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Category:Letter
MONTHYEARML24022A1492024-01-17017 January 2024 Independent Spent Fuel Storage Installation, Revision 4 to the Physical Security Plan IR 05000361/20230062023-11-29029 November 2023 NRC Inspection Report 05000361/2023-006 and 05000362/2023-006 ML23333A0682023-11-22022 November 2023 (SONGS) Units 1, 2, 3 and Independent Spent Fuel Storage Installation - Notification of Change in Nuclear Officer IR 05000361/20230052023-10-11011 October 2023 NRC Inspection Report 05000361/2023005 and 05000362/2023005 ML23276A5942023-09-28028 September 2023 and Independent Spent Fuel Storage Installation - Supplement to Decommissioning Funding Status Reports ML23268A0922023-09-20020 September 2023 Generation Station, Units 1, 2 and 3, and the Independent Spent Fuel Storage Facility (ISFSI) - Re-Registration of Dry Fuel Storage Casks for Amended Certificate of Compliance No. 1040 IR 05000361/20230012023-09-13013 September 2023 NRC Inspection Report 05000361 2023-001 and 05000362 2023-004 ML23240A5372023-08-18018 August 2023 Confirmatory Survey Activities Summary and Results for the Unit 2 and 3 Intake Structures at the San Onofre Nuclear Generating Station San Clemente CA ML23129A1802023-06-14014 June 2023 Cover Letter to State of CA on Draft EA Regarding San Onofre ISFSI Updated DFPs IR 05000361/20230032023-05-31031 May 2023 NRC Inspection Report 05000361/2023003 and 05000362/2023003 IR 05000361/20230022023-05-23023 May 2023 NRC Inspection Report 05000361/2023-002 and 05000362/2023-002 ML23137A1032023-05-11011 May 2023 (Songs), Units 1, 2 and 3, and Independent Spent Fuel Storage Installation - 2022 Annual Radiological Environmental Operating Report ML23123A0932023-04-28028 April 2023 (Songs), Units 1, 2 and 3, Submittal of Annual Radioactive Effluent Release Report - 2022 ML23230A0882023-04-10010 April 2023 Independent Spent Fuel Storage Installation - Decommissioning Quality Assurance Plan ML23094A1272023-03-29029 March 2023 Independent Spent Fuel Storage Installation - 10 CFR 50.82(a)(8)(v and VII) and 10 CFR 72.30(c) Decommissioning Funding Status Report 2021 ML23094A1332023-03-29029 March 2023 Nuclear Property Insurance ML23062A1172023-02-28028 February 2023 Generation Station Units 1, 2 and 3, Annual Radioactive Effluent Release Report for Independent Spent Fuel Storage Installation - 2022 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23059A2812023-02-22022 February 2023 (Songs), Units 1, 2 and 3, 2022 Annual Turtle Incidental Take Report ML23046A3792023-02-22022 February 2023 NRC Inspection Report 050-00361/2023-001 and 050-00362/2023-001 ML23045A2022023-02-0909 February 2023 Submittal of Annual Corporate Financial Reports for San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 for Fy Ending June 30, 2022 ML22287A1352023-01-0505 January 2023 Issuance of Exemption from Title 10 of the Code of Federal Regulations Part 72.106(B), Independent Spent Fuel Storage Installation Controlled Area Boundary (L-2021-LLE-0056) ML22348A0622023-01-0404 January 2023 NRC to SCE, Transmittal of the National Marine Fisheries Service'S December 12, 2022, Letter of Concurrence for Decommissioning of San Onofre Nuclear Generating Statiion, Units 2 and 3 IR 05000206/20220062022-12-15015 December 2022 NRC Inspection Report 05000206/2022006, 05000361/2022-006, and 05000362/2022-006 ML22347A2122022-12-12012 December 2022 NMFS to NRC, Endangered Species Act Section 7(a)(2) Concurrence Letter for Decommissioning of the San Onofre Nuclear Generating Station ML22340A6652022-12-0505 December 2022 Letter from John Fassell, Chief; Re., State of California Department of Public Health Review and Comments on SONGS Draft Environmental Assessment ML22333A8192022-11-21021 November 2022 Submittal of San Onofre Nuclear Generating Station, Units 2 and 3, Defueled Safety Analysis Report, Revised November 2022 IR 05000361/20220052022-11-17017 November 2022 NRC Inspection Report 05000361/2022-005 and 05000362/2022-005 ML22301A1462022-10-20020 October 2022 Report of Violations of the National Pollutant Discharge Elimination System Permit San Onofre Nuclear Generating Station (Songs), Units 2 and 3 ML22277A0162022-09-29029 September 2022 Independent Spent Fuel Storage Installation Response to Request for Additional Information Regarding Request for Exemption from 10 CFR 72.106(b) IR 05000361/20220042022-09-26026 September 2022 NRC Inspection Report 05000361/2022-004 and 05000362/2022-004 ML22238A0552022-08-29029 August 2022 U.S. Nuclear Regulatory Commission'S Analysis of Southern California Edison'S Decommissioning Funding Status Report for San Onofre Nuclear Generating Station, Units 1, 2, and 3 ML22234A1602022-07-31031 July 2022 Final Report Per 10 CFR Part 21, Degraded Snubber SF1154 Hydraulic Fluid Batch No. 18CLVS431 ML22207B8612022-07-26026 July 2022 NRC (Public) Inspection Report 05000361/2022003; 05000362/2022003 IR 05000361/20220032022-07-26026 July 2022 NRC Inspection Report (Public) 05000361-2022003 and 05000362-2022003 (002) IR 05000361/20220022022-05-12012 May 2022 NRC Inspection Report 05000361/2022-002 and 05000362/2022-002 ML22136A0842022-05-12012 May 2022 Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report ML22122A0402022-04-28028 April 2022 (Songs), Units 1, 2 and 3 - Annual Radioactive Effluent Release Report - 2021 ML22105A5662022-04-0505 April 2022 20053 Letter - OI Closure to Licensee - Wrongdoing Signed ML22081A1692022-03-31031 March 2022 SONGS Application Acceptance Proposed Exemption from Title 10 of the CFR, Part 72.106(b), ISFSI Controlled Boundary IR 05000206/20214022022-03-24024 March 2022 Notice of Violation, NRC Inspection Report 05000206/2021402, 05000361/2021402, 05000362/2021402, and 07200041/2021401; and Investigation Report 4-2021-004- Public- Cover Letter ML22084A0552022-03-23023 March 2022 10 CFR 50.82(a)(8Xv and VII) and 10 CFR 72.30(c) Decommissioning Funding Status Report 2021 San Onofre Nuclear Generating Station Units 1, 2, and 3 and Independent Spent Fuel Storage Installation IR 05000361/20220012022-03-14014 March 2022 NRC Inspection Report 05000361/2022-001; 05000362/2022-001 ML22066B0242022-03-0303 March 2022 (Songs), Units 1, 2, and 3, and the Independent Spent Fuel Storage Installation - Revision 2 to the ISFSI-Only Emergency Plan and Associated Changes to Emergency Plan Implementing Procedures ML22062B0282022-02-28028 February 2022 and Independent Spent Fuel Storage Installation (Isfsi), Response to Request for Supplemental Information Regarding Request for Exemption from 10 CFR 72.106(b) ML22059B0392022-02-25025 February 2022 International, Proprietary Information to Support SCE Exemption ML22060A1132022-02-24024 February 2022 Nuclear Property Insurance ML22060A1152022-02-24024 February 2022 Generation Station Units 1, 2 and 3, Annual Radioactive Effluent Release Report for Independent Spent Fuel Storage Installation - 2021 ML22048B4972022-02-15015 February 2022 (Songs), Units 1, 2 and 3 - 2021 Annual Turtle Incidental Take Report ML22031A1112022-01-26026 January 2022 (Songs), Units 2 and 3 - Annual Corporate Financial Reports 2024-01-17
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML22333A8202022-11-30030 November 2022 Defueled Safety Analysis Report, Revised November 2022 ML20343A2272020-11-24024 November 2020 Submittal of Defueled Safety Analysis Report, Revised November 2020 ML20343A2262020-11-24024 November 2020 Defueled Safety Analysis Report, Revised November 2020 ML19011A2092018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 4, Reactor ML19011A2102018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML19011A2152018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML19011A2112018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 6, Engineered Safety Features ML19011A2122018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 7, Instrumentation and Controls ML19011A2052018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Appendices 2.5L Through 2.5T ML19011A2062018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 2, Site Characteristics ML19011A2022018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Appendices 2.3A Through 2.5B ML19011A2012018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML19011A2032018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Appendices 2.5C Through 2.5K ML19011A2082018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems ML19011A2142018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 9, Auxiliary Systems ML19011A2132018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 8, Electric Power ML19011A2162018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 11, Radioactive Waste Management ML19011A3992018-12-0606 December 2018 Submittal of Revision 4 to Defueled Safety Analysis Report ML19011A2262018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Master Contents ML19011A2252018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 9A Redacted ML19011A2242018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 17, Quality Assurance ML19011A2232018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 16, Technical Specifications ML19011A2212018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 15, Accident Analyses ML19011A2202018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 15, Appendix 15G, Dose Models Used to Evaluate the Consequences of Accidents Analyzed with the Alternative Source Term Methodology ML19011A2192018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 14, Initial Test Program ML19011A2182018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 13, Conduct of Operations ML19011A2172018-12-0606 December 2018 Revision 4 to Defueled Safety Analysis Report, Chapter 12, Radiation Protection ML16357A3932016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 12, Radiation Protection ML16357A3982016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 16, Technical Specifications ML16357A3952016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 14, Initial Test Program ML16357A2862016-12-15015 December 2016 Transmittal of Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report ML16357A3032016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 9 - Appendix 9A ML16357A3912016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML16357A2982016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML16357A3002016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 6, Engineered Safety Features ML16357A3012016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 7, Instrumentation and Controls ML16357A3022016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 8, Electric Power ML16357A3942016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 13, Conduct of Operations ML16357A3962016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 15, Appendix 15G Dose Models ML16357A2972016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 4, Reactor ML16357A3972016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 15, Accident Analyses ML16357A4002016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Summary of Changes ML16357A4022016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Master Table of Contents ML16357A3922016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 11, Radioactive Waste Management ML16357A3042016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 9, Auxiliary Systems ML16357A2902016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML16357A2932016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 2, Site Characteristics, Appendices 2.5L Through 2.5T ML16357A2942016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 2, Site Characteristics ML16357A2952016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and Systems ML16357A2922016-12-15015 December 2016 Revised Updated Final Safety Analysis Report/Defueled Safety Analysis Report, Chapter 2, Site Characteristics, Appendices 2.5C Through 2.5K 2022-11-30
[Table view] |
Text
Tliomas J. Palmisano Vice President Decommissioning &
Chief Nuclear Officer An EDISON INTERNATIONAL Company December 15, 2016 10 CFR 50.71(e)
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Docket Nos. 50-361 and 50-362 Updated Final Safety Analysis Report l Defueled Safety Analysis Report, Revised November, 2016 San Onofre Nuclear Generating Station, Units 2 and 3
References:
- 1) Letter from P. T. Dietrich (SCE) to U.S. Nuclear Regulatory Commission (Document Control Desk) dated June 12, 2013,
Subject:
Certification of Permanent Cessation of Power Operations, San Onofre Nuclear Generating Station, Units 2 and 3
- 2) Letter from P. T. Dietrich (SCE) to U. S. Nuclear Regulatory Commission (Document Control Desk) dated June 28, 2013,
Subject:
Permanent Removal of Fuel from the Reactor Vessel, San Onofre Nuclear Generati1_1g Station, Unit 3
- 3) Letter from P. T. Dietrich (SCE) to U. S. Nuclear Regulatory Commissio*n (Document Control Desk) dated July 22, 2013,
Subject:
Permanent Removal of Fuel from the Reactor Vessel, San Onofre Nuclear Generating Station, Unit 2
- 4) Letter from T. J. Palmisano (SCE) to U.S. Nuclear Regulatory Commission (Document Control Desk) dated February 11, 2015,
Subject:
Docket Nos. 50-361 and 50-362, Updated Final Safety Analysis Report and Updated Fire Hazard Analysis, Revised February, 2015, San Onofre Nuclear Generating Station, Units 2 and 3
Dear Sir or Madam:
In accordance with the requirements of 10 CFR 50.71(e), Southern California Edison (SCE) hereby submits the revision to the Updated Final Safety Analysis Report (UFSAR) for San Onofre Nuclear Generating Station (SONGS), Units 2 and 3. All UFSAR changes reflecting the SONGS Units 2 and 3 transition to a decommissioned state that were approved prior to November 30, 2016 have been incorporated.
P.O. Box 128 San Clemente, CA 92674 Security-Related Information -
(949) 368-6575 Withhold Under 10 CFR 2.390 Fax: (949) 368-6183 Decontrolled Upon Removal of Enclosure 1 tom.palmisano@sce.com
Document Control Desk 2 December 15, 2016 As part of the decommissioning planning process, SCE notified the NRC that it had permanently ceased operation of SONGS Units 2 and 3 (Reference 1) and certified both Units 2 and 3 have beeo permanently defueled (References 2 and 3). The irradiated fuel will be stored in the spent fuel pools (SFP) until the fuel is moved to the Independent Spent Fuel Storage Installation (ISFSI). In this configuration, the number of operable systems and credible accidents/transients is significantly less than for a plant authorized to operate the reactor or emplace or retain fuel in the reactor vessel.
Systems that no longer serve a function to support spent fuel management, storing or processing of radioactive waste, or are not required to support the current applicable Technical Specifications or Emergency Plan, have been identified as "Removed from Service." For those Systems identified as "Removed from Service," the design criteria, -design basis, system description, system operation, system parameters, and safety evaluations have been deleted. Additionally, descriptions of equipment added due to modifications made to SONGS Units 2 and 3 supporting the decommissioned state have been added to the appropriate Chapters.
As a result of the large scope reductions occurring to reflect SONGS Units 2 and 3 being in a decommissioned state, a subtitle of Defueled Safety Analysis Report (DSAR) has been added to the UFSAR. The terms UFSAR and DSAR will be used interchangeably.
The changes made to the UFSAR/DSAR reflect a complete re-write of many chapters and updates to some of the Appendices. Information that had been previously addressed in multiple UFSAR Sections has been consolidated into single UFSAR Chapters. Because of the extent of the changes and the resulting reformatting and renumbering of the information provided in the UFSAR Chapters, it was not appropriate to annotate specific changes with revision bars. Therefore, no revision bars are included in the provided UFSAR/DSAR.
A list of changes for each Chapter of the UFSAR/DSAR is provided in Attachment 1.
Information which was originally provided in the UFSAR as part of the licensing basis for the SONGS Units 2 and 3 operating plants that: 1) is no longer relevant in the permanently shutdown and defueled condition; and 2) provides the bounding (initial) condition for Decommissioning and for which no updated values will be provided, have been transferred to SCE Controlled Document 90216, SONGS Units 2 and 3 UFSAR Historical Information.
The Updated Fire Hazard Analysis (UFHA) is not included in this submittal and is available for review.
Consistent with the regulations contained in 10 CFR 50. 71 (e), this update is being provided within 24 months following the previous update submitted on February 11, 2015 (Reference 4 ).
Enclosures 1 and 2 are disks containing the SONGS Units 2 and 3 UFSAR/DSAR.
Enclosure 1 of this submittal contains information that is deemed security-related sensitive information, and the files are requested to be withheld from public disclosure in accordance with 10 CFR 2.390.
Enclosure 2 provides the redacted version of Enclosure 1.
Security-Related Information -
Withhold Under 10 CFR 2.390 Decontrolled Upon Removal of Enclosure 1 L
Document Control Desk 3 December 15, 2016 There are no commitments contained in this letter or its enclosures.
Should there be any questions regarding this submittal, please contact Mr. James Kay at (949) 368-7418.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on .1-L/ .r1/ "'2.....G / (
(Date)
Sincerely, : Compact Disk, San Onofre Nuclear Generating Station Units 2 and 3 UFSAR/DSAR, Revised November 2016, Security-Related Information - Withhold Under 10 CFR 2.390 : Compact Disk, San Onofre Nuclear Generating Station Units 2 and 3 UFSAR/DSAR, Revised November 2016, Redacted 10 CFR 2.390 : Summary of Changes to the Updated Final Safety Analysis Report I Defueled Safety Analysis Report cc: K. Kennedy, Regional Administrator, NRC Region IV M. Vaaler, NRC Project Manager, SONGS Units 1, 2 and 3 S. Y. Hsu, California Department of Public Health, Radiologic Health Branch Security-Related Information -
Withhold Under 10 CFR 2.390 Decontrolled Upon Removal of Enclosure 1