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MONTHYEARML21266A4232021-09-23023 September 2021 10 CFR 50.59 Summary Report Project stage: Request ML21305B8022021-11-0101 November 2021 NRR E-mail Capture - South Texas Project - Acceptance of Requested Licensing Action - Inservice Inspection Impracticality Project stage: Acceptance Review ML22244A2322022-09-0101 September 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Project stage: Supplement ML22244A1152022-09-0101 September 2022 Response to NRC Comments on Relief Request RR-ENG-3-25 Project stage: Request ML22245A0012022-09-12012 September 2022 Relief from the Requirements of the ASME Code Project stage: Approval ML23026A3542023-01-26026 January 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Project stage: Supplement 2022-09-01
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Category:Letter
MONTHYEARIR 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 NOC-AE-240040, Application for Order Consenting to Direct Transfer of Licenses2024-07-31031 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 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 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 ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual NOC-AE-240040, Operator Licensinq Examination Schedule Revision 32024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 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 ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment 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 NOC-AE-240040, Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 752024-04-0606 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 NOC-AE-240040, Financial Assurance for Decommissioning - 2024 Update2024-03-28028 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 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 ML24050A0082024-02-19019 February 2024 Evidence of Financial Protection ML24045A0922024-02-16016 February 2024 Response to STP FOF Move Letter (2024) NOC-AE-240040, Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation2024-02-0808 February 2024 Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation ML24039A1112024-02-0808 February 2024 Operator Licensing Examination Schedule Revision 2 ML24038A3342024-02-0707 February 2024 Change to South Texas Project Electric Generating Station (Stepgs) Emergency Plan ML24033A3002024-02-0707 February 2024 Summary of Regulatory Audit Regarding a Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML24029A2752024-01-29029 January 2024 Request to Reschedule Evaluated Force-on-Force Drill IR 05000498/20230042024-01-29029 January 2024 Integrated Inspection Report 05000498/2023004 and 05000499/2023004 ML24024A1162024-01-24024 January 2024 STP Unit 2 Request for Information IR 05000498/20230032023-12-28028 December 2023 Acknowledgment of Reply to a Notice of Violation (NRC Inspection Report 05000498/2023003 and 05000499/2023003) ML23360A1692023-12-26026 December 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the South Texas Project Medical Services Drill Evaluated on August 31, 2023 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 ML23339A1902023-12-0505 December 2023 Update Foreign Ownership, Control, or Influence (FOCI) ML23326A2592023-12-0505 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report IR 05000498/20234012023-12-0404 December 2023 Security Baseline Inspection Report 05000498/2023401 and 05000499/2023401 ML23324A0102023-11-16016 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23310A2282023-11-13013 November 2023 Integrated Inspection Report 05000498/2023003 and 05000499/2023003, and Notice of Violation ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23298A0002023-11-0101 November 2023 the Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 226 and 211 Related to Order Approving Indirect Transfer of Licenses and Conforming License Amendments ML23279A0342023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Letter) ML23303A0782023-10-30030 October 2023 Submittal of Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments IR 05000498/20234032023-10-26026 October 2023 Material Control and Accounting Program Inspection Report 05000498/2023403 and 05000499/2023403 (Cover Letter) ML23317A1262023-10-12012 October 2023 South. Texas Project Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 26 ML23279A1382023-10-0505 October 2023 Responses to Requests for Additional Information Related to Application for Order Approving Indirect Transfer of Control of Licenses 2024-08-09
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50 Response to Request for Additional Information (RAI)
MONTHYEARML22244A2322022-09-0101 September 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements 2022-09-01
[Table view] Category:Technical Specification
MONTHYEARML23177A2522023-06-26026 June 2023 Units 1, 2 & Independent Spent Fuel Storage Installation - Biennial Submittal of Technical Specification Bases Changes, Commitment Changes, 10 CFR 50.59 Evaluation Summary, and 10 CFR 72.48 Evaluation Summary ML23089A2042023-03-30030 March 2023 License Amendment Request to Revise Alternative Source Term Dose Calculation ML22244A2322022-09-0101 September 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML22221A2122022-08-0909 August 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML21175A3252021-06-24024 June 2021 Technical Specification Bases Control Program NOC-AE-21003814, Technical Specification Bases Control Program2021-06-24024 June 2021 Technical Specification Bases Control Program ML20212L5212020-07-30030 July 2020 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 Improvement Process ML20134K7582020-05-13013 May 2020 License Amendment Request Under Exigent Circumstances for One-Time Revision to Technical Specification 3.5.1 to Reduce Minimum Allowed Accumulator Pressures NOC-AE-20003734, License Amendment Request Under Exigent Circumstances for One-Time Revision to Technical Specification 3.5.1 to Reduce Minimum Allowed Accumulator Pressures2020-05-13013 May 2020 License Amendment Request Under Exigent Circumstances for One-Time Revision to Technical Specification 3.5.1 to Reduce Minimum Allowed Accumulator Pressures NOC-AE-19003677, License Amendment Request to Revise Technical Specifications to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec.2019-09-26026 September 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec. NOC-AE-19003670, Technical Specification Bases Control Program2019-06-19019 June 2019 Technical Specification Bases Control Program NOC-AE-19003617, License Amendment Request to Revise Technical Specifications Tables for a Terminology Change to the P-13 Permissive Interlock Description2019-04-24024 April 2019 License Amendment Request to Revise Technical Specifications Tables for a Terminology Change to the P-13 Permissive Interlock Description NOC-AE-15003272, Technical Specification Bases Control Program2015-07-0202 July 2015 Technical Specification Bases Control Program NOC-AE-14003115, Correction of Technical Specification Typographical Error Incurred During Prior License Amendment Nos. 188 and 1752014-03-27027 March 2014 Correction of Technical Specification Typographical Error Incurred During Prior License Amendment Nos. 188 and 175 NOC-AE-13003011, Report of Changes Made to the Technical Specification Bases Covering the Period from June 16, 2011 to June 16, 20132013-06-17017 June 2013 Report of Changes Made to the Technical Specification Bases Covering the Period from June 16, 2011 to June 16, 2013 NOC-AE-10002554, Technical Specification Bases Control Program (Section 6.8.3.m)2010-04-29029 April 2010 Technical Specification Bases Control Program (Section 6.8.3.m) NOC-AE-09002400, Technical Specification Bases Control Program2009-03-16016 March 2009 Technical Specification Bases Control Program ML0836400802009-01-30030 January 2009 Issuance of Amendment Nos. 190 and 178, Revision to Technical Specification 3.6.1.3, Containment Air Locks NOC-AE-08002319, Response to RAI Revision to Proposed Amendment to TS 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C2008-07-28028 July 2008 Response to RAI Revision to Proposed Amendment to TS 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C NOC-AE-08002255, Transmittal of Proposed Amendment to Technical Specification 3.8.3.12008-03-0606 March 2008 Transmittal of Proposed Amendment to Technical Specification 3.8.3.1 NOC-AE-07002234, Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C2008-01-28028 January 2008 Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C NOC-AE-07002228, License Amendment Request Proposed Revision to Technical Specification 3.6.1.3, Containment Air Locks2008-01-23023 January 2008 License Amendment Request Proposed Revision to Technical Specification 3.6.1.3, Containment Air Locks ML0734503832007-12-0505 December 2007 Technical Specification Bases Control Program ML0730503482007-10-23023 October 2007 License Amendment Request, Proposed Revision to Technical Specifications to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk-Informed Initiative 5b) NOC-AE-07002167, Amended Changes to Technical Specification 3/4.8.2 for Batteries and DC Systems2007-05-31031 May 2007 Amended Changes to Technical Specification 3/4.8.2 for Batteries and DC Systems NOC-AE-07002156, Proposed Change to Surveillance Requirement 4.5.2.d2007-05-21021 May 2007 Proposed Change to Surveillance Requirement 4.5.2.d ML0701201552007-01-11011 January 2007 License Pages 4 & TS 3/4 3-27 - Issuance of Amendment 176 One-Time Change to Loss of Power Instrumentation Technical Specifications NOC-AE-06002101, Proposed One-Time Exigent Change to Loss of Power Instrumentation Technical Specifications2006-12-28028 December 2006 Proposed One-Time Exigent Change to Loss of Power Instrumentation Technical Specifications NOC-AE-06002096, Proposed One-Time Exigent Change to Loss of Power Instrumentation Technical Specifications2006-12-20020 December 2006 Proposed One-Time Exigent Change to Loss of Power Instrumentation Technical Specifications NOC-AE-06002013, License Amendment Request - Proposed Amendment to Technical Specifications: Revision of the Spent Fuel Pool and In-Containment Storage Area Criticality Analysis2006-06-0707 June 2006 License Amendment Request - Proposed Amendment to Technical Specifications: Revision of the Spent Fuel Pool and In-Containment Storage Area Criticality Analysis NOC-AE-05001914, Proposed Change to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation.2006-03-30030 March 2006 Proposed Change to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation. NOC-AE-06001964, Proposed Amendment to Technical Specification 3/4.8.2 to Modify Requirements Related to Batteries and DC Systems -- Revised2006-02-28028 February 2006 Proposed Amendment to Technical Specification 3/4.8.2 to Modify Requirements Related to Batteries and DC Systems -- Revised ML0514407962005-05-19019 May 2005 Tech.Spec.Pages to S.Texas Amendment Nos. 172/160 NOC-AE-05001847, Technical Specification Bases Change2005-02-15015 February 2005 Technical Specification Bases Change NOC-AE-05001834, License Amendment Request Proposed One-Time Change to Technical Specification 3.7.4, Essential Cooling Water System, and Associated Supported Systems Limiting Condition for Operation Action Statement2005-01-0606 January 2005 License Amendment Request Proposed One-Time Change to Technical Specification 3.7.4, Essential Cooling Water System, and Associated Supported Systems Limiting Condition for Operation Action Statement NOC-AE-04001794, License Amendment Request Revision to Proposed Amendment to Technical Specifications for Steam Generators2004-10-0505 October 2004 License Amendment Request Revision to Proposed Amendment to Technical Specifications for Steam Generators NOC-AE-04001786, License Amendment Request to Eliminate the Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports2004-09-30030 September 2004 License Amendment Request to Eliminate the Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports NOC-AE-04001795, Units I and 2 - Proposed Change to Technical Specification Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves.2004-09-30030 September 2004 Units I and 2 - Proposed Change to Technical Specification Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves. NOC-AE-04001780, License Amendment Request Proposed Revision to the Technical Specifications Regarding Deletion of Requirements Related to Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process2004-08-26026 August 2004 License Amendment Request Proposed Revision to the Technical Specifications Regarding Deletion of Requirements Related to Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process NOC-AE-04001697, Proposed Exigent Change to Technical Specification 3/4.7.72004-03-18018 March 2004 Proposed Exigent Change to Technical Specification 3/4.7.7 NOC-AE-04001668, License Amendment Request, Proposed Revision to Technical Specifications Regarding Mode Change Using the Consolidated Line Item Improvement Process2004-02-0303 February 2004 License Amendment Request, Proposed Revision to Technical Specifications Regarding Mode Change Using the Consolidated Line Item Improvement Process NOC-AE-03001660, Supplement 2 to Proposed Emergency Change to Technical Specification 3.8.1.1, Note 122003-12-28028 December 2003 Supplement 2 to Proposed Emergency Change to Technical Specification 3.8.1.1, Note 12 NOC-AE-03001657, Proposed Emergency Change to Technical Specification 3.8.1.1, Note 122003-12-27027 December 2003 Proposed Emergency Change to Technical Specification 3.8.1.1, Note 12 NOC-AE-03001647, Proposed Emergency Change to Technical Specification 3.8.1.1 Re Allowed Outage Time for Unit 2 Standby Diesel Generator 22 from 14 Days to 61 Days2003-12-15015 December 2003 Proposed Emergency Change to Technical Specification 3.8.1.1 Re Allowed Outage Time for Unit 2 Standby Diesel Generator 22 from 14 Days to 61 Days ML0330904832003-10-31031 October 2003 Technical Specification for Amendment 157 NOC-AE-03001580, License Amendment Request - Proposed Amendment to Technical Specification 4.4.5.3a2003-10-16016 October 2003 License Amendment Request - Proposed Amendment to Technical Specification 4.4.5.3a NOC-AE-03001522, TS Bases Changes2003-05-0505 May 2003 TS Bases Changes NOC-AE-03001502, Administrative Revision to Proposed Change to Radiation Monitoring Technical Specifications2003-03-27027 March 2003 Administrative Revision to Proposed Change to Radiation Monitoring Technical Specifications ML0233900782002-11-26026 November 2002 Technical Specifications Pages for Amendmentds 144 & 132 End of Life (Eol) Moderator Temperature Coefficient (Mtc) Surveillance Requirements ML0234005242002-11-26026 November 2002 Technical Specifications Pages for Amendmentds 144 & 132 End of Life (Eol) Moderator Temperature Coefficient (Mtc) Surveillance Requirements 2023-06-26
[Table view] Category:Amendment
MONTHYEARML22244A2322022-09-0101 September 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML22221A2122022-08-0909 August 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML20212L5212020-07-30030 July 2020 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 Improvement Process NOC-AE-20003734, License Amendment Request Under Exigent Circumstances for One-Time Revision to Technical Specification 3.5.1 to Reduce Minimum Allowed Accumulator Pressures2020-05-13013 May 2020 License Amendment Request Under Exigent Circumstances for One-Time Revision to Technical Specification 3.5.1 to Reduce Minimum Allowed Accumulator Pressures ML20134K7582020-05-13013 May 2020 License Amendment Request Under Exigent Circumstances for One-Time Revision to Technical Specification 3.5.1 to Reduce Minimum Allowed Accumulator Pressures NOC-AE-19003677, License Amendment Request to Revise Technical Specifications to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec.2019-09-26026 September 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec. NOC-AE-19003617, License Amendment Request to Revise Technical Specifications Tables for a Terminology Change to the P-13 Permissive Interlock Description2019-04-24024 April 2019 License Amendment Request to Revise Technical Specifications Tables for a Terminology Change to the P-13 Permissive Interlock Description ML0836400802009-01-30030 January 2009 Issuance of Amendment Nos. 190 and 178, Revision to Technical Specification 3.6.1.3, Containment Air Locks NOC-AE-08002255, Transmittal of Proposed Amendment to Technical Specification 3.8.3.12008-03-0606 March 2008 Transmittal of Proposed Amendment to Technical Specification 3.8.3.1 NOC-AE-07002234, Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C2008-01-28028 January 2008 Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C NOC-AE-07002228, License Amendment Request Proposed Revision to Technical Specification 3.6.1.3, Containment Air Locks2008-01-23023 January 2008 License Amendment Request Proposed Revision to Technical Specification 3.6.1.3, Containment Air Locks ML0730503482007-10-23023 October 2007 License Amendment Request, Proposed Revision to Technical Specifications to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk-Informed Initiative 5b) NOC-AE-07002167, Amended Changes to Technical Specification 3/4.8.2 for Batteries and DC Systems2007-05-31031 May 2007 Amended Changes to Technical Specification 3/4.8.2 for Batteries and DC Systems NOC-AE-07002156, Proposed Change to Surveillance Requirement 4.5.2.d2007-05-21021 May 2007 Proposed Change to Surveillance Requirement 4.5.2.d ML0701201552007-01-11011 January 2007 License Pages 4 & TS 3/4 3-27 - Issuance of Amendment 176 One-Time Change to Loss of Power Instrumentation Technical Specifications NOC-AE-06002101, Proposed One-Time Exigent Change to Loss of Power Instrumentation Technical Specifications2006-12-28028 December 2006 Proposed One-Time Exigent Change to Loss of Power Instrumentation Technical Specifications NOC-AE-06002096, Proposed One-Time Exigent Change to Loss of Power Instrumentation Technical Specifications2006-12-20020 December 2006 Proposed One-Time Exigent Change to Loss of Power Instrumentation Technical Specifications NOC-AE-06002013, License Amendment Request - Proposed Amendment to Technical Specifications: Revision of the Spent Fuel Pool and In-Containment Storage Area Criticality Analysis2006-06-0707 June 2006 License Amendment Request - Proposed Amendment to Technical Specifications: Revision of the Spent Fuel Pool and In-Containment Storage Area Criticality Analysis NOC-AE-05001914, Proposed Change to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation.2006-03-30030 March 2006 Proposed Change to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation. ML0514407962005-05-19019 May 2005 Tech.Spec.Pages to S.Texas Amendment Nos. 172/160 NOC-AE-05001834, License Amendment Request Proposed One-Time Change to Technical Specification 3.7.4, Essential Cooling Water System, and Associated Supported Systems Limiting Condition for Operation Action Statement2005-01-0606 January 2005 License Amendment Request Proposed One-Time Change to Technical Specification 3.7.4, Essential Cooling Water System, and Associated Supported Systems Limiting Condition for Operation Action Statement NOC-AE-04001794, License Amendment Request Revision to Proposed Amendment to Technical Specifications for Steam Generators2004-10-0505 October 2004 License Amendment Request Revision to Proposed Amendment to Technical Specifications for Steam Generators NOC-AE-04001795, Units I and 2 - Proposed Change to Technical Specification Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves.2004-09-30030 September 2004 Units I and 2 - Proposed Change to Technical Specification Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves. NOC-AE-04001786, License Amendment Request to Eliminate the Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports2004-09-30030 September 2004 License Amendment Request to Eliminate the Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports NOC-AE-04001780, License Amendment Request Proposed Revision to the Technical Specifications Regarding Deletion of Requirements Related to Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process2004-08-26026 August 2004 License Amendment Request Proposed Revision to the Technical Specifications Regarding Deletion of Requirements Related to Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process NOC-AE-04001697, Proposed Exigent Change to Technical Specification 3/4.7.72004-03-18018 March 2004 Proposed Exigent Change to Technical Specification 3/4.7.7 NOC-AE-04001668, License Amendment Request, Proposed Revision to Technical Specifications Regarding Mode Change Using the Consolidated Line Item Improvement Process2004-02-0303 February 2004 License Amendment Request, Proposed Revision to Technical Specifications Regarding Mode Change Using the Consolidated Line Item Improvement Process NOC-AE-03001647, Proposed Emergency Change to Technical Specification 3.8.1.1 Re Allowed Outage Time for Unit 2 Standby Diesel Generator 22 from 14 Days to 61 Days2003-12-15015 December 2003 Proposed Emergency Change to Technical Specification 3.8.1.1 Re Allowed Outage Time for Unit 2 Standby Diesel Generator 22 from 14 Days to 61 Days ML0330904832003-10-31031 October 2003 Technical Specification for Amendment 157 NOC-AE-03001580, License Amendment Request - Proposed Amendment to Technical Specification 4.4.5.3a2003-10-16016 October 2003 License Amendment Request - Proposed Amendment to Technical Specification 4.4.5.3a ML0234005242002-11-26026 November 2002 Technical Specifications Pages for Amendmentds 144 & 132 End of Life (Eol) Moderator Temperature Coefficient (Mtc) Surveillance Requirements ML0233900782002-11-26026 November 2002 Technical Specifications Pages for Amendmentds 144 & 132 End of Life (Eol) Moderator Temperature Coefficient (Mtc) Surveillance Requirements NOC-AE-02001402, Response to NRC Questions on Proposed Change to Loss of Power & AC Sources TS2002-10-24024 October 2002 Response to NRC Questions on Proposed Change to Loss of Power & AC Sources TS NOC-AE-02001272, Application for Amendment to Several Sections of TS & Unit 2 Operating License to Delete Information Specific to Model E Steam Generators2002-05-23023 May 2002 Application for Amendment to Several Sections of TS & Unit 2 Operating License to Delete Information Specific to Model E Steam Generators NOC-AE-02001237, Proposed Amendment to Technical Specification 3/4.6.1.7, Containment Ventilation System2002-02-18018 February 2002 Proposed Amendment to Technical Specification 3/4.6.1.7, Containment Ventilation System ML0201605202002-01-10010 January 2002 STP, Units 1 and 2 - TS for Amendments No. 135 and 124 2022-09-01
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September 1, 2022 NOC-AE-22003913 10 CFR 50.90 STI: 35356816 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Supplement to Application to Revise Technical Specifications to Adopt TSTF-554, "Revise Reactor Coolant Leakage Requirements" (EPID: L-2021-LLR-0075)
References:
- 1. Letter from K. Harshaw to Document Control Desk; South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Application to Revise Technical Specifications to Adopt TSTF-554, "Revise Reactor Coolant Leakage Requirements; August 9, 2022; NOC-AE-22003908; ML22221A212.
- 2. Email from D. Galvin, NRC to W. Brost, STPNOC; Errors in STP TSTF-554 LAR TS Page Markups; August 23, 2022; AE-NOC-22003346.
In response to Reference 2, STP Nuclear Operating Company (STPNOC) submits this supplement to correct errors identified in Reference 1. These changes do not alter the technical content of the license amendment request.
In the previous submittal Technical Specification page 1-3 did not have Amendments 220 and 205 incorporated and was submitted in error. The corrected page with Amendments 220 and 205 has been incorporated in the enclosure.
In the previous submittal Technical Specification page 1-4 text did not exactly match the authority file of the South Texas Project Technical Specifications. Specifically, Item 1.18 was identified as MEMBER OF THE PUBLIC instead of MEMBER(S) OF THE PUBLIC. The corrected page is incorporated in the enclosure.
This letter contains no new regulatory commitments.
Should you have any questions regarding this submission, please contact Zachary Dibbern at (361) 972-4336 or me at (361) 972-4778.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on _______________________
Kimberly Harshaw Executive VP and CNO Attachments:
- 1. Corrected Proposed Technical Specification Changes (Markup)
- 2. Corrected Revised Technical Specification Pages
NOC-AE-22003913 Page 2 of 2 cc:
Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 E. Lamar Boulevard Arlington, TX 76011-4511 Dennis Galvin Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Operating Reactor Licensing Licensing Project Branch 4 Gregory Kolcum Senior Resident Inspector, South Texas Project U.S. Nuclear Regulatory Commission Chad Stott Resident Inspector, South Texas Project U.S. Nuclear Regulatory Commission
NOC-AE-22003913 Attachment 1 Attachment 1 Corrected Proposed Technical Specification Changes (Markup)
DEFINITIONS DOSE EQUIVALENT XE-133 1.12 DOSE EQUIVALENT XE-133 shall be the concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table III.1 of EPA Federal Guidance Report No. 12, 1993, External Exposure to Radionuclides in Air, Water, and Soil.
ENGINEERED SAFETY FEATURES RESPONSE TIME 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.
FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
GASEOUS WASTE PROCESING SYSTEM 1.15 A GASEOUS WASTE PROCESSING SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
IDENTIFIED LEAKAGE 1.16 IDENTIFIED LEAKAGE shall be:
- a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or
- b. Leakage into the containment atmosphere from sources that are both specifically located and known either to not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or
- c. Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.
SOUTH TEXAS - UNITS 1 & 2 1-3 Unit 1 - Amendment No. 130, 220 Unit 2 - Amendment No. 119, 205
DEFINITIONS MASTER RELAY TEST 1.17 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.
MEMBER(S) OF THE PUBLIC 1.18 MEMBER(S) OF THE PUBLIC means an individual in a controlled area or UNRESTRICTED AREA. However, an individual is not a member of the public during any period in which the individual receives an occupational dose.
1.19 Not Used OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or have OPERABLITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).
OPERATIONAL MODE - MODE 1.21 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.
PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation: (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.
PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall. Leakage past seals, packing, and gaskets is not PRESSURE BOUNDARY LEAKAGE.
SOUTH TEXAS - UNITS 1 & 2 1-4 Unit 1 - Amendment No. 47,52,57, 151 Unit 2 - Amendment No. 36,41,46, 139
REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System operational leakage shall be limited to:
- a. No PRESSURE BOUNDARY LEAKAGE,
- b. 1 gpm UNIDENTIFIED LEAKAGE,
- c. 150 gallons per day of primary-to-secondary leakage through any one steam generator,
- d. 10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System, and
- e. 0.5 gpm leakage per nominal inch of valve size up to a maximum of 5 gpm at a Reactor Coolant System pressure of 2235 20 psig from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.*
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
- a. With any PRESSURE BOUNDARY LEAKAGE, isolate the affected component, pipe, or vessel from the RCS by use of a close manual valve, closed and de-activated automatic valve, blind flange, or check valve within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or , or with primary-to secondary leakage not within limit, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. With Reactor Coolant System operational UNIDENTIFIED or IDENTIFIED LEAKAGE greater than the above limits, reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- c. With primary-to-secondary leakage not within the limit, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
cd. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- Test pressures less than 2235 psig but greater than 150 psig are allowed. Observed leakage shall be adjusted for the actual test pressure up to 2235 psig assuming the leakage to be directly proportional to pressure differential to the one-half power.
SOUTH TEXAS - UNITS 1 & 2 3/4 4-20 Unit 1 - Amendment No. 83, 90, 164 Unit 2 - Amendment No. 77, 154
NOC-AE-22003913 Attachment 2 Attachment 2 Corrected Revised Technical Specification
DEFINITIONS DOSE EQUIVALENT XE-133 1.12 DOSE EQUIVALENT XE-133 shall be the concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table III.1 of EPA Federal Guidance Report No. 12, 1993, External Exposure to Radionuclides in Air, Water, and Soil.
ENGINEERED SAFETY FEATURES RESPONSE TIME 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.
FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
GASEOUS WASTE PROCESING SYSTEM 1.15 A GASEOUS WASTE PROCESSING SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
IDENTIFIED LEAKAGE 1.16 IDENTIFIED LEAKAGE shall be:
- a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or
- b. Leakage into the containment atmosphere from sources that are both specifically located and known to not interfere with the operation of Leakage Detection Systems, or
- c. Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.
SOUTH TEXAS - UNITS 1 & 2 1-3 Unit 1 - Amendment No. 130, 220 Unit 2 - Amendment No. 119, 205
DEFINITIONS MASTER RELAY TEST 1.17 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.
MEMBER(S) OF THE PUBLIC 1.18 MEMBER(S) OF THE PUBLIC means an individual in a controlled area or UNRESTRICTED AREA. However, an individual is not a member of the public during any period in which the individual receives an occupational dose.
1.19 Not Used OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or have OPERABLITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).
OPERATIONAL MODE - MODE 1.21 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.
PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation: (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.
PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a fault in a Reactor Coolant System component body, pipe wall, or vessel wall. Leakage past seals, packing, and gaskets is not PRESSURE BOUNDARY LEAKAGE.
SOUTH TEXAS - UNITS 1 & 2 1-4 Unit 1 - Amendment No. 47,52,57, 151 Unit 2 - Amendment No. 36,41,46, 139
REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System operational leakage shall be limited to:
- a. No PRESSURE BOUNDARY LEAKAGE,
- b. 1 gpm UNIDENTIFIED LEAKAGE,
- c. 150 gallons per day of primary-to-secondary leakage through any one steam generator,
- d. 10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System, and
- e. 0.5 gpm leakage per nominal inch of valve size up to a maximum of 5 gpm at a Reactor Coolant System pressure of 2235 20 psig from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.*
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
- a. With any PRESSURE BOUNDARY LEAKAGE, isolate the affected component, pipe, or vessel from the RCS by use of a close manual valve, closed and de-activated automatic valve, blind flange, or check valve within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. With Reactor Coolant System operational UNIDENTIFIED or IDENTIFIED LEAKAGE greater than the above limits, reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- c. With primary-to-secondary leakage not within the limit, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- d. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- Test pressures less than 2235 psig but greater than 150 psig are allowed. Observed leakage shall be adjusted for the actual test pressure up to 2235 psig assuming the leakage to be directly proportional to pressure differential to the one-half power.
SOUTH TEXAS - UNITS 1 & 2 3/4 4-20 Unit 1 - Amendment No. 83, 90, 164 Unit 2 - Amendment No. 77, 154