|
---|
Category:Letter
MONTHYEARML24346A4162024-12-11011 December 2024 Operator Licensing Examination Schedule ML24319A0342024-12-11011 December 2024 The Associated Independent Spent Fuel Storage Installation - Order Approving Direct Transfer of Licenses (EPID L-2024-LLM-0002) - Letter/Safety Evaluation IR 05000498/20240122024-11-25025 November 2024 License Renewal Phase 1 Inspection Report 05000498/2024012 IR 05000498/20240502024-11-21021 November 2024 Project Electric Generating Station, Units 1 and 2 - NRC Special Inspection Report 05000498/2024050 and 05000499/2024050 and Preliminary White Finding ML24318C5082024-11-13013 November 2024 Condition Prohibited by Technical Specifications IR 05000498/20253012024-11-0707 November 2024 Notification of NRC Initial Operator Licensing Examination 05000498/2025301; 05000499/2025301 IR 05000498/20240032024-11-0707 November 2024 Integrated Inspection Report 05000498/2024003 and 05000499/2024003 ML24305A1742024-10-31031 October 2024 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML24304B0512024-10-30030 October 2024 Cycle 26 Core Operating Limits Report IR 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 ML24290A1162024-10-16016 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 ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment 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 ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report 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 2024-09-04
[Table view] Category:Report
MONTHYEARML24305A1742024-10-31031 October 2024 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes 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) 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 NOC-AE-210038, 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 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) 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-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. 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 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 ML14072A0832014-02-24024 February 2014 CHLE-010, Chle Tank Test Results for Blended and NEI Fiber Beds with Aluminum Addition, Revision 3 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 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 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 2024-10-31
[Table view] Category:Miscellaneous
MONTHYEARML23243B0562023-08-31031 August 2023 Supplemental Information to Application for Order Approving Indirect Transfer of Control of Licenses NOC-AE-210038, Commitment Change Summary Report2021-06-30030 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
[Table view] |
Text
Nuclear Operating Company South Teas Pro/ect Electric Generatin$ Station P.. Box 289 Wadsworth. Texas 77483 /
April 25, 2013 NOC-AE-1 3002966 STI: 33655779 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Units 1 -nd 2 Docket Nos. STN 50-498, STN 50-499 License Ame-2ment Request Proposed Revision to Technical Spocifluation 5.0. "Design Features" In accordance with the provisions of 10 CFR 50.90, STP Nuclear Operating Company (STPNOC) hereby requests a license amendment to South Texas Project Operating Licenses NPF-76 and NPF-80. This proposed license amendment revises Technical Specification (TS) 5.1, "Site," Figures with respect to the removal of the Visitor's Center building and references to the location of the Emergency Operations Facility.
The Enclosure provides a technical and regulatory evaluation of the changes demonstrating that no significant hazards will result from the change. Proposed TS page markups are included as an attachment to the Enclosure.
The STPNOC Plant Operations Review Committee has reviewed and concurred with the proposed change to the Technical Specifications.
STPNOC requests approval of this license amendment application by the end of February 2014 with a 30-day implementation period to provide time to revise applicable STP licensing documents.
In accordance with 10 CFR 50.91(b), STPNOC is notifying the State of Texas of this request for license amendment by providing a copy of this letter and the Enclosure.
There are no commitments in this letter.
Aoo(g
NOC-AE-1 3002966 Page 2 If there are any questions regarding the proposed amendment, please contact Marilyn Kistler at (361) 972-8385.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on 0 D, W. Rencurrel Senior Vice President, Operations
Enclosure:
Evaluation of the Proposed Change
NOC-AE-1 3002966 Page 3 cc:
(paper copy) (electronic copy)
Regional Administrator, Region IV A. H. Gutterman, Esquire U. S. Nuclear Regulatory Commission Morgan, Lewis & Bockius LLP 1600 East Lamar Boulevard Arlington, TX 76011-4511 Balwant K. Singal U. S. Nuclear Regulatory Commission Balwant K. Singal John Ragan Senior Project Manager Chris O'Hara U.S. Nuclear Regulatory Commission Jim von Suskil One White Flint Korth (MS 8 B13) NRG South Texas LP 11555 Rockville Pike Rockville, MD 20852 Kevin Polio Senior Resident Inspector Richard Pena U. S. Nuclear Regulatory Commission City Public Service P. 0. Box 289, Mail Code: MN1 16 Wadsworth, TX 77483 C. M. Canady Peter Nemeth City of Austin Crain Caton & James, P.C.
Electric Utility Department 721 Barton Springs Road C. Mele Austin, TX 78704 City of Austin Richard A. Ratliff Texas Department of State Health Services Alice Rogers Texas Department of State Health Services
ENCLOSURE Evaluation of the Proposed Change
Subject:
Proposed Revision to Technical Specification 5.0, "Design Features" 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
5.0 ENVIRONMENTAL CONSIDERATION
S
6.0 REFERENCES
ATTACHMENTS:
- 1. Technical Specification Page Markups
NOC-AE-1 3002966 Page 1 of 3 Enclosure 1.0
SUMMARY
DESCRIPTION The proposed license amendment would revise figures located in Technical Specification (TS) 5.1, "Site". Specifically, the change removes the Visitor's Center building and reference to the onsite Emergency Operations Facility (EOF). Attachment 1 provides the markups for the TS pages.
2.0 DETAILED DESCRIPTION TS 5.1 "Site" Figures 5.1-1 through 5.1-4 identify a Visitor's Center. The Visitor's Center has been demolished. TS 5.1 "Site" Figures 5.1-1, 5.1-3 and 5.1-4 identify the Emergency Operations Facility within the Nuclear Trining Facility. The EOF was relocated to Bay City, Texas approximately 12.5 air miles no.rth north-east of the Station, in the Center for Energy Development building. The relocation of the EOF did not represent a decrease in effectiveness of the Emergency Plan (EP) and did not require prior NRC approval. Reference 6.1 provided notification to the NRC of the EOF relocotion.
3.0 TECHNICAL EVALUATION
The proposed changes to Figures 5.1-1 through 5.1-4 are aýdministrative in nature. Figures 5.1-1 through 5.1-4 contain information beyond the criteria of 10CFR50.36(c)(4) for inclusion in the Design Features section of the Technical Specifications. The new location of the EOF is described in the STP Updated Final Safety Analysis Report (UFSAR) and the STP EP.
The Technical Specification Figure 5.1-1 is a map of the site showing the Exclusion Area as described in the STP UFSAR and the meteorological tower locations. The proposed changes to this figure are the deletion of the Visitor's Center and reference to the onsite EOF. There are no changes to the Exclusion Area as described in the UFSAR.
Figure 5.1-2 is a map of the site showing the Low Population Zone (LPZ) as described in the STP UFSAR. The proposed change to this figure is the deletion of the Visitor's Center. There are no changes to the LPZ as described in the UFSAR.
Figure 5.1-3 is a map identifying the site boundary for radioactive gaseous effluents. In addition the figure identifies structure and release point locations, and areas within the site boundary that are accessible to mernbcrs of the general public. The proposed changer to this figure are the deletion of the Visitor's CL t er and refera to the onsite EOF. There is no change to the site boundary for radioactive g .Jeous effluIsor to the areas closed to public use around the fenced-in plant area (i.e., protccted area). Also, this change does not affect the methodology or parameters used in the Offsite Do3e Calculation Manual for the calculation of radioactive gaseous effluents from 'he plant.
Figure 5.1-4 identifies the location of the liquid effluent discharge into the Colorado River. Also shown is the site boundary for radioactive liquid effluents that is accessible to the public. The proposed changes to this figure are the deletion of the Visitor's Center and reference to the onsite EOF. There are no changes to the site boundary for radioactive liquid effluents or changes to the area closed to public use around the discharge point to the Colorado River.
Also, this change does not affect the methodology or parameters used in the Offsite Dose Calculation Manual for the calculation of radioactive liquid effluents into the Colorado River.
NOC-AE-1 3002966 Page 2 of 3 Enclosure
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria 10CFR50.36(c)(4) Design features. Design features to be included are those features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in categories described in paragraphs (c) (1), (2), and (3) of this section.
4.2 Significant Hazards Considera'ion STP has evaluated whether or not a significant hazards consideration is involved with the proposed anmendment by focusing on the three standards set forth in 10CFR50.92, "Issuance of amendment," as discussed below.
- 1) Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change is an administrative change to STP TS design features to remove reference to the Visitor's Center and onsite EOF. The design function of structures, systems and components (SSC) important to safety are not impacted by the proposed change. The proposed change will not initiate an event. The proposed change does not alter or prevent the ability of SSCs from performing their intended function to mitigate the consequences of an initiating event.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2) Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed change is an admini,-.ico Z hange to STP TS design features to remove reference to the Visitor's: Center ar." E!OF. The Froposed change does not impact create the possibility of a new or d~ix~rent kind of accidunt from any ý.ccident previously evaluated. There are no new failure modes or mechanisms associated with the proposed change. This change does not involve any modification in operational limits or physical design of equipment important to safety.
Therefore, the proposed change does not involve a different kind of accident from any accident previously evaluated.
NOC-AE-13002966 Page 3 of 3 Enclosure
- 3) Does the proposed change involve a significant reduction in a margin of safety?
Response: No The proposed change is an administrative change to STP TS design features to remove reference to the Visitor's Center and onsite EOF. The proposed change does not impact TS safety limits, TS limiting safety system set points, or the results of any of the safety analyses.
Therefore, the proposed change d.)e. not involve a significant reduction in a margin of safety.
Based on the above, STPNOC concludes that the proposed amendments do not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
4.3 CONCLUSION
Based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
S STPNOC has evaluated the proposed amendment for environmental considerations. The proposed amendment is confined to (i) changes to surety, insurance, and/or indemnity requirements, or (ii) changes to recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCES
6.1 Letter, G.O. Hildebrandt to Document Control Deck, "Changes to STP Emergency Plan and Implementing Procedures," D,_*cember 10, 2009 (ML093510267)
Enclosure Aft.chment 1 Technical Specification Page Markups
toI 0=
CLC 99 r+C C) 0C 9l o~ 0 FIGURE 5.1-1 EXCLUSION AREA
0x
-4
-4 C:
-4 C
C+ C+
a) 0 0 FIGURE 5.1-2 LOW POPULATION AREA C)
Cd, 0
-4
-6 In C
-4 Cd, p
N 431 C C c+
N h II 410 0.0.
410 00 II FIGURE 5.1-3 a) ( 0 UNRESTRICTED AREA* AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS EFFLUENTS (SEE ALSO FIGURE 5.1-4) M (0 CA) 0)
FARM ROAD CL
= :1 r+C
- The UNRESTRICTED AREA consists of the orea beyond the SITE BOUNDARY.
SOUTH TEXAS PROJECT UNITS 1 & 2
= M a)0
- 0) 0(
FIGURE 5.1-4 UNRESTRICTED AREA* AND SITE BOUNDARY FOR RADIOACTIVE LIQUID EFFLUENTS CA)