Letter Sequence RAI |
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TAC:MC8850, Steam Generator Tube Integrity (Approved, Closed) TAC:MC8851, Steam Generator Tube Integrity (Approved, Closed) |
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MONTHYEARML0603202882006-01-26026 January 2006 Westinghouse Electric Company Request for Withholding Information (WCAP-16208-P, Rev. 1, Suppl. 1) from Public Disclosure Project stage: Withholding Request Acceptance ML0608300242006-03-23023 March 2006 Request for Additional Information on the Proposed C* Amendment for Steam Generator Tube Inspection and Repair in the Tubesheet Project stage: RAI ML0612403262006-04-30030 April 2006 LTR-CDME-06-27-NP, Revision 0, Responses to NRC Request for Addition Information on License Amendment Request for Proposed Technical Specification Change Regarding Repair Criteria and Inspection Depth for Steam Generator Tubes.. Project stage: Request ML0612403202006-05-0101 May 2006 Response to Request for Additional Information and Submittal of Supplement 1 to Proposed Change Number NPF-10/15-565, License Amendment Request, Proposed Technical Specification Change.. Project stage: Supplement ML0617400372006-06-21021 June 2006 SONGS, RAI on the Proposed C* Amendment for Steam Generator Tube Inspection and Repair in the Tubesheet Project stage: RAI ML0623401462006-08-15015 August 2006 Response to Request for Additional Information and Submittal of Supplement 2 to Proposed Change Number NPF-10/15-585 License Amendment Request, Proposed Technical Specification.... Project stage: Supplement ML0628300302006-10-0505 October 2006 Submittal of Supplement 3 to Proposed Change Number NPF-10/15-565 License Amendment Request, Proposed Technical Specification Change, Define the Extent of the Required Tube Inspections and Repair Criteria within the Tubesheet. Project stage: Supplement ML0629704442006-11-0909 November 2006 Issuance of Amendments 206 and 198 Change, Define Extent of the Required Tube Inspections, and Repair Criteria within the Tubesheet Region of the Steam Generators Project stage: Approval ML0631304962006-11-0909 November 2006 Tech Spec Pages for Amendments 206 and 198 Change, Define Extent of the Required Tube Inspections, and Repair Criteria within the Tubesheet Region of the Steam Generators Project stage: Other 2006-03-23
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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:Request for Additional Information (RAI)
MONTHYEARML21117A3492021-03-30030 March 2021 March 30, 2021, Email from Public Watchdogs on Providing New Information to Its October 13, 2020, 2.206 Petition ML21068A2722021-03-0909 March 2021 SONGS Endangered Species Act Additional Information Request ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML18193A2002018-07-19019 July 2018 SONGS ISFSI Only Dqap RAI ML15083A4552015-03-27027 March 2015 and Independent Spent Fuel Storage Installation - Request for Additional Information Decommissioning Quality Assurance Program Review ML15071A1842015-03-19019 March 2015 Independent Spent Fuel Storage Installation - Request for Additional Information Regarding the 10 CFR 50.54(p) Changes to the Security Plans ML15042A3942015-01-23023 January 2015 NRR E-mail Capture - SONGS - Draft RAI Permanently Defueled Technical Specifications License Amendment Request ML15033A0522014-12-11011 December 2014 NRR E-mail Capture - SONGS - Draft RAI Permanently Defueled Technical Specifications License Amendment Request ML14248A5902014-09-18018 September 2014 Independent Spent Fuel Storage Installation - Request for Additional Information, Amendment Request to Revise Emergency Plan to Support Permanently Defueled Condition ML14248A5602014-09-18018 September 2014 Independent Spent Fuel Storage Installation - Request for Additional Information, Amendment Request to Revise Emergency Action Level Scheme to Support Permanently Defueled Condition ML14258A0172014-09-11011 September 2014 NRR E-mail Capture - SONGS - Revised Draft RAI Concerning TS Section 5 Administrative Controls License Amendment Request (TACs MF2954 and MF2955) ML14209A0052014-08-27027 August 2014 Request for Additional Information, Exemption Request from 10 CFR 50.47 and 10 CFR Part 50 Appendix E, Discontinue Offsite Emergency Planning Activities and Reduce Scope of Onsite Emergency Planning (TAC MF3835-MF3837) ML14139A4782014-06-0505 June 2014 Request for Additional Information, License Amendment Request to Revise Technical Specifications 5.1, 5.2, and 5.3 to Reflect Reduced Staffing/Training in Permanently Shutdown and Defueled Condition ML14093A6772014-05-0101 May 2014 SONGS - Request for Additional Information Concerning Pre-Emption Authority ML13352A0912013-12-30030 December 2013 Decommissioning Funding Status Report - Request for Additional Information ML13191A8372013-09-12012 September 2013 Request for Additional Information, Review of Decommissioning Funding Status Report ML13154A4312013-06-0404 June 2013 Rai'S Following Ifib Analysis of Edison'S 2013 Decommissioning Funding Status Report for San Onofre Units 2 and 3 ML13113A2562013-05-10010 May 2013 Request for Additional Information No. 73 Regarding Response to Confirmatory Action Letter ML13072A0542013-03-18018 March 2013 Redacted, Request for Additional Information, Nos. 33-67, Southern California Edison'S Response to Nrc'S Confirmatory Action Letter ML13074A6872013-03-15015 March 2013 Email, Draft Request for Additional Information, Nos. 68-72, Southern California Edison'S Response to Nrc'S Confirmatory Action Letter ML13053A1842013-02-21021 February 2013 Draft Request for Additional Information, Nos. 53-67, Southern California Edison'S Response to Nrc'S Confirmatory Action Letter 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 ML13053A3672013-02-0101 February 2013 E-mail, Draft Request for Additional Information Southern California Edison'S Response to Nrc'S Confirmatory Action Letter 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 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 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 ML12313A4752012-11-0808 November 2012 Request for Additional Information Email, Relief Request IST-4-P-2, ASME OM Code Requirements for Testing CSS and LPSI Pumps, Fourth 10-Year Inservice Inspection Interval ML12297A3972012-10-23023 October 2012 Request for Additional Information Email, Relief Request ISI-3-36, Reactor Coolant Pressure Boundary Testing, Third 10-Year Inservice Inspection Interval ML12283A2302012-10-0909 October 2012 Request for Additional Information Email, Round 3 W/Corrected Due Date, Request to Revise Technical Specification (TS) 2.1.1.2, TS 4.2.1, and TS 5.7.1.5, to Support Unrestricted Use of Areva Fuel ML12283A2252012-10-0909 October 2012 Request for Additional Information Email, Round 3, Request to Revise Technical Specification (TS) 2.1.1.2, TS 4.2.1, and TS 5.7.1.5, to Support Unrestricted Use of Areva Fuel ML12220A0492012-08-0707 August 2012 Request for Additional Information Email, Round 2, License Amendment Request to Revise Technical Specification (TS) 2.1.1.2, TS 4.2.1, and TS 5.7.1.5, to Support Unrestricted Use of Areva Fuel ML12207A2612012-08-0101 August 2012 Redacted, Request for Additional Information, License Amendment Request to Revise Technical Specification (TS) 2.1.1.2, TS 4.2.1, and TS 5.7.1.5, to Support Unrestricted Use of Areva Fuel ML12201A1552012-07-19019 July 2012 R. Onge Ltr Request for Additional Information Decommissioning Funding ML12056A0502012-03-12012 March 2012 Enclosure 4 - Recommendation 2.3: Flooding ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML1200603242012-01-19019 January 2012 Fleet, RAI, Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-789 (N-789) ML1126604602011-10-14014 October 2011 Request for Additional Information Regarding Use of American Concrete Institute Reports for Restoration of Unit 3 Containment ML11182C0322011-06-30030 June 2011 Notification of Inspection (Inspection Report 05000361; 05000362/2011004) and Request for Information ML1113003952011-05-10010 May 2011 Email, Draft Request for Additional Information, Review of Biennial Decommissioning Funding Status Report ML1113004002011-05-10010 May 2011 Draft Request for Additional Information, Review of Biennial Decommissioning Funding Status Report ML1112307842011-05-0303 May 2011 Draft Request for Additional Information, Relief Requests ISI-3-32 Through ISI-3-34, Alternative to Requirements for Examinations of Welds and Core Support Structure Surfaces, Third 10-Year Inservice Inspection ML1106006612011-03-0101 March 2011 Draft Generic Request for Additional Information, License Amendment Request to Revise License Condition and Approve Cyber Security Plan ML1024301262010-08-31031 August 2010 Request for Additional Information Relief Request ISI-3-31 ML1022404532010-08-11011 August 2010 Draft Request for Additional Information LAR on Fuel Assembly Movement ML0933601212009-12-0202 December 2009 Request for Additional Information Relief Request ISI-3-30 ML0831705532008-12-0808 December 2008 Request for Additional Information, License Amendment Request to Support Replacement Steam Generators ML0831901202008-11-26026 November 2008 Request for Additional Information Test Protocol Used in the Testing at Vuez 2021-03-09
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Text
March 23, 2006Mr. Richard M. RosenblumSenior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station
P.O. Box 128 San Clemente, CA 92674-0128
SUBJECT:
SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 - REQUEST FOR ADDITIONAL INFORMATION ON THE PROPOSED C*
AMENDMENT FOR STEAM GENERATOR TUBE INSPECTION AND REPAIR IN THE TUBESHEET (TAC NOS. MC8850 and MC8851)
Dear Mr. Rosenblum:
By letter dated November 3, 2005 (Agencywide Documents Access and Management SystemAccession No. ML053110284), Southern California Edison submitted an application to change the San Onofre Nuclear Generating Station, Units 2 and 3, technical specifications related tosteam generator tube inspection. The changes would define the depth of the required tubeinspections and plugging criteria within the tubesheet.After reviewing your request, the Nuclear Regulatory Commission staff has determined thatadditional information is required to complete the review. We discussed this information with your staff by telephone and they agreed to provide the additional information requested in the enclosure by April 30, 2006. If you have any questions, please contact me at (301) 415-1480.Sincerely,/RA/N. Kalyanam, Project ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-361 and 50-362
Enclosure:
Request for Additional Information cc w/encl: See next page March 23, 2006Mr. Richard M. RosenblumSenior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station
P.O. Box 128 San Clemente, CA 92674-0128
SUBJECT:
SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 - REQUEST FOR ADDITIONAL INFORMATION ON THE PROPOSED C*
AMENDMENT FOR STEAM GENERATOR TUBE INSPECTION AND REPAIR IN THE TUBESHEET (TAC NOS. MC8850 and MC8851)
Dear Mr. Rosenblum:
By letter dated November 3, 2005 (Agencywide Documents Access and Management SystemAccession No. ML053110284), Southern California Edison submitted an application to change the San Onofre Nuclear Generating Station, Units 2 and 3, technical specifications related tosteam generator tube inspection. The changes would define the depth of the required tubeinspections and plugging criteria within the tubesheet.After reviewing your request, the Nuclear Regulatory Commission staff has determined thatadditional information is required to complete the review. We discussed this information with your staff by telephone and they agreed to provide the additional information requested in the enclosure by April 30, 2006. If you have any questions, please contact me at (301) 415-1480.Sincerely,/RA/
N. Kalyanam, Project ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-361 and 50-362
Enclosure:
Request for Additional Information cc w/encl: See next pageDISTRIBUTIONPUBLICLPLIV r/fRidsNrrDorl (CHaney/CHolden)RidsNrrDorlLplg (DTerao)RidsNrrPMNKalyanamRidsNrrLALFeizollahiRidsNrrDciCsgbRidsAcrsAcnwMailCenterRidsOgcRpRidsRgn4MailCenter (TPruett)RidsNrrDorlDpr GMakar ACCESSION NO: ML060830024* No major change from Staff provided RAIOFFICENRR/LPL4/PMNRR/LPL4/LANRR/DE/EEEB*NRR/LPL4/BCNAMENKalyanamLFeizollahiAHiserDTeraoDATE3/22/063/22/063/26/063/23/06OFFICIAL RECORD COPYDOCUMENT NAME: E:\Filenet\ML060830024.wpd REQUEST FOR ADDITIONAL INFORMATIONLICENSE AMENDMENT REQUEST FOR PROPOSED TECHNICAL SPECIFICATIONCHANGE REGARDING REPAIR CRITERIA AND INSPECTION DEPTH FOR STEAMGENERATOR TUBES WITHIN THE TUBESHEET REGIONSOUTHERN CALIFORNIA EDISONSAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3DOCKET NOS. 50-361 AND 50-362By letter dated November 3, 2005 (Agencywide Documents Access and Management System(ADAMS) Accession No. ML053110284), Southern California Edison submitted an application to change the San Onofre Nuclear Generating Station (SONGS), Units 2 and 3, technicalspecifications (TS) related to steam generator tube inspection. The changes would define the depth of the required tube inspections and plugging criteria within the tubesheet, with the depthof inspection defined as "C*" ("C-star"). The technical basis for these changes was initiallydocumented for the hot leg in Westinghouse topical report WCAP-16208-P, Revision 0, "NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions," dated October 2004. In a letter dated December 16, 2004 (ADAMS Accession No. ML043510406), the NuclearRegulatory Commission (NRC) staff requested additional information from Florida Power andLight (FPL) about their C* amendment application for St. Lucie, Unit 2. FPL's response to this request was issued March 31, 2005 (ADAMS Accession No. ML050960517), and Revision 1 of WCAP-16208-NP was subsequently issued in May 2005 (ADAMS Accession No. ML051520417).
The licensee for SONGS, Units 2 and 3, referenced WCAP-16208, Revision 1, and submitted a Supplement 1, which applies the C* methodology in the cold leg of the SONGS, Units 2 and 3,steam generators.In order to complete its review of the license amendment for SONGS, Units 2 and 3, the NRCstaff needs the additional information requested below.1.Please confirm that your operating parameters (e.g., temperature, pressure, etc.)
willalways be conservatively bounded by the conditions for which the hot-leg and cold-leg C* distances were determined in WCAP-16208-P, Revision 1 (including Supplement 1).
If the conditions will not always be bounded, what controls are in place to ensure anadequate depth of inspection in the tubesheet?For example, please confirm that the hot-leg temperature at SONGS, Unit 2 and 3, isgreater than that assumed (600 degrees Fahrenheit) in the tubesheet deflectionanalyses and in determining the increase in contact pressure as a result of differential thermal expansion between the tube and the tubesheet. If the hot-leg temperature ineither unit is lower than 600 degrees, please discuss the effect on the C* distance. 2.The SONGS, Units 2 and 3, currently allow the installation of leak-tight sleevesaccording to Asea Brown Boveri/Combustion Engineering, Inc. (ABB/CE) Topical Report CEN-630-P, Revision 2. The proposed revision of TS 5.5.2.11.h excludes from inspection the portions of the tube below the C* distance in the tubesheet. Since sleeves could extend into the tubesheet below the C* distance, the proposed TS wouldno longer require the sleeve or tube to be inspected in this region. Sleeves were not addressed in the testing and analysis used to justify excluding part of the tube from inspection (WCAP-16208-P, Revision 1, including Supplement 1). What plans do you have to ensure the lower ends of sleeves (i.e., those within the tubesheet below the C*
distance) will be inspected, including the pressure-retaining portion of the parent tube incontact with the sleeve, the sleeve-to-tube weld, and the pressure retaining portion of the sleeve? Please discuss your plans to modify your TS to address this issue.
Consider, for example, the following wording:For a tube with no portion of a sleeve extending below (a) 10.4 inches from thebottom of the hot-leg expansion transition or the top of the tubesheet (whicheveris lower) or (b) 10.7 inches from the bottom of the cold-leg expansion transition or the top of the tubesheet (whichever is lower), a tube inspection means an inspection of the steam generator tube from 10.4 inches below the bottom of the hot-leg expansion transition or top of the tubesheet (whichever is lower) completely around the U-bend to 10.7-inches below the bottom of the cold-leg expansion transition or top of the tubesheet (whichever is lower).For all other tubes, a tube inspection means an inspection from the bottom of thesleeve completely around the U-bend to either (a) 10.4 inches below the bottom of the hot-leg expansion transition or top of the tubesheet (whichever is lower) or(b) 10.7 inches below the bottom of the cold-leg expansion transition or top of the tubesheet (whichever is lower), as appropriate.3.It is the NRC staff's understanding that load at first slip, rather than maximum load, wasreported and plotted in Figure 5-1 of WCAP-16208-P, Revision 1. If the load at first slip was not used in all cases, please discuss the effect on the required inspection distance if the load at first slip was used. In addition, if the load at first slip was not used in Table 6-8 of WCAP-16208-P, Revision 1 ("Burst Based Inspection Length"), please provide Table 6-8 values to confirm the 10.4 inch (hot leg) and 10.7 inch (cold leg) proposed inspection distances are bounded when the most limiting specimen is evaluated using load at first slip. In addition, please discuss the effect on the leakage-based inspection distance (Tables 6-9 and 6-15). If the leakage-based inspection length increased, discuss your plans to modify your TS accordingly.4.Please discuss your plans to revise your TS to include the reporting requirements listedbelow:(a) Number of total indications, location of each indication, orientation of eachindication, size of each indication, and whether the indications are initiated from the inside or outside surface. (b) The cumulative number of indications detected in the tubesheet region as afunction of elevation within the tubesheet.(c) Projected end-of-cycle (EOC) accident-induced leakage from tubesheetindications. This leakage shall be combined with the postulated EOC accident-induced leakage from all other sources. If the preliminary estimated total projected EOC accident-induced leakage from all sources exceeds the leakage limit, the NRC staff shall be notified prior to unit restart.5.The proposed revision of TS 5.5.2.11.f.1.f provides exceptions, based on the C*distance, to applying the tube Repair Limit within the hot-leg tubesheet for tubes thathave not been repaired and tubes that have been repaired (sleeved). These exceptions are not included for the cold-leg tubesheet. It is, therefore, the NRC staff'sunderstanding that any tube degradation detected below the bottom of the cold-legexpansion transition or cold-leg top-of-tubesheet, whichever is higher, shall be removed from service or repaired on detection. Please confirm or correct the staff's understanding. Please provide a justification for the difference in plugging/repair requirements for degradation in the hot-leg and cold-leg tubesheet in your proposed TS,or discuss your plans for modifying the proposed TS for consistency between the hot-and cold-leg tubesheet repair requirements.6.According to Enclosure 3 to your November 3, 2005, submittal, the primary-to-secondary accident-induced leakage limit for SONGS, Units 2 and 3, is 0.5 gpm per steam generator (SG). For Unit 3, this limit is the same as the limiting condition for operation in your TS LCO 3.4.13.d since no sleeves are installed. For Unit 2, LCO 3.4.13.d specifies a maximum operational leakage rate of 0.1 gpm per SG since sleeves are installed. Since the operational leakage limit is equal to the accident-induced leakage limit, please address the following for Unit 3:a. During a steamline break the differential pressure across the tubes is greaterthan the differential pressure during normal operation. As a result, the primary-to-secondary leakage may be greater during a steamline break than during normal operation. Since you could be operating with leakage as high as your normal operating leakage limit (0.5 gpm), the amount of leakage during a steamline break (or other postulated accidents) could be greater than thatassumed in your accident analyses. If so, please discuss what controls are in place to ensure that you do not exceed your accident-induced leakage limit simply as a result of normal operating leakage. b. As part of the C* amendment, you will be assuming there is 0.2 gpm acci dent-induced primary-to-secondary leakage as a result of flaws within the tubesheet region. In addition, you may have accident-induced leakage from other sources such as sleeves or other degradation. This latter amount of leakage will need tobe limited to 0.3 gpm to ensure you do not exceed your accident-induced leakage limits in your updated final safety analysis report (UFSAR). Since the source of any normal operating leakage is not known (i.e., it could be from sources other than the tubesheet or sleeves or other defects assumed to leak in your operational assessment) and it could be as high as your TS limit of 0.5 gpm(or even higher during some postulated accidents due to the increased differential pressure), it is not clear that you will be able to stay within your accident-induced leakage limits unless you change your TS normal operating leakage or your UFSAR accident analysis leakage limit. Please discuss whether you will be able to stay within your accident-induced leakage limits and yourproposed C* inspection requirements.7.Do all of the tubes in your SGs have adequate expansion in the tubesheet to meet theleakage and pullout criteria? That is, are all of the tubes nominally expanded for the full depth of the tubesheet? If any tubes are not nominally expanded for the full depth of thetubesheet, have you verified that the expansion length is adequate to ensure structuraland leakage integrity consistent with the C* approach? For those tubes which may nothave adequate expansion lengths, discuss how you will ensure structural and leakageintegrity for these tubes (e.g., inspection of the tube-to-tubesheet weld). Also, discuss whether any changes are needed to your TSs to address this issue.8.Please describe the expected condition of the tube-to-tubesheet crevice, such as theamount of corrosion product and sludge at the top of the tubesheet. Discuss the effectsof these conditions on tube-to-tubesheet contact pressure and the potential for leakage.
February 2006San Onofre Nuclear Generating Station Units 2 and 3 cc:Mr. Daniel P. Breig Southern California Edison Company San Onofre Nuclear Generating Station
P. O. Box 128 San Clemente, CA 92674-0128Mr. Douglas K. Porter, EsquireSouthern California Edison Company 2244 Walnut Grove Avenue Rosemead, CA 91770Mr. David Spath, ChiefDivision of Drinking Water and Environmental Management P. O. Box 942732 Sacramento, CA 94234-7320Chairman, Board of SupervisorsCounty of San Diego 1600 Pacific Highway, Room 335 San Diego, CA 92101Mark L. ParsonsDeputy City Attorney City of Riverside 3900 Main Street Riverside, CA 92522Mr. Gary L. Nolff Assistant Director - Resources City of Riverside 3900 Main Street Riverside, CA 92522Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064Mr. Michael OlsonSan Diego Gas & Electric Company P.O. Box 1831 San Diego, CA 92112-4150Mr. Ed Bailey, ChiefRadiologic Health Branch State Department of Health Services Post Office Box 997414 (MS7610)
Sacramento, CA 95899-7414Resident Inspector/San Onofre NPS c/o U.S. Nuclear Regulatory Commission Post Office Box 4329 San Clemente, CA 92674Mayor City of San Clemente 100 Avenida Presidio San Clemente, CA 92672Mr. James T. Reilly Southern California Edison Company San Onofre Nuclear Generating Station
P.O. Box 128 San Clemente, CA 92674-0128Mr. James D. Boyd, CommissionerCalifornia Energy Commission 1516 Ninth Street (MS 31)
Sacramento, CA 95814Mr. Ray Waldo, Vice PresidentSouthern California Edison Company San Onofre Nuclear Generating Station
P.O. Box 128 San Clemente, CA 92764-0128Mr. Brian KatzSouthern California Edison Company San Onofre Nuclear Generating Station
P.O. Box 128 San Clemente, CA 92764-0128Mr. Steve HsuDepartment of Health Services Radiologic Health Branch MS 7610, P.O. Box 997414 Sacramento, CA 95899Mr. A. Edward SchererSouthern California Edison Company San Onofre Nuclear Generating Station
P.O. Box 128 San Clemente, CA 92674-0128