additional survey plans
E-3 Verification and Confirmatory Surveys (IP Section 02.02)
The inspectors performed limited independent verification and confirmatory surveys, as warranted, such that the NRC could effectively assess the adequacy of the licensee's survey results. The inspectors:
- (1) Conducted qualitative surveys of two trenches for comparison of survey results to the associated action levels specified in the licensees survey plans
- (2) Conducted qualitative surveys of excavated soil created during installation of soil vapor probes per Decommissioning Work Package SDS-0-C-OC-2458, Installation of Soil Vapor Probes and Support Environmental in Performing Soil and Soil Vapor Sampling Activities, Revision 0 During the inspection, the inspectors utilized a Ludlum Model 3003i survey kit (serial number 25038476, calibration due date 02/11/2026) to perform independent alpha, beta, and gamma radiation surveys in areas where ongoing decommissioning and radiological survey activities were in progress at SONGS. The survey kit was configured with the appropriate detectors for each radiation type, and instrument response was verified prior to use in accordance with NRC inspection procedures to perform general surveys. Surveys were conducted in accessible work areas, material handling locations, and pathways used for the movement of contaminated components. The inspectors did not identify any ambient radiation levels or residual radioactivity above established background and/or expected levels. The inspectors measurements were consistent with the licensees radiological survey data and confirmed that radiological conditions were adequately controlled. All observed dose rates, contamination levels, and ambient gamma readings were within regulatory limits and aligned with the licensees postings, radiological work controls, and the requirements of 10 CFR Part 20.
Problem Identification and Resolution (IP Section 02.03)
The inspectors verified that the licensee was identifying problems related to safety reviews, design changes, and modifications at an appropriate threshold and was entering problems into its corrective action program. Specifically, the inspectors reviewed the licensees list of open condition reports in the remedial activities and final status survey program areas.
IP 83750 - Decommissioning Occupational Radiation Control Radiological Work Planning and Execution (IP Section 03.01)
The inspectors conducted work observations and tours of radiological areas to verify the licensee was identifying and assessing the magnitude and extent of radiological hazards and was adequately implementing radiological controls during planning and execution of radiological work. The inspectors:
- (1) Toured Unit 2 and Unit 3 containment buildings to observe posting and control of radiological areas, negative ventilation operation, and storage and marking of radioactive material
- (2) Toured the 10 CFR Part 37 restricted areas to verify adequate implementation of access controls
E-4
- (3) Toured radioactive material storage areas adjacent and external to the containment buildings to observe adequate packaging, marking, and control of access to material
- (4) Toured the material handling facility to observe waste loading operations and implementation of airborne radioactivity contamination control
- (5) Observed RP technician instrument use during personnel monitoring when personnel exited the material handling facility and the waste storage areas adjacent to the containment buildings
- (6) Reviewed the radiation work permit, As Low As Is Reasonably Achievable (ALARA) work plan, and survey records for the Unit 3 transfer tube segmentation work to verify effective radiological controls were used during execution of work and to verify that the work execution was in accordance with procedure SDS-RP2-PGM-2000, Radiological Work Planning and Controls, revision 17, and procedure SDS-RP1-PCD-3001, Material Release Surveys, revision 9. The additional documents reviewed included:
- AWP #25-3-903 Improvement 1, Remove U3 Transfer Tube and Prep for Shipment Outside Containment, revision 0
- Radiation Work Permit 25-3-903, Remove U3 Transfer Tube and Prep for Shipment. Work will be Performed Outside Containment. All Associated Work Groups, revision 0
- Radiological survey records: SDS-RP1-SRV-13446, revision 0; SDS-RP1-SRV-13556, revision 0; SDS-RP1-SRV-13597, revision 0; and SDS-RP1-SRV-13747, revision 0
- (7) Observed personnel and material contamination monitoring at the Unit 2 and Unit 3 control point areas
- (8) Reviewed WMG Memo 22-210-002, SONGs decommissioning (23-453D) U3 Rx Vessel Box D-2, August 29, 2025, to verify adequate disposition and control of removed reactor vessel segments IP 86750 - Decommissioning Solid Radioactive Waste Management, Demolition, and Transportation of Radioactive Materials Demolition and Disposition Radiological Impacted Structures (IP Section 3.03)
The inspectors verified that the demolition and disposal of radiological impacted structures was conducted in accordance with applicable regulations and licensee procedures. The inspectors:
- (1) Observed demolition of the fuel handling buildings to verify that open air demolition was performed in accordance with SDS procedures SDS-RP1-TSD-21-08, Surgical Demolition Plan for Radiological Open Air Demolition Readiness, revision 6; SDS-RP1-TSD-24-01, Open-Air Demolition Plan for San Onofre, revision 4; and 10 CFR Part 20 regulations
- (2) Observed demolition of the fuel handling buildings, sorting demolition debris in the turbine basin, and loading of demolition material into railcars at the material handling facility
- (3) Interviewed the ALARA manager to verify adequate implementation of SONGS DecommissioningSolutions (SDS) procedures SDS-RP1-TSD-21-08, Surgical Demolition Plan for Radiological Open Air Demolition Readiness, revision 6; and SDS-RP1-TSD-24-01, Open-Air Demolition Plan for San Onofre, revision 4
E-5
- (4) Reviewed Open Air Demo Nightly Report(s) generated from September 16-18, 2025, to validate effective monitoring and control of radiation and airborne contamination exposure resulting from onsite demolition work
INSPECTION RESULTS
No violations of more than minor significance were identified during the inspection.
EXIT MEETING AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report:
- On November 24, 2025, the inspectors conducted a final exit meeting with Mark Morgan, Southern California Edison, Regulatory Affairs Manager.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
N/A
25 ALARA Performance
09/14/2025
N/A
09/16/2025
N/A
Review
04/08/2025
ALARA Plans
SDS-RP2-
PCD-1001
ALARA Work Plan
08/13/2025
83750-
Cat3
Procedures
SDS-RP1-
PCD-1001
Radiological Surveys
06/09/2025
Radiation Work
Permits
25-3-903
Radiation Work Permit
Summary
08/13/2025
A1301-104C1
North Industrial Area Open
Land Radiological Assessment
09/16/2025
Miscellaneous
C1301-201C1
North Industrial Area Aux
Feedwater Trench
09/10/2025
C1301-201C1
North Industrial Area Aux
Feedwater Trench
09/10/2025
09/11/2025
83801
Procedures
E1601-201F1
Storm and Yard Drain Buried
Pipes - North Industrial Area
N/A
N/A
Open Air Demo Nightly Report
09/03/2025
SDS-RP1-
TSD-21-08
Surgical Demolition Plan for
Radiological Open Air
Demolition Readiness
06/25/2025
86750-
Cat3
Miscellaneous
SDS-RP1-
TSD-24-01
Open-Air Demolition Plan for
San Onofre
08/27/2025
ATTACHMENT
Document request sent to licensee prior to inspection date on August 14, 2025.
Document Request for Upcoming Inspection
at San Onofre Units 2 & 3
September 15-18, 2025
Inspection Report 2025-005
Inspection Procedures:
1.
IP 86750, Decommissioning Solid Radioactive Waste Management, Demolition and
Transportation of Radioactive Materials
2.
IP 83750, Decommissioning Occupational Radiation Control
3.
IP 83801, Inspection of Remedial and Final Surveys at Permanently Shutdown Reactors
Please have the requested information available and uploaded to SharePoint by Friday,
September 5, 2025.
Inspectors:
Robert Evans, Lead, Sr Health Physicist
Christian Dennes, Health Physicist
Eric McManus, Health Physicist
Muhammadali Abbaszadeh, Training, Sr Health Physicist
If there are any questions, please contact Christian Dennes, 817-200-1529,
Christian.Dennes@nrc.gov
1.
IP 86750, Decommissioning Solid Radioactive Waste Management, Demolition and
Transportation of Radioactive Materials
- A. Copy of the following documents, as applicable:
1.
Open Air Demo Plan
2.
Surgical Demo Plan
3.
Demolition planned for the inspection week
4.
All other site demolition plans
5.
Copy of Open-Air Demo Nightly Report conducted just before the inspection
B. List of decontamination and dismantlement activities completed since the previous
inspection conducted on May 15, 2025
C. List of planned decontamination and dismantlement activities schedule for the onsite
inspection period
2.
IP 83750, Decommissioning Occupational Radiation Control
A. Last three ALARA Committee meeting minutes
- B. List of the surveillances, maintenance, and all other decommissioning activities
scheduled for the onsite inspection period
- C. List of locations for any HRAs, LHRAs at the facility
D. A copy of the following SDS and SCE procedures:
1.
Radiation surveys
2.
Air sample collection and analysis
3.
Contamination survey (including alpha monitoring and hard-to-detect
isotopes)
4.
Surveying and releasing material from radiologically controlled areas for
unrestricted use
5.
Radiological posting, labelling, and marking
6.
Airborne monitoring and respiratory protection procedures
E. List of Radiological Work Package and ALARA Work Package generated since the
last inspection on July 7, 2025
F. List of Condition Reports and Action Requests issued in this program area since the
last inspection on July 7, 2025
3.
IP 83801, Inspection of Remedial and Final Surveys at Permanently Shutdown
Reactors
A. List of program procedures for design and implementation of final status surveys
B. List of Action Requests and Condition Reports associated with final status survey
program areas since November 2024
C. List of planned final status survey activities scheduled for the onsite inspection period
- D. Embedded Piping Estimated DCGL and Survey Action Levels, SDS-LT1-TSD-23-01