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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] Category:Report
MONTHYEARNOC-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) ML23243B0562023-08-31031 August 2023 Supplemental Information to Application for Order Approving Indirect Transfer of Control of Licenses ML23229A4992023-08-17017 August 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) 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) ML21266A4262021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report ML21182A2412021-06-30030 June 2021 Commitment Change Summary Report ML17019A0032017-07-11011 July 2017 Attachment 2 to Safety Evaluation - In-Vessel Thermal-Hydraulic Analysis, Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 NOC-AE-17003468, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2017-05-10010 May 2017 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML16302A0152016-10-20020 October 2016 South Texas Project, Units 1 & 2 - Supplement 3 to Revised Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Address Generic Safety Issue (GSl)-191 and Respond to Generic Letter (GL) 2004-02 NOC-AE-16003345, LTR-PAFM-16-11-NP, Revision 0, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2016-03-31031 March 2016 LTR-PAFM-16-11-NP, Revision 0, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. NOC-AE-15003249, Submittal of 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes and Annual Report2015-06-0909 June 2015 Submittal of 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes and Annual Report ML14357A1362015-01-22022 January 2015 Review of Analysis of Capsule Withdrawal Schedule from Reactor Vessel Radiation Surveillance Program NOC-AE-14003190, Attachment 2 to NOC-AE-14003190 - ALION-REP-STP-8998-14, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application2014-10-30030 October 2014 Attachment 2 to NOC-AE-14003190 - ALION-REP-STP-8998-14, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application ML14344A5462014-10-30030 October 2014 Attachment 1 to NOC-AE-14003190 - Alion REP-STP-8998-13, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application Executive Summary NOC-AE-14003178, Update Foreign Ownership, Control, or Influence (FOCI)2014-09-17017 September 2014 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-14003161, Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2.2014-08-31031 August 2014 Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2. ML14260A4382014-08-31031 August 2014 Engineering Report ER-1059, Rev. 1, Bounding Uncertainty Analysis for Thermal Power Determination at South Texas Project Units 1 & 2 Using LEFM System. NOC-AE-14003101, Enclosure 1 to Enclosure 6 Concerning Second Set of Responses to April 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Application2014-06-25025 June 2014 Enclosure 1 to Enclosure 6 Concerning Second Set of Responses to April 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Application ML14168A2682014-05-0101 May 2014 Texas Pollutant Discharge Elimination System Major Amendment with Renewal Application for a Major Facility Tpdes Permit No. WQ000190800 NOC-AE-14003103, University of Texas White Paper, Means of Aggregation and NUREG-1829: Geometric and Arithmetic Means, Rev. 3, Enclosure 2 to Attachment 12014-04-18018 April 2014 University of Texas White Paper, Means of Aggregation and NUREG-1829: Geometric and Arithmetic Means, Rev. 3, Enclosure 2 to Attachment 1 ML14087A0782014-04-15015 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident (TAC MF0178 & MF0179) NOC-AE-14003114, Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai..2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai.. NOC-AE-14003082, Alternate Source Term Dose Analysis: an Estimate of Risk Attributed to GSI-191, Attachment 32014-03-11011 March 2014 Alternate Source Term Dose Analysis: an Estimate of Risk Attributed to GSI-191, Attachment 3 NOC-AE-13003067, Supplement to Seismic Walkdown Summary Report of Items Classified as Inaccessible2014-02-27027 February 2014 Supplement to Seismic Walkdown Summary Report of Items Classified as Inaccessible ML14072A0832014-02-24024 February 2014 CHLE-010, Chle Tank Test Results for Blended and NEI Fiber Beds with Aluminum Addition, Revision 3 ML14072A0872014-02-24024 February 2014 CHLE-016, Calculated Material Release to Estimate Chemical Effects, Revision 3 ML14072A0862014-02-24024 February 2014 CHLE-015, Summary of Chemical Effects Testing in 2012 for STP GSI-191 License Submittal, Revision 4 ML14072A0802014-02-24024 February 2014 CHLE-006, STP Material Calculations, Revision 2 ML14072A0822014-02-23023 February 2014 CHLE-008, Debris Bed Preparation & Formation Test Results, Revision 4 ML14072A0792014-02-22022 February 2014 CHLE-020, Test Results for 10-Day Chemical Effects Test Simulating LBLOCA Condition (T5), Revision 3 ML14072A0882014-02-22022 February 2014 CHLE-018, Results of Bench Tests to Assess Corrosion of Aluminum in STP Containment Conditions, Revision 3 ML14072A0852014-02-22022 February 2014 CHLE-014, T2 LBLOCA Test Report, Revision 3 ML14072A0842014-02-18018 February 2014 CHLE-012, T1 Mbloca Test Report, Revision 4 ML14072A0772014-02-18018 February 2014 CHLE-005, Determination of the Initial Pool Chemistry for the Chle Test, Revision 2 ML14149A4352014-02-14014 February 2014 Project, Units 1 and 2 - ALION-REP-STP-8998-02, Rev. 0, STP Casa Grande Analysis and LAR Enclosure 4-3 RAI Response, Enclosure 1 to Attachment 1 ML14072A0812014-02-13013 February 2014 CHLE-007, Debris Bed Requirements & Preparation Procedures, Revision 4 ML13339A7362014-01-29029 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13354B8332014-01-23023 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for South Texas Project, Units 1 and 2, TAC Nos.: MF0825 and MF0826 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 ML13323A1862013-11-12012 November 2013 Enclosure 4-1 - Risk-Informed Closure of GSI-191, Volume 1 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 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 ML13323A1892013-10-22022 October 2013 Enclosure 4-2 - Risk-Informed Closure of GSI-191, Volume 2 Probabilistic Risk Analysis ML13323B2092013-10-0404 October 2013 Attachment 12: CHLE-020, Rev. 2, Test Results for a 10-day Chemical Effects Test Simulating LBLOCA Conditions (T5). ML13323B2082013-09-23023 September 2013 Attachment 11: CHLE-019, Rev. 2, Test Results for Chemical Effect Tests Stimulating Corrosion and Precipitation (T3 & T4) ML13323B2072013-09-16016 September 2013 Attachment 10: CHLE-018, Rev. 2, Results of Bench Tests to Assess Corrosion of Aluminum in STP Containment Conditions. NOC-AE-13003019, Submittal of Commitment Change Summary Report for the Period June 21, 2011 Through June 21, 20132013-07-18018 July 2013 Submittal of Commitment Change Summary Report for the Period June 21, 2011 Through June 21, 2013 ML13175A2122013-06-18018 June 2013 Project, Units 1 and 2, Enclosure 4-1 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 1 Project Summary NOC-AE-13002986, Enclosure 4-3 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 3 Engineering Casa Grande Analysis, Page 161 of 260 Through End2013-06-0606 June 2013 Enclosure 4-3 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 3 Engineering Casa Grande Analysis, Page 161 of 260 Through End 2023-08-31
[Table view] Category:Miscellaneous
MONTHYEARML23243B0562023-08-31031 August 2023 Supplemental Information to Application for Order Approving Indirect Transfer of Control of Licenses ML21182A2412021-06-30030 June 2021 Commitment Change Summary Report NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report ML17019A0032017-07-11011 July 2017 Attachment 2 to Safety Evaluation - In-Vessel Thermal-Hydraulic Analysis, Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 NOC-AE-17003468, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2017-05-10010 May 2017 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes NOC-AE-15003249, Submittal of 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes and Annual Report2015-06-0909 June 2015 Submittal of 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes and Annual Report ML14357A1362015-01-22022 January 2015 Review of Analysis of Capsule Withdrawal Schedule from Reactor Vessel Radiation Surveillance Program NOC-AE-14003190, Attachment 2 to NOC-AE-14003190 - ALION-REP-STP-8998-14, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application2014-10-30030 October 2014 Attachment 2 to NOC-AE-14003190 - ALION-REP-STP-8998-14, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application ML14344A5462014-10-30030 October 2014 Attachment 1 to NOC-AE-14003190 - Alion REP-STP-8998-13, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application Executive Summary NOC-AE-14003178, Update Foreign Ownership, Control, or Influence (FOCI)2014-09-17017 September 2014 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-14003101, Enclosure 1 to Enclosure 6 Concerning Second Set of Responses to April 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Application2014-06-25025 June 2014 Enclosure 1 to Enclosure 6 Concerning Second Set of Responses to April 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Application ML14168A2682014-05-0101 May 2014 Texas Pollutant Discharge Elimination System Major Amendment with Renewal Application for a Major Facility Tpdes Permit No. WQ000190800 NOC-AE-14003103, University of Texas White Paper, Means of Aggregation and NUREG-1829: Geometric and Arithmetic Means, Rev. 3, Enclosure 2 to Attachment 12014-04-18018 April 2014 University of Texas White Paper, Means of Aggregation and NUREG-1829: Geometric and Arithmetic Means, Rev. 3, Enclosure 2 to Attachment 1 ML14087A0782014-04-15015 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident (TAC MF0178 & MF0179) NOC-AE-14003114, Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai..2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai.. NOC-AE-13003067, Supplement to Seismic Walkdown Summary Report of Items Classified as Inaccessible2014-02-27027 February 2014 Supplement to Seismic Walkdown Summary Report of Items Classified as Inaccessible ML13323A1862013-11-12012 November 2013 Enclosure 4-1 - Risk-Informed Closure of GSI-191, Volume 1 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 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 ML13323A1892013-10-22022 October 2013 Enclosure 4-2 - Risk-Informed Closure of GSI-191, Volume 2 Probabilistic Risk Analysis NOC-AE-13003019, Submittal of Commitment Change Summary Report for the Period June 21, 2011 Through June 21, 20132013-07-18018 July 2013 Submittal of Commitment Change Summary Report for the Period June 21, 2011 Through June 21, 2013 NOC-AE-13003004, Revised Phase 1 Staffing Assessment Submitted in Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights2013-06-0303 June 2013 Revised Phase 1 Staffing Assessment Submitted in Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights ML13141A2852013-04-25025 April 2013 License Amendment Request, Proposed Revision to Technical Specification 5.0, Design Features NOC-AE-12002912, Submittal of 10 CFR 50.46 ECCS Evaluation Model Significant Change/Error Report2012-10-17017 October 2012 Submittal of 10 CFR 50.46 ECCS Evaluation Model Significant Change/Error Report ML12234A6042012-08-21021 August 2012 Email - Documents for NRC Public Meeting on Corrosion Head Loss Experiments (Chle) Part 1 and 2 ML1130606152011-10-31031 October 2011 LOCA Frequencies for STP Nuclear Operating Company GSI-191 ML1130506232011-10-26026 October 2011 Alion- Expected Impact of Chemical Effects on GSI-191 Risk Informed Evaluation for South Texas Project NOC-AE-11002708, 10CFR50.59 Summary Report2011-10-10010 October 2011 10CFR50.59 Summary Report ML11256A0582011-08-31031 August 2011 Documents to Support Review of the South Texas Project License Renewal Application, WR-5, Tceq Id No. 1610103/1610051 (Operation of Public Potable Water System) ML11196A0052011-08-0404 August 2011 Summary of Site Audit Related to the Review of the License Renewal Application for South Texas Project, Units 1 and 2 ML11217A0162011-07-27027 July 2011 Commitment Change Summary Report NOC-AE-09002457, Nuclear Decommissioning Trust Fund Agreements (Updated)2009-09-15015 September 2009 Nuclear Decommissioning Trust Fund Agreements (Updated) NOC-AE-09002445, Submittal of Commitment Change Summary Report for July 31, 2008 Through July 30, 20092009-07-30030 July 2009 Submittal of Commitment Change Summary Report for July 31, 2008 Through July 30, 2009 NOC-AE-09002424, Submittal of Description and Summary of the 10CFR50.59 Evaluations of Changes, Tests and Experiments Report2009-04-28028 April 2009 Submittal of Description and Summary of the 10CFR50.59 Evaluations of Changes, Tests and Experiments Report NOC-AE-08002325, Commitment Change Summary Report2008-08-11011 August 2008 Commitment Change Summary Report ML0807006992008-02-28028 February 2008 Evidence of Financial Protection NOC-AE-07002231, Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46)2007-11-0707 November 2007 Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46) NOC-AE-07002177, Proposed Alternative to ASME Section XI Requirements for Weld Overlay Hold-Time (RR-ENG-2-48)2007-06-19019 June 2007 Proposed Alternative to ASME Section XI Requirements for Weld Overlay Hold-Time (RR-ENG-2-48) NOC-AE-07002168, Summary Assessment of Pressurizer Nozzle Safe End Weld Overlays: Shrinkage and Fatigue Crack Growth (RR-ENG-2-43)2007-05-29029 May 2007 Summary Assessment of Pressurizer Nozzle Safe End Weld Overlays: Shrinkage and Fatigue Crack Growth (RR-ENG-2-43) NOC-AE-06002049, Commitment Change Summary Report2006-08-21021 August 2006 Commitment Change Summary Report NOC-AE-06001977, Submittal of Nuclear Insurance Protection2006-02-0909 February 2006 Submittal of Nuclear Insurance Protection NOC-AE-05001919, Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for the Essential Cooling Water System (Ecw Train 1A)2005-09-0808 September 2005 Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for the Essential Cooling Water System (Ecw Train 1A) NOC-AE-05001874, Transmittal of the 10CFR50.59 Summary Report2005-04-28028 April 2005 Transmittal of the 10CFR50.59 Summary Report ML0532204612004-06-14014 June 2004 Power Reactor Status Report for 6/14/04 ML0319800132003-07-18018 July 2003 Misc Report ,Stars, 6/10-11/2003 Licensing Workshop Held in Overland Park, Kansas with Strategic Teaming and Resource Sharing-Integrated Regulatory Affairs Group for Licensees of Callaway, Comanche Peak, Diablo Canyon, Palo Verde, So Texas NOC-AE-03001532, Request for One-Time Approval of an Alternative Approach for Containment Tendon Surveillances2003-05-15015 May 2003 Request for One-Time Approval of an Alternative Approach for Containment Tendon Surveillances NOC-AE-03001509, Special Report Re Power-Operated Relief Valve Actuation to Mitigate Reactor Coolant System Pressure Transient2003-04-25025 April 2003 Special Report Re Power-Operated Relief Valve Actuation to Mitigate Reactor Coolant System Pressure Transient NOC-AE-02001277, Project Comprehensive Cultural Assessment2002-04-17017 April 2002 Project Comprehensive Cultural Assessment 2023-08-31
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LMM§A Nuclear Operating Company South Texs Pm/Cd Electric Generating Stationi PO Bor 28.9 Wdsworth, Texs 77483 _ _________________
June 19, 2007 NOC-AE-070021 77 File No.: G25 10 CFR 50.55a U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 South Texas Project Unit 1 Docket No. STN 50-498 Proposed Alternative to ASME Section XI Requirements for Weld Overlay Hold-Time (RR-ENG-2-48)
In accordance with the provisions of 10 CFR 50.55a(a)(3)(i), the South Texas Project requests NRC approval of an alternative approach to the requirements of ASME Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components."
ASME Section XI Code Case N-638-1 requires a 48-hour hold-time after the weld overlay temperature reaches ambient conditions following completion of the weld overlay. Under the proposed alternative, the examination will be performed no sooner than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after completion of the third temperbead layer over the ferritic base material.
The proposed alternative approach will provide an acceptable level of quality and safety.
The overlay will be applied during the South Texas Project Unit 1 spring 2008 refueling outage.
The discussion in Attachment 1 provides the basis and justification for the proposed alternative.
To support preparation for the upcoming outage, NRC approval of this proposed alternative is requested by December 31, 2007.
A similar request from the Callaway plant was submitted August 14, 2006 (Adams Accession No. ML062360200) and followed up with correspondence dated March 26, 2007 (ML070990115). Approval for the change was given in a telephone conference on April 5, 2007.
There are no commitments included in the attached request.
If there are any questions, please contact either Mr. P. L. W iker at (361) 972-8392 or me at (361) 972-7030.
4s nglPrograms PLW
Attachment:
Proposed Alternative to ASME Section XI Requirements for Weld Overlay Hold-Time (RR-ENG-2-48)
STI: 32172627
NOC-AE-070021 77 Page 2 of 2 cc:
(paper copy) (electronic copy)
Regional Administrator, Region IV A. H. Gutterman, Esquire U. S. Nuclear Regulatory Commission Morgan, Lewis & Bockius LLP 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mohan C. Thadani U. S. Nuclear Regulatory Commission Mohan C. Thadani Thad Hill Project Manager Steve Winn U.S. Nuclear Regulatory Commission Harry Holloway One White Flint North (MS 7 D1) Eddy Daniels 11555 Rockville Pike Marty Ryan Rockville, MD 20852 NRG South Texas LP Senior Resident Inspector J. J. Nesrsta U. S. Nuclear Regulatory Commission R. K. Temple P.O0. Box 289, Mail Code: MN1 16 E. Alarcon Wadsworth, TX 77483 Kevin Polio City Public Service C. M. Canady Jon C. Wood City of Austin Cox Smith Matthews Electric Utility Department 721 Barton Springs Road C. Kirksey Austin, TX 78704 City of Austin Richard A. Ratliff Bureau of Radiation Control Texas Department of State Health Services 1100 West 49th Street Austin, TX 78756-3189
Attachment NOC-AE-070021 77 Page 1 of 6 SOUTH TEXAS PROJECT PROPOSED ALTERNATIVE TO ASME SECTION XI REQUIREMENTS FOR WELD OVERLAY HOLD TIME (RELIEF REQUEST RR-ENG-2-48)
1.0 ASME Code Components Affected
System: 'Reactor Coolant System Identifiers: Unit 1 6"RC1 0031311 (Pressurizer Spray Line Nozzle Safe End Welds) 6"RC1 004NSS (Pressurizer Safety Line Nozzle Safe End Welds) 6"RC1 009NSS (Pressurizer Safety Line Nozzle Safe End Welds) 6"RC101 2NSS (Pressurizer Safety Line Nozzle Safe End Welds) 6"RC101 5NSS (Pressurizer Relief Line Nozzle Safe End Welds)
Function: There are six low alloy steel nozzles for each pressurizer. Each has an Alloy 82/182 weld connecting the low alloy steel nozzle to an austenitic stainless steel (SS) safe end, and an SS weld connecting the safe end to SS piping. One nozzle located on the bottom of the pressurizer connects the surge line from the Loop 4 hot leg to the pressurizer - the weld overlay for this nozzle has been completed. Of the remaining five nozzles, one nozzle at the top of the pressurizer receives flow from the Loop 1 and Loop 4 cold legs for pressurizer spray. Four nozzles at the top of the pressurizer provide a relief path to the pressurizer relief tank for overpressure protection. The pressurizer design data are attached.
Code Class: Class 1
2.0 Applicable Code Edition and Addenda
The South Texas Project Inservice Inspection program for the second ten-year interval complies with the requirements of ASME Section Xl, 1989 Edition and the 1995 Edition with 1996 Addenda for application of Section X1, IWA-2300, Appendix I, Appendix VII, and Appendix VI II.
Design and fabrication are in accordance with ASME Section 111,1974 Edition.
3.0 Applicable Code Requirements Paragraph 4.0(b) of Code Case N-638-1 states that examination of the final weld surface and the band around the weld area (at least 1-1/2 times the component thickness or 5-inches, whichever is less) using surface and ultrasonic methods is to be performed when the completed weld has been at ambient temperature for at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
4.0 Reason for Request
Examination requirements of. Code Case N-638-1 effectively prolong the process of applying pressurizer nozzle weld overlays. The additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> has the potential for delaying completion of other tasks such that the actual duration of the outage is extended, with no apparent benefit.
Attachment NOC-AE-070021 77 Page 2 of 6 5.0 Proposed Alternatives Examination of the final weld surface and the band around the weld area (at least 1-1/2 times the component thickness or 5-inches, whichever is less) shall be performed using surface and ultrasonic methods. Examination of the weld overlay covering the ferritic base material and examination of the adjacent ferritic base material shall be performed no sooner than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after completion of the third temperbead layer over the ferritic base material. This removes the requirement for a hold time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after ambient temperature is reached following completion of the weld overlay before examination can be performed.
6.0 Basis for Use Application of a weld overlay requires welding on the low alloy steel nozzle material with Alloy 52M (ERNiCrFe-7a). Temper bead welding will be used for this purpose using. the guidance of Code Case N-638-1, "Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique." Code Case N-638-1 describes the process for welding similar and dissimilar metals using the ambient temperature machine gas tungsten arc weld (GTAW) temper bead method. Code Case N-638-1 was conditionally approved for generic use in NRC Regulatory Guide 1.147, Revision 14.
Weld overlay by GTAW will be performed at the South Texas Project in accordance with Code Case N-638-1, with some exceptions. The exceptions are:
" The maximum area of an individual weld based on the finished surface over the ferritic material shall not exceed 200 square inches. (Code Case N-638-1, paragraph 1.0(a))
- The ultrasonic test coverage area will be defined using Code Case N-504-2 and Appendix Q. The band around the welded area will only receive a surface examination. (Code Case N-638-1, paragraph 4.0(b))
These exceptions were approved in NRC correspondence dated April 2, 2007, "Request for Relief No. RR-ENG-2-43 for Remainder of Second 10-Year Inservice Inspection Interval Re: Application of Weld Overlays in Pressurizer Nozzle Safe End Welds" (ADAMS Accession No. ML070810264).
The presence of monatomic hydrogen in a hardened base metal heat-affected-zone microstructure that has not been adequately tempered may result in delayed heat-affected-zone cracking. The 48-hour hold time is specified to allow sufficient time for hydrogen cracking to occur (if it is to occur) in the heat-affected zone (HAZ) of ferritic materials prior to performing NDE so that NDE would be able to detect it.
Based on extensive research and industry experience, the Electric Power Research Institute (EPRI) has provided a technical basis for starting the 48-hour hold after completion of the third temper bead weld layer rather than waiting for the weld overlay to cool to ambient temperature. EPRI has documented their technical basis in Technical Report 1013558, 'Temper Bead Welding Applications - 48 Hour Hold Requirements for Ambient Temperature Temperbead Welding" (ADAMS Accession No. ML070670060).
The EPRI report addresses previous concerns regarding the 48-hour hold time prior to final NDE examinations. Areas of concern imposing the 48-hour hold time addressed through this report include: material microstructure; sources for hydrogen introduction; tensile stress and temperature; and diffusivity and solubility of hydrogen in steels. The report concludes there is no technical basis for waiting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the weld overlay
Attachment NOC-AE-070021 77 Page 3 of 6 cools to ambient temperature before beginning to perform final NDE of the completed weld overlay.
The ferritic nozzle base material heat-affected zone of the first Alloy 52M layer is the only region susceptible to potential hydrogen-delayed cracking. Code Case N-504-2 and Appendix Q require liquid penetrant examination (PT) prior to installation of the weld overlay. Cleaning the base metal for PT provides assurance, in addition to typical welding process controls, that deleterious hydrogen from surface contamination is not introduced in the first layer of the weld overlay. Examination of the volume and area required by Code Case N-504-2 and Appendix 0 is adequate for detection of hydrogen-delayed cracks occurring in the vicinity of the first layer HAZ.
Hydrogen contamination to deleterious levels. from outside sources is unlikely when applying the ambient temperature temperbead machine GTAW process with the associated methodologies specified for welding control, cleanliness, and examination.
As compared to flux-type welding processes, machine GTAW with argon shielding is an inherently low-hydrogen process that provides optimum temperbead welding controls to ensure adequately tempered base metal HAZ with high fracture toughness. The low hydrogen and tempering characteristics of the machine GTAW process are documented in EPRI GC-1 11050, "Ambient Temperature Preheat for Machine GTAW Temperbead Applications."
Weld layers beyond the third layer are not designed to provide tempering to the ferritic HAZ when performing ambient temperature temper bead welding. The technical data
,provided by EPRI in their report is based on testing performed on SA-508 Class 2 low-alloy steels and other P-Number 3, Group 3 materials. The South Texas Project
,pressurizer nozzles are manufactured from SA-508 Class 2 carbon steel.
After evaluating all of the issues relevant to hydrogen cracking, such as microstructure of
,susceptible materials, availability of hydrogen, applied stresses, temperature, and diffusivity and solubility of hydrogen in steels, EPRI concluded that: ". ..[t]here appears to be no technical basis for waiting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after cooling to ambient temperature before beginning the NDE of the completed weld. There should be no hydrogen present, and even if it were present, the temper bead welded component should be very tolerant of the moisture...." EPRI also notes that over 20 weld overlays and 100 repairs have been performed using temper bead techniques on low alloy steel components over the last 20 years. During this time, there has never been an indication of hydrogen cracking identified by NDE performed after the 48-hour hold or by subsequent 151.
In addition, the ASME Section XI Code Committee published Technical Basis Paper RRA 05-08 (ADAMS Accession No. MIL070790679) supporting the 48-hour hold time alternative. The ASME report points out that introduction of hydrogen to the ferritic HAZ is limited to the first weld layer since this is the only weld layer that makes contact with the ferritic-base material. While the potential for the introduction of hydrogen to the ferritic HAZ is negligible during subsequent weld layers, these layers provide a heat source that accelerates the dissipation of hydrogen from the ferritic HAZ in non-water backed applications. Furthermore, the solubility of hydrogen in austenitic materials such as Alloy 52M is much higher than that of ferritic materials while the diffusivity of hydrogen in austenitic materials is lower than that of ferritic materials. As a result, hydrogen in the ferritic HAZ tends to diffuse into the austenitic weld metal, which has a much higher solubility for hydrogen. This diffusion process is enhanced by heat supplied in subsequent weld layers. The ASME Technical Basis Paper concludes that there is
Attachment NOC-AE-070021 77 Page 4 of 6 sufficient delay time to facilitate the detection of potential hydrogen cracking when NDE is performed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after completion of the third weld layer.
The high affinity of fully austenitic Alloy 52M filler metal for monatomic hydrogen combined with a low diffusion coefficient keeps diffusion of deleterious hydrogen into the low alloy ferritic base material to negligible levels. Furthermore, only welding in contact with the low alloy ferritic base material has potential for introducing deleterious monatomic hydrogen into a hardened untempered HAZ. Each successive temperbead layer has a decreasing propensity for introducing hydrogen into the ferritic base material due to increasing distance from the susceptible base metal HAZ. After three layers, the temperbead process adequately tempers the martensite formed in the ferritic base material by the first layer. Tempering by the third weld layer decreases the hardness and increases the fracture toughness in the potentially susceptible ferritic base material HAZ, thus mitigating susceptibility to delayed hydrogen cracking.
Additionally, the interpass temperature controls of Code Case N-638-1 maintain the temperature near or at ambient temperature between the relatively short and infrequent localized welding heat cycles. N-638-1 requires a 350OF interpass temperature for the first three layers to ensure adequately high cooling rates to promote a base metal HAZ microstructure with high fracture toughness. A 350OF interpass temperature is required for the fourth and subsequent layers to protect against sensitization of the austenitic groove weld and austenitic base materials, and to maintain an acceptable microstructure in the Alloy 52M overlay weld metal. The 350OF interpass temperature control maintains the ferritic base metal HAZ at relatively low temperatures, which effectively contributes to time at or near ambient temperature. For times during the welding process when temperatures are above ambient, the elevated temperatures are beneficial and enhance diffusion of hydrogen out of the ferritic base material HAZ. Therefore, it is both reasonable and conservative to include the temperbead welding time following
.completion of the third layer in the total 48-hour hold time required prior to performing final examination of the ferritic base material and of the weld overlay on the ferritic base material.
ASME Code Case N-638-3, which does not require examination of the band around the repair area, has been published in Supplement 9 to the 2004 Edition of ASME Section Xl. Also, the Boiler and Pressure Vessel Main Committee in August 2006 approved a revision to N-638-3 which permits the 48-hour hold to start following completion of the third temperbead layer.
In summary, the inherent low hydrogen nature of the prescribed ambient temperature temperbead machine GTAW process, the relatively low susceptibility of hydrogen-induced cracking in ferritic base material HAZ when using nickel alloy filler metals, and performance of the Appendix Q and N-504-2 final examination (as modified) 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after completion of the third layer over the ferritic base material provide substantial assurance against the potential for delayed hydrogen cracking in the ferritic base material HAZ.
7.0 Duration of Proposed Alternative This proposed alternative is for application as needed during the remainder of the current inspection interval which ends September 24, 2010 for Unit 1. The duration of the proposed alternative is the remaining service life of the affected components.
Attachment NOC-AE-070021 77 Page 5 of 6 8.0 Implementation The structural WOL will be installed during the South Texas Project Unit 1 Spring 2008 refueling outage as a preventive measure against flaw development or means of repair for any flaws that may be present in the dissimilar metal welds. NRC approval of the proposed alternative to the 48-hour hold time criterion of Code Case N-638-1 is requested by December 31, 2007, to support scheduling of activities during the outage.
Attachment NOC-AE-070021 77 Page 6 of 6 PRESSURIZER DESIGN DATA Pressurizer Spray Line, nominal pipe size 6 inches Pressurizer Spray Line, nominal thickness 0.719 inch Pressurizer Safety and Relief Line, nominal pipe size 6 inches Pressurizer Safety and Relief Line, nominal thickness 0.719 inch Design Pressure 2,485 psig Design Temperature 6800 F Nozzle Material SA-508 Class 2 steel Safe End Material SA-1 82 F316L Existing Nozzle Weld Material Alloy 82/182 (Connects the low alloy steel nozzle to the austenitic stainless steel safe end)