Letter Sequence Other |
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TAC:MF0613, (Open) TAC:MF0614, (Open) TAC:MF2400, Control Room Habitability (Open) TAC:MF2401, Control Room Habitability (Open) TAC:MF2402, Control Room Habitability (Open) TAC:MF2403, Control Room Habitability (Open) TAC:MF2404, Control Room Habitability (Open) TAC:MF2405, Control Room Habitability (Open) TAC:MF2406, Control Room Habitability (Open) TAC:MF2407, Control Room Habitability (Open) TAC:MF2409, Control Room Habitability (Open) TAC:MF2427, (Open) |
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MONTHYEARML13323B1962012-06-12012 June 2012 Attachment 4: CHLE-008, Rev. 3, Debris Bed Preparation and Formation Test Results. Project stage: Other ML13323B1942012-08-11011 August 2012 Attachment 3: CHLE-007, Rev. 3, Debris Bed Requirements and Preparation Procedures. Project stage: Other NOC-AE-13003040, Attachment 1: CHLE-005, Rev. 1, Determination of the Initial Pool Chemistry for the Chle Test.2012-08-13013 August 2012 Attachment 1: CHLE-005, Rev. 1, Determination of the Initial Pool Chemistry for the Chle Test. Project stage: Other ML13323B1912012-08-14014 August 2012 Attachment 2: CHLE-006, Rev. 1, STP Material Calculations. Project stage: Other ML13323B1982012-08-19019 August 2012 Attachment 5: CHLE-010, Rev. 2, Chle Tank Test Results for Blended and NEI Fiber Beds with Aluminum Addition. Project stage: Other ML13323B1992013-01-0909 January 2013 Attachment 6: CHLE-012, Rev. 3, T1 Mbloca Test Report, Cover Through Figure 52 Project stage: Other ML13323B2002013-01-0909 January 2013 Attachment 6: CHLE-012, Rev. 3, T1 Mbloca Test Report, Figure 53 Through End Project stage: Other ML13323B2022013-01-15015 January 2013 Attachment 8: CHLE-015, Rev. 3, Summary of Chemical Effects Testing in 2012 for STP GSI-191 License Submittal. Project stage: Other ML13323B2012013-01-22022 January 2013 Attachment 7: CHLE-014, Rev. 2, T2 LBLOCA Test Report. Project stage: Other ML13323B2042013-01-22022 January 2013 Attachment 9: CHLE-016, Rev. 2, Calculated Material Release to Estimate Chemical Effects. Project stage: Other NOC-AE-13002954, Pilot Submittal and Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-1912013-01-31031 January 2013 Pilot Submittal and Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 Project stage: Request ML13066A5192013-04-0101 April 2013 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue 191 Project stage: Acceptance Review ML13098A5112013-04-0808 April 2013 Corrosion/Head Loss Experiment Program Project stage: Other ML13098A4312013-04-0808 April 2013 Development of Chemical Effects Modules for Risk-Informed GSI-191 Resolution Project stage: Other ML13098A3962013-04-0808 April 2013 Email Risk Informed GSI-191 Evaluation Project stage: Other ML13101A3142013-04-12012 April 2013 Notice of Meeting Via Conference Call with STP Nuclear Operating Company to Discuss Risk-Informed Approach to Resolve Generic Safety Issue 191 for South Texas, Units 1 and 2 Project stage: Meeting NOC-AE-13002994, Schedule for Supplement to STP Pilot Submittal and Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-1912013-04-17017 April 2013 Schedule for Supplement to STP Pilot Submittal and Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 Project stage: Supplement ML13112A2522013-04-25025 April 2013 Approval of Extension to Submit Supplemental Information for Acceptance of Licensing Action; Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue 191 Project stage: Acceptance Review ML13119A0802013-04-30030 April 2013 Notice Meeting Via Conference Call with STP Nuclear Operating Company to Discuss Risk-Informed Approach to Resolve Generic Safety Issue 191 for South Texas, Units 1 and 2 Project stage: Meeting ML13140A2692013-05-20020 May 2013 NRC Slides for 5/23/13 Meeting Regarding Risk - Informed GSI-191 Pilot Application Initial Review Insights Project stage: Meeting ML13140A2562013-05-20020 May 2013 Licensee Slides for 5/23/13 Meeting - STP Pilot Submittal for Risk Informed Approach to Resolving GSI-191 Project stage: Meeting ML13150A2162013-05-23023 May 2013 Licensee Slides for 5/23/13 Public Meeting Regarding GSI-191 Project stage: Meeting ML13161A1632013-06-14014 June 2013 5/23/13 Summary of Public Meeting Via Conference Call with STP Nuclear Operating Company to Discuss Risk-Informed Approach to Resolve Generic Safety Issue 191 for South Texas, Units 1 and 2 Project stage: Meeting ML13175A2112013-06-19019 June 2013 Project, Units 1 and 2, Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-191 Project stage: Other ML13168A1622013-06-26026 June 2013 Summary of Meeting Via Conference Call with STP Nuclear Operating Company to Discuss Risk-Informed Approach to Resolve Generic Safety Issue 191 for South Texas, Units 1 and 2 Project stage: Meeting ML13214A0312013-08-13013 August 2013 Acceptance Review, Exemption Requests and License Amendment Request to Revise UFSAR for Resolution of Generic Safety Issue 191, Assessment of Debris Accumulation on PWR Sump Performance (TAC MF0613-MF0614; MF2400-09) Project stage: Acceptance Review ML13323B2072013-09-16016 September 2013 Attachment 10: CHLE-018, Rev. 2, Results of Bench Tests to Assess Corrosion of Aluminum in STP Containment Conditions. Project stage: Other ML13323B2082013-09-23023 September 2013 Attachment 11: CHLE-019, Rev. 2, Test Results for Chemical Effect Tests Stimulating Corrosion and Precipitation (T3 & T4) Project stage: Other NOC-AE-13003039, Corrections to Information Provided in Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)2013-10-0303 October 2013 Corrections to Information Provided in Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI) Project stage: Other ML13323B2092013-10-0404 October 2013 Attachment 12: CHLE-020, Rev. 2, Test Results for a 10-day Chemical Effects Test Simulating LBLOCA Conditions (T5). Project stage: Other ML13323A1892013-10-22022 October 2013 Enclosure 4-2 - Risk-Informed Closure of GSI-191, Volume 2 Probabilistic Risk Analysis Project stage: Other ML13323B1872013-10-31031 October 2013 Project, Units 1 & 2, Submittal of GSI-191 Chemical Effects Test Reports (TAC Nos. MF2400 and MF2401) Project stage: Other ML13323A1902013-11-0606 November 2013 Enclosure 4-3 Risk-Informed Closure of GSI-191, Volume 3, Engineering (Casa Grande) Analysis, Cover - Page 211 of 248 Project stage: Other ML13323A1912013-11-0606 November 2013 Enclosure 4-3 Risk-Informed Closure of GSI-191, Volume 3, Engineering (Casa Grande) Analysis, Page 212 of 1-122 Project stage: Other ML13323A1862013-11-12012 November 2013 Enclosure 4-1 - Risk-Informed Closure of GSI-191, Volume 1 Project stage: Other ML13323A1852013-11-13013 November 2013 Enclosure 3 - License Amendment Request for STP Piloted Risk-Informed Approach to Closure for GSI-191 Project stage: Request ML13323A1832013-11-13013 November 2013 Project Units 1 and 2 - Supplement 1 to Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-191 Project stage: Supplement NOC-AE-13003043, Enclosure 5 - Response to NRC Supplemental Information Items2013-11-13013 November 2013 Enclosure 5 - Response to NRC Supplemental Information Items Project stage: Supplement NOC-AE-13003054, Supplement 1 to Revised STP Pilot Submittal for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-191 to Supersede and Replace the Revised Pilot Submittal2013-11-21021 November 2013 Supplement 1 to Revised STP Pilot Submittal for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-191 to Supersede and Replace the Revised Pilot Submittal Project stage: Supplement ML13330B7152013-11-26026 November 2013 RAI from the Mechanical & Civil Engineering Branch Re. Revise STP Submittal and Request for Exemptions and License Amendment for a Risk-information Approach to Resolving Generic Safety Issues (GSI)-191 Project stage: RAI ML13330B2222013-12-0505 December 2013 Notice of Meeting with STP Nuclear Operating Company to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas Project, Units 1 and 2 (TAC MF2400-MF24 Project stage: Meeting NOC-AE-13003065, Response to STP-GSI-191-EMCB-RAI-12013-12-23023 December 2013 Response to STP-GSI-191-EMCB-RAI-1 Project stage: Other NOC-AE-13003070, Response to NRC Request for Reference Document for STP Risk-Informed GSI-191 Application2013-12-23023 December 2013 Response to NRC Request for Reference Document for STP Risk-Informed GSI-191 Application Project stage: Request ML13357A2662013-12-24024 December 2013 1/8/14 - Notice of Meeting with STP Nuclear Operating Co. to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas Project, Units 1 and 2 Project stage: Meeting NOC-AE-13003057, Response to Request for Additional Information Re Use of RELAP5 in Analyses for Risk-Informed GSI-191 Licensing Application2014-01-0909 January 2014 Response to Request for Additional Information Re Use of RELAP5 in Analyses for Risk-Informed GSI-191 Licensing Application Project stage: Response to RAI ML14009A3072014-01-0909 January 2014 NRR E-mail Capture - Request for Additional Information - TACs MF2400 Through MF2409 Project stage: RAI ML14015A0452014-01-14014 January 2014 NRR E-mail Capture - Rai'S Regarding South Texas Project'S Submittal for Risk-Informed Resolution of GS-191 Project stage: Other ML13358A0622014-01-14014 January 2014 Summary of 12/16/13 Meeting with STP Nuclear Operating Co. to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas Project, Units 1 and 2 Project stage: Meeting NOC-AE-14003081, STP-Specific Casa Grande Inputs CASA01 JT4, CASA09 JT4, CASA22 JT4, CASA26 JT4, & CASA43 JT42014-02-13013 February 2014 STP-Specific Casa Grande Inputs CASA01 JT4, CASA09 JT4, CASA22 JT4, CASA26 JT4, & CASA43 JT4 Project stage: Request ML14052A0532014-02-13013 February 2014 Project Units 1 & 2, Submittal of Casa Grande Code & Analyses for Risk-Informed GSI-191 Licensing Application Project stage: Other 2013-12-23
[Table View] |
Corrections to Information Provided in Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)ML13295A222 |
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Site: |
South Texas |
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Issue date: |
10/03/2013 |
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From: |
Rencurrel D South Texas |
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To: |
Document Control Desk, Office of Nuclear Reactor Regulation |
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References |
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NOC-AE-13003039, TAC MF0613, TAC MF0614, TAC MF2400, TAC MF2401, TAC MF2402, TAC MF2403, TAC MF2404, TAC MF2405, TAC MF2406, TAC MF2407, TAC MF2409, TAC MF2427 |
Download: ML13295A222 (7) |
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Category:Letter type:NOC
MONTHYEARNOC-AE-240040, Nuclear Liability Certificates of Insurance2024-03-19019 March 2024 Nuclear Liability Certificates of Insurance NOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-230039, Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/20230032023-12-12012 December 2023 Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/2023003 NOC-AE-230039, Submittal of Update Foreign Ownership, Control or Influence (FOCI)2023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) NOC-AE-220039, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 252023-02-0606 February 2023 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 25 NOC-AE-220038, Supplement to Request for Exemption from Certificate of Compliance (CoC) Inspection Requirement for One Multipurpose Canister2022-04-0101 April 2022 Supplement to Request for Exemption from Certificate of Compliance (CoC) Inspection Requirement for One Multipurpose Canister NOC-AE-210038, Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 252022-01-0404 January 2022 Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 25 NOC-AE-21003858, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2021-12-0606 December 2021 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes NOC-AE-21003853, Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-12-0303 December 2021 Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003848, Unit 1 Cycle 24 Core Operating Limits Report2021-11-18018 November 2021 Unit 1 Cycle 24 Core Operating Limits Report NOC-AE-21003846, Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-11-0404 November 2021 Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003842, 10 CFR 50.59 Summary Report2021-09-23023 September 2021 10 CFR 50.59 Summary Report NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003832, Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-0909 September 2021 Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003812, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-08-10010 August 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003825, Update of Foreign Ownership, Control, or Influence Information (FOCI)2021-08-0505 August 2021 Update of Foreign Ownership, Control, or Influence Information (FOCI) NOC-AE-21003824, Update Foreign Ownership, Control, or Influence (FOCI)2021-07-29029 July 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003823, Update Foreign Ownership Control or Influence (FOCI)2021-07-28028 July 2021 Update Foreign Ownership Control or Influence (FOCI) NOC-AE-21003820, Nuclear Insurance Protection2021-07-20020 July 2021 Nuclear Insurance Protection NOC-AE-21003819, Inservice Inspection Summary Report - 2RE212021-07-15015 July 2021 Inservice Inspection Summary Report - 2RE21 NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report NOC-AE-21003814, Technical Specification Bases Control Program2021-06-24024 June 2021 Technical Specification Bases Control Program NOC-AE-21003810, Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy NOC-AE-21003811, Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval2021-05-20020 May 2021 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval NOC-AE-21003801, Annual Dose Report for 20202021-04-26026 April 2021 Annual Dose Report for 2020 NOC-AE-21003802, 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report2021-04-26026 April 2021 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report NOC-AE-21003804, Operator Licensing Examination Schedule2021-04-21021 April 2021 Operator Licensing Examination Schedule NOC-AE-21003800, Radioactive Effluent Release Report2021-04-19019 April 2021 Radioactive Effluent Release Report NOC-AE-21003799, Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2021-04-15015 April 2021 Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan NOC-AE-21003795, Cycle 22 Core Operating Limits Report2021-04-15015 April 2021 Cycle 22 Core Operating Limits Report NOC-AE-21003796, Update Foreign Ownership, Control, or Influence (FOCI)2021-04-15015 April 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003790, Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter)2021-03-31031 March 2021 Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter) NOC-AE-21003791, Financial Assurance for Decommissioning - 2021 Update2021-03-31031 March 2021 Financial Assurance for Decommissioning - 2021 Update NOC-AE-210037, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-21003792, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-200037, License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications2021-03-11011 March 2021 License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications NOC-AE-21003784, Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing2021-03-0808 March 2021 Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-21003786, Annual Fitness for Duty Performance Report for 20202021-03-0101 March 2021 Annual Fitness for Duty Performance Report for 2020 NOC-AE-21003785, Evidence of Financial Protection2021-02-23023 February 2021 Evidence of Financial Protection NOC-AE-21003781, Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts2021-01-27027 January 2021 Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts NOC-AE-21003780, Submittal of Update Foreign Ownership, Control, or Influence (FOCI)2021-01-0707 January 2021 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-20003778, Changes to South Texas Project Electric Generating Station Emergency Plan2020-12-17017 December 2020 Changes to South Texas Project Electric Generating Station Emergency Plan NOC-AE-20003777, STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency2020-12-10010 December 2020 STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency NOC-AE-20003766, Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan2020-12-0202 December 2020 Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan NOC-AE-20003767, Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-16016 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval2020-10-28028 October 2020 Inservice Testing Program Description for the Fourth Ten-Year Interval NOC-AE-20003764, 1 RE22 Inspection Summary Report for Steam Generator Tubing2020-10-0707 October 2020 1 RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-20003762, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen2020-09-22022 September 2020 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen NOC-AE-20003761, Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic2020-09-10010 September 2020 Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic 2024-03-19
[Table view] |
Text
Nuclear Operating Company Sm /,/; Tm.7
. P -Iqrlrlertrk: Ce hmfI' .S-.ii n; fPO Rai M.9 *,i. ijrrtai4. 7e,.J 774,*'U.I _ _._- ,._.__
October 3, 2013 NOC-AE-1 3003039 10 CFR 50 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Units 1 and 2 Docket Nos. STN 50-498 and STN 50-499 Corrections to Information Provided in Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-191 (TAC NOS. MF0613, MF0614, MF2400, MF2401, MF2402, MF2403, MF2404, MF2405, MF2406, MF2407, MF2408, AND MF2409)
References:
- 1. Letter dated June 19, 2013, D. W. Rencurrel, STPNOC, to NRC Document Control Desk, "Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-1 91" (NOC-AE-1 3002986, ML131750250)
- 2. Letter dated August 13, 2013, Balwant Singal, NRC, to Dennis Koehl, STPNOC, "South Texas Project, Units 1 and 2 - Acceptance of Requests for Exemptions and License Amendment Request for Approval of a Risk-Informed Approach to Resolve Generic Safety Issue GSI-191 (TAC NOS. MF0613, MF0614, MF2400, MF2401, MF2402, MF2403, MF2404, MF2405, MF2406, MF2407, MF2408, AND MF2409)"
(ML13214A031) (AE-NOC-13002457)
This letter documents errors identified in Reference 1. The NRC Staff was verbally apprised of the errors in calls on September 23, 2013 and September 27, 2013.
In Reference 1, STP Nuclear Operating Company (STPNOC) requested exemptions from certain requirements of 10 CFR 50.46(b)(5), "Long-term cooling", and Appendix A to 10 CFR Part 50 General Design Criteria (GDC) 35, "Emergency Core Cooling", GDC 38, "Containment Heat Removal", and GDC 41, "Containment Atmosphere Cleanup". In accordance with the provisions of 10 CFR 50.90, STPNOC also requested an amendment to South Texas Project (STP) Operating Licenses NPF-76 and NPF-80, to revise the STP Units 1 and 2 licensing basis.
Approval for the License Amendment Request (LAR) is expected to be contingent upon approval of the exemption requests.
In Reference 2, the NRC accepted the STPNOC application of Reference 1.
S3 19 ST1 33761944
NOC-AE-13003039 Page 2 of 3 Reference 1 included Enclosure 4-3, "Risk-Informed Closure of GSI-191, Enclosure 4-3, Engineering (CASA Grande) Analysis". CASA Grande was developed to produce the basic event probabilities needed in the STPNOC Probabilistic Risk Analysis (PRA) to calculate the risk associated with effects identified in GSI-191. Enclosure 4-3 summarizes the analysis methodology and results.
Subsequent to the submittal of Reference 1, STPNOC discovered differences between the descriptions in Enclosure 4-3 and the CASA Grande analysis. The differences pertain only to the proposed risk-informed GSI-191 licensing application described in Reference 1 and do not affect current design basis calculations or impact operability at the STP Units 1 and 2.
In response to this discovery, STPNOC has taken the following actions:
- Entered the condition into the STPNOC Corrective Action Program (CR 13-10732).
- Briefed the NRC staff in calls on September 23, 2013 and September 27, 2013.
- Performed a detailed comparison of the descriptions in Enclosure 4-3 and the CASA Grande analysis to assure the differences have been identified and assessed.
- Reviewed other parts of the Reference 1 submittal to assure that the extent of condition is addressed, including the following compensatory action with other GSI-191 vendors:
o Apprised the vendors of the condition and reinforced expectations regarding accuracy of information o Required the vendors to review their scope of information and process to assure accuracy Differences were identified that will require a re-quantification of the PRA due to changes in the basic event probabilities from the supporting analysis described in Enclosure 4-3. STPNOC will perform required PRA and submit a supplement to Reference 1 by November 15, 2013. See licensing commitment in Attachment 2 to this letter. There are no other commitments in this letter.
A description of the assessment process and the results of the comparison are attached and have been discussed with the NRC staff.
If there are questions regarding this submittal, please contact Ken Taplett at 361-972-8416, or me at 361-972-7867.
DOW. Rncrrel Senior Vice President, Zperations awh Attachments
- 1. Assessment Process and Results
- 2. List of Commitments
NOC-AE-13003039 Page 3 of 3 cc: (paper copy) (electronic copy)
Regional Administrator, Region IV Steven P. Frantz, Esquire U. S, Nuclear Regulatory Commission A. H. Gutterman, Esquire 1600 East Lamar Boulevard Morgan, Lewis & Bockius LLP Arlington, TX 76011-4511 Balwant K. Singal Balwant K. Singal Michael Markley Senior Project Manager John Stang U.S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission One White Flint North (MS 8 B1) 11555 Rockville Pike John Ragan Rockville, MD 20852 Chris O'Hara Jim von Suskil NRC Resident Inspector NRG South Texas LP U. S, Nuclear Regulatory Commission P. 0, Box 289, Mail Code: MN1 16 Kevin Polio Wadsworth, TX 77483 Richard Peha City Public Service Jim Collins City of Austin Peter Nemeth Electric Utility Department Crain Caton & James, P.C.
721 Barton Springs Road Austin, TX 78704 C. Mele City of Austin Richard A. Ratliff Robert Free Texas Department of State Health Services
NOC-AE-13003039 Attachment 1 Page 1 of 3 Assessment Process and Results Assessment Process STPNOC discovered differences between the descriptions of the CASA Grande analysis input in Enclosure 4-3 of the June 19, 2013 licensing submittal (Reference 1) and the actual input to the CASA Grande analysis.
The differences did not indicate an issue with the methodology used in the CASA Grande analyses. STPNOC's evaluation consequently focused primarily on reconciling the differences between the CASA Grande inputs and their description in the submittal, with the goal being to develop corrections that STPNOC will submit in a supplement that will correct the docket for the licensing application. Based on this intent, STPNOC's review process had two key elements:
- 1. Assuring that the differences between the CASA Grande analysis and the description in Enclosure 4-3 of the STPNOC application were identified and addressed.
- 2. Determining if the condition extended to other parts of the application.
Identification of Differences in the Enclosure 4-3 Documentation of STP Risk-Informed Resolution Submittal STPNOC elected to systematically identify and disposition differences that are found through the following two-step process: (1) line-by-line comparison of numeric input in the CASA Grande input files to the tabular information provided in Enclosure 4-3, and (2) subject-matter-expert review of the Enclosure 4-3 modeling assumptions with CASA Grande implementation. This quality assurance review is designed to reveal the following generic types of differences:
a) Intentional CASA Grande input that conservatively increased the reported quantitative risk relative to Enclosure 4-3 descriptions.
b) Analysis input described in Enclosure 4-3 that is not fully implemented in CASA Grande, c) Analysis input in CASA Grande that is not precisely described in Enclosure 4-3, d) Errors in CASA Grande input caused by misinterpretation of information or mistaken transcription.
e) Errors in Enclosure 4-3 tabular data caused by misinterpretation of information or mistaken transcription.
f) Errors in CASA Grande model implementation, g) Errors in Enclosure 4-3 model description.
The primary focus of this review is to identify differences between the CASA Grande analysis and its description in the docketed application (i.e. Enclosure 4-3) so corrections can be made to assure an accurate representation of the analysis results is presented for review. The nature of the differences did not indicate the need for re-verification or validation of the methodology itself.
Identified differences are logged and dispositioned prior to risk re-quantification using a staged evaluation process.
NOC-AE-1 3003039 Attachment 1 Page 2 of 3 Description of Enclosure 4-3 Review Process Comparison of Enclosure 4-3 documentation to the CASA Grande input was conducted in two phases:
Phase I: Initial screening by two staff engineers to note any observations of perceived inconsistencies.
This review was conducted over the entire input section of Section 2.2 of Enclosure 4-3.
Some observations were duplicated for completeness; some observations were resolved by information found later in the document; however, a master list of observations was compiled without deleting any items for confirmation and resolution in Phase II.
Phase II: Committee review of initial observations and the entirety of Enclosure 4-3 to confirm actual findings and add new findings.
This review was conducted over a 5-day period where review actions were recorded and tracked for the purpose of quality assurance traceability. Technical discussions of each initial observation revealed additional action items that were recorded and assessed for disposition. Each item is recorded and tracked to final resolution. The systematic review was conducted from two perspectives:
- a. Sequentially walking through Enclosure 4-3 and verifying input values and implementation in CASA Grande
- b. Sequentially walking through CASA Grande and verifying model input matched the description in Enclosure 4-3.
Limited initial comparison of numeric values between Enclosure 4-3 and source references (engineering calculations and precursor analysis reports) revealed one transcription error. Because of this finding, numeric input adopted in Enclosure 4-3 will be reviewed with source references. Deeper levels of confirmation will not be pursued unless specific items are identified.
Objectives of the review included:
- 1. Identifying differences between Enclosure 4-3 documentation and CASA Grande input files
- 2. Confirming the validity of identified differences.
- 3. Assessing the options for changing either Enclosure 4-3 documentation or CASA Grande input to achieve agreement between documentation and the analysis input.
The following logic was applied:
- a. Correcting any confirmed errors
- b. Addressing any identified non-defensible approaches
- c. Minimizing changes to CASA Grande input with a preference toward correcting Enclosure 4-3 for accuracy and preserving existing conservatism in quantitative input.
NOC-AE-13003039 Attachment 1 Page 3 of 3 Results Enclosure 4-3 Review STPNOC documented the observations that were recorded during the review. Each of the observations was assigned one of three categories:
- 1. a change is recommended for CASA Grande input.
- 2. a change is recommend for documentation in Enclosure 4-3, or
- 3. no change is recommended for either Enclosure 4-3 or CASA Grande input.
Specific information regarding these observations, their assigned categories and their expected resolution was separately provided in a briefing to the staff on September 27, 2013.
Differences were identified that will require a re-quantification of the Probabilistic Risk Analysis (PRA) due to changes in the basic event probabilities from the supporting analysis described in -3. The re-quantification will also require revision to other parts of the STPNOC application (e.g., Enclosure 4-2 describing the PRA results).
STPNOC will provide the details of the resolution of this issue in the supplement to STPNOC application (Reference 1 of the cover letter).
Evaluation of Extent of Condition Extent of condition is being evaluated in accordance with STPNOC's corrective action program to determine if similar conditions existed for information provided for Reference 1 by other GSI-191 vendors. Actions taken to assess extent of condition include the following:
- 1. Current vendor controls established to satisfy quality requirements for the GSI-191 project were documented.
- 2. Vendors were required to assess current controls relative to work performed to determine if similar conditions exist for their respective documents, analyses, or other reports.
- 3. Vendors were required to review their scope of information provided for Reference 1 for any differences in documentation and associated analyses.
- 4. Results of vendor assessments will be documented and attached to the corresponding condition report action.
At the time of the calls in which the NRC staff was briefed, STPNOC had not identified any similar conditions in the information provided by the other GSI-1 91 vendors. Two vendors have subsequently apprised STPNOC of potentially incorrect input for some CASA Grande break frequency calculations and the subsequent RISKMAN© quantification. STPNOC will evaluate this in accordance with the categorization process described in the Results section above and include their resolution in the supplement as described above. STPNOC will also promptly apprise the NRC if any conditions identified in the extent of condition review are considered likely to affect the conclusions in the Reference 1 licensing application.
NOC-AE-1 3003039 Attachment 2 Page 1 of 1 List of Commitments The following table identifies the actions to which STP Nuclear Operating Company (STPNOC) has committed. Statements in the submittal with the exception of those in the table below are provided for information purposes and are not considered regulatory commitments.
Commitment Tracking Scheduled Number Completion Date STPNOC discovered that the description of the CR13-10732-18 November 15, 2013 CASA Grande analysis in Enclosure 4-3 of NOC-AE-1 3002986 did not match the actual CASA Grande analysis input in some areas.
Correction of several of these differences will require a re-quantification of the PRA due to changes in the supporting analysis (CASA Grande). STPNOC will perform that analysis and submit a supplement to the licensing application submitted in NOC-AE-13002986 by November 15, 2013. The supplement will also include a description of the changes required to resolve the differences that were identified between the CASA Grande analysis and the description in Enclosure 4-3.