IR 05000361/2025003

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NRC Inspection Report 05000361/2025003; 05000362/2025003
ML25163A217
Person / Time
Site: San Onofre  
Issue date: 06/26/2025
From: Jeffrey Josey
NRC/RGN-IV/DRSS/DIOR
To: Bailly F
Southern California Edison Co
References
IR 2025003
Download: ML25163A217 (1)


Text

June 26, 2025

SUBJECT:

SAN ONOFRE NUCLEAR GENERATING STATION - NRC INSPECTION REPORT 050-00361/2025-003; 050-00362/2025-003

Dear Frederic Bailly:

This letter refers to the U.S. Nuclear Regulatory Commission (NRC) inspection conducted onsite from May 12-15, 2025, for San Onofre Nuclear Generating Station, Units 2 and 3. The inspectors discussed the inspection results with you and members of your staff at the end of the onsite inspection on May 15, 2025. The inspection results are documented in the enclosures to this letter.

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; radioactive waste treatment, and effluent and environmental monitoring; and solid radioactive waste management and transportation of radioactive materials. Within the scope of the inspection, no violations 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 Procedure, 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 or from the NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRCs Website at https://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy or proprietary information so that it can be made available to the public without redaction. 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 Decommissioning, ISFSI, Operating Reactor Branch Division of Radiological Safety and Security Docket Nos. 5000361; 5000362 License Nos. NPF-10; NPF-15 Enclosure:

Inspection Report 050-00361/2025-003; 050-00362/2025-003 w/Attachment: Supplemental Inspection Information Distribution via ListServ Signed by Josey, Jeffrey on 06/26/25

ML25163A217 SUNSI Review By: RJE ADAMS:

Yes No Sensitive Non-Sensitive Non-Publicly Available Publicly Available Keyword:

NRC-002 OFFICE SHP:DRSS/DIOR HP:DRSS/DIOR HP:DRSS/DIOR C:DRSS/DIOR NAME SAnderson EMcManus CDennes JJosey SIGNATURE

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DATE 06/18/25 06/16/25 06/13/25 06/26/25

Enclosure U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Docket Nos.

050-00361; 050-00362

License Nos.

NPF-10; NPF-15

Report Nos.

050-00361/2025-003; 050-00362/2025-003

Licensee:

Southern California Edison Company

Facility:

San Onofre Nuclear Generating Station, Units 2 and 3

Location:

5000 South Pacific Coast Highway San Clemente, California

Inspection Dates:

May 12-15, 2025

Exit Date:

May 15, 2025

Inspectors:

Eric S. McManus, Health Physicist Decommissioning, ISFSI, and Operating Reactor Branch Division of Radiological Safety and Security

Stephanie G. Anderson, Senior Health Physicist Decommissioning, ISFSI, and Operating Reactor Branch Division of Radiological Safety and Security

Christian R. Dennes, Health Physicist Decommissioning, ISFSI, and Operating Reactor Branch Division of Radiological Safety and Security

Accompanied by:

Muhammadali Abbaszadeh, Senior Health Physicist Decommissioning, ISFSI, and Operating Reactor Branch Division of Radiological Safety and Security

Approved By:

Jeffrey E. Josey, Chief Decommissioning, ISFSI, and Operating Reactor Branch Division of Radiological Safety and Security

Attachment:

Supplemental Inspection Information

EXECUTIVE SUMMARY

San Onofre Nuclear Generating Station NRC Inspection Report 050-00361/2025-003; 050-00362/2025-003

This U.S. Nuclear Regulatory Commission (NRC) inspection was a routine, announced inspection of decommissioning activities being conducted at the San Onofre Nuclear Generating Station. In summary, the licensee and its decommissioning general contractor were found to be conducting activities in accordance with site procedures, license requirements, and applicable NRC regulations.

Decommissioning Performance and Status Reviews at Permanently Shutdown Reactors

  • The licensee was effectively implementing decommissioning activities at Units 2 and 3 in accordance with approved procedures and commitments provided in the Post-Shutdown Decommissioning Activities Report. The licensee maintained good radiological control over these work activities. The inspectors reviewed the previously cited violation and concluded that the licensees actions to be adequate and closed the cited violation. (Section 1.2)

Radioactive Waste Treatment, and Effluent and Environmental Monitoring

  • In accordance with Post-Shutdown Decommissioning Activities Report, the licensee established adequate procedural and radiological controls for the environmental monitoring program. The inspectors inspected the licensees environmental monitoring equipment and observed implementation of sampling procedures. The inspectors concluded that these areas were adequately controlled and implemented. (Section 2.2)

Solid Radioactive Waste Management and Transportation of Radioactive Materials

  • The licensee and its decommissioning contractor conducted waste management and transportation activities in accordance with procedural instructions, Post-Shutdown Decommissioning Activities Report commitments, and regulatory requirements. (Section 3.2)

Report Details

Summary of Plant Status

Southern California Edison Company (SCE), the licensee, formally notified the NRC in June 2013 that it had permanently ceased power operations at San Onofre Nuclear Generating Station (SONGS), Units 2 and 3 (Agencywide Documents Access and Management System

[ADAMS] Accession No. ML131640201). The NRC subsequently issued the permanently defueled technical specifications in July 2015 (ML15139A390), along with revised facility operating licenses to reflect the permanent cessation of operations at Units 2 and 3.

As required by Title 10 to the Code of Federal Regulations (10 CFR) 50.82(a)(4), the licensee submitted its PSDAR to the NRC on September 23, 2014 (ML14269A033). The PSDAR outlined the licensees planned decommissioning activities. The current version of the PSDAR is dated May 7, 2020 (ML20136A339). As discussed in the revised PSDAR, the licensee chose the decommissioning alternative DECON. DECON is the removal or decontamination of equipment, structures, or portions of the facility and site that contain radioactive contaminants to levels that permit termination of the license.

On December 20, 2016, the licensee announced the selection of AECOM and Energy Solutions as the decommissioning general contractor. The joint venture between the two companies was named SONGS Decommissioning Solutions (SDS). The SDS organization manages most of the decommissioning activities as described in the PSDAR.

During the inspection, in Unit 3 containment the licensee was completing their final test cuts on a mockup station to prepare for the reactor vessel segmentation activity. In Unit 2 containment, the licensee was moving the scaffolding in the reactor cavity in preparation for reactor vessel segmentation. The material handling facility was operational for open air demolition of the site radioactive structures.

Decommissioning Performance and Status Reviews at Permanently Shutdown Reactors (Inspection Procedure [IP] 71801)

1.1 Inspection Scope

The inspectors observed site activities, reviewed documents, and interviewed site personnel in order to: (1) evaluate the status of decommissioning and verify whether the licensee was conducting decommissioning and maintenance activities in accordance with regulatory and license requirements; (2) evaluate the licensee awareness of work activities to assess their control and conduct of decommissioning; and (3) evaluate the licensees decommissioning staffing, personnel qualifications, and training requirements, including that of the contracted workforce, to ensure that license requirements were met, as applicable to the current decommissioning status.

1.2 Observations and Findings

a.

Status of Decommissioning

At the time of the onsite inspection, the licensee and its decommissioning general contractor SDS were conducting major decommissioning activities in accordance with the commitments provided in Section II.B.1 of the PSDAR. The inspectors discussed the

current decommissioning schedule with management staff, attended daily planning meetings, and observed open air demolition work in progress. The status of decommissioning was noted to be commensurate with the challenges encountered.

The inspectors attended meetings that included discussion of decommissioning activities as well as the current plant status for each day. The topics discussed included an As Low As Is Reasonably Achievable (ALARA) briefing, safety briefing, current work projects, and near-term work projects. The meeting provided participants with current information of the work in progress including radiological and industrial safety updates as needed.

The inspectors performed tours of Unit 2 and Unit 3 containment buildings, material handling facility, south yard, and the hazardous material storage area. Plant staff appeared to be knowledgeable of site conditions and based on observations, the inspectors determined that the licensee was adequately maintaining the material condition of the facilities, as well as the structures, systems, and components that are necessary for safe decommissioning. The inspectors identified good housekeeping practices and appropriate radiological postings and labeling. The inspectors did not identify any radiological areas that were not adequately identified and posted by the licensee.

The inspectors conducted site tours, in part, to observe open air demolition activities.

The licensee was actively demolishing the Unit 3 Fuel Handling Building and the penetration building. The licensee was also preparing the Unit 2 tank farm for demolition.

The work was being conducted in accordance with the instructions provided in SDS-RP1-TSD-24-01, Open-Air Demolition Plan for San Onofre, revision 3. The licensee was demolishing the buildings, sorting the debris, transferring the debris to the adjacent material handling facility, and loading the debris into railcars for offsite disposal.

b.

Observation of Decommissioning Work Activities in Units 2 and 3 Containments

The inspectors toured Unit 2 and 3 containments to observe work in progress and to independently assess radiological conditions. In Unit 2 containment, the licensee continued to prepare for future reactor vessel segmentation activities including reconfiguration of the scaffolding in the cavity. In Unit 3 containment, the major work activities included segmentation of the steam generator and continued preparation for cutting of the reactor vessel shell. The licensee was performing practice cuts on a mockup piece of the reactor vessel.

The inspectors observed strong radiation protection support in both containments.

Housekeeping was adequate based on the work in progress. The inspectors conducted independent radiological surveys during site tours using a Thermo Scientific Radeye G survey meter (serial number 13420, calibration due date of 7/23/2025, calibrated to cesium-137). Overall, the measured exposure rates were consistent with existing signs, boundaries, and postings.

The licensee and its decommissioning contractor were conducting decommissioning activities in accordance with the instructions provided in site procedures and commitments provided in the PSDAR.

c.

Notice of Violation 05000285/2024-004-01 (Closed) Failure to verify all combustibles had been removed when performing hot work. [10 CFR 50.48(f)(1)]

During the January 2025 inspection (ML25045A210), the inspectors identified a violation involving the licensees failure to implement the fire protection program as required by 10 CFR 50.48(f)(1). Specifically, on three separate occasions, the licensee failed to maintain the require standoff distance between ignition sources and combustible materials between December 4, 2024 and February 6, 2025.

The licensee responded to the violation by letter dated March 20, 2025 (ML25084A053).

This letter included the corrective actions completed by the licensee. The NRC acknowledged the licensees response by letter dated March 26, 2025 (ML25085A299).

The inspectors reviewed the licensees corrective actions and concluded that the licensees actions should reasonably prevent a recurrence of the incident.

1.3 Conclusions

The licensee was effectively implementing decommissioning activities at Units 2 and 3 in accordance with approved procedures and commitments provided in the PSDAR. The licensee maintained good radiological control over these work activities. The inspectors reviewed the previously cited violation and concluded that the licensees actions to be adequate and closed the cited violation.

Radioactive Waste Treatment, and Effluent and Environmental Monitoring (IP 84750)

2.1 Inspection Scope

The inspectors observed site activities, reviewed documents, and interviewed site personnel to ensure that: (1) radioactive effluent sampling and analysis requirements were being satisfied so that discharges of radioactive materials were quantified and evaluated from all established release; (2) radiological environmental monitoring programs were effectively implemented; and (3) ground water protection monitoring is implemented adequately.

2.2 Observations and Findings a.

Changes in the Offsite Dose Calculations Manual (ODCM), Process Control Program (PCP), Radwaste Systems Design and Operation

The inspectors reviewed the ODCM and PCP. Inspectors also reviewed implementation of the liquid, gaseous, and solid radwaste system to verify implementation is aligned with the sites licensing basis and regulations. The inspectors verified that the licensee had revised the ODCM to require monitoring of open air demolition activities at the site. This change was documented in the latest revision in SO123-ODCM, ODCM Nuclear Organization SONGS, revision 20.

The inspectors determined that the ODCM changes were adequately evaluated and implemented. The inspectors also reviewed the licensees PCP as documented in SDS-WM1-PCD-0018, Radwaste PCP, revision 2. There were no changes to PCP and the

liquid, gaseous, and solid radwaste system design and operations were consistent to last inspection in this area.

b.

Radioactive Gaseous and Liquid Effluent Treatment

The inspectors performed a walk down of the effluent monitoring ventilation system operated in the material handling facility to verify that the current system configurations, flow paths, and operation are consistent with the description in the ODCM. The inspectors noted that the material handling facility ventilation system was well maintained and met the requirements in the ODCM.

The inspectors observed and reviewed the licensees radioactive gaseous effluent monitoring program. Specifically, the inspectors verified that measurable concentrations of radioactive materials and associated radiation levels were within expected values based on environmental exposure pathway effluent measurements. The inspectors also verified that the gaseous effluent sampling instrumentation was maintained and that no instances of exceeding radioactive gaseous effluent limits were identified.

The inspectors reviewed one radioactive liquid discharge permit and one radioactive gaseous waste discharge permit to verify that the projected doses to members of the public were within the limits specified in 10 CFR Part 50, Appendix I and Technical Specifications dose criteria. The inspectors determined that the liquid and gaseous release permit logs did not contain any entries with projected doses approaching the applicable dose criteria limits.

The inspectors reviewed the licensees 2024 Annual Radioactive Effluent Release Report (ARERR) to verify compliance with regulatory requirements, and to determine whether any anomalous results, unexpected trends, or abnormal releases were identified and appropriately entered into the licensees corrective action program. The inspectors reviewed the ARERR and verified the report was submitted in a timely manner. Based on the review, the inspectors concluded that the effluent release results documented in the ARERR meet the applicable regulatory requirements.

c.

Radiological Environmental Monitoring Program (REMP)

The inspectors conducted a review of the REMP, which included field observations of equipment and procedures, and review of records associated with the program. The inspectors reviewed and observed procedure SDS-CH2-PCD-1022, REMP Air Sampling, revision 10, to verify the licensee process for the collection and shipment of air samples taken in the vicinity of SONGS in support of REMP. The inspectors determined that the licensees environmental monitoring equipment was properly located, calibrated, and maintained, that environmental samples were being adequately collected in accordance with program requirements.

In accordance with the PSDAR, the licensee has implemented a groundwater protection program. The inspectors verified that the program was conducted in accordance with NEI 07-07, Industry Ground Protection Initiative, Final Guidance Document. The inspectors reviewed procedure SDS-CH2-PGM-1004, Groundwater Protection Program, revision 5, to assess the licensees process for implementing the Industry Groundwater Protection Initiative. The inspectors did not identify any significant deficiencies in the licensees implementation of the Groundwater Protection Initiative program.

d.

Problem Identification and Resolution

The inspectors reviewed the status of the corrective action program entries related to radioactive waste treatment, and effluent and environmental monitoring. The inspectors determined that the licensee and its contractors were effectively initiating condition reports to address identified issues, with corresponding corrective actions developed and implemented in a timely manner. The inspectors also noted that the corrective actions demonstrated a focus on preventing recurrence.

2.3 Conclusions In accordance with PSDAR, the licensee established adequate procedural and radiological controls for the environmental monitoring program. The inspectors inspected the licensees environmental monitoring equipment and observed implementation of sampling procedures. The inspectors concluded that these areas were adequately controlled and implemented.

Solid Radioactive Waste Management and Transportation of Radioactive Materials (IP 86750)

3.1 Inspection Scope

The inspectors observed site activities, reviewed documents, and interviewed site personnel to determine if the contractor was effectively implementing the waste management and transportation programs.

3.2 Observations and Findings

a.

Radioactive Material Storage and Control

The inspectors conducted walkdowns of radioactive waste storage areas located inside containments and in areas externally adjacent to the containment buildings. Storage of radioactive material is controlled by SDS procedure SDS-RP1-PGM-3000, Control of Radioactive Material, revision 5. A sampling of accessible radioactive material containers was inspected and verified to be adequately labeled, marked, and free of physical damage or leaks. Radioactive material was also controlled and secured against unauthorized removal in accordance with licensee procedures and 10 CFR 20 regulations. The inspectors identified minor labeling discrepancies which were immediately corrected by the licensee.

The inspectors conducted walkdowns of the South Yard and the hazardous material storage area. During the walkdowns, inspectors interviewed the mixed waste program manager, inspected a sampling of waste containers, and discussed emergency response procedures for the mixed waste area. Storage of mixed waste is controlled by SDS procedure SDS-WM1-PCD-0001, Hazardous Waste Management, revision 12 and SDS-WM1-PGM-0001, Waste Management Program, revision 20. The inspectors discussions with the waste program manager and review of records validated mixed wastes were managed in accordance with licensee procedures and regulations.

The inspectors reviewed sealed source inventory records and toured the location where Category 2 sealed sources were stored. These sources were used to perform

operational checks for radiation protection instruments. In accordance with procedure SDS procedure SDS-RP4-PCD-2001, Sealed Radioactive Sources, revision 7, and 10 CFR Part 37 regulations, the sealed sources were locked within a secure storage container, and the container had adequate access controls in place. Security personnel demonstrated the access alarm was functioning and the posted guard was observed verifying that all personnel accessing the Category 2 storage area were on the list of authorized persons. Access logs were maintained by security personnel for each individual entry into the source storage container. The measured exposure rates outside the container were consistent with existing signs and postings. The source containers were clearly marked with isotope and activity. The sealed source locations and activities were aligned with licensee inventory records. The licensee demonstrated how leak tests are performed and provided inventories and leak tests records for inspectors review.

The source locations and activities were aligned with licensee inventory records.

b.

Radioactive Waste Processing

The licensees contractor was not processing wastes at the time of the inspection; therefore, a physical inspection of this program area was not performed. Inspectors reviewed the licensees solid waste processing procedure SDS procedure SDS-WM1-PCD-0018, Radwaste Control Program, revision 2 and discussed the program with the waste program managers.

c.

Transportation of Radioactive Materials

The inspectors reviewed three completed shipping packages for recently shipped radioactive material; one Class B shipment and two Class A shipments. The inspectors verified each shipment was appropriately characterized, classified, prepared, and offered to a carrier in accordance with site procedures and 49 CFR regulations. Additionally, the inspectors interviewed a certified waste broker and waste package certifier while they labeled and placarded a rail car at the onsite rail spur in order to validate their knowledge and actions were consistent with the information in the shipping documentation, site procedures, and 49 CFR regulations. Both personnel interviewed were knowledgeable on applicable licensee procedure and regulations. The inspectors independent surveys validated radiation level information on the radioactive material tag affixed to the container.

The inspectors reviewed the contractors training program for selected staff supporting the radwaste management and transportation programs. Training is implemented in licensee procedure SDS-WM1-PCD-0011, Training and Qualifications of Waste Management Organization Personnel, revision 17. The inspectors review included the complete training records for three certified waste brokers. Training was adequate, up to date, and implemented in accordance with the licensee procedure and 49 CFR regulations.

The inspectors interviewed the radwaste transport and logistics manager; the SDS waste manager; the SDS director of Low-Level Radioactive Waste subcontracts. The inspectors discussed mixed was storage and transport; waste destinations; waste class determination process; available qualified personnel and training programs; and the use of RADMAN for tracking waste. The inspectors discussions with the waste management validated waste is packaged and transported in accordance with licensee procedures and 49 CFR regulations.

d.

Problem Identification and Resolution

The inspectors reviewed the status of the licensees and contractors corrective action programs for entries involving waste management and transportation activities. The licensee appears to be effectively writing condition reports to address problems as they occur with corresponding corrective actions developed and implemented with a focus on preventing reoccurrence.

3.3 Conclusions

The licensee and its decommissioning contractor conducted waste management and shipping activities in accordance with procedural instructions, PSDAR commitments, and regulatory requirements.

Exit Meeting Summary

The inspectors presented the inspection results to Frederic Bailly, Vice President and Chief Nuclear Officer, and other members of the licensees staff at the conclusion of the onsite inspection on May 15, 2025. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified except for certain SDS procedures and documents which were marked as proprietary.

Attachment SUPPLEMENTAL INSPECTION INFORMATION

KEY POINTS OF CONTACT

Licensee and Contractor Personnel

F. Bailly, SCE, Chief Nuclear Officer and Vice President Decommissioning G. Ferrigno, SDS, Radiation Protection Manager J. Nowak, SDS, Executive Sponsor T. Laursen, SDS, Corrective Action Program Manager J. Madigan, SCE, Manager, Radiation Protection and Waste Oversight; Nuclear Oversight S. Mannon, SDS, Programs Project Director/Regulatory Manager A. Martinez, SDS, Performance Improvement Manager M. Morgan, SCE, Manager, Regulatory Affairs L. Mosher, SCE, Manager, Communications J. Peattie, SCE, General Manager, Site Operations R. Pontes, SCE, General Manager, Site Closure and Environmental Oversight M. Cuarenta, SDS, LLRW manager L. Rafner, SCE, Regulatory Affairs S. Seward, Audit Services Representative S. Sewell, SCE, Manager, Radiation Protection and Waste B. Sholler, SDS, LT/FSS Project Manager J. Stephenson, SCE, Manager, Engineering

INSPECTION PROCEDURES USED

IP 71801 Decommissioning Performance and Status Reviews at Permanently Shutdown Reactors IP 84750 Radioactive Waste Treatment, and Effluent and Environmental Monitoring IP 86750 Solid Radioactive Waste Management and Transportation of Radioactive Materials

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened None

Closed 05000362/2025-01-01

VIO

Failure to verify all combustibles had been removed when performing hot work

[10 CFR 50.48(f)(1)]

Discussed None

Attachment

PARTIAL LIST OF DOCUMENTS REVIEWED

Procedures SDS-WM1-PCD-0001, Hazardous Waste Management, revision 12 SDS-WM1-PCD-0007, Waste Material Control and Tracking, revision 17 SDS-WM1-PCD-0009, Operating Procedure for Brokering of Hazardous Materials, revision 10 SDS-WM1-PCD-0011, Training and Qualifications of Waste Management Organization Personnel, revision 17 SDS-WM1-PCD-0018, Radwaste Process Control Program, Certification, revision 2 SDS-WM1-PCD-0019, RADMAN Suite Software Package, revision 6 SDS-WM1-PCD-0021, Packaging Solid Radioactive Waste, revision 9 SDS-WM1-PCD-0022, Container Receipt and Inspection, revision 12 SDS-WM1-PCD-0023, Waste Package Certification, revision 9 SDS-RP1-TSD-24-01, Open-Air Demolition Plan for San Onofre, revision 3 SDS-WM1-PCD-0003, Transportation Incident and Emergency Response Plan, revision 7 SDS-RP1-PGM-3000, Control of Radioactive Material, revision 5 SDS-WM1-PCD-0018, Radwaste PCP, revision 2 SDS-CH2-PCD-1022, REMP Air Sampling, revision 10 SDS-CH2-PGM-1004, Groundwater Protection Program, revision 5

Condition Reports/Action Requests (AR) Reviewed

AR 0425-61712 AR 0525-48476 AR 0225-10333 SDS-002125 SDS-002050 AR 0425-89702 SDS 002067 SDS-002023 AR 0125-56281 SDS-002142 SDS-002043 AR 0125-98453 SDS-002141 SDS-002047 SDS-002054 SDS -002139 SDS-002048

Condition Reports/Action Requests Generated from Inspection None

Licensing Bases Documents San Onofre Nuclear Generating Station Units 2 & 3 Defueled Safety Analysis Report November 2024 Post-Shutdown Decommissioning Activities Report and Irradiated Fuel Management Plan dated May 7, 2022

Miscellaneous Radiation Work Permit 25-0-700, Routine Visual Inspections, Tours, and Walkdowns Sealed source inventory, Dated May 14, 2025 Open Air Demo Nightly Report dated May 13, 2025 WMG Nuclide Distribution Report, April 23, 2025, revision 8/28/2024 WMG Waste Stream Distribution Listing, Report date April 23, 2025 NRC Reg Guide 1.21 Report Shipment and Package Summary, Report date April 23, 2025 Signed Shipping Manifest LLRW-25-083, January 27, 2025 Signed Shipping Manifest MLLW-25-004, April 24, 2025 Signed Shipping Manifest LLRW-24-460, December 16, 2024 SO123-ODCM, ODCM Nuclear Organization SONGS, revision 20

Attachment

Safety Reviews, Design Changes, and Modifications None

LIST OF ACRONYMS

ADAMS Agencywide Documents Access and Management System ALARA As Low As Is Reasonably Achievable AR Action Request ARERR Annual Radioactive Effluent Release Report CFR Code of Federal Regulations CR Condition Report IP Inspection Procedure ISFSI Independent Spent Fuel Storage Installation NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculations Manual PCP Process Control Program PSDAR Post-Shutdown Decommissioning Activities Report REMP Radiological Environmental Monitoring Program SCE Southern California Edison Company SDS SONGS Decommissioning Solutions SONGS San Onofre Nuclear Generating Station