Letter Sequence Response to RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
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MONTHYEARML12285A2652012-10-0101 October 2012 Attachment 4 - MHI Document L5-04GA564 - Tube Wear of Unit-3 RSG, Technical Evaluation Report Project stage: Request ML12285A2672012-10-0101 October 2012 Attachment 4: SG Tube Wear Analysis for Unit-2/3 Project stage: Request ML12285A2662012-10-0101 October 2012 Attachment 4: Appendix-2 Attachment-1, Tube-to-TSP Wear Depth Diagram for Unit-2/3 Project stage: Request ML12285A2642012-10-0101 October 2012 Attachment 3 - Areva Document 51-9180143-001 - SONGS Unit 3 February 2012 Leaker Outage Steam Generator Condition Monitoring Report Project stage: Request ML12285A2682012-10-0202 October 2012 Attachment 6 - Appendix B: SONGS U2C17 - Steam Generator Operational Assessment for Tube-to-Tube Wear Project stage: Request ML12285A2692012-10-0202 October 2012 Attachment 6: Appendix a: Estimates of FEI-Induced Ttw Rates Project stage: Request ML12285A2632012-10-0303 October 2012 Confirmatory Action Letter - Actions to Address Steam Generator Tube Degradation Project stage: Request ML12338A1102012-11-30030 November 2012 Email, Request for Additional Information Southern California Edison'S Response to Nrc'S Confirmatory Action Letter (CAL) 4-12-001 Dated March 27, 2012 Project stage: RAI ML12341A1122012-12-0707 December 2012 Notice of Meeting with Southern California Edison to Discuss Its Response to Nrc'S Confirmatory Action Letter and Return to Service Report for San Onofre Nuclear Generating Station, Unit 2 Project stage: Meeting ML12347A0662012-12-0707 December 2012 Revised Notice of 12/18/12 Meeting with Southern California Edison to Discuss Its Response to Nrc'S Confirmatory Action Letter and Return to Service Report for San Onofre Nuclear Generating Station, Unit 2 Project stage: Meeting ML12345A4272012-12-10010 December 2012 Revised Email, Request for Additional Information Review of Southern California Edison'S Response to Nrc'S 3/27/2012 Confirmatory Action Letter (CAL) 4-12-001 and Return to Service Report Project stage: RAI ML12353A0972012-12-13013 December 2012 LTR-12-0795 - E-mail Don Leichtling Concerns Media Alert - Nuclear News - NRR Forthcoming Meeting with Southern California Edison Company Project stage: Meeting ML12352A3852012-12-18018 December 2012 Licensee Slides for 12/18/12 Public Meeting Project stage: Meeting ML12352A4112012-12-18018 December 2012 NRC Slides for 12/18/12 Meeting with Southern California Edison Project stage: Meeting ML12356A1982012-12-20020 December 2012 Email, Request for Additional Information, Round 3, Review of Southern California Edison'S Response to Nrc'S 3/27/2012 Confirmatory Action Letter (CAL) 4-12-001 and Return to Service Report Project stage: RAI ML13009A3492013-01-0808 January 2013 Response to Request for Additional Information Regarding Confirmatory Action Letter Response Project stage: Response to RAI ML13014A2512013-01-0909 January 2013 Response to Request for Additional Information (RAI 30) Regarding Confirmatory Action Letter Response Project stage: Response to RAI ML13014A2492013-01-0909 January 2013 Response to Request for Additional Information (RAI 15) Regarding Confirmatory Action Letter Response Project stage: Response to RAI ML13015A0042013-01-10010 January 2013 Response to Request for Additional Information (RAI 16), Regarding Confirmatory Action Letter Response (TAC No. Me 9727) Project stage: Response to RAI ML13022A0882013-01-16016 January 2013 Response to Request for Additional Information (RAI 19) Regarding Confirmatory Action Letter Response (TAC No. Me 9727) Project stage: Response to RAI ML13022A4132013-01-17017 January 2013 Response to Request for Additional Information (RAIs 10 and 17) Regarding Confirmatory Action Letter Response Project stage: Response to RAI ML13022A4812013-01-18018 January 2013 Response to Request for Additional Information (RAI 13), Regarding Confirmatory Action Letter Response Project stage: Response to RAI ML13022A4082013-01-18018 January 2013 Response to Request for Additional Information (RAI 12), Regarding Confirmatory Action Letter Response (TAC No. Me 9727) Project stage: Response to RAI ML13022A4112013-01-21021 January 2013 Response to Request for Additional Information (RAI 11) Regarding Confirmatory Action Letter Response (TAC Me 9727) Project stage: Response to RAI ML13022A4052013-01-21021 January 2013 Response to Request for Additional Information (RAI 28), Regarding Confirmatory Action Letter Response (TAC No. Me 9727) Project stage: Response to RAI ML13028A0982013-01-24024 January 2013 Response to Request for Additional Information (RAI 18) Regarding Confirmatory Action Letter Response Project stage: Response to RAI ML13028A4752013-01-25025 January 2013 Response to Request for Additional Information (RAI 27) Regarding Confirmatory Action Letter Project stage: Response to RAI ML13028A4742013-01-25025 January 2013 Response to Request for Additional Information (RAIs 5, 7, and 9) Regarding Confirmatory Action Letter Response Project stage: Response to RAI ML13032A0092013-01-29029 January 2013 Response to Request for Additional Information (RAI 14) Regarding Confirmatory Action Letter Response (TAC No. Me 9727) Project stage: Response to RAI ML13037A1122013-01-31031 January 2013 Response to Request for Additional Information (RAI 29) Regarding Confirmatory Action Letter Response Project stage: Response to RAI ML13053A3672013-02-0101 February 2013 E-mail, Draft Request for Additional Information Southern California Edison'S Response to Nrc'S Confirmatory Action Letter Project stage: Draft RAI ML13038A0102013-02-0404 February 2013 Response to Request for Additional Information (RAI 8) Regarding Confirmatory Action Letter Response Project stage: Response to RAI ML13038A0092013-02-0404 February 2013 Response to Request for Additional Information (RAI 6) Regarding Confirmatory Action Letter Response Project stage: Response to RAI ML13039A2782013-02-0606 February 2013 Response to Request for Additional Information (RAIs 20, 21, 22, 23, 24, 26 & 31), Confirmatory Action Letter Project stage: Response to RAI ML13039A3172013-02-0707 February 2013 Response to Request for Additional Information (RAI 25) Regarding Confirmatory Action Letter Response Project stage: Response to RAI ML13050A1892013-02-14014 February 2013 Supplemental Document Submittal Regarding Confirmatory Action Letter Response, Concerning Steam Generator Tubes Project stage: Supplement ML13051A1972013-02-15015 February 2013 Enclosure 6, LTR-SGDA-12-36, Rev. 3, Flow-Induced Vibration and Tube Wear Analysis of the San Onofre Nuclear Generating Station Unit 2 Replacement Steam Generators Supporting Restart. Cover Through Page 227 of 415 Project stage: Other ML13051A1992013-02-15015 February 2013 Enclosure 6, LTR-SGDA-12-36, Rev. 3, Flow-Induced Vibration and Tube Wear Analysis of the San Onofre Nuclear Generating Station Unit 2 Replacement Steam Generators Supporting Restart. Page 228 of 415 Through End Project stage: Other ML13046A1232013-02-15015 February 2013 2/27/2013 Notice of Forthcoming Meeting with Southern California Edison Company to Discuss Confirmation Action Letter Project stage: Meeting ML13051A1932013-02-18018 February 2013 Enclosure 5, L5-04GA585, Rev. 2, Analytical Evaluations for Operational Assessment Project stage: Other ML13051A1922013-02-18018 February 2013 Enclosure 4, L5-04GA567, Rev. 6, Evaluation of Stability Ratio for Return to Service Project stage: Other ML13051A1902013-02-18018 February 2013 Supplemental Document Submittal Regarding Confirmatory Action Letter Response to Address Steam Generator Tube Degradation Project stage: Supplement ML13056A0922013-02-20020 February 2013 Email, Draft Request for Additional Information Nos. 38-52, Southern California Edison'S Response to Nrc'S Confirmatory Action Letter Project stage: Draft RAI ML13053A1732013-02-21021 February 2013 Email, Draft Request for Additional Information, Nos. 53-67, Southern California Edison'S Response to Nrc'S Confirmatory Action Letter Project stage: Draft RAI ML13053A1842013-02-21021 February 2013 Draft Request for Additional Information, Nos. 53-67, Southern California Edison'S Response to Nrc'S Confirmatory Action Letter Project stage: Draft RAI ML13058A0262013-02-25025 February 2013 Response to Request for Additional Information (Rals 2, 3, and 4) Regarding Confirmatory Action Letter Response (TAC No. Me 9727) Project stage: Response to RAI ML13056A6012013-02-25025 February 2013 Response to Request for Additional Information (RAI 32) Regarding Confirmatory Action Letter Response Project stage: Response to RAI ML13059A1572013-02-27027 February 2013 Licensee Slides from 2/27/13 Meeting Regarding a Request for Additional Information Project stage: Meeting ML13059A1522013-02-27027 February 2013 NRC Meeting Slides from 2/27/13 Public RAI Meeting Project stage: RAI ML13074A7932013-03-14014 March 2013 Operational Assessment for 100% Power Case Regarding Confirmatory Action Letter Response Project stage: Other 2013-01-25
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Category:Graphics incl Charts and Tables
MONTHYEARML20034D9072020-02-0303 February 2020 Mesa Locations Summary Table 2 ML20034D9062020-02-0303 February 2020 Mesa Event Summary Table 1 ML20034E6052018-07-23023 July 2018 SONGS - Mesa Navy All Parcels Fig1_v9 ML20034D9472016-05-16016 May 2016 Mesa Master Sample Locations Lat-Lon ML20034D9482016-05-16016 May 2016 Soil Sample Gps Coordinates ML20034E4982016-05-16016 May 2016 Memo to File Mesa Assessment Event Summary Table 1 ML20034D9152016-05-16016 May 2016 Table 2 Mesa Survey Plan Vs Actual Summary ML20034D9142016-05-16016 May 2016 Table 1 Mesa Survey Plan Summary ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML20034E5002015-05-28028 May 2015 Memo to File Mesa Assessment Locations Summary Table 2 ML14351A0782014-12-15015 December 2014 Redacted Version of Response to Request for Additional Information Proposed Exemptions from Certain Portions of 10 CFR 50.47 and Appendix E ML13063A4422013-02-27027 February 2013 LTR-13-0183 - E-mail Don Leichtling Media Alert - Chart of Three Modes of San Onofre Unit 2 Operation, 100%, 70% and MSLB with Multiple Tube Failures ML13009A3492013-01-0808 January 2013 Response to Request for Additional Information Regarding Confirmatory Action Letter Response ML12194A1362012-07-12012 July 2012 SONGS, Steam Generator Tube, Unit 2, Wear Data 7-12-12 ML12194A1632012-07-12012 July 2012 SONGS, Unit 3 Steam Generator Tube Wear Data 7-12-12 ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML1019004182010-06-28028 June 2010 Quick View Chart ML0825503212008-04-17017 April 2008 Table for AST Methodology Issue (Email) ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0631904142006-11-0808 November 2006 Oak Ridge Institute for Science and Education (Orise); Ltr. Dated 11/08/2006; Analytical Results for Soil & Water Samples Associated with the San Onofre Nuclear Generating Station, San Clemente, California on 10/13/2006 (IR #050-00206/06-01 ML0632500232006-10-30030 October 2006 11-2006 Draft-Outlines ML0632500712006-10-30030 October 2006 11-2006-Draft-Written-Exam-Comments ML0632502792006-10-30030 October 2006 11-2006-Draft-Operating-Exam-Comments ML0612902272005-04-0101 April 2005 04-2005-Written Exam Comments ML0434101252004-12-0202 December 2004 Additional Information Supporting the Third Ten-Year Inservice Inspection (ISI) Interval Relief Requests ISI-3-11, Revision 1 and ISI-3-12 to Support Pressurizer Heater Sleeve Repairs ML0416002992004-06-0303 June 2004 60-day Post Refueling Outage Reactor Pressure Vessel Head Inspection Report for San Onofre, Unit 2 2020-02-03
[Table view] Category:Legal-Affidavit
MONTHYEARML22062B0282022-02-28028 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) ML22059B0422022-02-23023 February 2022 International, Affidavit ML21355A2432021-11-11011 November 2021 (Songs), Independent Spent Fuel Storage Installation (ISFSI) - Request for Exemption from 10 CFR 72.106(b) - Affidavit ML19214A1432019-07-31031 July 2019 Transmittal of CEN-283(S)-P/NP, Part 1, Statistical Combination of Uncertainties Part 1; Combination of System Parameter Uncertainties in Thermal Margin Analyses for San Onofre Nuclear Units 2 and 3, and CEN-283(S)-P/NP, Part 2, Statistical ML13085A0412013-03-22022 March 2013 Response to Request for Additional Information (RAI 50) Regarding Confirmatory Action Letter Response ML13080A4132013-03-20020 March 2013 Response to Request for Additional Information (RAIs 38, 40, 41, 57, 59, 60, and 63-67) Regarding Confirmatory Action Letter Response ML13050A1892013-02-14014 February 2013 Supplemental Document Submittal Regarding Confirmatory Action Letter Response, Concerning Steam Generator Tubes ML13014A2492013-01-0909 January 2013 Response to Request for Additional Information (RAI 15) Regarding Confirmatory Action Letter Response ML13009A3492013-01-0808 January 2013 Response to Request for Additional Information Regarding Confirmatory Action Letter Response ML12348A2872012-11-28028 November 2012 Confirmatory Action Letter Response - Proprietary Documents ML11215A0902011-07-29029 July 2011 Proposed Permanent Exemption Request and Proposed Change Number (PCN) 600, Amendment Application Numbers 261 and 249, Request for Unrestricted Use of Areva Fuel ML0601901072005-12-14014 December 2005 Non-Proprietary Rev. 0 to LTR-RCPL-05-153, Response to NRC Request for Additional Information on WCAP-16005-NP, Rev. 03, 'San Onofre Nuclear Generating Station Unit 2 RCS Pressure & Temperature Limits Report' & WCAP-16167-NP, Rev. 0. ML0515301212005-05-27027 May 2005 Southern California Edison (SCE) Requests an Amendment to Facility Operating Licenses NPF-10 and NPF-15 for the San Onofre Nuclear Generating Station, Units 2 and 3 (SONGS 2&3) by Approving a Change in the SONGS Physical Security Plan (PSP) ML0508705352005-03-24024 March 2005 Proposed Change Number (PCN) 559 Request to Implement Technical Specification Task Force Items Related to Cycle Specific Values and Shutdown Margin San Onofre Nuclear Generating Station Units 2 and 3 ML0436504032004-12-27027 December 2004 Proposed Change Number (PCN) 555 Alternative Source Term ML15350A2151985-09-0505 September 1985 Overview Description of Core Operating Limit Supervisory System (Colss)(Rev 00-NP to CEN-312-NP) 2022-02-28
[Table view] 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
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SOUTHERN CALIFORNIA Richard J. St. Onge 1E D IS O N Proprietary Information Withhold from Public Disclosure Director, Nuclear Regulatory Affairs and Emergency Planning An EDISON INTERNATIONAL Company January 8, 2013 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Docket No. 50-361 Response to Request for Additional Information (RAI 1)
Regarding Confirmatory Action Letter Response (TAC No. ME 9727)
San Onofre Nuclear Generating Station, Unit 2
References:
- 1. Letter from Mr. Elmo E. Collins (USNRC) to Mr. Peter T. Dietrich (SCE), dated March 27, 2012, Confirmatory Action Letter 4-12-001, San Onofre Nuclear Generating Station, Units 2 and 3, Commitments to Address Steam Generator Tube Degradation
- 2. Letter from Mr. Peter T. Dietrich (SCE) to Mr. Elmo E. Collins (USNRC), dated October 3, 2012, Confirmatory Action Letter - Actions to Address Steam Generator Tube Degradation, San Onofre Nuclear Generating Station, Unit 2
- 3. Letter from Mr. James R. Hall (USNRC) to Mr. Peter T. Dietrich (SCE), dated December 26, 2012, Request for Additional Information Regarding Response to Confirmatory Action Letter, San Onofre Nuclear Generating Station, Unit 2
Dear Sir or Madam,
On March 27, 2012, the Nuclear Regulatory Commission (NRC) issued a Confirmatory Action Letter (CAL) (Reference 1) to Southern California Edison (SCE) describing actions that the NRC and SCE agreed would be completed to address issues identified in the steam generator tubes of San Onofre Nuclear Generating Station (SONGS) Units 2 and 3. In a letter to the NRC dated October 3, 2012 (Reference 2), SCE reported completion of the Unit 2 CAL actions and included a Return to Service Report (RTSR) that provided details of their completion.
By letter dated December 26, 2012 (Reference 3), the NRC issued Requests for Additional Information (RAIs) regarding the CAL response. Enclosure 2 of this letter provides the response to RAI 1.
Enclosure 2 of this submittal contains proprietary information. SCE requests that this proprietary enclosure be withheld from public disclosure in accordance with 10 CFR 2.390(a)(4).
Enclosure 1 provides notarized affidavits from Mitsubishi Heavy Industries (MHI) and AREVA, which set forth the basis on which the information in Enclosure 2 may be withheld from public Proprietary Information Withhold from Public Disclosure P.O. Box 128 Decontrolled Upon Removal From Enclosure 2 San Clemente, CA 92672
Proprietary Information Withhold from Public Disclosure Document Control Desk January 8, 2013 disclosure by the NRC and address with specificity the considerations listed by paragraph (b)(4) of 10 CFR 2.390. Proprietary information identified in Enclosure 2 was extracted from MHI Report L5-04GA567, Evaluation of Stability Ratio for Return to Service and AREVA report 51-9187230, SONGS U2C1 7 Steam Generator Operational Assessment for Tube-to-Tube Wear, which are addressed in the affidavits. Enclosure 3 provides the non-proprietary version of Enclosure 2.
There are no new regulatory commitments contained in this letter. If you have any questions or require additional information, please call me at (949) 368-6240.
Sincerely,
Enclosures:
- 1. Notarized Affidavits
- 2. Response to RAI 1 (Proprietary)
- 3. Response to RAI 1 (Non-proprietary) cc: E. E. Collins, Regional Administrator, NRC Region IV R. Hall, NRC Project Manager, San Onofre Units 2 and 3 G. G. Warnick, NRC Senior Resident Inspector, San Onofre Units 2 and 3 R. E. Lantz, Branch Chief, Division of Reactor Projects, NRC Region IV Proprietary Information Withhold from Public Disclosure Decontrolled Upon Removal From Enclosure 2
ENCLOSURE 1 Notarized Affidavits
MITSUBISHI HEAVY'INDUSTRIES, LTD.
AFFIDAVIT I, Jinichi.Miyaguchi, state as follows:
- 1. i am Director, Nuclear Plant Component Designing Department, of Mitsubishi Heavy
.Industries, Ltd. ("MHI"), and *have been delegated the function of reviewing the referenced MHI technical documentationto determine whether itcontains information that should be withheld from public disclosure pursuant to 10 C.F.R. § 2.390 (a)(4) as trade secrets and commercial or financial information that is privileged or confidential.
- 2. In accordance with my responsibilities, I have, determined that the following MHI document contains MHI proprietary information that should be withheld from public.
disclosure pursuant to 10 C.F.. § 2.390 (a)(4).. Those pages of the document containing proprietary information. have been bracketed with an open and closed bracket as shown.
here"[ ]"/and should be withheld from public disclosure.
MHI document Document; L5-04GA567
- 3. The information identified as proprietary in the enclosed document has in the past been, and will continue to be, held in confidence by MHI and its disclosure outside the company is limited to regulatory bodies, customers and potential customers, and their agents, suppliers, and licensees, and others witha legitimate need for the information, and is always subject to suitable measures to protect it from unauthorized Use. or disclosure.
- 4. The basis for holding the referenced information confidential is that it describes unique design, manufacturing, experimental and investigative information developed by MHI and not, used in the exact form by any of MHr's competitors. This information was developed at significant cost to MHI, since it is the result of an intensive MHI effort.
- 5. The referenced information was :furnished to the :Nuclear Regulatory Commission
("NRC") in confidence and, solely for the purpose of information to the NRC staff.
- 6. The referenced information is not available in public~sources and could not begathered readily from other publicly available information. Other than through the provisions in
paragraph 3 above, MHI knows of no way the information could be lawfully acquired by organizations or individuals outside of MHI.
- 7. Public disclosure of the referenced information would assist competitors of MHI intheir design and manufacture .of nuclear plant components without incurring the costs or risks associated with the design and the manufacture of the subject component. Therefore, disclosure of the information :contained in the referenced document would have the following negative impacts on the competitive position of MHI in the U.S. and world.
nuclear markets:
A. Loss of competitive advantage due to the costs associated with development of technologies relating to *he component design, manufacture and examination.
Providing public access to such information permits competitors to duplicate or mimic the methodology without incurring the associated costs, B. Loss of competitive advantage of MHI's ability to supply replacement or new heavy components such as steam generators.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct .to the best of my knowledge, information and belief.
Executed on this day of 2012.
JinichiMygci Director- Nuclear Plant Component Designing Department Mitsubishi Heavy Industries, LTD Sworn to and subscribed Before me this /5/ day SP14.2012
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, 12 Notary Public My Commission Expires
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Registered Number 27 7 Date SEP, 14,2012 NOTARIAL CERTIFICATE This is to certify that JINICHI MIYAGUCHI. , Director-Nuclear Plant Component Designing Department MITSUBISHI HEAVY INDUSTRIES, LTD has affixed his signature in my very presence to the. attached document.
MASAHIKO KUBOTA Notary 44 Akas'himachi,Chuo-Ku,
.Kobe, Japan Kobe District Legal Affairs Bureau (Efl 2)
AFFIDAVIT COMMONWEALTH OF VIRGINIA )
) ss.
COUNTY OF CAMPBELL )
- 1. My name is Gayle F. Elliott. I am Manager, Product Licensing, for AREVA NP Inc. (AREVA NP) and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by AREVA NP to determine whether certain AREVA NP information is proprietary. I am familiar with the policies established by AREVA NP to ensure the proper application of these criteria.
- 3. I am familiar with the AREVA NP information contained in the Southern California Edison document entitled "SONGS U2C17 Steam Generator Operational Assessment," dated October 2012, and referred to herein as "Document." Information contained in this Document has been classified by AREVA NP as proprietary in accordance with the policies established by AREVA NP for the control and protection of proprietary and confidential information.
- 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA NP and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
- 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is
requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information".
- 6. The following criteria are customarily applied by AREVA NP to determine whether information should be classified as proprietary:
(a) The information reveals details of AREVA NP's research and development plans and programs or their results.
(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA NP.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA NP in product optimization or marketability.
(e) The information is vital to a competitive advantage held by AREVA NP, would be helpful to competitors to AREVA NP, and would likely cause substantial harm to the competitive position of AREVA NP.
The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b) and 6(c) above.
- 7. In accordance with AREVA NP's policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside AREVA NP only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. AREVA NP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
SUBSCRIBED before me this .?
day of ' 2012.
Kathleen A. Bennett NOTARY PUBLIC, COMMONWEALTH OF VIRGINIA MY COMMISSION EXPIRES: 8/31/2015 Reg. #110864 KATHLEEN ANN BENNETT Notary Public .
,1 Commonwealth of Virginia 1 110864 MY Commission Expires Aug 31, 207 1
ENCLOSURE 3 SOUTHERN CALIFORNIA EDISON RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSE TO CONFIRMATORY ACTION LETTER DOCKET NO. 50-361 TAC NO. ME 9727 Response to RAI 1 (NON-PROPRIETARY)
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RAI 1
The Operational Assessment (OA) in Attachment 6, Appendix A (Reference 2), reports the 3 times normal operating pressure differential as being 4290 psi for 100% power conditions. This is the same value assumed in the Condition Monitoring Assessment provided in Attachment 2.
This value is significantly higher than the values ranging from 3972-3975 psi for 100% power reported in Attachment 6, Appendices B, C, and D (References 3-5). Describe the reason for the differences.
RESPONSE
Table 1 summarizes the bases for the values of 3 times normal operating pressure differential (3xNOPD) used in each operational assessment (OA). Steam generator (SG) secondary side pressure, and consequently the 3xNOPD, is influenced by power, TCOLD (see discussion at end of this response), and SG tube plugging. Each of the OAs assumes a different set of relevant conditions in their respective analysis. The reference numbers in the discussion below correspond to the RAI reference numbers.
Reference 2 (AREVA document number 51-9182833-002, SONGS U2C17 Outage - Steam GeneratorOperationalAssessment) assesses tube integrity due to all wear mechanisms, with the exception of tube-to-tube wear (TTW). The OA analysis uses a 3xNOPD equal to 4290 psid, which was selected to bound the potential operating conditions for the next operating interval including possible changes due to tube plugging and/or a decrease in power level. As shown in Table 1, the NOPD is based on the operating pressures in the SGs during the previous operating cycle, which included operation at 100% power, increased TCOLD, and no tube plugging (same conditions used in SONGS 2C17 Steam GeneratorCondition Monitoring Report). The 0% plugging condition is bounding because as plugging increases, secondary side pressure increases reducing NOPD.
Reference 3 (AREVA document number 51-9187230-000, SONGS U2C17 Steam Generator OperationalAssessment for Tube-to-Tube Wear) uses a conservative approach to demonstrate that TTW due to fluid elastic instability will be prevented while operating at 70% power. This OA utilizes probability of stability rather than 3xNOPD to determine SG inspection interval.
However, the defense in depth section of this OA uses a 3xNOPD equal to [ ] psid, which is derived from the secondary side pressure in Table 6.2-1 "Basic parameters for calculation for 2A SG evaluation after plugging" of MHI document L5-04GA567 R6. It is based on operation at 70% power, increased TCOLD, and approximately 3% tube plugging. When power level is decreased, the secondary side pressure increases resulting in a reduction in differential pressure.
Reference 4 (APTECH OA document number AES 12068150-2Q-1, OperationalAssessment for SONGS Unit 2 Steam Generatorsfor Upper Bundle Tube-to-Tube Wear Degradationat End of Cycle 16) uses established industry methods to predict TTW degradation based on Unit 3 TTW data and a 70% power. The table in Section 4.2 of Reference 4 lists three values of NOPD. The NOPD of [ ] psid (3xNOPD = [ ] psid) was used for the OA analysis, which was the same value used in Reference 3 and described above. The other two NOPD values in the Section 4.2 table were not used in the OA analysis. The first value of NOPD equal to [
psid (3xNOPD = [ ] psid) is for Cycle 16 actual secondary side pressures at 100% power.
The second value of NOPD equal to [ ] psid (3xNOPD = [ ] psid) was based on secondary side pressure of [ ] psia (rounded to [ ] psia, conservative) at 100% power, increased TCOLD, and approximately 3% tube plugging.
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Reference 5 (Westinghouse OA document number SG-SGMP-1 2-10, Rev 3, Operational Assessment of Wear Indications in the U-bend Region of San Onofre Nuclear Generating Station Unit 2 Replacement Steam Generators)uses a 3xNOPD equal to [ I psid. This OA uses the 100% power NOPD, which is derived from the secondary side pressure in Table 6.2-1 "Basic parameters for calculation for 2A SG evaluation after plugging" of MHI Document L5-04GA567 R4, and is based on operation at 100% power, increased TCOLD, and approximately 3% tube plugging.
At the end of Cycle 16, the Unit 2 original reactor vessel head (ORVH), comprised of Alloy 600, was replaced with a replacement reactor vessel head (RRVH), comprised of Alloy 690, due to Alloy 690's enhanced resistance to stress corrosion cracking (SCC) at elevated temperatures.
Prior to the reactor vessel head replacement, TCOLD had been lowered to reduce Alloy 600's susceptibility to SCC. Increasing TCOLD increases secondary side pressure and decreases NOPD. With the installation of the RRVH, TCOLD will be increased to a nominal value of [ ] OF, reducing effective velocities and increasing margin to fluid elastic instability.
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Table 1 Summary of 3xNOPD Differences in Operational Assessments RTSR Attachment 6, RTSR Attachment 6, RTSR Attachment 6, RTSR Attachment 6, Appendix A Appendix B Appendix C Appendix D (RAI Reference 2) (RAI Reference 3) (RAI Reference 4) (RAI Reference 5)
Primary Side 2250 2250 2250 2250 Pressure (psia)
Secondary Side 820 Pressure (psia)
NOPD 1430 [ ] [ ] [ ]
(psid) 3xNOPD 4290 [ ] [ ]
(psid)
Power Level 100 70 70 100
(%)
Plugging 0 =3 3 3
(%)
TCOLD 541 [ ] [ ] [
(°F)
Summary of NOPD is based on operating NOPD based on 70% NOPD based on 70% NOPD based on 100%
Operating pressures in the SGs during the power at increased power at increased power at increased Parameters Used previous operating cycle at 100% TcOLD with approximately TCOLD with approximately TCOLD with approximately and basis power and reduced TCOLD. Parameters 3% tube plugging. 3% tube plugging. 3% tube plugging.
were selected to bound possible conditions for the next operating cycle at the time the document was issued.
The 0% plugging condition is bounding because as plugging increases, secondary side pressure increases reducing NOPD.
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