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MONTHYEARML0612207012006-04-28028 April 2006 Amendment Application Numbers 243 and 227, Proposed Change Number (PCN) 556 Request to Revise Fuel Storage Pool Boron Concentration Project stage: Request ML0629805852006-10-26026 October 2006 Request for Additional Information on the Proposed Amendment to Revise Fuel Storage Pool Boron Concentration Project stage: RAI ML0632104252006-11-13013 November 2006 Additional Information in Support of Amendment Application Numbers 243 and 227 Project stage: Other ML0636100422006-12-22022 December 2006 Additional Information in Support of Amendment Application Numbers 243 and 227 Project stage: Other ML0706705282007-03-16016 March 2007 Request for Additional Information on the Proposed Amendment to Revise Fuel Storage Pool Boron Concentration Project stage: RAI ML0709500412007-04-12012 April 2007 Request for Additional Information on the Proposed Amendment to Revise Fuel Storage Pool Boron Concentration Project stage: RAI ML0724004512007-04-18018 April 2007 SONGS 2 & 3 - 4/18/07 E-mail to D. Mercurio RAI Criticality Analysis & Ts/Lcs/Bases Changes - (Tacs. MD1405 and 1406) Project stage: RAI ML0724005052007-04-20020 April 2007 SONGS 2 & 3 - 4/20/07 E-mail to L. Conklin, RAI Acceptability to CEAs & Gt Inserts, Etc. (Tacs. MD1405 and 1406) Project stage: RAI ML0712203232007-05-0707 May 2007 Request for Additional Information on the Proposed Amendment to Revise Fuel Storage Pool Boron Concentration Project stage: RAI ML0715701692007-05-14014 May 2007 5/14/07 E-Mail to L. Conklin, SCE, from N. Kalyanam, NRC - San Onofre Nuclear Generating Station, Unit 2 & 3 - Request for Additional Information Project stage: RAI ML0717000972007-06-15015 June 2007 Amendment Application Numbers 243, Supplement 1 and 227, Supplement 1, Proposed Change Number (PCN) 556, Revision 1, Request to Revise Fuel Storage Pool Boron Concentration Project stage: Supplement ML0721300572007-07-27027 July 2007 Response to Request for Additional Information in Support of Amendment Application Numbers 243 and 227 Proposed Change Number 556, Rev 1 Request to Revise Fuel Storage Pool Boron Concentration Project stage: Response to RAI ML0725503042007-09-11011 September 2007 Amendment Application Numbers 243, Supplement 2 and 227, Supplement 2, Proposed Change Number (PCN) 556, Revision 2 Project stage: Supplement ML0725501752007-09-27027 September 2007 Issuance of Amendment Nos. 213 and 205 Request to Revise Fuel Storage Pool Boron Concentration Project stage: Approval ML0725501832007-09-27027 September 2007 Technical Specifications Pages, Revise Fuel Storage Pool Boron Concentration Project stage: Other ML1005504682010-03-0404 March 2010 Withdrawal of an Amendment Request Exclude the Source Range Neutron Flux Instrument Channel Preamplifier from the TS Channel Calibration Requirements Project stage: Withdrawal 2007-04-20
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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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April 12, 2007 Mr. Richard M. Rosenblum Senior 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 AMENDMENT TO REVISE FUEL STORAGE POOL BORON CONCENTRATION (TAC NOS. MD1405 AND MD1406)
Dear Mr. Rosenblum:
By letter dated April 28, 2006 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML061220701), and as supplemented by letters dated November 13 and December 22, 2006 (ADAMS Accession Nos. ML063210425 and ML063610042, respectively), Southern California Edison submitted an application to change the San Onofre Nuclear Generating Station, Units 2 and 3, technical specifications related to fuel storage pool boron concentration. The proposed change will increase the minimum allowed boron concentration of the spent fuel pool and allow credit for soluble boron, guide tube inserts made from borated stainless steel, and fuel storage patterns in place of Boraflex.
After reviewing your request, the Nuclear Regulatory Commission staff has determined that additional information outlined in the enclosure is needed to complete the review. We discussed this information with your staff by telephone and they agreed to provide the additional information requested by April 27, 2007.
If you have any questions, please contact me at (301) 415-1480.
Sincerely,
/RA/
N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362
Enclosure:
Request for Additional Information cc: See next page
ML063210425 and ML063610042, respectively), Southern California Edison submitted an application to change the San Onofre Nuclear Generating Station, Units 2 and 3, technical specifications related to fuel storage pool boron concentration. The proposed change will increase the minimum allowed boron concentration of the spent fuel pool and allow credit for soluble boron, guide tube inserts made from borated stainless steel, and fuel storage patterns in place of Boraflex.
After reviewing your request, the Nuclear Regulatory Commission staff has determined that additional information outlined in the enclosure is needed to complete the review. We discussed this information with your staff by telephone and they agreed to provide the additional information requested by April 27, 2007.
If you have any questions, please contact me at (301) 415-1480.
Sincerely,
/RA/
N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362
Enclosure:
Request for Additional Information cc: See next page DISTRIBUTION:
PUBLIC RidsNrrDorl (CHaney/JLubinski) RidsNrrLAJBurkhardt LPLIV r/f RidsNrrDorlDpr RidsNrrPMNKalyanam RidsAcrsAcnwMailCenter RidsNrrDorlLpl4 (THiltz) RidsRgn4MailCenter (TPruett)
RidsOgcRp RidsNrrDssSpwb SSun, DSS ADAMS Accession No.: ML070950041 *No major change from Staff provided RAI.
OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DSS/SPWB* NRR/LPL4/BC NAME NKalyanam JBurkhardt GCranston THiltz DATE 4/10/07 4/11/07 3/22/07 4/12/07 San Onofre Nuclear Generating Station Units 2 and 3 cc:
Mr. Daniel P. Breig Director, Radiologic Health Branch Southern California Edison Company State Department of Health Services San Onofre Nuclear Generating Station P.O. Box 997414, MS 7610 P.O. Box 128 Sacramento, CA 95899-7414 San Clemente, CA 92674-0128 Resident Inspector/San Onofre NPS Mr. Douglas K. Porter, Esquire c/o U.S. Nuclear Regulatory Commission Southern California Edison Company Post Office Box 4329 2244 Walnut Grove Avenue San Clemente, CA 92674 Rosemead, CA 91770 Mayor Mr. David Spath, Chief City of San Clemente Division of Drinking Water and 100 Avenida Presidio Environmental Management San Clemente, CA 92672 P.O. Box 942732 Sacramento, CA 94234-7320 Mr. James T. Reilly Southern California Edison Company Chairman, Board of Supervisors San Onofre Nuclear Generating Station County of San Diego P.O. Box 128 1600 Pacific Highway, Room 335 San Clemente, CA 92674-0128 San Diego, CA 92101 Mr. James D. Boyd, Commissioner Mark L. Parsons California Energy Commission Deputy City Attorney 1516 Ninth Street (MS 31)
City of Riverside Sacramento, CA 95814 3900 Main Street Riverside, CA 92522 Mr. Ray Waldo, Vice President Southern California Edison Company Mr. Gary L. Nolff San Onofre Nuclear Generating Station Assistant Director - Resources P.O. Box 128 City of Riverside San Clemente, CA 92764-0128 3900 Main Street Riverside, CA 92522 Mr. Brian Katz 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 Mr. Steve Hsu Mr. Michael R. Olson Department of Health Services San Diego Gas & Electric Company Radiologic Health Branch 8315 Century Park Ct. CP21G MS 7610, P.O. Box 997414 San Diego, CA 92123-1548 Sacramento, CA 95899 March 2006
San Onofre Nuclear Generating Station Units 2 and 3 cc:
Mr. A. Edward Scherer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128 March 2006
REQUEST FOR ADDITIONAL INFORMATION SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 (SONGS 2 AND 3)
SOUTHERN CALIFORNIA EDISON DOCKET NOS. 50-361 AND 50-362 REQUEST TO REVISE FUEL STORAGE POOL BORON CONCENTRATION
- 1. Criticality Accident Analyses Page 13 of Enclosure 2 to Reference 1 indicated that specific accidents considered for criticality analyses included fuel assembly drop, fuel misloading in the racks and spent fuel pool (SFP) water temperature changes. Also, Section 3.2.9 of Attachment L to Reference 1 discussed criticality analyses for various postulated accidents including: (1) pool water temperature accident and (2) fuel assembly misplacement. For the fuel assembly misplacement, the following accidents were discussed: (1) fuel assembly dropped horizontally on top of the rack, (2) fuel assembly dropped vertically into a storage location already containing a fuel assembly, (3) fuel assembly dropped to the SFP, and (4) fuel misloading in either Region I or II.
Furthermore, Section 5.6 of Attachment L to Reference 1 provided the quantitative results of analyses for a pool heat-up accident and fuel mishandling accident. However, the respective Attachments G and H containing the proposed Bases pages for SONGS 2 and 3 did not include adequate and sufficient information regarding applicable safety analyses. Specifically, Page B 3.7-71 stated in the applicable safety analyses section that this accident was analyzed assuming the misloading of one fresh assembly with the maximum permissible enrichment.
The discussion of other accidents analyzed or considered as discussed in the above paragraph were either deleted (a fuel assembly dropped vertically into a storage location already containing a fuel assembly), or omitted (such as the pool water temperature accident).
Modify the applicable safety analyses section on page B 3.7-71 to appropriately reflect the analyses considered for determining the required boron concentration in the SFP.
- 2. Licensee-Controlled Specification (LCS) 4.0.100 vs. NUREG-1432 Page 17 of Enclosure 2 to Reference 1 stated that LCS 4.0.100 was consistent with NUREG-1432, Standard Technical Specifications Combustion Engineering Plants. It should be noted that the requirement of the LCS documentation was discussed in Section 4.3(f) of NUREG-1432, which stated that new or partially spent fuel assemblies (SFAs) with a discharge burnup in the unacceptable range of Figure [3.7.18-1] would be stored in compliance with the Nuclear Regulatory Commission (NRC)-approved plant-specific information such as specific document containing the analytical methods, title, date or specific configuration or figure.
The proposed LCS 4.0.100 for SONGS 2 and 3 was contained in Attachment I and J, respectively. Based on the review of the proposed LCSs, it appeared to the NRC staff that LCS 4.0.100 did not contain the analytical methods used to determine the associated storage
patterns for the SFAs and thus, was not fully consistent with Section 4.3(f) of NUREG-1432 that requires the inclusion of analytical methods in the LCS.
Clarify the inconsistency between LCS 4.0.100 and Section 4.3(f) of NUREG-1432 regarding inclusion of analytical methods.
Also, Reference (5) in Section 7, REFERENCES, had the title: NRC: Standard Technical Specifications Combustion Engineering Plants Bases (NUREG-1432, Vol. 2, Rev. 3). The NRC staff found that Reference (5) misquoted the title of the Standard Technical Specifications (TS) since Bases sections do not contain information addressing LCS documentation requirements for the SFA storage patterns. The documentation requirements are discussed in Standard TS Section 4.3(f), as referenced in the first paragraph above. The licensee should correct the error by deleting Bases and replacing Vol. 2" with Vol. 1" in the title for Reference (5).
- 3. Inconsistency in the Note for LCS 4.0.100 The note on page 4.0.100-1 of Attachments I and J to Reference 1 indicated that the LCS was listed by revision number and date in TS 4.3.1. The NRC staff found that the LCS was listed in TS 4.3.1.k and TS 4.3.1.l (of Attachments C and D to Reference 1); however, the TSs listed the LCS revision number without specifying the date.
Clarify the inconsistency between the LCS note and TS 4.3.1 regarding inclusion of the LCS date.
- 4. No SONGS 1 Fuel to Be Stored in Region I Racks LCS Subsection 4.0.100.3 (in Attachments I and J to Reference 1) requires that SONGS 1 fuel not be stored in Region I racks. This requirement is consistent with the criticality analysis discussed in Section 4.6 of Attachment L that indicates that Unit 1 fuel has not been analyzed to be stored in Region I. However, Table 2-2, Spent Fuel Data (Each Unit), of Attachment L listed and/or SONGS 1 14x14 fuel in the row of the Table specifying the fuel types for the SFAs in Region I.
Modify Table 2-2 to correct the information that is inconsistent with LCS 4.0.100.3 and Section 4.6 of the criticality analysis.
- 5. Omissions of the Cooling Times in Figures Specifying Minimum Burnup for Category I Fuel Figures I-1 through I-6 in Attachments I and J to Reference 1 specify the relationship of the minimum burnup and initial uranium enrichment. There are five lines in each figure to show the minimum required burnup at the fuel cooling times of 0, 5, 10, 15, and 20 years. In each of the lines, the symbols to represent the cooling times were omitted.
Modify the figures to correct the omissions.
- 6. Control Element Assembly Lifetime Analysis Section 2.2.1 of Attachment L to Reference 1 indicated that a control element assembly (CEA) lifetime analysis would ensure that the CEAs used were suitable for use in the SFP. Before using any CEA, a visual inspection would be performed.
Discuss the CEA lifetime analysis and the associated acceptance criteria for selection of CEA to be used in the SFP. Discuss the criteria of the visual inspection for the CEA that would pass the inspection.
- 7. CASMO-3 Benchmarking Section 3.1.1 of Attachment L to Reference 1 indicated that CASMO-3 was used to perform the fuel depletion analyses and criticality analyses for fuel assemblies in the SFP, and CASMO-3 was compared with industry critical experiments with good agreement.
List the values of the bias and 95/95 uncertainty in the bias of the critical benchmark calculation for CASMO-3, and discuss how the CASMO-3 code bias and uncertainty were used in the fuel depletion analyses and criticality analyses for fuel assemblies in the SFP.
- 8. Computer Codes (KENO-V.a and the Related Codes) Benchmarking Section 3.1.2 of Attachment L to Reference 1 indicated that KENO-V.a was benchmarked by Southern California Edison against industry critical experiments performed by Babcock and Wilcox (B&W). The bias and 95/95 uncertainty in the bias for CELLDAN, NITAWL-II and KENO-V.a, and 27 group cross-section library were 0.00814 and 0.00172, respectively. The NRC staff found that these bias and uncertainty were different from that on page 9.1-13 of the updated final safety analysis report (UFSAR), which indicated that the bias and 95/95 uncertainty in the bias for CELLDAN, NITAWL-II and KENO-V.a, and 27 group cross-section library were 0.00928 and 0.00148, respectively. The bias and uncertainty in the UFSAR were also determined by analyses of B&W critical experiments.
Discuss why the values of the bias and uncertainty predicted for the KENO-V.a-related codes are different as they are shown in Section 3.1.2 of Reference 1 and Section 9.1 of the UFSAR, and justify that the values for the bias and uncertainty discussed in Section 3.1.2 of Reference 1 are adequate for use in the criticality analysis.
- 9. Manufacturing Tolerances Section 3.2.2 of Attachment L to Reference 1 discussed the reactivity effects of the manufacturing tolerances for the components including enrichment, stainless steel thickness and minimum cell inner dimension. It specifically indicated that the reactivity effect of the manufacturing tolerance of the storage cell pitch was only considered for Region I.
Discuss the storage rack configurations in Regions I and II to justify that the storage cell pitch tolerance effect needs to be considered for Region I only.
- 10. Minimum Axial Burnup Section 3.2.4 of Attachment L to Reference 1 indicated that the CASMO-3 depletions were performed based on the following reactor operating conditions: reactor outlet temperature of 600 ºF; constant beginning of cycle fuel temperature of 1200 ºF; and constant soluble boron of 1,000 parts per million (ppm). It indicated that the operating conditions so selected were to eliminate axial burnup effects.
Discuss the effects of the reactor outlet temperature, fuel temperature, and soluble boron on the axial burnup, and justify that the operating conditions assumed in the CASMO-3 depletion calculations would eliminate the axial burnup effects.
- 11. SIMULATE-3 All-Rod-Out 2D Depletions Section 3.2.5 of Attachment L to Reference 1 discussed the calculation of the axial burnup bias for two SIMULATE-3 cases. For the all-rod-out 2D cases, it indicated that at 0, 10, 20, 30, 40, 50, and 60 gigawatt days per ton (GWD/T), the 2D was expanded to 3D.
Explain how the 2D SIMULATE-3 calculations were expanded from 2D to 3D calculations, and justify the adequacy of the calculations in determining the axial burnup effects.
- 12. CEA Bias Section 3.2.6 of Attachment L to Reference 1 discussed the calculations for CEA bias. It indicated that CASMO-3 (through SIMULATE-3) has accurately predicted SONGS 2 and 3 CEA bank worth measurements.
Explain how CASMO-3 was benchmarked through SIMULATE-3 to predict the CEA worth measurements.
- 13. Boron Concentration of 370 ppm Under Non-Accident Conditions Section 5.1 of Attachment L to Reference 1 indicated that the soluble boron concentration needed to maintain effective multiplication factor (Keff) less than or equal to 0.95, including biases and uncertainties, under non-accident conditions was 370 ppm.
Discuss the boron worths in terms of ppm/k used in determining the required boron concentration of 370 ppm, and justify the adequacy of the values of the boron worth used.
Identify the limiting storage patterns with the associated enrichment that would result in a maximum required boron concentration of 370 ppm.
- 14. Reactivity Equivalence Uncertainty Section 5.2 of Attachment L to Reference 1 indicated that the reactivity equivalence uncertainty was 0.00 k at 0 GWD/T and 0.01 k at 30 GWD/T, linear with burnup. It also indicated that this reactivity equivalence uncertainty was approved by the NRC staff. Furthermore, it indicated that the soluble boron needed to compensate for the reactivity equivalence uncertainty was 178 ppm.
Provide the name of the author, title, and date of the NRC document approving the reactivity equivalence uncertainty. Discuss how the boron concentration of 178 was calculated from the reactivity equivalence uncertainty that was expressed in terms of k and a linear relationship with burnup.
- 15. Discharge Burnup Uncertainty Section 5.3 of Attachment L to Reference 1 indicated that the soluble boron needed to compensate for the fuel assembly discharge burnup uncertainty was 218 ppm. This boron compensation was based on a discharge burnup uncertainty of 7 percent for SONGS 2 and 3 fuel assemblies.
Discuss information including plant-specific fuel discharge burnup data to demonstrate the adequacy of the uncertainty of 7 percent used in the criticality analysis. Discuss how the boron compensation of 218 ppm was calculated from the fuel discharge burnup uncertainty of 7 percent.
Reference
- 1. Letter from B. Katz (SCE) to NRC, Docket Nos. 50-361 and 50-362, Amendment Application Numbers 243 and 227, Proposed Change Number (PCN) 556, Request to Revise Fuel Storage Pool Boron Concentration, San Onofre Nuclear Generating Station Units 2 and 3, dated April 28, 2006.