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MONTHYEARML0223208152002-09-10010 September 2002 Songs Units 2 & 3, Relief, American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code Concerning Use of Electrical Discharge Machining, MB5251, MB5252 Project stage: Other 2002-09-10
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Category:Code Relief or Alternative
MONTHYEARML13035A1882013-04-29029 April 2013 Relief Request ISI-3-36, Reactor Coolant Pressure Boundary Testing, Third 10-Year Inservice Inspection Interval ML12341A2782012-12-0404 December 2012 Relief Request: American Society of Mechanical Engineers (Asme), Code Case N-770-1 ML12250A6422012-10-15015 October 2012 Correction to Relief Request ISI-3-35, Use of Subsequent Edition of ASME OM Code for Snubbers Program, for 3rd and 4th 10-Year Inservice Inspection Intervals ML12179A4922012-07-20020 July 2012 Relief Request ISI-3-35, Use of Subsequent Edition of ASME OM Code for Snubbers Program, for 3rd and 4th 10-Year Inservice Inspection Intervals ML1127300742011-11-0404 November 2011 Relief Requests ISI-3-32, ISI-3-33, and ISI-3-34, Alternative to Requirements for Examinations of Welds and Core Support Structure Surfaces, Third 10-Year Inservice Inspection ML0927901532009-10-0202 October 2009 Revision 1 to Third Ten-Year Inservice Inspection (ISI) Interval Relief Request ISI-3-29, Inspection of Reactor Vessel Head Control Element Drive Mechanism Nozzles ML0927901552009-10-0202 October 2009 Third Ten-Year Inservice Inspection (ISI) Interval Relief Request ISI-3-30, Inspection of Reactor Vessel Head In-Core Instrument Nozzles ML0836403752009-01-23023 January 2009 Relief Requests ISI-3-27, Revision 1, and ISI-3-28, Revision 1, for the Application of Weld Overlay on Dissimilar and Similar Metal Welds ML0832201312008-11-12012 November 2008 Revision to Third Ten-Year Inservice Inspection (ISI) Interval Requests ISI-3-27 and ISI-3-28, Use of Structural Weld Overlay and Associated Alternative Repair Techniques ML0824609302008-09-0808 September 2008 Corrections to Safety Evaluations Issued for Approval to Use Alternative to the Requirements for Repair / Replacement Activities Related to the Performance of Structural Weld Overlays (TAC Nos. MD458.. ML0732404372007-12-13013 December 2007 Request for Relief ISI-3-28 - Approval to Use Alternatives to the Requirements of ASME Code for Repair/Replacement Activities Re Performance of Structural Weld Overlays (Tac Nos. MD6256 & MD6257) ML0732500042007-12-13013 December 2007 RR ISI-3-27 - Approval to Use Alternatives to the Requirements of ASME Code for Repair/Replacement Activities Related to Performance of Structural Weld Overlays (TACs MD4580 & MD4581) ML0713800132007-06-12012 June 2007 Relief Request ISI-3-25 - Third 10-Year Inservice Inspection Interval Re Use of Structural Weld Overlay and Associated Alternative Repair Techniques ML0713707402007-06-12012 June 2007 Relief Request ISI-3-24 Third 10-Year ISI Interval Regarding Four Reactor Coolant System Pressurizer, Dissimilar Metal, Nozzle-to-safe-end Welds Structural Overlay & Alternative Repair Techniques ML0703101542007-02-15015 February 2007 Relief Request for Relief from Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Concerning Reactor Vessel Head Penetration Repairs ML0701807372007-02-0707 February 2007 Third 10-year Inservice Inspection Interval, Requests for Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML0634503472006-12-27027 December 2006 Relief, Relief Request ISI-3-23 for Third 10-Year ISI Interval to Allow Use of American Society of Mechanical Engineers Code Case N-746, MC9433 & MC9434 ML0628500962006-12-21021 December 2006 Request for Relief for the In-Service Inspection Program and Approval to Use the Alternative Requirements of ASME Code Case N-513-2 ML0631103222006-12-14014 December 2006 Request for Relief (RR ISI-3-18) from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code - Third 10-Year ISI Interval ML0632405892006-12-14014 December 2006 Third 10-year Inservice Inspection Interval, Requests for Relief ISI-3-19 and ISI-3-20 from the Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code-TAC MD1128/1129 ML0626204912006-10-0202 October 2006 Request for Relief (ISI-3-16) from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (TAC Nos. MC9433/MC9433) ML0626402822006-10-0202 October 2006 Request for Relief (ISI-3-17) from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (TAC Nos. MC9487/MC9488) ML0622902412006-08-15015 August 2006 Revision to the Duration of Relief Request ISI-3-22 Third 10-Year Inspection Interval, San Onofre Unit 3 ML0613503702006-05-11011 May 2006 Third Ten-Year Inservice Inspection (ISI) Interval Relief Request ISI-3-21 Requests for Alternative to ASME Code Rules for the Embedded Flaw Repair Process for Control Element Drive Mechanism (CEDM) # 56 ML0613600652006-05-11011 May 2006 Third Ten-Year Inservice Inspection (ISI) Interval Relief Request ISI-3-22 Request for Alternative to ASME Code Rules for the Inside Diameter Structural Weld Overlay Repair Process for Control Element Drive Mechanism (CEDM) # 56 ML0604103232006-02-0808 February 2006 Inservice Inspection Program Relief Request ISI-3-15 ML0602602212006-01-18018 January 2006 Withdrawal of Relief Request ISI-3-10, Revision 1 ML0505600352005-03-0909 March 2005 Evaluation of Relief for Use of Mechanical Nozzle Assemblies as an Alternate to the American Society of Mechanical Engineers Code Repairs ML0506800542005-03-0202 March 2005 Safety Evaluation of Relief for Repair of Pressurizer Sleeves During the Third 10-Year Inservice Inspection (ISI) Interval (Tacs. MC4789 and MC4790) ML0436203412004-12-23023 December 2004 SONGS, Unit 3 - Request for Relief from Requirements of the ASME Code Concerning Reactor Vessel Head Penetration Repairs ML0613503742004-10-31031 October 2004 Attachment 1, Relief Request ISI-3-21 Evaluation of the Acceptability of Embedded Flaw Repair of the Indication in Reactor Vessel Head Penetration No. 56 at SONGS Unit 3 ML0426403392004-09-15015 September 2004 Revision to the Duration of Relief Request ISI-3-7 Third 10-Year Inspection Interval ML0420504262004-07-22022 July 2004 SONGS, Request Relief from Requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Concerning Inservice Inspection (ISI) Program Updates for the Third 10-Year ISI (TAC Nos. MC0334 & MC0335) ML0412604592004-05-0505 May 2004 SONGS, Units 2 & 3, Inservice Inspection Program Relief Request ISI-38, Embedded Flaw Repair Process ML0411401662004-04-21021 April 2004 SONGS, Units 2 and 3, Request for Relief from the Requirements of the ASME Code Concerning Updates to Inservice Testing Program ML0408401282004-03-19019 March 2004 Songs, Units 2 and 3 - Relief Request- Relaxation of the Requirements of Order EA-03-009 Regarding Reactor Pressure Vessel Head Inspections ML0408405762004-03-19019 March 2004 Relief, Requirements of the ASME Boiler and Pressure Vessel Code Concerning Mechanical Nozzle Seal Assemblies ML0302801692003-01-24024 January 2003 Mechanical Nozzle Seal Assembly Type 2 Code Replacement Request for Relief from 10 CFR 50.55a ML0232502022002-11-19019 November 2002 Second Ten-Year Interval Inservice Inspection Program Pressure Retaining Piping Welds Relief Requests B-2-06 & B-2-07 ML0223208152002-09-10010 September 2002 Songs Units 2 & 3, Relief, American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code Concerning Use of Electrical Discharge Machining, MB5251, MB5252 ML0208704592002-03-27027 March 2002 Relief, Mechanical Nozzle Assemblies as an Alternative to American Society of Mechanical Engineers (Amse) Code Repairs ML0133902732002-01-11011 January 2002 SONGS, Units 2 and 3, Request for Relief Regarding Reactor Pressure Vessel Nozzle Examinations (TAC Nos. MB2484 and MB2485) 2013-04-29
[Table view] Category:Letter
MONTHYEARIR 05000361/20240052024-10-0404 October 2024 NRC Inspection Report 05000361/2024005 and 05000362/2024005 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 07200041/20244012024-08-16016 August 2024 San Onofe Nuclear Generating Station, Security Baseline Inspection Report 07200041/2024401 IR 05000361/20240042024-08-0909 August 2024 NRC Inspection Report 05000361/2024004 and 05000362/2024004 ML24191A2472024-07-0202 July 2024 (Songs), Units 1, 2, and 3, and the Independent Spent Fuel Storage Installation - Revision to the ISFSI-Only Emergency Plan and Associated Changes to Emergency Plan Implementing Procedures ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24141A0802024-05-15015 May 2024 (Songs), Units 1, 2 and 3 and Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Operating Report IR 05000361/20240022024-04-0101 April 2024 – NRC Inspection Report 050-00361/2024-002 and 050-00362/2024-002 ML24094A0642024-03-27027 March 2024 Independent Spent Fuel Storage Installation, Decommissioning Funding Status Report 2023 ML24065A0152024-02-28028 February 2024 Generation Station Units 1, 2 and 3, Annual Radioactive Effluent Release Report for Independent Spent Fuel Storage Installation 2023 ML24044A0812024-02-14014 February 2024 LTR-24-0008: NRC Response to Paul Blanch Email Safety of Spent Nuclear Fuel at SONGS ISFSI IR 05000361/20240012024-02-13013 February 2024 NRC Inspection Report 050-00361/2024-001 and 050-00362/2024-001 (1) ML24037A0542024-01-30030 January 2024 (Songs), Units 2 and 3, Submittal of Annual Corporate Financial Reports ML24022A1492024-01-17017 January 2024 Independent Spent Fuel Storage Installation, Revision 4 to the Physical Security Plan ML24017A2432024-01-15015 January 2024 LTR-24-0008 Paul Blanch, E-mails Request for Formal Response to Requests for Meeting to Discuss Safety Issues with NRC Staff 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 Services 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 Commissions Analysis of Southern California Edisons 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 2024-09-18
[Table view] Category:Safety Evaluation
MONTHYEARML18101A2312018-09-24024 September 2018 SONGS ISFSI Only QAPD Letter ML17311A3642018-04-23023 April 2018 Issuance of Amendments to Change the Physical Security Plan to Reflect an ISFSI - Only Configuration ML17345A6572018-01-0909 January 2018 /2/3 - Issuance of Amendments 169/237/230 Re Change the Defueled Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pools (CAC Nos. L53157, L53158, and L53159) ML17310B4822017-11-30030 November 2017 Issuance of Amendments to Revise the Permanently Defueled Emergency Plan (CAC Nos. L53160, L53161, and L53162) ML17300A0422017-11-0909 November 2017 2/3 - Issuance of Amendments 235 and 228 Removal of Cyber Security Plan License Condition (CAC Nos. L53191 and L53192) ML16252A2072017-01-23023 January 2017 Issuance of Amendments 234 and 227 to Revise the Cyber Security Plan Milestone 8 Completion Date in the Facility Operating Licenses (CAC Nos. L53132 and L53133) ML16055A5222016-03-11011 March 2016 San Onofre Nuclear Generating Station, Units 2 and 3 - Issuance of Amendments Modifying Licenses to Allow Changes to Specific Regulatory Guide Commitments ML15027A2392016-01-0505 January 2016 Independent Spent Fuel Storage Installation - Safety Evaluation Issuance of Order and Conforming Amendments Concerning Preemption Authority ML15027A2302016-01-0505 January 2016 Independent Spent Fuel Storage Installation - Cover Letter and Amendment Issuance of Order and Conforming Amendments Concerning Preemption Authority. ML15209A9352015-10-0101 October 2015 LTR-15-0424 - San Onofre Nuclear Generating Station, Units 2 and 3 - Issuance of Amendments to Revise the Cyber Security Plan Milestone 8 Completion Date in the Facility Operating Licenses ML15182A2562015-08-19019 August 2015 NRC Staff Review of San Onofre Nuclear Generating Station, Units 2 and 3 - Review and Preliminary Approval of Irradiated Fuel Management Plan ML15191A4612015-08-10010 August 2015 the Independent Spent Fuel Storage Installation - Review of Changes to the Decommissioning Quality Assurance Program (TAC Nos, MF5215, Mf 5216, and Mf 5217) ML15139A3902015-07-17017 July 2015 Issuance of Amendment for Permanently Shutdown and Defueled Technical Specifications and Certain License Conditions ML15126A4612015-06-0505 June 2015 and the Independent Spent Fuel Storage Installation - Issuance of Amendment Changes to the Emergency Plan ML15105A3492015-06-0505 June 2015 the Independent Spent Fuel Storage Installation - Issuance of Amendments Changes to the Emergency Action Level Scheme ML13268A1652014-08-0101 August 2014 Approval of Safe Storage Shift Manager/Certified Fuel Handler Training Program ML13035A1882013-04-29029 April 2013 Relief Request ISI-3-36, Reactor Coolant Pressure Boundary Testing, Third 10-Year Inservice Inspection Interval ML12215A3992012-10-16016 October 2012 Issuance of Amendment Nos. 226 and 219, Revise Technical Specifications Applicable to Movement of Irradiated and Non-Irradiated Fuel Assemblies in the Containment or Fuel Storage Pool ML12250A6422012-10-15015 October 2012 Correction to Relief Request ISI-3-35, Use of Subsequent Edition of ASME OM Code for Snubbers Program, for 3rd and 4th 10-Year Inservice Inspection Intervals ML1127300742011-11-0404 November 2011 Relief Requests ISI-3-32, ISI-3-33, and ISI-3-34, Alternative to Requirements for Examinations of Welds and Core Support Structure Surfaces, Third 10-Year Inservice Inspection ML1027902802010-10-15015 October 2010 Issuance of Amendment Nos. 224 and 217, Revise Technical Specification 3.8.1, AC Sources - Operating, Condition a to Allow One-time Extension to 10-day Completion Time ML1013201682010-06-30030 June 2010 Issuance of Amendment Nos. 223 and 216, Revise Completion Time in Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System, Based on TSTF-340, Revision 3 ML17010A1052010-02-24024 February 2010 Safety Evaluation by the Office of Federal and State Materials and Environmental Management Programs Related to Amendment No. 165 to Facility Operating License No. DPR-13 San Onofre Nuclear Generating Station, Unit 1 ML0905502312009-03-10010 March 2009 Independent Spent Fuel Storage Installation - Correction to NRC Response to Proposed Changes to the Emergency Plan, Increase in Emergency Response Organization Augmentation Time ML0834700912009-02-0303 February 2009 Issuance of Amendment Nos. 219 and 212, Changes to Adopt TSTF-487, Revision 1, Relocate Departure from Nucleate Boiling Parameters to the Core Operating Limits Report ML0836403752009-01-23023 January 2009 Relief Requests ISI-3-27, Revision 1, and ISI-3-28, Revision 1, for the Application of Weld Overlay on Dissimilar and Similar Metal Welds ML0835309252009-01-13013 January 2009 Independent Spent Fuel Storage Installation, Correction to NRC 11/28/2008 Safety Evaluation, Proposed Changes to the Emergency Plan, Increase in Emergency Response Organization Augmentation Time ML0833300972008-11-28028 November 2008 License Amendments 218 & 211 Regarding Battery and DC Sources Upgrades and Cross-Tie ML0832306082008-11-28028 November 2008 Independent Fuel Storage Installation Proposed Changes to the Emergency Plan - Increase in Emergency Response Organization Augmentation Time (Tac Nos. MD5837 and MD5838) ML0820307202008-08-15015 August 2008 Issuance of Amendment No. 210 Containment Leakage Rate Testing Program ML0806001502008-03-25025 March 2008 Issuance of Amendment Nos. 217 and 209, Revise Technical Specification Surveillance Requirements 3.3.7.3.a and 3.8.1 Degraded Voltage Function Values ML0805905282008-03-18018 March 2008 License Amendment, Revise Technical Specification Surveillance Requirements 3.3.7.3.a and 3.8.1 Degraded Voltage Function Values ML0732500042007-12-13013 December 2007 RR ISI-3-27 - Approval to Use Alternatives to the Requirements of ASME Code for Repair/Replacement Activities Related to Performance of Structural Weld Overlays (TACs MD4580 & MD4581) ML0732404372007-12-13013 December 2007 Request for Relief ISI-3-28 - Approval to Use Alternatives to the Requirements of ASME Code for Repair/Replacement Activities Re Performance of Structural Weld Overlays (Tac Nos. MD6256 & MD6257) ML0731705292007-11-29029 November 2007 Issuance of Amendment Nos. 215 and 207, Revise TS 5.5.2.11 Related to Steam Generator Tube Surveillance Program, Tube Repair ML0728900122007-10-31031 October 2007 Issuance of License Amendments 214 and 206 Regarding Adoption of Technical Specifications Task Force (TSTF)-448, Revision 3, Control Room Envelope Habitability, Using the Consolidated Line Item Improvement Process ML0725501752007-09-27027 September 2007 Issuance of Amendment Nos. 213 and 205 Request to Revise Fuel Storage Pool Boron Concentration ML0726001582007-09-12012 September 2007 Request to Revise Safety Evaluation for License Amendments 210 and 202 ML0720600102007-07-26026 July 2007 Conforming License Amendment to Incorporate the Mitigation Strategies Required by Section B.5.b. of Commission Order EA-02-026 (Tac Nos. MD4564 and MD4565) ML0713800132007-06-12012 June 2007 Relief Request ISI-3-25 - Third 10-Year Inservice Inspection Interval Re Use of Structural Weld Overlay and Associated Alternative Repair Techniques ML0713707402007-06-12012 June 2007 Relief Request ISI-3-24 Third 10-Year ISI Interval Regarding Four Reactor Coolant System Pressurizer, Dissimilar Metal, Nozzle-to-safe-end Welds Structural Overlay & Alternative Repair Techniques ML0713000182007-06-0505 June 2007 License Amendment, Issuance of Amendment Nos. 212 and 204 to Revise TS 3.7.1, Main Steam Safety Valves Requirements and Actions ML0703803162007-04-0404 April 2007 License Amendments 211 and 203 Regarding Emergency Diesel Generator Fuel Oil Volume Requirements ML0704305722007-02-21021 February 2007 Correction Ltr for the Issuance Relief Request No. ISI-3-23 for Third 10-year Inservice Inspection Interval to Allow the Use of American Society of Mechanical Engineers Code Case N-746 (TAC MD1809/10) ML0703706302007-02-20020 February 2007 Correction Letter for Issuance for Request for Relief Relief Request ISI-3-18, from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML0703101542007-02-15015 February 2007 Relief Request for Relief from Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Concerning Reactor Vessel Head Penetration Repairs ML0701807372007-02-0707 February 2007 Third 10-year Inservice Inspection Interval, Requests for Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML0634003592006-12-29029 December 2006 Issuance of Amendments 210 and 202 Full-scope Implementation of an Alternative Accident Source Term ML0631103222006-12-14014 December 2006 Request for Relief (RR ISI-3-18) from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code - Third 10-Year ISI Interval ML0632405892006-12-14014 December 2006 Third 10-year Inservice Inspection Interval, Requests for Relief ISI-3-19 and ISI-3-20 from the Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code-TAC MD1128/1129 2018-09-24
[Table view] |
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September 10, 2002 Mr. Harold B. Ray Executive Vice President Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128
SUBJECT:
SAN ONOFRE NUCLEAR GENERATING STATION (SONGS), UNITS 2 AND 3 - REQUEST FOR RELIEF FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) BOILER AND PRESSURE VESSEL CODE (CODE) CONCERNING USE OF ELECTRICAL DISCHARGE MACHINING (EDM) (TAC NOS. MB5251 AND MB5252)
Dear Mr. Ray:
By letter dated May 31, 2002, Southern California Edison Company (SCE) submitted Relief Request RVHP-3 from the requirements of ASME Code Section XI, Subsection IWA-4320 "Thermal Removal Process," 1989 Edition, no Addenda.
In Relief Request RVHP-3, SCE proposed using the EDM process as an alternative means to remove thermally processed material from the reactor vessel head penetrations (RVHP) should removal be necessary as a result of the Bulletin 2001-01, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles," inservice inspections at SONGS, Units 2 and 3.
SCE has proposed to use the qualifying requirements of ASME Code Section XI, IWA-4461.4, 1995 Edition, 1997 Addenda, in lieu of the requirements of IWA-4320 of the 1989 Edition, no Addenda. SCE has stated that adherence to the more recent edition would meet the ASME Codes intent without the unnecessary removal of mechanical material.
The NRC staffs evaluation and conclusions are contained in the enclosed safety evaluation.
The staff finds that the proposed alternative in RVHP-3 provides an acceptable level of quality and safety; therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the proposed alternative is authorized for the remainder of the terms of the current operating licenses in the event that inspections during refueling outages for SONGS, Unit 2 and 3 reveal the need for RVHP repairs.
Sincerely,
/RA/
Stephen Dembek, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362
Enclosure:
Safety Evaluation cc w/encl: See next page
September 10, 2002 Mr. Harold B. Ray Executive Vice President Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128
SUBJECT:
SAN ONOFRE NUCLEAR GENERATING STATION (SONGS), UNITS 2 AND 3 - REQUEST FOR RELIEF FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) BOILER AND PRESSURE VESSEL CODE (CODE) CONCERNING USE OF ELECTRICAL DISCHARGE MACHINING (EDM) (TAC NOS. MB5251 AND MB5252)
Dear Mr. Ray:
By letter dated May 31, 2002, Southern California Edison Company (SCE) submitted Relief Request RVHP-3 from the requirements of ASME Code Section XI, Subsection IWA-4320 "Thermal Removal Process," 1989 Edition, no Addenda.
In Relief Request RVHP-3, SCE proposed using the EDM process as an alternative means to remove thermally processed material from the reactor vessel head penetrations (RVHP) should removal be necessary as a result of the Bulletin 2001-01, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles," inservice inspections at SONGS, Units 2 and 3.
SCE has proposed to use the qualifying requirements of ASME Code Section XI, IWA-4461.4, 1995 Edition, 1997 Addenda, in lieu of the requirements of IWA-4320 of the 1989 Edition, no Addenda. SCE has stated that adherence to the more recent edition would meet the ASME Codes intent without the unnecessary removal of mechanical material.
The NRC staffs evaluation and conclusions are contained in the enclosed safety evaluation.
The staff finds that the proposed alternative in RVHP-3 provides an acceptable level of quality and safety; therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the proposed alternative is authorized for the remainder of the terms of the current operating licenses in the event that inspections during refueling outages for SONGS, Unit 2 and 3 reveal the need for RVHP repairs.
Sincerely,
/RA/
Stephen Dembek, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362 DISTRIBUTION:
PUBLIC
Enclosure:
Safety Evaluation PDIV-2 r/f RidsNrrDlpmLpdiv (W.Ruland) cc w/encl: See next page RidsNrrDlpmLpdiv2 (S.Dembek)
RidsNrrPMBPham RidsNrrPMAWang RidsNrrLAMMcAllister RidsOgcRp RidsAcrsAcnwMailCenter G. Hill (4)
SCoffin/W.Held EMCB/DE SMorris, RIV Plants (SAM1)
RidsRgn4MailCenter (CJohnson)
Accession No: ML022320815 *EMCB Memo dated 8/14/02 OFFICE PDIV-2/PM PDIV-2/PM PDIV-1/LA DE/EMCB* OGC PDIV-2/SC NAME BPham/kes AWang MMcAllister EAndruszkiewicz SDembek DATE 8/14/02 DOCUMENT NAME: C:\ORPCheckout\FileNET\ML022320815.wpd OFFICIAL RECORD COPY
San Onofre Nuclear Generating Station, Units 2 and 3 cc:
Mr. Raymond Waldo, Plant Manager Mr. Michael Olson Nuclear Generation San Onofre Liaison Southern California Edison Company San Diego Gas & Electric Company San Onofre Nuclear Generating Station P.O. Box 1831 P. O. Box 128 San Diego, CA 92112-4150 San Clemente, CA 92674-0128 Mr. Ed Bailey, Radiation Program Director Mr. Douglas K. Porter Radiologic Health Branch Southern California Edison Company State Department of Health Services 2244 Walnut Grove Avenue Post Office Box 942732 (MS 178)
Rosemead, CA 91770 Sacramento, CA 94327-7320 Mr. David Spath, Chief Resident Inspector/San Onofre NPS Division of Drinking Water and c/o U.S. Nuclear Regulatory Commission Environmental Management Post Office Box 4329 P. O. Box 942732 San Clemente, CA 92674 Sacramento, CA 94234-7320 Mayor Chairman, Board of Supervisors City of San Clemente County of San Diego 100 Avenida Presidio 1600 Pacific Highway, Room 335 San Clemente, CA 92672 San Diego, CA 92101 Mr. Dwight E. Nunn, Vice President Eileen M. Teichert, Esq. Southern California Edison Company Supervising Deputy City Attorney San Onofre Nuclear Generating Station City of Riverside P.O. Box 128 3900 Main Street San Clemente, CA 92674-0128 Riverside, CA 92522 Mr. James D. Boyd, Commissioner Mr. Gary L. Nolff California Energy Commission Power Projects/Contracts Manager 1516 Ninth Street (MS 31)
Riverside Public Utilities Sacramento, CA 95814 2911 Adams Street Riverside, CA 92504 Mr. Joseph J. Wambold, Vice President Southern California Edison Company Regional Administrator, Region IV San Onofre Nuclear Generating Station U.S. Nuclear Regulatory Commission P.O. Box 128 611 Ryan Plaza Drive, Suite 400 San Clemente, CA 92764-0128 Arlington, TX 76011-8064 August 2002
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST TO USE ALTERNATIVE THERMAL REMOVAL TECHNIQUES FOR REACTOR VESSEL HEAD PENETRATION REPAIRS SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION (SONGS) UNITS 2 AND 3 DOCKET NOS. 50-361 AND 50-362
1.0 INTRODUCTION
By letter dated May 31, 2002, Southern California Edison Company (SCE/licensee), submitted Relief Request Number RVHP-3. SCE requests NRC approval for the use of an electrical discharge machining (EDM) process should repairs of reactor vessel head penetration (RVHP) nozzles or J-groove welds become necessary at SONGS, Units 2 and 3. The RVHP nozzles at SONGS Units 2 and 3 were determined to have a moderate susceptibility to primary water stress corrosion cracking (PWSCC). These nozzles were manufactured from SB-166 or SB-167 Alloy 600 materials which are P-Number 43 Inconel alloys. SCE plans to utilize the EDM process to excavate PWSCC cracks or defects and remove weld crown surfaces of repair welds to facilitate performance of final nondestructive examination (NDE). SCE proposes to qualify the EDM process in accordance with IWA-4461.4 of the 1995 Edition, 1997 Addenda of ASME Section XI to allow the use of thermal methods for metal removal without further mechanical processing.
2.0 BACKGROUND
Licensees are required per 10 CFR 50.55a to comply with ASME Code requirements. As part of their licensing basis, SONGS, Units 2 and 3 are in compliance with the 1989 Edition, no Addenda of the ASME Code. In this Edition of the Code,Section XI, IWA-4322 states, "if thermal removal processes are used on P-No. 8 and P-No. 43 materials, a minimum of 1/16" material shall be mechanically removed from the thermally processed areas."
To propose an alternative to their existing ASME Code requirements, a licensee must make a submittal per 10 CFR 50.55a(a)(3). SCE specifically applied for this relief based on the provision in 10 CFR 50.55a(a)(3)(i) which states that proposed alternatives must provide an acceptable level of quality and safety.
3.0 EVALUATION 3.1 Code Requirement Pursuant to 10 CFR 50.55a(a)(3)(i), SCE proposes an alternative to the thermal removal requirements of IWA-4322 applicable to P-No. 43 materials. Instead of mechanically removing 1/16" of material from all thermally processed areas as required by IWA-4322, SCE proposes to qualify the EDM process in accordance with the qualification requirements from IWA-4461.4 of the 1995 Edition, 1997 Addenda of ASME Section XI. IWA-4322 requires the removal of a minimum of 1/16" of material from all thermally processed areas of P-No. 43 materials. The basis of this requirement is to ensure that thermally cut or excavated surfaces are free of unacceptable surface irregularities, oxides, and fissures that were created by the thermal removal process.
3.2 Licensees Basis for Proposed Alternative SCE has proposed to use the qualification requirements of IWA-4461.4, ASME Section XI, 1995 Edition, 1997 Addenda to ensure that the proposed thermal process is capable of producing a surface finish that is free of cracks or fissures and meets the required surface roughness criteria of the owner. Where the cut surface is exposed to a corrosive medium, corrosion testing or evaluations must also be performed. The qualification requirements of IWA-4461.4 are summarized below.
(a) The qualification test shall consist of two coupons of the same P-No. material to be cut in production.
(b) The qualification coupons shall be cut using the maximum heat input to be used in production.
(c) The thermally cut surface of each coupon shall be visually examined at 10X and shall be free of cracks. The owner shall specify surface roughness acceptable for the application and shall verify that the qualification coupon meets the criterion.
(d) Each qualification test coupon shall be cross-sectioned, and the exposed surfaces shall be polished, etched with a suitable etchant, and visually examined at 10X. All sectioned surfaces shall be free of cracks.
(e) Corrosion testing of the thermally cut surface and heat affected zone shall be performed if the cut surface is to be exposed to a corrosive media. Alternatively, corrosion resistance of the thermally cut surface may be evaluated. The owner shall specify the acceptance criteria.
In addition to the requirements of IWA-4461.4, SCE has also proposed to perform the following:
- 1. Determine the thickness of the resultant oxide layer on the cut surface by metallographic examination during the EDM process qualification.
- 2. Based upon the oxide thickness measurements obtained during the EDM qualification process, remove the oxide layer from cut or excavated surfaces when performing repair activities on RPV head penetration nozzles or J-welds.
Based on this proposal, the licensee concluded that their proposed alternative process would provide for an acceptable level of quality and safety with respect to the repair of the RVHP nozzles and welds.
3.3 Staff Evaluation Although considered a thermal process for removing metal since it uses an electrical arc, EDM leaves an extremely small oxide layer on the cut surface of the metal remaining after the removal process. The licensee has committed to removing that oxide layer by mechanical means after metal removal by the EDM process. The amount of metal removed will be determined by the qualification requirements of IWA-4461.4, ASME Section XI, 1995 Edition, 1997 Addenda, with the additional requirements that SCE will determine the thickness of the resultant oxide layer on the cut surfaces as part of the EDM qualification. The thickness of the resultant oxide layer will be determined by metallographic examination. Based on the oxide thickness measurements obtained during the EDM process qualification, post-EDM polishing operations will be performed to ensure that the oxide surface layer is removed. Therefore, the NRC staff has concluded that the qualification requirements of IWA-4461.4, with additional proposed conditions, meet the intent of IWA-4322 to ensure that thermally cut or excavated surfaces are free of unacceptable surface irregularities, oxides, and fissures created by the thermal removal process.
The NRC staff has evaluated the licensees request and supporting information to use Relief Request RVHP-3 for the EDM process for metal removal should repairs of RPV head penetration nozzles or J-groove welds become necessary at SONGS, Units 2 and 3 and concluded that it provides an acceptable alterative method of weld removal.
4.0 CONCLUSION
The NRC staff concludes that the licensees request and supporting information to use the EDM process for metal removal, should repairs of the RVHP nozzles or J-welds at SONGS, Units 2 and 3 be necessary, provides an acceptable alternative method of metal removal for weld repair or removal of weld crown surfaces of repair welds to facilitate performance of final NDE.
Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the relief request is authorized for the remainder of the terms of the current operating licenses since the applicant has demonstrated that the proposed alternative would provide an acceptable level of quality and safety.
Principal Contributor: W. Held Date: September 10, 2002