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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] |
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Nuclear Operating Company South Tex*s Project Elerc Generatbng Station PO. Box289 adsworth, Texas 77483 May 22, 2002 NOC-AE-02001332 File No.: G25 10CFR50.90 STI:31450855 U. S. Nuclear Regulatory Commission Attention: Document Control Desk 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 License Amendment Request Proposed Amendment to Technical Specification 3/4.3.5, "Atmospheric Steam Relief Valve Instrumentation" Pursuant to 10 CFR 50.90, STP Nuclear Operating Company hereby requests the following amendment:
Amend Technical Specification 3/4.3.5 to allow automatic operation of the atmospheric steam relief valves during Mode 2 to maintain secondary side pressure at or below an indicated steam generator pressure of 1225 psig during startup and shutdown activities.
The proposed amendment involves no significant hazards determination. See Attachment 1. The proposed revised document pages are shown in Attachments 2 and 3.
STP Nuclear Operating Company requests approval of the proposed amendment by March 1, 2003 to support the spring refueling outage. Once approved, the amendment shall be implemented within 30 days.
There are no licensee commitments with this proposed amendment. A copy of this letter is provided to the State of Texas.
NOC-AE-02001332 Page 2 This proposed amendment is an addition to the number of estimated plant-specific licensing action requests that STP Nuclear Operating Company provided in a January 17, 2002, letter to the NRC. This request will provide additional operator flexibility during plant startup and shutdown operations.
If you should have any questions concerning this matter, please contact Mr. Ken Taplett at (361) 972-8416 or me at (361) 972-8757.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on:
11~4-4 J. J. Sheppard Vice President, Engineering & Technical Services Attachments:
- 1. Licensee's Evaluation
- 2. Proposed Technical Specification Changes (mark-up)
- 3. Proposed Technical Specification Pages (retyped)
NOC-AE-02001332 Page 3 cc:
(paper copy) (electronic copy)
Ellis W. Merschoff A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 M. T. Hardt/W. C. Gunst Arlington, Texas 76011-8064 City Public Service U. S. Nuclear Regulatory Commission Mohan C. Thadani Attention: Document Control Desk U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike R. L. Balcom Rockville, MD 20852 Reliant Energy, Inc.
Richard A. Ratliff A. Ramirez Bureau of Radiation Control City of Austin Texas Department of Health 1100 West 49th Street C. A. Johnson Austin, TX 78756-3189 AEP - Central Power and Light Company Cornelius F. O'Keefe Jon C. Wood U. S. Nuclear Regulatory Commission Matthews & Branscomb P. 0. Box 289, Mail Code: MN116 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704
NOC-AE-02001332 ATTACHMENT 1 LICENSEE' S EVALUATION
Attachment 1 NOC-AE-02001332 Page 1 of 5
1.0 DESCRIPTION
This letter is a request to amend Operating License No. NPF-76 for South Texas Project, Unit 1, and Operating License No. NPF-80 for South Texas Project, Unit 2.
The proposed change would revise the Operating Licenses to amend Technical Specification 3/4.3.5, "Atmospheric Steam Relief Valve Instrumentation" to allow automatic operation of the valves during Mode 2 to maintain secondary side pressure at or below an indicated steam generator pressure of 1225 psig during startup and shutdown operations. The current specification only allows controlling of secondary side pressure with the valves in manual control and open during these operations. This change will allow additional operator flexibility in the control of these valves. It is requested that the amendment be approved prior to March 1, 2003, with a 30-day implementation period to support the spring refueling outage.
2.0 PROPOSED CHANGE
Specifically the proposed change would revise the following:
The NOTE to Table 3.3-14 of Technical Specification 3/4.3.5 is revised to allow automatic operation of the atmospheric steam relief valves at or below an indicated steam generator pressure of 1225 psig to support startup and shutdown operations.
3.0 BACKGROUND
Technical Specification 3/4.3.5 was approved by License Amendment Numbers 114/102 to South Texas Project, Units 1 and 2, respectively on August 16, 1999 (See References A and B). This new technical specification for the atmospheric steam relief valves ensured that the automatic feature of the valves remained operable during Modes 1 and 2. In order to support startup and shutdown activities (including post-refueling low power physics testing), the Specification allowed the valves to be operated in manual and open in Mode 2 as long as the secondary side pressure was maintained at or below an indicated steam generator pressure of 1225 psig to ensure the safety analysis limit would not be exceeded in the event of the accident.
Technical Specification 3/4.3.5 requires that the atmospheric steam relief valves [to be referred to as the steam generator power-operated relief valves (SG PORVs) hereafter] automatic controls be operable with a nominal setpoint of 1225 psig in Modes 1 and 2. This is because the safety analyses assumes automatic operation of the valves with a nominal setpoint of 1225 psig with uncertainties. In order to support startup and shutdown activities (including post-refueling low power physics testing),
the current Specification allows the valves only to be operated in manual and open in Mode 2 to maintain the secondary side pressure at or below an indicated steam generator pressure of 1225 psig.
The allowance for manual operation at or below the nominal automatic setpoint is provided in a
Attachment 1 NOC-AE-02001332 Page 2 of 5 footnote to Table 3.3-14. The proposed change of this amendment request adds the words "or in automatic operation" to the footnote. Attachment 2 provides a mark-up of the proposed change. The change will still require that the secondary side pressure be maintained at or below an indicated steam generator pressure of 1225 psig when using the automatic mode of operation. This change will allow for additional operator flexibility for control of these valves during startup and shutdown activities.
Operating experience has determined that automatic control of the setpoint is the preferred method of valve control when steady-state conditions exist.
Upon approval of this change, STP Nuclear Operating Company plans to revise the Technical Specification Bases by adding the following statement:
"In addition to support startup and shutdown activities (including post-refueling low power physics testing), secondary side pressure can be maintained in Mode 2 with the atmospheric steam relief valves left in automatic operation as along as the setpoint is controlled at or below an indicated steam generator pressure of 1225 psig."
The SG PORVs are provided to protect the steam generator and the main steam system in the event of high steam pressure. In addition, the SG PORVs are provided to allow a controlled cooldown of the plant when the main condenser is not available or the main steam isolation valves are shut. The accident analyses credits the automatic operation of the SG PORVs in Modes 1 and 2. The hydraulic operation of the SG PORVs and the electrical power requirements are described in the Updated Final Safety Analysis Report (UFSAR) and in Reference A.
Operation of the SG PORVs can be controlled either automatically or manually. When the valves are selected for automatic operation, the opening and closing of the valves is controlled by circuitry that compares secondary pressure with the valve setpoint. The automatic control setpoint is adjusted from the valve control station on the main control room control board. When the valves are selected for automatic operation, a manual adjustment of the setpoint will determine the automatically controlled secondary pressure. When the valves are selected for manual operation, the valves can be manually opened and closed from the valve control station while monitoring secondary pressure.
The function and operation of the SG PORVs is described in Section 10.3.2.4 of the UFSAR. The automatic operation of these valves that is assumed in the safety analysis is described in Sections 15.2.7 and 15.6.5 of the UFSAR.
4.0 TECHNICAL ANALYSIS
The proposed amendment revises the footnote to Table 3.3-14 for Technical Specification 3/4.3.5.
See the mark-up in Attachment 2. The revision to the footnote will allow for automatic operation of the SG PORVs in addition to manual operation in Mode 2 for additional operator flexibility. The specific conditions are for supporting startup and shutdown activities (including post-refueling low power physics testing), provided that the secondary side pressure is maintained at or below an indicated steam generator pressure of 1225 psig. No design change is required to implement this revision since both methods for controlling the valves already exist in the plant configuration. The
Attachment 1 NOC-AE-02001332 Page 3 of 5 safety analysis will be unaffected by this change since the secondary side pressure will be maintained at or below the control limit assumed in the accident analysis. Manual control of the valves is already allowed by the specification. In effect, the additional method of control of the valves that is being proposed is another method of manually controlling the valves by adjustment of the valve setpoint.
The operator is required to adjust the setpoint for automatic operation at 1225 psig when the footnote no longer applies.
The proposed change is consistent with the purpose of Technical Specification 3/4.3.5. The change allows for an additional method of controlling the SG PORVs during startup and shutdown activities.
This allows for additional operator flexibility for controlling these valves when in this condition.
Since approval of Technical Specification 3/4.3.5, operating experience has determined that this additional flexibility is desired for plant control.
The proposed amendment is not risk-informed.
5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration STP Nuclear Operating Company 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, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change only provides another method of controlling the SG PORVs under specified operating conditions. The operating conditions in Specification 3/4.3.5 remain unchanged. No change is required to plant design since the proposed method of control is already part of the plant's configuration. The proposed method of control is the same method of control normally required by the specification in Modes 1 and 2. The proposed method of control will not impact the accident analysis assumptions or results. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
Attachment 1 NOC-AE-02001332 Page 4 of 5 The proposed method of controlling the SG PORVs is the same method that these valves are controlled in Modes 1 and 2 by the specification under normal conditions. The proposed change will allow the setpoint of these valves to be adjusted to support startup and shutdown activities. The adjustment of the setpoint is restricted so that the accident analysis is not impacted. No change to the design of the valves or plant configuration is required to implement the proposed change. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The proposed change that will allow for an additional method of controlling the SG PORVs during startup and shutdown activities is consistent with the operating restrictions for the current method of valve control. The accident analysis assumptions and results will remain unaffected. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, The STP Nuclear Operating Company concludes that the proposed amendments present 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.
5.2 Applicable Regulatory Requirements/Criteria The regulatory bases for Technical Specification 3/4.3.5 is to ensure that adequate safety injection flow into the reactor coolant system will occur during a small break LOCA so that the peak clad temperature limit of 10CFR50.46 is met and to prevent pressurizer overfill for a loss of normal feedwater accident. This change is consistent with these bases.
10 CFR Part 50, Appendix A, General Design Criterion (GDC) 20, "Protection system functions",
requires that the protection system be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety. The SG PORV automatic controls must be operable with a nominal setpoint of 1225 psig in Modes 1 and 2 because the safety analysis assumes automatic operation of the valves with a nominal setpoint of 1225 psig with uncertainties for mitigation of the small break loss of coolant accident. The proposed change is consistent with the current operating restrictions in the specification so that the assumptions in the accident analysis are met.
Attachment 1 NOC-AE-02001332 Page 5 of 5 The following General Design Criteria are met because no change is being proposed to the system design by the proposed amendment.
"* Criterion 21: Protection system reliability and testability
"* Criterion 22: Protection system independence
"* Criterion 23: Protection system failure modes
"* Criterion 24: Separation of protection and control systems
"* Criterion 29: Protection against anticipated operational occurrences In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
6.0 ENVIRONMENTAL CONSIDERATION
The proposed amendment changes a requirement with respect to use of a facility component.
However, (i) the proposed amendment involves no significant hazards consideration, (ii) there is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite, and (iii) there is no 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 environmental assessment need be prepared in connection with the proposed amendment.
7.0 REFERENCES
A. Letter from T. H. Cloninger to the NRC Document Control Desk, "Proposed New Amendment for Atmospheric Steam Relief Valve Instrumentation and Revised Amendment of Technical Specification 3.7.1.6, Atmospheric Steam Relief Valves," dated March 22, 1999 (NOC-AE-000462)
B. Letter from T. W. Alexion to W. T. Cottle, "South Texas Project, Units 1 and 2 - Issuance of Amendments re: Atmospheric Steam Relief Valves (TAC Nos. MA5078 and MA5079)",
dated August 16, 1999 (ST-AE-NOC-000487)
This specification is unique to the South Texas Project units. Therefore, there is no precedent.
References A and B provide the information on the development and approval of this specification.
NOC-AE-02001332 ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)
INSTRUMENTATION 3/4.3.5 ATMOSPHERIC STEAM RELIEF VALVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION:
3.3.5.1 The atmospheric steam relief valve instrumentation shown in Table 3.3-14 shall be OPERABLE.
APPLICABILITY: As shown in Table 3.3-14 ACTION: As shown in Table 3.3-14 SURVEILLANCE REQUIREMENTS:
4.3.5.1 Perform a CHANNEL CHECK on each atmospheric steam relief valve automatic actuation channel at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.3.5.2 Perform a CHANNEL CALIBRATION on each atmospheric steam relief valve automatic actuation channel at a nominal setpoint of 1225 psig +/- 7 psi at least once every 18 months.
4.3.5.3 Perform an ANALOG CHANNEL OPERATIONAL TEST on each atmospheric steam relief valve automatic actuation channel at a nominal setpoint of 1225 psig +/- 7 psi at least once every 18 months.
No changes on this page SOUTH TEXAS - UNITS 1 & 2 3/4 3-85 Unit 1 - Amendment No. 114 Unit 1 - Amendment No. 102
Cf, 0
"-4 m
x CD TABLE 3.3-14 z ATMOSPHERIC STEAM RELIEF VALVE INSTRUMENTATION
--i Cn REQUIRED NO. APPLICABLE FUNCTIONAL UNIT OF CHANNELS MODES ACTION Manual actuation control 4 1,2,3,4 1 channels (1 /valve)
Automatic actuation 4 1, 2# 2 control channels (1 /valve)
C.,
C.
No changes on this page C C B 3
=3 CD B33(D zz o o 00
TABLE 3.3-14 (Continued)
TABLE NOTATIONS When steam generators are being used for decay heat removal.
- Atmospheric steam relief valve(s) may be in manual operation and open, orn automatic operation, to maintain secondary side pressure at or below an indicated steam generator pressure of 1225 psig.
ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels less than the required number of channels, declare the affected valve(s) inoperable and apply Technical Specification 3.7.1.6.
ACTION 2- a. With one less than the required number of OPERABLE channels, restore the inoperable channel to OPERABLE status within 7 days; 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 />.
- b. With two less than the required number of OPERABLE channels, restore at least three channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SOUTH TEXAS - UNITS 1 & 2 3/4 3-87 Unit 1 - Amendment No.
Unit 2 - Amendment No.
NOC-AE-02001332 ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATION PAGES (RETYPED)
TABLE 3.3-14 (Continued)
TABLE NOTATIONS When steam generators are being used for decay heat removal.
- Atmospheric steam relief valve(s) may be in manual operation and open, or in automatic operation, to maintain secondary side pressure at or below an indicated steam generator pressure of 1225 psig.
ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels less than the required number of channels, declare the affected valve(s) inoperable and apply Technical Specification 3.7.1.6.
ACTION 2- a. With one less than the required number of OPERABLE channels, restore the inoperable channel to OPERABLE status within 7 days; 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 />.
- c. With two less than the required number of OPERABLE channels, restore at least three channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SOUTH TEXAS - UNITS 1 & 2 3/4 3-87 Unit 1 - Amendment No.
Unit 1 - Amendment No.