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MONTHYEARNOC-AE-12002877, Proposed Revision to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation.2012-08-0101 August 2012 Proposed Revision to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation. Project stage: Request ML12229A5662012-08-16016 August 2012 Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.3.3.6, Accident Monitoring Instrumentation Project stage: Acceptance Review NOC-AE-13002992, Supplement to License Amendment Request for Proposed Revision to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation.2013-04-15015 April 2013 Supplement to License Amendment Request for Proposed Revision to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation. Project stage: Supplement ML13008A5282013-04-25025 April 2013 Issuance of Amendment Nos. 200 and 188, Revise Technical Specification 3.3.3.6, Accident Monitoring Instrumentation Project stage: Approval 2012-08-16
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Category:Letter type:NOC
MONTHYEARNOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-230039, Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/20230032023-12-12012 December 2023 Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/2023003 NOC-AE-230039, Submittal of Update Foreign Ownership, Control or Influence (FOCI)2023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) NOC-AE-220039, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 252023-02-0606 February 2023 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 25 NOC-AE-220038, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2022-06-23023 June 2022 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask NOC-AE-210038, Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 252022-01-0404 January 2022 Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 25 NOC-AE-21003858, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2021-12-0606 December 2021 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes NOC-AE-21003853, Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-12-0303 December 2021 Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003848, Unit 1 Cycle 24 Core Operating Limits Report2021-11-18018 November 2021 Unit 1 Cycle 24 Core Operating Limits Report NOC-AE-21003846, Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-11-0404 November 2021 Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003842, 10 CFR 50.59 Summary Report2021-09-23023 September 2021 10 CFR 50.59 Summary Report NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003832, Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-0909 September 2021 Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003812, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-08-10010 August 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003825, Update of Foreign Ownership, Control, or Influence Information (FOCI)2021-08-0505 August 2021 Update of Foreign Ownership, Control, or Influence Information (FOCI) NOC-AE-21003824, Update Foreign Ownership, Control, or Influence (FOCI)2021-07-29029 July 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003823, Update Foreign Ownership Control or Influence (FOCI)2021-07-28028 July 2021 Update Foreign Ownership Control or Influence (FOCI) NOC-AE-21003820, Nuclear Insurance Protection2021-07-20020 July 2021 Nuclear Insurance Protection NOC-AE-21003819, Inservice Inspection Summary Report - 2RE212021-07-15015 July 2021 Inservice Inspection Summary Report - 2RE21 NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report NOC-AE-21003814, Technical Specification Bases Control Program2021-06-24024 June 2021 Technical Specification Bases Control Program NOC-AE-21003810, Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy NOC-AE-21003811, Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval2021-05-20020 May 2021 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval NOC-AE-21003801, Annual Dose Report for 20202021-04-26026 April 2021 Annual Dose Report for 2020 NOC-AE-21003802, 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report2021-04-26026 April 2021 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report NOC-AE-21003804, Operator Licensing Examination Schedule2021-04-21021 April 2021 Operator Licensing Examination Schedule NOC-AE-21003800, Radioactive Effluent Release Report2021-04-19019 April 2021 Radioactive Effluent Release Report NOC-AE-21003799, Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2021-04-15015 April 2021 Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan NOC-AE-21003795, Cycle 22 Core Operating Limits Report2021-04-15015 April 2021 Cycle 22 Core Operating Limits Report NOC-AE-21003796, Update Foreign Ownership, Control, or Influence (FOCI)2021-04-15015 April 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003791, Financial Assurance for Decommissioning - 2021 Update2021-03-31031 March 2021 Financial Assurance for Decommissioning - 2021 Update NOC-AE-21003790, Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter)2021-03-31031 March 2021 Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter) NOC-AE-210037, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-21003792, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-200037, License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications2021-03-11011 March 2021 License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications NOC-AE-21003784, Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing2021-03-0808 March 2021 Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-21003786, Annual Fitness for Duty Performance Report for 20202021-03-0101 March 2021 Annual Fitness for Duty Performance Report for 2020 NOC-AE-21003785, Evidence of Financial Protection2021-02-23023 February 2021 Evidence of Financial Protection NOC-AE-21003781, Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts2021-01-27027 January 2021 Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts NOC-AE-21003780, Submittal of Update Foreign Ownership, Control, or Influence (FOCI)2021-01-0707 January 2021 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-20003778, Changes to South Texas Project Electric Generating Station Emergency Plan2020-12-17017 December 2020 Changes to South Texas Project Electric Generating Station Emergency Plan NOC-AE-20003777, STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency2020-12-10010 December 2020 STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency NOC-AE-20003766, Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan2020-12-0202 December 2020 Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan NOC-AE-20003767, Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-16016 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval2020-10-28028 October 2020 Inservice Testing Program Description for the Fourth Ten-Year Interval NOC-AE-20003764, 1 RE22 Inspection Summary Report for Steam Generator Tubing2020-10-0707 October 2020 1 RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-20003762, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen2020-09-22022 September 2020 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen NOC-AE-20003761, Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic2020-09-10010 September 2020 Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic NOC-AE-20003760, Update Foreign Ownership. Control. or Influence(FOCI)- Transmittal2020-09-0808 September 2020 Update Foreign Ownership. Control. or Influence(FOCI)- Transmittal 2023-07-11
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23089A2042023-03-30030 March 2023 License Amendment Request to Revise Alternative Source Term Dose Calculation ML22221A2122022-08-0909 August 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements NOC-AE-21003832, Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-0909 September 2021 Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21252A7582021-09-0909 September 2021 Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21222A2272021-08-10010 August 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003812, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-08-10010 August 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-200037, License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications2021-03-11011 March 2021 License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications ML20253A0462020-09-29029 September 2020 Issuance of Amendment Nos. 220 and 205 to Revise Technical Specifications to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec ML20266H8192020-09-22022 September 2020 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen NOC-AE-20003762, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen2020-09-22022 September 2020 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen 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 ML20090B7452020-03-30030 March 2020 License Amendment Request for Revise South Texas Project Electric Generating Station (STPEGS) Emergency Plan NOC-AE-20003712, License Amendment Request for Revise South Texas Project Electric Generating Station (STPEGS) Emergency Plan2020-03-30030 March 2020 License Amendment Request for Revise South Texas Project Electric Generating Station (STPEGS) Emergency Plan 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-18003604, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Using the Consolidated Line Item Improvement Process2019-05-0101 May 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Using the Consolidated Line Item Improvement Process NOC-AE-18003583, License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item ...2018-09-27027 September 2018 License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item ... NOC-AE-17003529, License Amendment Request to Revise Technical Specification 3.8.1.1 (A.C. Sources, Operating)2018-03-27027 March 2018 License Amendment Request to Revise Technical Specification 3.8.1.1 (A.C. Sources, Operating) NOC-AE-17003510, License Amendment Request to Revise Technical Specifications for Administrative Changes and to Relocate Fxy Exclusion Zones to the Core Operating Limits Reports (Colrs)2017-09-18018 September 2017 License Amendment Request to Revise Technical Specifications for Administrative Changes and to Relocate Fxy Exclusion Zones to the Core Operating Limits Reports (Colrs) NOC-AE-16003406, License Amendment Request for Revision to Staffing and Staff Augmentation Times in the South Texas Project Electric Generating Station Emergency Plan2017-07-31031 July 2017 License Amendment Request for Revision to Staffing and Staff Augmentation Times in the South Texas Project Electric Generating Station Emergency Plan NOC-AE-17003459, Supplement to the License Renewal Application Re Aging Management Programs2017-04-19019 April 2017 Supplement to the License Renewal Application Re Aging Management Programs NOC-AE-16003403, Supplemental Information for the Review of the South Texas Project, Units 1 and 2, License Renewal - (TAC Nos. ME4936 and ME4937)2016-09-28028 September 2016 Supplemental Information for the Review of the South Texas Project, Units 1 and 2, License Renewal - (TAC Nos. ME4936 and ME4937) NOC-AE-16003385, 2016 Annual Update to the License Renewal Application2016-06-28028 June 2016 2016 Annual Update to the License Renewal Application NOC-AE-16003378, Additional Information for the Review of the License Renewal Application - Aluminum Bronze AMP (TAC Nos. ME4936 and ME4937)2016-05-31031 May 2016 Additional Information for the Review of the License Renewal Application - Aluminum Bronze AMP (TAC Nos. ME4936 and ME4937) NOC-AE-16003351, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies2016-04-0707 April 2016 License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies NOC-AE-16003330, Transmittal of Information of Foreign Ownership, Control, or Influence (FOCI)2016-01-27027 January 2016 Transmittal of Information of Foreign Ownership, Control, or Influence (FOCI) NOC-AE-15003318, Response to Request for Additional Information and Supplement to Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 202015-12-0909 December 2015 Response to Request for Additional Information and Supplement to Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 20 NOC-AE-15003315, Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 202015-12-0303 December 2015 Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 20 NOC-AE-15003307, Supplement - Error Correction - License Amendment Request for Extension of Containment Leakage Rate Testing Program2015-11-11011 November 2015 Supplement - Error Correction - License Amendment Request for Extension of Containment Leakage Rate Testing Program NOC-AE-15003227, License Amendment Request for Extending the 10 Year ILRT to 15 Years2015-04-29029 April 2015 License Amendment Request for Extending the 10 Year ILRT to 15 Years NOC-AE-15003223, License Amendment Request: Proposed Revision to Updated Final Safety Analysis Report Table 15.6-172015-04-29029 April 2015 License Amendment Request: Proposed Revision to Updated Final Safety Analysis Report Table 15.6-17 NOC-AE-14003116, Application to Revise Technical Specifications to Adopt TSTF-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, Using the Consolidated Line Item Improvement Process2015-04-23023 April 2015 Application to Revise Technical Specifications to Adopt TSTF-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, Using the Consolidated Line Item Improvement Process NOC-AE-15003214, Response to Request for Additional Information Regarding License Amendment Request for Emergency Action Level Scheme Change2015-02-11011 February 2015 Response to Request for Additional Information Regarding License Amendment Request for Emergency Action Level Scheme Change ML14260A4372014-08-14014 August 2014 Project Units 1 & 2, License Amendment Request - Proposed Administrative Controls Technical Specification 6.9.1.6, Core Operating Limits Report ML14164A3032014-05-15015 May 2014 Project, Revision to Unit 1 and Unit 2 Emergency Action Levels, Evaluation of the Proposed Changes License Amendment Request (LAR) for Revision of EAL Scheme to NEI 99-01 Revision 6. Part 2 of 7 NOC-AE-14003087, Revision to Unit 1 and Unit 2 Emergency Action Levels, Evaluation of the Proposed Changes License Amendment Request (LAR) for Revision of EAL Scheme to NEI 99-01 Revision 6. Part 7 of 72014-05-15015 May 2014 Revision to Unit 1 and Unit 2 Emergency Action Levels, Evaluation of the Proposed Changes License Amendment Request (LAR) for Revision of EAL Scheme to NEI 99-01 Revision 6. Part 7 of 7 ML14164A3082014-05-15015 May 2014 Project, Revision to Unit 1 and Unit 2 Emergency Action Levels, Evaluation of the Proposed Changes License Amendment Request (LAR) for Revision of EAL Scheme to NEI 99-01 Revision 6. Part 5 of 7 ML14164A3002014-05-15015 May 2014 Project, Revision to Unit 1 and Unit 2 Emergency Action Levels, Evaluation of the Proposed Changes License Amendment Request (LAR) for Revision of EAL Scheme to NEI 99-01 Revision 6. Part 1 of 7 ML14164A3112014-05-15015 May 2014 Project, Revision to Unit 1 and Unit 2 Emergency Action Levels, Evaluation of the Proposed Changes License Amendment Request (LAR) for Revision of EAL Scheme to NEI 99-01 Revision 6. Part 3 of 7 ML14164A3182014-05-15015 May 2014 Project, Revision to Unit 1 and Unit 2 Emergency Action Levels, Evaluation of the Proposed Changes License Amendment Request (LAR) for Revision of EAL Scheme to NEI 99-01 Revision 6. Part 6 of 7 ML14164A3142014-05-15015 May 2014 Project, Revision to Unit 1 and Unit 2 Emergency Action Levels, Evaluation of the Proposed Changes License Amendment Request (LAR) for Revision of EAL Scheme to NEI 99-01 Revision 6. Part 4 of 7 NOC-AE-13003031, License Amendment Request, Proposed Revision to Technical Specification 3.3. 1, Functional Unit 20, Reactor Trip Breakers.2014-01-0606 January 2014 License Amendment Request, Proposed Revision to Technical Specification 3.3. 1, Functional Unit 20, Reactor Trip Breakers. ML13323A1852013-11-13013 November 2013 Enclosure 3 - License Amendment Request for STP Piloted Risk-Informed Approach to Closure for GSI-191 NOC-AE-13002962, License Amendment Request for Approval of a Revision to the South Texas Project Fire Protection Program Related to the Alternative Shutdown Capability2013-07-23023 July 2013 License Amendment Request for Approval of a Revision to the South Texas Project Fire Protection Program Related to the Alternative Shutdown Capability ML13175A2112013-06-19019 June 2013 Project, Units 1 and 2, Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-191 NOC-AE-12002915, Annual Update to the South Texas Project License Renewal Application2012-10-29029 October 2012 Annual Update to the South Texas Project License Renewal Application NOC-AE-12002877, Proposed Revision to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation.2012-08-0101 August 2012 Proposed Revision to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation. ML11335A1402011-11-30030 November 2011 Annual Update to the South Texas Project License Renewal Application (TAC Nos. ME4936 and ME4937) NOC-AE-11002643, License Amendment Request for Approval of a Revision to the South Texas Project Fire Protection Program Related to the Alternative Shutdown Capability2011-06-0202 June 2011 License Amendment Request for Approval of a Revision to the South Texas Project Fire Protection Program Related to the Alternative Shutdown Capability NOC-AE-11002665, Proposed Amendment to Technical Specifications for Containment Post-Tensioning System Surveillance Program (Revision 2) (TAC ME3969/ME3970)2011-05-0202 May 2011 Proposed Amendment to Technical Specifications for Containment Post-Tensioning System Surveillance Program (Revision 2) (TAC ME3969/ME3970) 2023-03-30
[Table view] Category:Technical Specifications
MONTHYEARML21320A0022021-12-0808 December 2021 Issuance of Amendment Nos. 223 and 208 to Revise Technical Specification 3.6.3 and to Remove the Technical Specifications Index ML21106A2862021-05-0606 May 2021 Correction to Amendment Nos. 188 and 175 Regarding Relocation of Surveillance Test Intervals to Licensee-Controlled Program (Risk-Informed Initiative 5b) ML19067A2222019-06-0606 June 2019 Issuance of Amendment Nos. 215 and 201 Adoption of TSTF-522 Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML18159A2122018-07-19019 July 2018 Issuance of Amendment Nos. 214 and 200 Emergency Response Organization Time Augmentation and Staffing Chances to the Emergency Plan (CAC Nos. MG0024 and MG0025; EPID L-2017-LLA-0265) ML17191B1372017-09-28028 September 2017 South Texas Project, Unit 1, Renewed Facility Operating License NPF-76 ML17192A0182017-09-28028 September 2017 South Texas Project, Unit 2, Renewed Facility Operating License and Appendices NPF-80 ML17038A2232017-07-11011 July 2017 Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 ML16116A0072016-04-29029 April 2016 Issuance of Amendment Nos. 210 and 197, Revise Technical Specification 6.8.3.j, Containment Leakage Rate Testing Program, to Extend Integrated Leak Rate Test Interval from 10 to 15 Years ML15342A0032015-12-28028 December 2015 Issuance of Amendment Nos. 209 and 196, Adopt Technical Specification Task Force (TSTF)-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (CAC MF6178-MF6179) ML15343A1282015-12-11011 December 2015 Issuance of Amendment No. 208, Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Unit 1 Cycle 20 (Emergency Circumstances) NOC-AE-15003315, Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 202015-12-0303 December 2015 Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 20 ML15209A6412015-09-22022 September 2015 Issuance of Amendment Nos. 207 and 195, Revise Updated Final Safety Analysis Report Table 15.6-17 to Correct Radiological Doses Resulting from Calculation Error Performed in Support of Amendments 182 and 169 ML15201A1952015-08-20020 August 2015 Issuance of Amendment Nos. 206 and 194, Revise the Emergency Action Level Scheme to the NRC-endorsed Scheme Contained in NEI-99, Revision 6 ML15075A1462015-04-29029 April 2015 Issuance of Amendment Nos. 205 and 193, Request to Revise Technical Specification 3.3.1, Functional Unit 20, Reactor Trip Breakers, for Required Actions and Allowed Outage Times ML15049A1292015-02-27027 February 2015 Issuance of Amendment Nos. 204 and 192, Revise Technical Specification 6.9.1.6, Core Operating Limits Report, with Respect to Analytical Methods Used to Determine Core Operating Limits ML14339A1702015-02-13013 February 2015 Issuance of Amendment Nos. 203 and 191, Revise Fire Hazards Analysis Report and Fire Protection Program License Conditions Related to Alternate Shutdown Capability ML14281A0652015-01-29029 January 2015 Issuance of Amendment Nos. 202 and 190, Revise Operating License Conditions Related to Cyber Security Plan Milestone 8 Full Implementation Date ML14260A4372014-08-14014 August 2014 Project Units 1 & 2, License Amendment Request - Proposed Administrative Controls Technical Specification 6.9.1.6, Core Operating Limits Report NOC-AE-14003143, Supplement to License Amendment Request Proposed Revision to Technical Specification 3.3.1, Functional Unit 20, Reactor Trip Breakers2014-06-0909 June 2014 Supplement to License Amendment Request Proposed Revision to Technical Specification 3.3.1, Functional Unit 20, Reactor Trip Breakers ML14106A3642014-04-22022 April 2014 Correction to Technical Specification Page 3/4 8-4, Amendment Nos. 188 and 175, Regarding Relocation of Surveillance Test Intervals to Licensee-Controlled Surveillance Frequency Control Program (TAC Nos. MF3732-33) NOC-AE-13003031, License Amendment Request, Proposed Revision to Technical Specification 3.3. 1, Functional Unit 20, Reactor Trip Breakers.2014-01-0606 January 2014 License Amendment Request, Proposed Revision to Technical Specification 3.3. 1, Functional Unit 20, Reactor Trip Breakers. ML13175A2112013-06-19019 June 2013 Project, Units 1 and 2, Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-191 NOC-AE-13002992, Supplement to License Amendment Request for Proposed Revision to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation.2013-04-15015 April 2013 Supplement to License Amendment Request for Proposed Revision to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation. ML12241A1932012-08-30030 August 2012 Correction Letter to Revised Technical Specification 3.7.7, Technical Specification Page 3/4 7-16 NOC-AE-12002877, Proposed Revision to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation.2012-08-0101 August 2012 Proposed Revision to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation. NOC-AE-11002677, Technical Specification Bases Control Program2011-06-16016 June 2011 Technical Specification Bases Control Program NOC-AE-10002605, License Amendment Request to Revise the Application of Risk-Managed Technical Specifications to Technical Specification 3.7.7, Control Room Makeup and Cleanup Filtration System.2010-11-22022 November 2010 License Amendment Request to Revise the Application of Risk-Managed Technical Specifications to Technical Specification 3.7.7, Control Room Makeup and Cleanup Filtration System. NOC-AE-10002541, Proposed Amendment to Technical Specification 6.8.3.I for Containment Post-Tensioning System Surveillance Program2010-05-18018 May 2010 Proposed Amendment to Technical Specification 6.8.3.I for Containment Post-Tensioning System Surveillance Program NOC-AE-09002389, License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26, Using the Consolidated Line Item Improvement Process2009-03-0303 March 2009 License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26, Using the Consolidated Line Item Improvement Process NOC-AE-09002390, Correction of Technical Specification Pages Previously Approved by Amendment2009-02-0404 February 2009 Correction of Technical Specification Pages Previously Approved by Amendment ML0822804722008-09-16016 September 2008 Technical Specifications, Issuance of Amendment Nos. 186 and 173, Deviation from Fire Protection Program Requirements ML0820504272008-07-29029 July 2008 License and Technical Specification Pages, Amendment Nos. 185 and 172, New License Condition/Revised TS Requirements Control Room Envelope Habitability in Accordance with TSTF-448, Rev. 3 ML0818902362008-07-0808 July 2008 Corrected Errata Sheet and TS Pages for Amendment No. 184 and 171 Issued June 30, 2008, Revise Technical Specification 3/4.8.2 to Modify Battery Surveillance Requirements ML0813303552008-06-30030 June 2008 License and Technical Specification Pages, Issuance of Amendment No. 184 and 171, Revise Technical Specification 3/4.8.2 to Modify Battery Surveillance Requirements NOC-AE-08002301, Withdrawal of Proposed Exception to Technical Specification 6.8.3.p.3, Control Room Envelope Habitability Program2008-05-27027 May 2008 Withdrawal of Proposed Exception to Technical Specification 6.8.3.p.3, Control Room Envelope Habitability Program ML0803603282008-03-25025 March 2008 Technical Specifications, Revise TS Surveillance Requirements for Emergency Core Cooling System Sumps ML0803604212008-03-0606 March 2008 Tech Spec Pages for Amendment Nos. 182 and 169, Adoption of Alternate Radiological Source Term in Assessment of Design-Basis Accident Dose Consequences ML0715901792007-07-20020 July 2007 Technical Specification Pages for Amendment Nos. 180 and 167 Technical Specification 3/4.8.2 for Batteries and DC Systems NOC-AE-07002183, Updated Pages to Incorporate Battery-Related Technical Specification Changes2007-07-17017 July 2007 Updated Pages to Incorporate Battery-Related Technical Specification Changes ML0720103122007-07-17017 July 2007 Project, Units 1 and 2 - Attachment to 7/18/07 E-Mail to M. Thadani, Nrr/Dorl/Lpliv, from P. Walker, STPNOC - Letter and Updated Technical Specification Pages - Battery Monitoring License Amendment Request (TAC MD0333, MD0334) ML0717801912007-07-13013 July 2007 Technical Specifications, Issuance of Amendment Nos. 179 and 166 Broad-Scope Risk-Informed Technical Specifications Amendments ML0714302512007-06-13013 June 2007 Tech Spec Pages for Amendment Nos. 177 and 164 Regarding TS 3.3.3.6, Accident Monitoring Instrumentation, NOC-AE-07002113, Proposed Change to Technical Specification 3.7.1.2, Auxiliary Feedwater System.2007-05-22022 May 2007 Proposed Change to Technical Specification 3.7.1.2, Auxiliary Feedwater System. NOC-AE-07002141, Resolution of Issues Regarding Proposed Amendment to Technical Specification 3/4.8.2 to Modify Requirements Related to Batteries and DC Systems2007-04-0606 April 2007 Resolution of Issues Regarding Proposed Amendment to Technical Specification 3/4.8.2 to Modify Requirements Related to Batteries and DC Systems NOC-AE-07002127, Request for License Amendment Related to Application of the Alternate Source Term2007-03-22022 March 2007 Request for License Amendment Related to Application of the Alternate Source Term ML0706503142007-02-28028 February 2007 South Texas Project, Units 1 and 2, Proposed Change to Technical Specification 3.7.1.2, Auxiliary Feedwater System. NOC-AE-06002036, Revised Broad Scope Risk-Informed Technical Specification Amendment Request2006-12-28028 December 2006 Revised Broad Scope Risk-Informed Technical Specification Amendment Request NOC-AE-06002095, Request for Enforcement Discretion for Technical Specifications 3.3.3.6 and 3.7.1.22006-12-18018 December 2006 Request for Enforcement Discretion for Technical Specifications 3.3.3.6 and 3.7.1.2 NOC-AE-06002060, Revision to Proposed Change to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation.2006-10-0202 October 2006 Revision to Proposed Change to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation. NOC-AE-06002040, Technical Specifications, Bases Control Program2006-07-20020 July 2006 Technical Specifications, Bases Control Program 2021-05-06
[Table view] |
Text
S'rlrANl Nuclear Operating Company
-NEW South Texas Pro/eet Electric GeneratinqStation PO. Box 289 Wadsworth, Texas 77483 -
August 1, 2012 NOC-AE- 12002877 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 License Amendment Request Proposed Revision to Technical Specification 3.3.3.6, "Accident Monitoring Instrumentation" 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) 3.3.3.6, "Accident Monitoring Instrumentation," with respect to the required actions and allowed outage times for inoperable instrumentation for Neutron Flux (Extended Range) and Neutron Flux - Startup Rate (Extended Range).
The proposed changes would revise the required actions and allowed outage times for inoperable channels to be consistent with those generically approved in NUREG-143 1, Standard Technical Specifications, Westinghouse Plants, Revision 4.
The Enclosure provides a technical and regulatory evaluation of the changes. 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 August 1, 2013 and requests 90 days for implementation of the amendment.
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.
STI: 33567245
NOC-AE-12002877 Page 2 If there are any questions regarding the proposed amendment, please contact Jim Morris at (361) 972-8652 or me at (361) 972-7867.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on / At 01L.
Cate
.fW.
Rencurrel Chief Nuclear Officer
Enclosure:
Evaluation of the Proposed Change
NOC-AE-12002877 Page 3 cc:
(paper copy) (electronic copy)
Regional Administrator, Region IV A. H. Guttennan, 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 North (MS 8 B1) NRG South Texas LP 11555 Rockville Pike Rockville, MD 20852 Kevin Pollo Senior Resident Inspector Richard Pena U. S. Nuclear Regulatory Commission City Public Service P. 0. Box 289, Mail Code: MN116 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
NOC-AE-12002877 Enclosure ENCLOSURE Evaluation of the Proposed Change
Subject:
Proposed Revision to Technical Specification 3.3.3.6, "Accident Monitoring Instrumentation" 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
5.0 ENVIRONMENTAL CONSIDERATION
6.0 REFERENCES
ATTACHMENTS:
- 1. Technical Specification Page Markups
- 2. Technical Specification Bases Inserts (for information only)
NOC-AE- 12002877 Enclosure Page 1 of 7 ENCLOSURE 1.0
SUMMARY
DESCRIPTION The proposed license amendment revises the Technical Specification (TS) 3.3.3.6, "Accident Monitoring Instrumentation," with respect to the required actions and allowed outage times for inoperable instrumentation for Neutron Flux (Extended Range) and Neutron Flux - Startup Rate (Extended Range).
The proposed amendment will revise the required actions to enhance plant reliability by reducing exposure to unnecessary shutdowns and increase operational flexibility by allowing more time to effect required repairs for inoperable Neutron Flux (Extended Range) and Neutron Flux - Startup Rate (Extended Range) instrumentation. The proposed changes are consistent with requirements generically approved as part ofNUREG-1431, Standard Technical Specifications, Westinghouse Plants, Revision 4 (TS 3.3.3, "Post Accident Monitoring (PAM) Instrumentation").
Attachment I provides the markups for the TS pages. Attachment 2 provides the associated Bases inserts for information.
2.0 DETAILED DESCRIPTION TS 3.3.3.6, Table 3.3-10, "Accident Monitoring Instrumentation," directs entry into Action 36 in the event that the Total Number of Channels column requirements or Minimum Channels Operable column requirements are not met for Neutron Flux (Extended Range) and Neutron Flux
- Startup Rate (Extended Range). Action 36 states:
- a. With the number of OPERABLE channels one less than the Total Number of Channels requirements, restore one inoperable channel to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b. With the number of OPERABLE channels less than the Minimum Channels Operable requirements, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The proposed amendment directs entry into Action 42 in the event that the Total Number of Channels column requirements or Minimum Channels Operable column requirements are not met for Neutron Flux (Extended Range) and Neutron Flux - Startup Rate (Extended Range).
Action 42 states:
- a. With one required channel inoperable, restore the required channel to OPERABLE status within 30 days; otherwise, a Special Report shall be submitted within the next 14 days. The report shall outline the preplanned alternate method of monitoring, the
NOC-AE-12002877 Enclosure Page 2 of 7 cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status.
- b. With two required channels inoperable, restore one required channel to OPERABLE status within 7 days; otherwise, be in 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 HOT SHUTDOWN in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The proposed changes to Technical Specification 3.3.3.6 are consistent with generically approved requirements provided in NUREG-1431, "Standard Technical Specifications, Westinghouse Plants," Revision 4 (TS 3.3.3, "Post Accident Monitoring (PAM) Instrumentation").
3.0 TECHNICAL EVALUATION
STP Updated Final Safety Analysis Report (UFSAR) Table 7.5-1, "Post-Accident Monitoring Instrumentation," provides a listing of the post-accident monitoring variables identified in the task analysis perforined in response to Regulatory Guide (RG) 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," Revision 2. UFSAR Table 7.5-1 includes the following information on the instrumentation utilized for each variable: (a) instrument range; (b) type and category (per the definitions found in Appendix 7B); (c) enviromnental qualification; (d) seismic qualification; (e) number of channels available; (f) display device and location; (g) the schedule for implementation; (h) power supply; and (i) a statement of conformance to RG 1.97, Rev. 2, or justification for deviations.
TS 3.3.3.6, Table 3.3-10, Action 36 applies to inoperable extended range nuclear instrumentation associated with the following variables:
Instrument 19, "Neutron Flux (Extended Range)," is shown in UFSAR Table 7.5-1 as a RG 1.97 B I and D2 variable. There are two channels indicating from 10-8 to 200% full power. Indication is provided on the Qualified Display Parameter System (QDPS) in the control room.
Neutron Flux (Extended Range) is used immediately following an accident or receipt of a reactor trip signal to confirmn subcriticality. The operators will determine the need for a manual reactor trip based on rod bottom lights, indication that reactor trip breakers are open, and decreasing neutron flux. The extended range neutron flux indication can provide indication of decreasing neutron flux to confirm subcriticality. If the extended range neutron flux indication is not available, an alternate method of monitoring subcriticality is a combination of either the intenrmediate range or source range neutron flux indications.
NOC-AE-12002877 Enclosure Page 3 of 7 Instrument 23, "Neutron Flux - Startup Rate (Extended Range)," is shown in UFSAR Table 7.5-1 as a RG 1.97 BI and D2 variable. There are two channels indicating from
-1.0 decades per minute (dpm) to +7.0 dpm. Indication is provided on the QDPS in the control room.
After subcriticality is achieved, the extended range neutron flux monitor can be used to confirm continued subcriticality by monitoring the startup rate. A positive startup rate indicates that core reactivity is changing in a direction that may result in a criticality. The extended range neutron flux startup rate indication can be used as a backup to the extended range neutron flux indication during shutdown to determine whether sufficient negative reactivity (e.g., boron, Reactor Coolant System (RCS) temperature during RCS cooldown) is available for long tenr subcriticality.
In the event one or more channels of the variables discussed above are inoperable, TS Table 3.3-10 directs entry into the required actions provided in Action 36. Currently, Action 36.a requires that with the number of Operable channels one less than the Total Number of Channels requirements, one channel must be restored to Operable status within 7 days, or the plant must be placed in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. STP proposes to apply Action 42.a to require that with the number of Operable channels one less than the Total Number of Channels requirements, the inoperable channel must be restored to Operable status within 30 days, or a special report must be submitted within the next 14 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the inoperable channels to OPERABLE status.
The 30-day Allowed Outage Time is acceptable because there is one channel of instrumentation that remains operable, the applicable instrumentation provides indication only (i.e., no automatic actuations are required to occur from the associated instrumentation post-accident), and because of the low probability of an event requiring post-accident monitoring instrumentation during this 30-day interval. The action to submit a special report in lieu of a plant shutdown is acceptable because alternative actions are identified before a loss of functional capability, and given the low likelihood of plant conditions that would require information provided by this instrumentation.
The report discusses the results of the root cause evaluation of the inoperability and identifies proposed restorative actions.
Currently, Action 36.b requires that with the number of Operable channels less than the Minimum Operable Channels requirements, one inoperable channel must be restored to Operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or the plant must be placed in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
STP proposes to apply Action 42.b to require that with the number of Operable channels less than the Minimum Operable Channels requirements, one inoperable channel must be restored to Operable status within 7 days, or the plant must be placed in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The 7-day Allowed Outage Time is acceptable because of the low probability of an event requiring post-accident monitoring instrumentation operation and the availability of alternate
NOC-AE- 12002877 Enclosure Page 4 of 7 means to obtain the required information. Continuous operation with two channels not available for any one variable is not acceptable because the alternate indications may not fully meet all performance qualification requirements applied to the post-accident monitoring instrumentation.
Therefore, requiring restoration of one inoperable channel limits the risk that the post-accident monitoring function will be in a degraded condition should an accident occur.
The proposed actions and allowed outage times are consistent with those approved generically in NUREG- 1431, Revision 4, (TS 3.3.3, "Post Accident Monitoring (PAM) Instrumentation").
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria General Design Criteria (GDC) 13, "Instrumentation and Control," of 10 CFR 50, Appendix A, includes a requirement that instrumentation be provided to monitor variables and systems over their anticipated ranges for accident conditions as appropriate to ensure adequate safety.
GDC 19, "Control Room," of 10 CFR 50, Appendix A, includes a requirement that a control room be provided from which actions can be taken to maintain the nuclear power unit in a safe condition under accident conditions, including loss-of-coolant accidents, and that equipment, including the necessary instrunmentation, at appropriate locations outside the control room be provided with a design capability for prompt hot shutdown of the reactor.
Regulatory Guide (RG) 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," Revision 2, describes a method acceptable to the NRC staff for complying with the Commission's regulations to provide instrumentation to monitor plant variables and systems during and following an accident in a light-water-cooled nuclear power plant.
The referenced requirements of GDC 13, GDC 19, and the guidance of RG 1.97 continue to be met because the proposed changes do not delete or add any post-accident monitoring variables to the Technical Specifications, do not revise the number of instrumentation channels required for any variable, and do not revise the instrumentation ranges for any of the post-accident monitoring variables included in the Technical Specifications.
4.2 Precedent The Nuclear Regulatory Commission (NRC) has approved similar changes for Turkey Point Units 3 and 4 (Amendment No. 227 to Facility Operating License No. DPR-3 1, and Amendment No. 223 to Facility Operating License No. DPR-41), dated January 6, 2005 (Reference 1).
NOC-AE- 12002877 Enclosure Page 5 of 7 In addition, the NRC has previously approved similar changes to TS 3.3.3.6, Table 3.3-10, Action 35, for STP Units I and 2 in Amendments 177 and 164 (for Unit I and Unit 2, respectively), dated June 13, 2007 (Reference 2).
4.3 Significant Hazards Consideration STP has evaluated whether a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in I OCFR50.92, "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 changes revise the actions and allowed outage times of the neutron flux (extended range) and neutron flux - startup rate (extended range) accident monitoring instrumentation. The instrumentation is not an initiator of any accident previously evaluated. As a result, the probability of any accident previously evaluated is not significantly increased by these proposed changes. The Technical Specifications continue to require the instrumentation to be operable. Therefore, the neutron flux (extended range) and neutron flux - startup rate (extended range) instrumentation will continue to provide sufficient information on selected plant parameters to monitor and assess these variables following an accident. The consequences of an accident during the extended allowed outage times are the same as the consequences during the current allowed outage time. As a result, the consequences of any accident previously evaluated are not significantly increased by these proposed changes. Therefore, the proposed changes do not increase 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 changes do not alter the design, physical configuration, or mode of operation of the plant. The neutron flux (extended range) and neutron flux - startup rate (extended range) accident monitoring instrumentation is not an initiator of any accident previously evaluated. No changes are being made to the plant that would introduce any new accident causal mechanisms. The proposed changes do not affect any other plant equipment. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously analyzed.
NOC-AE- 12002877 Enclosure Page 6 of 7
- 3) Does the proposed change involve a significant reduction in a margin of safety?
Response
No. The proposed changes do not change the operation, function, or modes of the plant or equipment operation. The proposed changes do not change the level of assurance that the neutron flux (extended range) and neutron flux - startup rate (extended range) accident monitoring instrumentation will be available to perform its function. The proposed changes provide a more appropriate time to restore the inoperable channel(s) to operable status, and only apply when one or more channels of the required instrument are inoperable. The additional time to restore an inoperable channel to operable status is appropriate based on the low probability of an event requiring a neutron flux (extended range) accident monitoring instrument during the interval, providing a reasonable time for repair, and other means which may be available to obtain the required information.
Therefore, the proposed changes do not result in a reduction in a margin of safety.
Based on the above, STP concludes that the proposed amendment presents no 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.
4.4 Conclusions 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 A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement, or enviromnental assessment need be prepared in connection with the proposed amendment.
NOC-AE-12002877 Enclosure Page 7 of 7
6.0 REFERENCES
- 1. Letter from NRC to Mr. J. A. Stall, "Turkey Point Units 3 and 4 - Issuance of Amendments Regarding Accident Monitoring Instrumentation Outage Times (TAC Nos. MC2884 and MC2885)," January 6, 2005 (Accession No. ML043480388).
- 2. Letter flom NRC to Mr. J. J. Sheppard, "South Texas Project, Units 1 and 2 - Issuance of Amendments re: Changes to Technical Specification 3.3.3.6, "Accident Monitoring hIstrumentation" (TAC Nos. MD0934 and MD0935)," June 13, 2007 (Accession No. ML071430234).
NOC-AE- 12002877 Enclosure, Att. 1 ENCLOSURE, ATTACHMENT 1 Technical Specification Page Markups
NO CHANGES ON THIS PAGE TABLE 3.3-10 Cl) ACC IDENT MONITORING INSTRUMENTATIO 0
r TOTAL MINIIv H- NO. OF CHAN M
INSTRUMENT CHANNELS OPER ACTION
- 1. Containment Pressure 4 1 43 Cn 2. Reactor Coolant Outlet Temperature- 4 (1/loop) 4 35 T HOT (Wide Range)
- 3. Reactor Coolant Inlet Temperature- 4 (1/loop) 4 35 T COLD (Wide Range)
- 4. Reactor Coolant Pressure - Wide Range 3 37 and Extended Range 1
- 5. Pressurizer Water Level 4 43
- 6. Steam Line Pressure 4/steam generator 1/steam generator 43
- 7. Steam Generator Water Level - 4/steam generator 1/steam generator 43 Narrow Range
- 8. Steam Generator Water Level - 4(1/steam generator) 4 35 CC
=34. =3 Wide Range
- 9. Refueling Water Storage Tank Water Level 3 1 37 3 3 CD CD 10. Auxiliary Feedwater Storage Tank Water Level 3 1 37
- 11. Auxiliary Feedwater Flow 4(1/steam generator) 4 35 CD CD Z Z
- 12. Reactor Coolant System Subcooling 2 36 0 0 Margin Monitoring
- 0) -- 4
TABLE 3.3-10 (Continued)
ACCIDENT MONITORING INSTRUMENTATION TOTAL MINIMUM NO. OF CHANNELS INSTRUMENT CHANNELS OPERABLE ACTION
- 13. Containment Water Level 2 1 36 (Narrow Range)
- 14. Containment Water Level (Wide Range) 3 1 37
- 15. Core Exit Thermocouples 42
- 16. Steam Line Radiation Monitor 1/steam line 1/steam line 40
- 17. Containment - High Range Radiation Monitor 2 1 39
- 18. Reactor Vessel Water Level (RVWL) 2* 1* 41
- 19. Neutron Flux (Extended Range) 2 1 36. 42
- 20. Not Used
- 21. Containment Pressure (Extended Range) 2 1 36
- 22. Steam Generator Blowdown Radiation Monitor 1/blowdown line 1/blowdown line 40
- 23. Neutron Flux - Startup Rate 2 1 . 42 (Extended Range)
- A channel is eight sensors in a probe. A channel is OPERABLE if four or more sensors, one or more in the upper section section and three or more in the lower section, are OPERABLE.
- A channel is OPERABLE if at least two core exit thermocouples per core quadrant are OPERABLE, and at least one quadrant has at least four OPERABLE thermocouples.
SOUTH TEXAS - UNITS 1 & 2 3/4 3-69 Unit 1 - Amendment No. -7-6 Unit 2 - Amendment No. 66, !55
NOC-AE-12002877 Enclosure, Att. 2 ENCLOSURE, ATTACHMENT 2 TS Bases Inserts (For information only)
NOC-AE-12002877 Enclosure, Att. 2 TS 3.3.3.6 Bases inserts for information:
Action 42.a requires that with the number of Operable channels one less than the Total Number of Channels requirements, one inoperable channel must be restored to Operable status within 30 days, or a special report must be submitted within the next 14 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the inoperable channels to OPERABLE status.
The 30-day Allowed Outage Time is acceptable because there is one channel of instrumentation that remains operable, the applicable instrumentation provides indication only (i.e., no automatic actuations are required to occur from the associated instrumentation post-accident), and because of the low probability of an event requiring post-accident monitoring instrumentation during this 30-day interval. The action to submit a special report in lieu of a plant shutdown is acceptable because alternative actions are identified before a loss of functional capability, and given the low likelihood of plant conditions that would require information provided by this instrumentation. The report discusses the results of the cause evaluation of the inoperability and identifies proposed restorative actions.
Action 42.b requires that one inoperable channel must be restored to Operable status within 7 days, or the plant must be placed in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The 7-day Allowed Outage Time is acceptable because of the low probability of an event requiring post-accident monitoring instrumentation operation and the availability of alternate means to obtain the required information. Continuous operation with two channels for any one variable is not acceptable because the alternate indications may not fully meet all performance qualification requirements applied to the post-accident monitoring instrumentation. Therefore, requiring restoration of one inoperable channel limits the risk that the post-accident monitoring function will be in a degraded condition should an accident occur.