Letter Sequence Request |
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TAC:MC0934, Increase Flexibility in Mode Restraints (Approved, Closed) |
Results
Other: ML043220180, ML043520018, ML050310149, ML050350208, ML050390497, ML050590047, ML050830149, ML050830226, ML051440796, ML052370096, ML052370125, ML061840302, ML071210143, ML071210176, ML071280118, ML071280688, ML071310312, ML071590179, ML072010312, ML073090302, ML080220065, NOC-AE-04001831, Additional Information Regarding the Sale of Ownership Interests in the South Texas Project, NOC-AE-05001850, Submittal of Erratum for Letter, E. D. Halpin to J. E. Dyer, Additional Information Regarding the Sale of Ownership Interests in the South Texas Project, NOC-AE-05001857, Texas Genco, LP Decommissioning Master Trust Agreement
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MONTHYEARML0422403662004-08-11011 August 2004 Review of Licensing Actions Project stage: Approval ML0432201802004-12-14014 December 2004 Notice of Consideration of Approval of Transfer of Facility Operating Licenses and Conforming Amendments, and Opportunity for a Hearing Project stage: Other NOC-AE-04001831, Additional Information Regarding the Sale of Ownership Interests in the South Texas Project2004-12-22022 December 2004 Additional Information Regarding the Sale of Ownership Interests in the South Texas Project Project stage: Other ML0435200182004-12-30030 December 2004 Texas Genco LLC and Texas Genco LP, Withholding from Public Disclosure, Attachments to Letter Dated December 13, 2004, for South Texas, Units 1 and 2 Project stage: Other ML0501402622005-01-27027 January 2005 License Amendment 246 Regarding Increasing Spent Fuel Pool Maximum Enrichment Limit Project stage: Approval ML0503101492005-01-27027 January 2005 Technical Specification Pages Re Spent Fuel Pool Max Enrichment Limit Project stage: Other ML0503904972005-02-0303 February 2005 Technical Specification Pages to Calvert Cliffs, Unit 2 - Correction to Amendment No. 246 Project stage: Other ML0503502082005-02-0303 February 2005 Correction to Amendment No. 246 Project stage: Other ML0505403952005-02-23023 February 2005 Correction to NRC Safety Evaluation for Amendment No. 246 Project stage: Approval NOC-AE-05001857, Texas Genco, LP Decommissioning Master Trust Agreement2005-03-0101 March 2005 Texas Genco, LP Decommissioning Master Trust Agreement Project stage: Other NOC-AE-05001850, Submittal of Erratum for Letter, E. D. Halpin to J. E. Dyer, Additional Information Regarding the Sale of Ownership Interests in the South Texas Project2005-03-0303 March 2005 Submittal of Erratum for Letter, E. D. Halpin to J. E. Dyer, Additional Information Regarding the Sale of Ownership Interests in the South Texas Project Project stage: Other ML0505900472005-03-0808 March 2005 Texas Genco LLC and Texas Genco LP - Withholding from Public Disclosure, Information in Attachment 7C (Proprietary), to the February 23, 2005 Letter Project stage: Other ML0508301492005-04-0404 April 2005 License Amendment, Order Approving Transfer of Licenses from Aep Texas Central Company and Indirect License Transfers to the Extent Effected Relating to South Texas Company and Conforming Amendments Project stage: Other ML0508302262005-04-0404 April 2005 FRN: Order Approving Transfer of Licenses and Conforming Amendments for South Texas, Units 1 and 2 Project stage: Other ML0509404582005-04-0404 April 2005 Non-proprietary Safety Evaluation, Order Approving Transfer of Licenses from Aep Texas Central Company & Indirect License Transfers to Extent Effected Re to South Texas Project Nuclear Operating Company & Conforming Amendments Project stage: Approval ML0509605932005-05-19019 May 2005 Southtexas, Units 1 and 2 - Issuance of Amendments Conforming Amendments Project stage: Approval ML0514407962005-05-19019 May 2005 Tech.Spec.Pages to S.Texas Amendment Nos. 172/160 Project stage: Other NOC-AE-05001841, License Amendment Request - Proposed Amendment to Technical Specifications 3.4.6.1 and 3.4.6.22005-06-0202 June 2005 License Amendment Request - Proposed Amendment to Technical Specifications 3.4.6.1 and 3.4.6.2 Project stage: Request ML0523701252005-10-17017 October 2005 Technical Specifications, Reactor Coolant System Leakage Detection Project stage: Other ML0523700962005-10-17017 October 2005 License Amendments, Reactor Coolant System Leakage Detection Project stage: Other ML0618403022006-07-21021 July 2006 Audit of the Licensee'S Management of Regulatory Commitments Project stage: Other ML0706503142007-02-28028 February 2007 South Texas Project, Units 1 and 2, Proposed Change to Technical Specification 3.7.1.2, Auxiliary Feedwater System. Project stage: Request ML0712101432007-05-0303 May 2007 Ltr Enclosing Notice of Consideration of Issuance of Amendments Revision to TS Reflecting Name Change from Texas Genco LP to Mrg South Texas LP (TAC Nos. MD5268 & MD5269) Project stage: Other ML0712101762007-05-0303 May 2007 Individual Fr Notice of Consideration of Issuance of Amendments Revision to TS Reflecting Name Change from Texas Genco LP to Mrg South Texas LP (TAC Nos. MD5268 & MD5269) Project stage: Other 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. Project stage: Request ML0713103122007-06-0808 June 2007 Environmental Assessment and Finding of No Significant Impact Proposed Licensee Name Change Project stage: Other ML0712806882007-06-29029 June 2007 License Amendment Nos. 178 and 165, License Pgs 1, 2, and 3, Change the Name of One Licensee from Texas Genco, LP, to Nrg South Texas LP Project stage: Other ML0712801182007-06-29029 June 2007 License Amendment Nos. 178 and 165, Change the Name of One Licensee from Texas Genco, LP, to Nrg South Texas LP Project stage: Other 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) Project stage: Other ML0720102982007-07-18018 July 2007 7/18/07 E-mail to M. Thadani, Nrr/Dorl/Lpliv, from Phillip Walker, Stpnotc Re Battery Technical Specification Pages for License Amendment Request Project stage: Request 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 Project stage: Other ML0715901712007-07-20020 July 2007 Issuance of Amendment Nos. 180 and 167 Technical Specification 3/4.8.2 for Batteries and DC Systems Project stage: Approval ML0730903022007-12-0606 December 2007 License Amendments 181 and 168, Clarification of Technical Specification 3.7.1.2 Project stage: Other ML0802200652008-02-0404 February 2008 Correction Letter, Revise License Pg 1 to Remove Owner Name for Amendment Nos. 172-181 for Unit 1 and 160-168 for Unit 2 (TAC Nos. MC4917/18, MC7258/59, MC8224/25, MD3852, MD0934/35, MD5268/69, MD2341/42, MD0333/34, MD4655/56) Project stage: Other 2005-05-19
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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
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Nuclear Operating Company
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June 2, 2005 NOC-AE-05001841 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Units 1 and 2 Docket No. STN 50498 and STN 50499 License Amendment Request -
Proposed Amendment to Technical Specifications 3.4.6.1 and 3.4.6.2 Pursuant to 10 CFR 50.90, STP Nuclear Operating Company (STPNOC) hereby requests an amendment to Technical Specification (TS) 3.4.6.1, "Reactor Coolant System Leakage Detection Systems," to specifically require only one containment radioactivity monitor (particulate channel) is to be operable in Modes 1, 2, 3 and 4. Additionally, corresponding changes to Surveillance Requirement 4.4.6.2.1, "Reactor Coolant System Operational Leakage," are also requested.
Currently, TS 3.4.6.1 states that one containment atmosphere radioactivity monitor (gaseous or particulate) is to be operable. The level of radioactivity in the reactor coolant normally is much lower than the value that was assumed in the Updated Final Safety Analysis Report. As a result, the gaseous channel of the containment atmosphere radioactivity monitor can no longer be used to promptly detect a small reactor coolant system (RCS) leak. However, the particulate channel sensitivity continues to support the licensing basis. Therefore, the proposed amendment specifically requires only the containment radioactivity monitor (particulate channel) to be operable. to this letter provides licensee evaluation including the No Significant Hazards Determination and Attachment 2 provides the TS page marked up with the proposed change.
The associated change to the TS Bases will be made accordingly as a part of the implementation of this license amendment.
The Plant Operations Review Committee has recommended approval of the proposed change.
STPNOC has notified the State of Texas in accordance with 10 CFR 50.91(b).
There are no commitments contained in this license amendment request.
4 I STI: 31837684
NOC-AE-05001841 Page 2 of 3 STPNOC requests approval of the proposed amendment by February 28, 2006. Once approved, the amendment shall be implemented within 90 days.
If there are any questions regarding this proposed amendment, please contact Scott Head at (361) 972-7136 or me at (361) 972-7902.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on 1t Z 5ooS Vice President of Engineering jai/
Attachments:
- 1. Licensee's Evaluation
- 2. Proposed Technical Specification Change (Mark-up)
STI:31837684
NOC-AE-05001841 Page 3 of 3 cc:
(paper copy) (electronic copy)
Bruce S. Mallett A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 David H. Jaffe Arlington, Texas 76011-8064 U. S. Nuclear Regulatory Commission Richard A. Ratliff Jack A. Fusco Bureau of Radiation Control Michael A. Reed Texas Department of State Health Services Texas Genco, LP 1100 West 49th Street Austin, TX 78756-3189 Jeffrey Cruz C. Kirksey U. S. Nuclear Regulatory Commission City of Austin P. 0. Box 289, Mail Code: MN1 16 Wadsworth, TX 77483 Jon C. Wood Cox Smith Matthews C. M. Canady J. J. Nesrsta City of Austin R. K. Temple Electric Utility Department E. Alarcon 721 Barton Springs Road City Public Service Austin, TX 78704
NOC-AE-05001 841 Attachment 1 Licensee's Evaluation
NOC-AE-05001841 Attachment I Page 1 of 6 LICENSEE'S EVALUATION
1.0 DESCRIPTION
This letter is a request to amend Operating Licenses NPF-76 and NPF-80 for South Texas Project (STP) Units 1 and 2. The proposed amendment revises Technical Specification (TS) 3.4.6.1, "Reactor Coolant System Leakage Detection Systems," to require specifically the containment radioactivity monitor (particulate channel) to be operable in Modes 1, 2, 3 and 4. The proposed amendment eliminates the gaseous channel from Limiting Condition for Operation (LCO) 3.4.6.1.
Additionally, corresponding changes to Surveillance Requirement 4.4.6.2.1, "Reactor Coolant System Operational Leakage," are also requested.
STPNOC requests approval of the proposed amendment by February 28, 2006. Once approved, the amendment shall be implemented within 90 days.
2.0 PROPOSED CHANGE
The current TS LCO 3.4.6.1 states the following:
3.4.6.1 The following Reactor Coolant System Leakage Detection Instrumentation shall be OPERABLE:
- a. One Containment Atmosphere Radioactivity Monitor (gaseous or particulate), and
- b. The Containment Normal Sump Level and Flow Monitoring System.
The proposed amendment would revise this LCO to state the following:
3.4.6.1 The following Reactor Coolant System Leakage Detection Instrumentation shall be OPERABLE:
- a. The Containment Radioactivity Monitor (particulate channel), and
- b. The Containment Normal Sump Level and Flow Monitoring System.
Corresponding changes to SR 4.4.6.2.I.a are also proposed, which would remove the gaseous channel from containment atmosphere monitoring requirements.
The associated change to the TS Bases will be made accordingly as a part of the implementation of this license amendment.
NOC-AE-05001841 Attachment I Page 2 of 6
3.0 BACKGROUND
System Design
The Reactor Coolant System (RCS) Leakage Detection Systems required by TS 3.4.6.1 are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary (RCPB).
The system was designed to conform with NRC General Design Criterion (GDC) 30 and Regulatory Guide (RG) 1.45.
RG 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems," dated May 1973, establishes requirements for detection and monitoring of leakage of reactor coolant into the containment area. RG 1.45 states that instrument sensitivities of 10-9 pCi/cc radioactivity for air particulate monitoring and 10-6 pCi/cc radioactivity for radiogas monitoring are practical for reactor coolant pressure boundary leakage detection systems. It also states that detector systems should respond to a one gal/min, or its equivalent, leakage increase in one hour or less. RG 1.45 goes on to say that "in analyzing the sensitivity of leak detection systems using airborne particulate or gaseous radioactivity, a realistic primary coolant radioactivity concentration assumption should be used. The expected values used in the plant environmental report would be acceptable." The expected percentage of leaking fuel used in the plant environmental report is 0.12 percent. This report also assumes a continuous low volume purge of the containment building at a rate of 5,000 cfm.
STP's RCS Leakage Detection instrumentation consists of a Containment Atmosphere Radioactivity Monitor (gaseous or particulate) and the Containment Normal Sump Level and Flow Monitoring System.
The particulate and gaseous channels of the Containment Atmosphere Radioactivity Monitor are used as part of the RCPB leakage detection system. The sensitivity and response time of the particulate channel, which is used for monitoring unidentified leakage to the containment, are sufficient to detect an increase in leakage rate of the equivalent of one gal/min within one hour in accordance with assumptions made consistent with RG 1.45.
Leakage Detection Methods The Reactor Containment Building Atmosphere Monitor is in place to monitor containment air for particulate, iodine, and gaseous activities. The monitor continuously samples from the containment atmosphere, which is drawn outside the containment in a closed system. The particulate channel of that monitor detects isotopes, which quantitatively relates the activity increase to the magnitude of RCPB leakage into the Containment.
The particulate channel's sensitivity and response time have been determined with the conclusion that the particulate channel is capable of measuring the equivalent of a one gal/min RCPB leakage to the Containment within one hour. Measurement interferences due to external ambient gamma background, naturally occurring airborne radioactivity, and normally undetectable RCPB leakage were considered. The display for this monitor is in units of pCi/cc.
NOC-AE-05001841 Attachment I Page 3 of 6 The alarm setpoint is calculated on the basis of monitor sensitivity, which corresponds to an RCPB leakage rate of one gal/min, such that the alarm is initiated within one hour from the start of the increased leak. Currently, the Reactor Containment Building Atmosphere particulate Alert Alarm and High Alarm design setpoints are approximately 8.4x10 pCi/cc and 1.0x10 6 pCi/cc respectively. Additionally, the Alert setpoint is normally lowered to increase the sensitivity and improve operator awareness of changes in atmosphere radioactivity levels.
The display for the noble gas channel of the monitor is in units of pCi/cc. The alarm setpoint is calculated on the basis of monitor sensitivity, which corresponds to an RCPB leakage rate of one gal/min, such that the alarm is initiated within one hour from the start of the increased leak.
Assuming 0.12 percent failed fuel based on the plant environmental report, the Reactor Containment Building Atmosphere gaseous channel Alert Alarm and High Alarm design setpoints are both approximately 5.8x10-3i Ci/cc. With the current RCS leakage and the low fuel clad leakage values, the majority of the gas that is sensed by the gaseous channel is activated Argon which is normally present in air and is activated by proximity to the high radiation field in the immediate vicinity of the reactor vessel. During normal operations, air flow inside containment distributes this activated gas throughout containment, such that a measured background level of approximately 8x10-6 pCi/cc is present.
Need for the Amendment During the period since startup of the South Texas Project (STP) to the present, the gaseous channel of the containment atmosphere radiation monitor has become less effective for RCS leakage detection due to improved fuel integrity and the resultant reduced RCS radioactivity levels. The gaseous channel was designed in accordance with the sensitivities specified in RG 1.45, (i.e., assuming 0.12 percent failed fuel) its alarm setpoint has been set as low as practicable, is fully functioning in accordance with its design requirements, and is meeting the current TS surveillance requirements. However, due to the high normal background levels of activated gas inside containment, the gaseous channel is unable to promptly detect RCS leakage with reduced reactor coolant radioactivity levels. Since TS 3.4.6.1 allows use of either the gaseous or the particulate channel to satisfy the requirement for one containment atmosphere radioactivity monitor, and the capability of the gaseous channel has been determined to be insufficient, removal of the gaseous channel requirement in TS 3.4.6.1 (and SR 4.4.6.2.1.a) is warranted.
4.0 TECHNICAL ANALYSIS
Detection of RCS leakage using radiation monitors is affected by the quantity of isotopes contained in the reactor coolant and the background level of radiation around the detectors.
With the level of radioactivity in the reactor coolant assumed in UFSAR, both the containment atmosphere particulate and gaseous radioactivity channels are capable of detecting a one gal/min leak in one hour. However, the level of radioactivity in the STP reactor coolant is normally much lower than the value that was assumed in the UFSAR.
NOC-AE-05001841 Attachment I Page 4 of 6 The ransge of the containment atmosphere particulate radioactivity channel isl.6x10-" to 1.6x10- iCi/cc, which meets the sensitivity criteria specified in RG 1.45. Varying detector background, RCS activity level, and failed fuel conditions contribute to changes in the particulate monitors' detection capabilities.
The containment atmosphere gaseous radioactivity channel has a range of approximately 5.4x 10-7 to 5.4x10-l ACi/cc, which also meets the sensitivity criteria specified in RG 1.45. As the detector background increases, either the time to detect a one gal/min leak would increase or the detectable RCS leak rate would be greater than one gal/min within the specified timeframe. At elevated RCS activity/failed fuel conditions, a one gal/min leak would be detectable within one hour even with a much higher detector background. For lower RCS activity levels, as described above, a one gal/min leak becomes more difficult to detect using the containment atmosphere gaseous radioactivity monitor.
Additional diverse means of leakage detection are available as part of the overall STPNOC leakage detection capability. For example, non-TS required Volume Control Tank (VCT) level is monitored in the control room with a level recorder. The level recorder is sensitive enough to record a one gal/min leak rate within one hour during steady state operations. RCS mass balance is performed in accordance with TS 3.4.6.1 with one inoperable RCS leakage detection monitor. The mass balance calculated from performing the surveillance can provide indication of a one gal/min leakrate change. Finally, additional non-TS required containment temperature and pressure instrumentation provide indication in the main control room.
It should be noted that STPNOC intends to maintain the containment atmosphere gaseous radioactivity monitor functional and available in accordance with normal non-TS equipment practices.
In summary, while the proposed amendment eliminates the gaseous channel from TS 3.4.6.1 (and SR 4.4.6.2.1.a), it results in a more restrictive requirement in the LCO for the containment atmosphere radioactivity monitor (i.e., the particulate channel). The proposed amendment continues to require diverse means of leakage detection equipment with capability to promptly detect RCS leakage consistent with the STP licensing basis.
5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration STPNOC has evaluated whether a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No
NOC-AE-05001841 Attachment I Page 5 of 6 The proposed change has been evaluated and determined to not increase the probability or consequences of an accident previously evaluated. The proposed change does not make any hardware changes and does not alter the configuration of any plant system, structure or component (SSC). The proposed change only removes the containment atmosphere gaseous radioactivity monitor as an option for meeting the operability requirement for TS 3.4.6.1, and correspondingly from the requirements of SR 4.4.6.2.1.a.
Therefore, the probability of occurrence of an accident is not increased. The TS will continue to require diverse means of leakage detection equipment, thus ensuring that leakage due to cracks would continue to be identified prior to breakage and the plant shutdown accordingly. Additionally, the proposed change is not modeled in the South Texas Project probabilistic risk assessment and has no impact on core damage frequency or large early release frequency. Therefore, the consequences of an accident are not increased.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed change does not involve the use or installation of new equipment and the currently installed equipment will not be operated in a new or different manner. No new or different system interactions are created and no new processes are introduced. The proposed changes will not introduce any new failure mechanisms, malfunctions, or accident initiators not already considered in the design and licensing bases. The proposed change does not affect any SSC associated with an accident initiator. Based on this evaluation, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No The proposed change does not make any alteration to any RCS leakage detection components. The proposed change only removes the gaseous channel of the containment atmosphere radioactivity monitor as an option for meeting the operability requirement for TS 3.4.6.1, and correspondingly from the requirements of SR 4.4.6.2.1.a. The proposed amendment continues to require diverse means of leakage detection equipment with capability to promptly detect RCS leakage. Although not required by TS, additional diverse means of leakage detection capability are available. Based on this evaluation, the proposed change does not involve a significant reduction in a margin of safety.
NOC-AE-05001841 Attachment I Page 6 of 6 Based on the above, STPNOC concludes that the proposed amendment involves no significant hazards consideration under the standards set forth in 10CFR50.92, and a finding of "no significant hazards consideration" is justified.
5.2 Applicable Regulatory Requirements/Criteria 10 CFR 50, Appendix A, "General Design Criteria for Nuclear Power Plants," Criterion 30, "Quality of reactor coolant pressure boundary," requires that means be provided for detecting and, to the extent practical, identifying the location of the source of reactor coolant leakage.
The various means for detecting reactor coolant leakage at STPNOC were previously discussed in Section 3.0, "Background."
The specific attributes of the reactor coolant leakage detection systems are outlined in Regulatory Positions 1 through 9 of RG 1.45. STP conformance with RG 1.45 is described in UFSAR Section 3.12, "Conformance with NRC Regulatory Guides." It should be noted that Regulatory Position 9 specifies that the TS should include the limiting conditions for identified and unidentified leakage and address the availability of various types of instruments to assure adequate coverage at all times; however, Position 9 does not specify how many instruments shall be contained in the TS. Both the containment sump monitor and the containment atmosphere:.
radioactivity particulate channel satisfy the RG 1.45 criteria for detecting RCS leakage.
Therefore, removal of the gaseous channel of the containment radiation monitor from the TS is not in conflict with this Regulatory Position.
10 CFR 50.36, "Technical Specifications," paragraph (c)(2)(ii)(A), specifies that a TS limiting condition for operation be established for installed instrumentation that is used to detect and indicate in the control room a significant abnormal degradation of the RCPB. Currently, the instrumentation addressed in TS 3.4.6.1 satisfies this requirement. The current instrumentation addressed in TS 3.4.6.1 includes one containment sump monitor and one containment atmosphere radioactivity monitor (gaseous or particulate). The removal of the gaseous channel of the containment atmosphere radioactivity monitor from the TS is not in conflict with this requirement as the containment sump monitor and the particulate channel of the containment atmosphere radioactivity monitor will remain in the TS LCO.
6.0 ENVIRONMENTAL CONSIDERATION
STPNOC has evaluated the proposed changes and determined the changes do not involve (1) a significant hazards consideration, (2) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (3) a significant increase in the individual or cumulative occupational exposure. Accordingly, the proposed changes meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9), and an environmental assessment of the proposed changes is not required.
NOC-AE-05001841 Attachment 2 Proposed Technical Specification Change (Mark-up)
NOC-AE-05001 841 Attachment 2 Page lof 2 REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Instrumentation shall be OPERABLE:
- a. ; 14m Containment Atmosphere Radioactivity Monitor {gas ou particulateh-nnel, and
- b. The Containment Normal Sump Level and Flow Monitoring System.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
- a. With the required containment atmosphere radioactivity monitor inoperable perform the following actions 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 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />s:
- 1) Restore i Jcontainment atmosphere monitorygi [parlicuLais channeD to OPERABLE status within 30 days and,
- 2) Obtain and analyze a grab sample of the containment atmosphere for ____
particulate radioactivity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or
- 3) Perform a Reactor Coolant System water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. With the required containment normal sump level and flow monitoring system inoperable perform the following actions or be in at least HOT STANBY 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 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />s:
- 1) Restore the containment normal sump and flow monitoring system to OPERABLE status within 30 days and,
- 2) Perform a Reactor Coolant System water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. With both a. and b. inoperable, enter 3.0.3.
SURVEILLANCE.REQUIREMENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:
- a. Containment Atmosphere p -. _ Monitoring Systernnel performance of the following:
- 1) CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and
- 2) CHANNEL CALIBRATION at least once per 18 months
- b. Containment Normal Sump Level and Flow Monitoring System performance of CHANNEL CALIBRATION at least once per 18 months.
SOUTH TEXAS - UNITS 1 & 2 3/4 4-19 Unit 1 - Amendment No. 86, 153 Unit 2 - Amendment No. 3 141
NOC-AE-05001841 Attachment 2 Page 2 of 2 REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.2.1 Note: this requirement is not applicable to primary-to-secondary leakage (refer to 4.4.6.2.3).
Reactor Coolant System operational leakage shall be demonstrated to be within each of the above limits by:
- a. Monitoring the containment atmosphere _ particulate radioactivity channef at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;
- b. Monitoring the containment normal sump inventory and discharge at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;
- c. Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and (1)
- d. Monitoring the Reactor Head Flange Leakoff System at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit:
- a. At least once per 18 months,
- b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9 months,
- c. Prior to returning the valve to service following maintenance, repair or replacement work on the valve, and
- d. Prior to entering MODE 2 following valve actuation due to automatic or manual action or flow through the valve except for valves XRH0O60 A, B, C, and XRHOO61 A, B, C.
4.4.6.2.3 Primary-to-secondary leakage shall be verified s 150 gallons per day through any one steam generator at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. (1)
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.
(1) Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
SOUTH TEXAS - UNITS 1 & 2 3/4 4-21 Unit 1 - Amendment No. 22,134, 164 Unit 2 - Amendment No. 42423, 154