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Category:Letter
MONTHYEARIR 05000498/20244022024-10-23023 October 2024 Security Baseline Inspection Report 05000498/2024402 and 05000499/2024402 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function ML24295A0772024-10-21021 October 2024 Licensed Operator Positive Fitness-for-Duty Test 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function NOC-AE-240040, Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2024-10-16016 October 2024 Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan IR 05000498/20243012024-10-0707 October 2024 NRC Examination Report 05000498/2024301 and 05000499/2024301 ML24255A0322024-09-30030 September 2024 The Associated Independent Spent Fuel Storage Installation - Notice of Consideration of Approval of Direct Transfer of Licenses and Opportunity to Request a Hearing (EPID L-2024-LLM-0002) - Letter ML24269A1762024-09-25025 September 2024 Tpdes Permit Renewal Application WQ0001 908000 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps ML24271A3022024-09-18018 September 2024 STP-2024-09 Post-Exam Comments - Redacted ML24274A0902024-09-16016 September 2024 Written Response - EA-24-026 STP Operator - Redacted ML24250A1882024-09-11011 September 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal ML24249A3372024-09-0404 September 2024 Inservice Inspection Summary Report - 2RE23 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators ML24234A0912024-08-27027 August 2024 NRC Initial Operator Licensing Examination Approval 05000498/2024301; 05000499/2024301 IR 05000498/20240052024-08-22022 August 2024 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2024005 and 05000499/2024005) IR 05000498/20240022024-08-0909 August 2024 Integrated Inspection Report 05000498/2024002 and 05000499/2024002 IR 05000498/20240102024-08-0808 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010 ML24213A0842024-07-31031 July 2024 Application for Order Consenting to Direct Transfer of Licenses ML24218A1462024-07-26026 July 2024 2. EPA Comments on South Texas Project Exemption Ea/Fonsi ML24207A1782024-07-25025 July 2024 Licensed Operator Positive Fitness-For-Duty Test 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function IR 05000498/20244042024-06-0303 June 2024 Cyber Security Inspection Report 05000498/2024404 (Cover Letter) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual ML24136A2842024-05-15015 May 2024 Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance ML24137A0882024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24128A1572024-05-0707 May 2024 Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000498/20240012024-05-0606 May 2024 Integrated Inspection Report 05000498/2024001 & 05000499/2024001 ML24120A3762024-04-29029 April 2024 Annual Dose Report for 2023 ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment ML24117A1602024-04-24024 April 2024 2023 Radioactive Effluent Release Report ML24102A2452024-04-23023 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24113A3122024-04-22022 April 2024 Cycle 24 Core Operating Limits Report ML24097A0072024-04-0606 April 2024 Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75 ML24092A1902024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24088A3022024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update ML24081A3972024-03-21021 March 2024 Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24080A2902024-03-19019 March 2024 Nuclear Liability Certificates of Insurance ML24066A2002024-03-0606 March 2024 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML24079A1312024-03-0505 March 2024 Nuclear Insurance Protection ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 IR 05000498/20230062024-02-28028 February 2024 Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006) IR 05000498/20240132024-02-27027 February 2024 Design Basis Assurance Inspection (Programs) Commercial Grade Dedication IR 05000498/2024013 and 05000499/2024013 2024-09-04
[Table view] Category:Report
MONTHYEARML23243B0562023-08-31031 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 ML14072A0802014-02-24024 February 2014 CHLE-006, STP Material Calculations, Revision 2 ML14072A0832014-02-24024 February 2014 CHLE-010, Chle Tank Test Results for Blended and NEI Fiber Beds with Aluminum Addition, Revision 3 ML14072A0862014-02-24024 February 2014 CHLE-015, Summary of Chemical Effects Testing in 2012 for STP GSI-191 License Submittal, Revision 4 ML14072A0872014-02-24024 February 2014 CHLE-016, Calculated Material Release to Estimate Chemical Effects, Revision 3 ML14072A0822014-02-23023 February 2014 CHLE-008, Debris Bed Preparation & Formation Test Results, Revision 4 ML14072A0852014-02-22022 February 2014 CHLE-014, T2 LBLOCA Test Report, Revision 3 ML14072A0882014-02-22022 February 2014 CHLE-018, Results of Bench Tests to Assess Corrosion of Aluminum in STP Containment Conditions, Revision 3 ML14072A0792014-02-22022 February 2014 CHLE-020, Test Results for 10-Day Chemical Effects Test Simulating LBLOCA Condition (T5), Revision 3 ML14072A0772014-02-18018 February 2014 CHLE-005, Determination of the Initial Pool Chemistry for the Chle Test, Revision 2 ML14072A0842014-02-18018 February 2014 CHLE-012, T1 Mbloca Test Report, Revision 4 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 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 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 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 ML13175A2402013-06-0606 June 2013 Project, Units 1 and 2, Enclosure 4-3 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 3 Engineering Casa Grande Analysis, Page 1 of 260 Through Page 160 of 260 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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Nuclear Operating Company South Teas Project Electric Generating Station P. Box 289 Wadsworth, Texas 77483 _August 11 2008 N(Y-AE-0d002325 File No.: G25 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 South Texas Project Commitment Chanqe Summary Report Attached is the South Texas Project (STP) Commitment Change Summary Report for the period August 1, 2006 through July 30, 2008. This report lists each commitment for which a change was made during the reporting period and provides the basis for each change.The commitments were evaluated in accordancewith the requirements of STP's Regulatory Commitment Change Process, which is consistent with the guidance in the Nuclear Energy Institute's NEI 99-04, "Guideline for Managing NRC Commitments." Additional documentation is available at STP for your review.There are no new commitments in this letter.If there are any questions, please contact either Marilyn Kistler at 361-972-8385 or me at 361-972-7136.
Scott M. Head Manager, Licensing mk
Attachment:
Commitment Change Summary Report A6oof STI: 32326961 NOC-AE-08002325 Page 2 of 2 cc: (paper copy)(electronic copy)Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 612 East Lamar Blvd, Suite 400 Arlington, Texas 76011-4125 Mohan C. Thadani Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North (MS 7 D1)11555 Rockville Pike Rockville, MD 20852 Richard A. Ratliff Bureau of Radiation Control Texas Department of State Health Services 1100 West 49th Street Austin, TX 78756-3189 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 289, Mail Code: MN116 Wadsworth, TX 77483 A. H. Gutterman, Esquire Morgan, Lewis & Bockius LLP Mohan C. Thadani U. S. Nuclear Regulatory Commission Thad Hill Catherine Callaway Jim von Suskil NRG South Texas LP Ed Alarcon J. J. Nesrsta R. K. 7 Temple Kevin Polio City Public Service Jon C. Wood Cox Smith Matthews C. Kirksey City of Austin ATTACHMENT Commitment Change Summary Report Attachment NOC-AE-08002325 Page 1 of 5 Condition Source Source Date of " -Original Commitment Revised Commitment Justification for Change Report Document Date Change Description Description Number 04-3365 NOC-AE- 08/05/2004 12/05/2006 NOC-AE-04001758, 08/05/04 -Response Alternative:
The vendor for the analyses could not 04001758 to Request for Information on NRC Generic produce their deliverables on the needed Letter 2003-01 -Control Room Habitability Revise the control room dose schedule.Response to accident analyses to reflect the Generic Letter Revise the control room dose accident results of the control room inleakage 2003-01 analyses to reflect the results of the control testing. Due Date April 30. 2007.room inleakage testing. Due Date December 31, 2005 04-12498 NOC-AE- 12/10/2007 07/09/2008 NOC-AE-07002237, 12/10/2007
-Request Submittal of letter verifying Extension of date to adopt revised ECCS 07002237 for Extension for Final Response to Generic completion and confirming sump strainer design basis is an Letter 2004-02 and Implementation of compliance will be submitted to the administrative change and has no effect Response to Revised Design Basis for ECCS Sump NRC by December 12, 2008. on plant operations.
NRC approval was Generic Letter provided by telephone July 1, 2008, and 2004-02 Following completion of the 10 CIFR 50, by correspondence dated July 2, 2008.Appendix B activities described above andb the associated changes to the STP licensing basis, STPNOC will submit a letter verifying completion of all GL 2004-02 corrective actions and confirming compliance with the regulatory requirements listed in GL 2004-02.06-6838 NOC-AE- 12/03/2001 05/25/2006 Commitment for SDG allowed outage time Implementation of risk management The existing requirements for implementing 01001196 extension:
actions will be based on reaching or risk management action (RMA) is simply expecting to reach the 1 E-06 based on being the configuration beyond a Proposed The NRC.Safety Evaluation (SE) lists incremental core damage probability prescribed time. For the Standby Diesel Amendment to the compensatory actions for risk threshold instead of a prescribed Generator, Essential Cooling Water, and Technical extending the allowed outage times for time. This approach is consistent with Essential Chilled Water, the RMA is Specification the Standby Diesel Generators (TS the Risk Managed Technical implemented if the SSC will be inoperable 3.7.1.2 3.8.1.1), Essential Cooling Water (TS Specifications (RMTS) Guidelines.
for longer than the duration of the allowed 3.7.4) and Essential Chilled Water (TS The specific requirement in the RMTS outage time prior to approval of Amendment 3.7.14). The internal memo (HS-HS- Guidelines reads: 85/72. For one inoperable MD Auxiliary 35345) documents a phone call with Feedwater pump, the RMA will be the NRC that confirms that the intent of For plant configurations in which implemented if the duration of the inoperable the SE was that the compensatory the RMAT (Risk Management condition will exceed 14 days. These times actions would be required if the outage Action Threshold) either has are prescriptive and do not take into account duration would be longer than the been exceeded (emergent the actual quantified risk of the plant original allowed outage time (i.e., event) or is anticipated to be configuration when the SSC is removed longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />). exceeded (either planned from service or becomes inoperable for an condition or emergent event), emergent condition.
Commitment for AFW motor-driven pump appropriate compensatory risk allowed outage time extension (ref. NOC-AE- management actions shall be Implementation of the Maintenance Rule 01001196):
identified and implemented.
For (MR) as described in 10CFR50.65(a)(4)
Attachment NOC-AE-08002325 Page 2 of 5 Condition Source Source Date of Original Commitment Revised Commitment Justification for Change Report Document Date Change Description Description Number Compensatory measures will be used to offset the increased risk of allowing a 28-day AOT and will be implemented when it is recognized that maintenance on a motor-driven AFW pump will last for more than 14 days.Both commitments to implement compensatory actions are based on a prescriptive time.Procedure OPOP01-ZO-0006 is the implementing procedure for the compensatory action requirements.
preplanned maintenance activities for which the RMAT is anticipated to be exceeded, RMAs shall be implemented at the earliest appropriate time.The RMAT is the risk management action threshold and is established at 1 E-06 incremental core damage probability or 1 E-07 incremental large early release probability.
RMAs are risk management actions (i.e., compensatory action).These thresholds are consistent with the thresholds used by STPNOC in implementing Maintenance Rule requirements.
requires an assessment of risk for maintenance and that the risk be managed.STPNOC has established a configuration risk management program (CRMP) to comply with the MR. Consistent with NUMARC 93-01, it establishes specific risk thresholds that require compensatory action if the configuration risk exceeds the threshold.
The Non-Risk-Significant Threshold is established at an incremental core damage probability (ICDP) of 1 E-06.RMA is required for configurations where the risk exceeds that threshold.
STPNOC is an industry pilot for a risk-informed process for determining allowed outage times for the STP Technical Specifications (TS). The risk-informed process involves the application of the STP Configuration Risk Management Program (CRMP) to calculate a risk-informed completion time (RICT) based on the time required for the risk calculated for a plant configuration to attain a threshold.
The risk thresholds, the process for calculating the configuration risk, and the requirements for PRA quality are described in the Electric Power Research Institute (EPRI) Risk Managed Technical Specification Guidelines (RMTS Guidelines).
The RMTS Guidelines applies the same ICDP threshold for RMA as the MR. The RMTS Guidelines also establishes a incremental large early release probability (ILERP) threshold of 1 E-07.These thresholds are known as risk management action thresholds (RMAT). The RMTS Guidelines specifically requires RMAs for conditions that exceed the RMAT: For plant configurations in which the RMAT either has been exceeded (emergent event) or is anticipated to be exceeded (either planned condition or emergent event), appropriate compensatory risk management actions shall be identified and implemented.
For Attachment NOC-AE-08002325 Page 3 of 5 Condition Source Source Date of Original Commitment Revised Commitment Justification for Change Report Document Date Change Description Description Number preplanned maintenance activities for which the RMAT is anticipated to be exceeded, RMAs shall be implemented at the earliest appropriate time.This commitment change is described in the license amendment request for the risk-informed TS (NOC-AE-06002005).
Revising the STP procedure to apply thresholds consistent with the MR and the RMTS Guidelines will establish an internally consistent risk-informed process with one set of criteria that are firmly grounded in industry and regulatory precedent.
07-457-66 NOC-AE- 02/22/2007 12/12/2007 NOC-AE-07002114, Attachment 1, Page 4 For both the SFP External Makeup During revision of implementing 07002114 of 18, Table A.2-3, SFP External Spray (Table A.2-2) and SFP External procedures it was determined that the Strategy General Description, states in Spray (Table A.2-3) strategies the backup method of connecting the portable Phase 2 and 3 part: preferred source of water will be pump to draw from the identified Mitigation firewater from a yard fire hydrant, if Circulating Water locations in the Strategies
...the preferred source of water will available, since it is more easily procedure would take more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.NOC-AE- 05/14/2007 be firewater from a yard fire hydrant, deployed.
Water can also be Therefore two other locations where it was 07002150 if available, since it is more easily supplied by pumping water from the deemed feasible to meet the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> deployed.
Water can also be Circulating Water System below deployment time were identified.
The Phase 2 and 3 supplied by pumping water from the ground piping located West of each Demineralized Water Storage Tank has a Mitigation Circulating Water System below Fuel Handling Building using the capacity of up to 1 million gallons. The Strategies
-ground piping located West of each diesel driven portable pump. Other Organics Basin contains water from outage RAI Response Fuel Handling Building using the sources are the Demineralized Water activities and rain water.diesel driven portable pump. Storage Tank located east of the Unit AE-NOC- 07/11/2007 1 Fuel Handling Building or the The capability to deploy the strategies 07001653 .- ...The strategy will be deployed within Organics Basin located southeast of within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2 hours when fuel is stored in an the Unit 2 Fuel Handling Building.
with onsite water sources will be met by Safety Evaluation undispersed configuration, the revised strategy.
The preferred source for EA-02-026
... The SFP External Makeup (Table of water will continue to be the firewater Similar commitments were made for the A.2-2) and SFP External Spray system from a yard fire hydrant, if SFP External Makeup Strategy (Table A.2- (Table A.2-3) strategies will be available.
There are options in the 2) on, Page 2 of 18, where it stated that the capable of being deployed within 2 strategies for long term water supply by portable diesel driven pump can be hours, connecting the portable pump to draw supplied from several different long term water from the Demineralized Water sources and supplement the existing fire Water Source & Capacity:
"...there Storage Tank, the Organics Basin, or the water system" to include is available over 1.2E7 gallons from Circulating Water System (CWS) below the Circulating Water System and ground piping to charge the fire header Water Source & Capacity "... 1.2E7 approximately 1 million gallons from. through a yard hydrant. The capability to gallons from the Circulating Water System." the Demineralized Water Storage set-up the portable pump to draw water Attachment NOC-AE-08002325 Page 4 of 5 Condition Source Source Date of Original Commitment Revised Commitment Justification for Change Report Document Date Change Description Description Number Tank." In addition, in NOC-AE-07002150, Attachment 1, Page 2 of 5, RAIs #5 and #8, STP clarified that both the SFP External Makeup (Table A.2-2) and SFP External Spray (Table A.2-3) strategies will be developed to deploy within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in accordance with NEI guidance.from the Demineralized Water Tank into the SFP within the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> requirement has been validated (CR 07-457-65).
The alternate water supplies are necessary because there may be competing needs for the firewater system. The equipment necessary to use these sources is staged and available.
CREE 07-457-63 validates the flow rates using the Demineralized Water Tank as the water source. CREE 07-457-37 and 07-457-38 validate flow rates and capacities using the CWS which can be still be deployed but will require additional set-up time to access the CWS piping if the CWS is determined to be necessary.
The commitment in NOC-AE-07002150, Attachment 1, RAI 8 Page 2 of 7, Table A.2-3 (SFP External Spray Strategy)further clarified that the strategy will be developed to deploy within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The (implementing procedures) guidance will require that the strategy be deployed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when fuel is not dispersed and no later than 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> when fuel is dispersed.
While the spray strategy has been developed to ensure deployment within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, it can be deployed no later than 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> when fuel is in a dispersed configuration.
These commitments were reflected in the Safety Evaluation for AE-NOC-07001653, Appendix B sections, 2.3.1 and section 2.3.2; however, the specific sources of water were not specified in the "Evaluation" section. It is acceptable to make this change without prior NRC notification and approval.
The change will be reflected in the next periodic report of commitment changes and the NRC will be advised of the change during their 2008 inspection of 15b implementation under NRC TI 2515/171.
Attachment NOC-AE-08002325 Page 5 of 5 Condition Source Source Date of. Original Commitment Revised Commitment Justification for Change Report Document Date Change Description Description Number 07-491 NOC-AE-02001320 Control Room Envelope Ventilation System 04/25/2002 07/30/2008 Licensee Event Report 02-001 -CRE Ventilation System Failed to Maintain Positive Pressure in the Control Room Corrective Action #2: Revised the Electrical Auxiliary Building HVAC System procedure to include a description of the CRE HVAC boundary, a list of fire dampers that can affect CRE HVAC operability and general precautions reminding personnel that surrounding HVAC systems can affect CRE HVAC operability.
Revised OPOP02-HE-001, Electrical Auxiliary Building HVAC System to remove the description and list described above and to add procedure precautions section to state: During normal (non-emergency) modes of operation, system registers or access panels may be'removed to facilitate inspection provided the following precautions are in place.A. Communications are established between the control room and the working group.B. In the event of an HVAC actuation to an emergency mode, the register or access panel is to be reinstalled immediately and secured in place.C. Notify the Control Room that the access panel or register has been reinstalled.
Replacing the damper tables and description in the addendum to the procedure with the instructions for communication with the control room provides Operations with positive and immediate configuration control of system boundaries rather than relying on a lengthy table of information.
The use of the dedicated individual for control of the damper configuration is consistent with the guidance for manual actions in Regulatory Issue Summary 2005-20 (now in Part 9900 of the NRC Inspection Manual). The restoration process is simple and there are no environmental conditions that would impact the ability of a dedicated individual to reinstall an access cover or register.Incorporation of the guidance into the operating procedure makes future changes subject to a codified change process (i.e., 10 CFR 50.59). In accordance with NEI 99-04, this corrective action need not be tracked as a commitment.
Note that this commitment change was not documented initially, and this justification was performed after the fact as a Condition Report action.