|
---|
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] |
Text
z - ~~~77 Nuclear Operating Company c17 E77 South Tcas ProectElecric GeneratinS Station O. Bor 289 Wadsworth, Teas 77483 A May 22, 2003 NOC-AE-03001454 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 Nos. STN 50-498 and STN 50-499 License Amendment Request -
Proposed Amendment to Technical Specification 3.4.2.2 Pursuant to 10CFR50.90, STP Nuclear Operating Company (STPNOC) hereby requests an amendment to Technical Specification (TS) 3.4.2.2, "Reactor Coolant System," to relax the lift setting tolerance of the pressurizer safety valves (PSVs) from +/-2% to +2%, -3%. The current TS requirement that the as left lift setting be within +/-1% following valve testing will remain intact.
STPNOC has determined that this proposed amendment to the operating licenses involves no significant hazards consideration. to this letter provides the No Significant Hazards Determination and Attachment 2 provides the TS page marked up with the proposed change. Attachment 3 provides the retyped TS page. There are no proposed changes to the Bases for TS 3.4.2.2, but they are provided in for information.
The Plant Operations Review Committee has recommended the proposed change for approval.
STPNOC has notified the State of Texas in accordance with OCFR50.91(b).
STPNOC requests approval of the proposed amendment by May 15, 2004. Once approved, the amendment shall be implemented within 30 days.
If there are any questions regarding this proposed amendment, please contact Mr. Scott Head at (361) 972-7136 or me at (361) 972-7209.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on May 22, 2003 J.Jran Vice President, Engineering & Technical Services _ cl STI: 31542679
NOC-AE-03001454 Page 2 of 2 Attachments:
- 1. Licensee's Evaluation
- 2. Proposed Technical Specification Change (Mark-up)
- 3. Proposed Technical Specification Page (Retyped) For Information Only
- 4. Bases (For Information Only) 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 L. D. Blaylock 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 Texas Genco, LP Richard A. Ratliff A. Ramirez Bureau of Radiation Control City of Austin Texas Departnent of Health 1100 West 49th Street C. A. Johnson Austin, TX 78756-3189 AEP Texas Central Company Cornelius F. O'Keefe Jon C. Wood U. S. Nuclear Regulatory Commission Matthews & Branscomb P. 0. Box 289, Mail Code: MN1 16 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704
NOC-AE-03001454 Attachment 1 Licensee's Evaluation
NOC-AE-03001454 Attachment I Page I of 7 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 change would revise Technical Specification (TS) 3.4.2.2, "Reactor Coolant System," to relax the lift setting tolerance of the pressurizer safety valves (PSVs) from +/-2% to +2%, -3%. The current TS requirement that the as left lift setting shall be within +/-1% following valve testing will remain intact.
This change is requested to reduce regulatory burden in complying with TS requirements that have little safety significance. During refueling outages, the PSVs are removed from the plant and sent to a test facility. A Licensee Event Report (LER) is submitted to the NRC if the lift setting of more than one PSV is found to be outside the allowable tolerance. The test facility returns any out-of-tolerance PSV to within + 1% of the required lift setting. Increasing the TS lift setting tolerance to the value, assumed in the safety analyses would reduce the number of LERs prepared and reviewed. There would be no change in the margin of safety, and both licensee and NRC resources could be applied to issues of greater safety significance.
Approval of the proposed amendment is requested by January 30, 2004. Once approved, the amendment shall be implemented within 30 days.
2.0 PROPOSED CHANGE
Specifically, the proposed change would revise the following TS Section:
3.4.2.2 All pressurizer Code safety valves shall be OPERABLE with a lift setting of 2485 psig +/-2%. 2 to read:
3.4.2.2 All pressurizer Code safety valves shall be OPERABLE with a lift setting of 2485 psig +2%, _3%. 2
NOC-AE-03001454 Attachment I Page 2 of 7
3.0 BACKGROUND
In each STP unit, there are three PSVs set at 2485 psig (2500 psia) to provide overpressure protection for the reactor coolant system (RCS). The PSVs are Class 1 components, designed and manufactured to meet Section III of the ASME Code. They are the totally enclosed pop type, spring-loaded, self-activated, with backpressure compensation.
The RCS design pressure is 2485 psig (2500 psia), which is also the setpoint for the PSVs. The PSVs prevent RCS pressure from exceeding 110% of system design pressure (approximately 2734 psig or 2750 psia) in compliance with the ASME Code,Section III.
The South Texas Project owns nine PSVs; three are installed in each unit and the remaining three are replacement spares. During refueling outages, all three valves installed in the outage unit are removed and replaced with the three spares, which have been previously tested and certified to lift at 2485 psig +/-1%. The three valves removed from the unit are sent offsite for testing and refurbishment in preparation for installation in the other unit during its next refueling outage. NWS Technologies in Spartanburg, South Carolina currently performs the PSV testing. STPNOC Engineering monitors all testing and valve maintenance.
There have been 58 as-found tests conducted on the PSVs at STP since operation began. In those tests, five valves have opened at > 2% above the setpoint and 24 valves have opened at
> 2% below the setpoint. The five Licensee Event Reports generated because of PSVs being out of tolerance at STPEGS determined that the condition was bounded by analysis and did not violate any safety analysis limits.
4.0 TECHNICAL ANALYSIS
The proposed change would revise TS 3.4.2.2 to relax the lift setting tolerance of the PSVs from
+/-2% to +2%, -3%. The current TS requirement that the as left lift setting be within +/-1%
following valve testing will remain intact. Table 1 depicts the various RCS nominal pressure settings.
This relaxation is applicable for drift of PSV lift settings that occurs during the operating cycle and is consistent with ASME Section III, Subarticles NB-7512.1 and NB-7512.2.
The 1989 edition of the ASME Code Section III, Subarticle NB-7410/NC-7410 specifies:
The set pressure of at least one of the pressure relief devices connected to the system shall not be greater than the design pressure of any component within the pressure retaining boundary of the protected system.
Additionally, the 1989 edition of the ASME Code,Section XI, requires that the PSVs be tested in accordance with ASME/ANSI OM-1987, Part 1, "Requirements for Inservice Performance Testing of Nuclear Power Plant Pressure Relief Devices." This standard allows a testing lift pressure to vary from the stamped pressure by no more than +/-3% before declaring a test failure.
NOC-AE-0300 1454 Attachment 1 Page 3 of 7 This standard also includes guidelines for testing additional valves when a valve exceeds the
+/-3% tolerance. Therefore, increasing the PSV setpoint tolerance to +2%, -3% for the "as-found" test acceptance criterion is in compliance with the 1989 ASME Code,Section XI requirements.
The proposed change has been reviewed to determine the impact on the PSV inlet and discharge piping. The components reviewed meet the applicable requirements of ASME Section III, Subarticle NB-3000. The calculated stress intensity levels do not exceed the service limits specified in the component specification for all system service loading.
Increasing the allowed tolerance from -2% to -3% (i.e., from 2450 to 2425 psia) could affect DNBR for events that lift the PSVs. If the PSV lift pressures are too low, they may lift earlier than anticipated during a reactor overpower event. This may result in a lower RCS pressure, which may adversely affect the calculated DNBR. The analysis for reactor overpower events, such as rod withdrawal from power, assumes the pressurizer power-operated relief valves lift at 2335 psig, which is well below the PSV setpoint with a -3% tolerance (2410 psig). Therefore, events that lift the PSVs are not the limiting DNB events. Reference 1 documents that sufficient DNB margin existed to accommodate a PSV lift at 2406 psig, or approximately 3.18% below the setpoint.
Some overpower events may result in an RCS pressure increase that exceeds the capacity of the pressurizer spray and pressurizer PORVs, and could result in lifting the PSVs. The limiting overpower event is rod withdrawal at power, which is analyzed for several power levels to identify the limiting DNB case. The DNB analysis assumes that pressurizer spray and the pressurizer PORVs operate as designed. This is a conservative assumption because it lowers RCS pressure and DNBR. The DNB analysis was revised as part of the power uprate proposal (Ref. 2) using the Delta 94 steam generator design and assuming that the PSVs lifted at 2425 psia. The analysis also used the Revised Thermal Design Procedure, which assumes nominal initial conditions and accounts for the uncertainties using an increased minimum DNBR limit of 1.52. The results of the analysis showed that the minimum DNBR stayed above 1.57.
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 10CFR50.92 as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No
NOC-AE-03001454 Attachment I Page 4 of 7 The proposed TS change takes credit for the assumptions made in the reanalysis of the rod withdrawal from power event already evaluated in the UFSAR. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed TS change takes credit for the assumptions made in the reanalysis of the rod withdrawal from power event already evaluated in the UFSAR. Therefore, the 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 Margin of safety is associated with confidence in the ability of the fission product barriers (i.e., fuel and fuel cladding, reactor coolant pressure boundary, and containment structure) to limit the level of radiation dose to the public. The proposed TS change takes credit for the assumptions made in the reanalysis of the rod withdrawal from power event already evaluated in the UFSAR. That analysis demonstrated that the fuel design limits were maintained by the reactor protection system since the DNBR was maintained above the limit value. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, STPNOC concludes that the proposed amendment involves no significant hazards consideration under the standards set forth in 10CFR50.92 and, accordingly, a finding of "no significant hazards consideration" is justified.
5.2 Applicable Regulatorv Requirements/Criteria The regulatory basis for TS 3.4.2.2 is to ensure that overpressure protection is operable such that reactor coolant system pressure does not exceed 110% of the design pressure. Overpressure protection for the RCS is accomplished by the utilization of safety valves along with the reactor protection system and associated equipment. Combinations of these systems provide compliance with the overpressure requirements of the ASME Boiler and Pressure Vessel Code,Section III, Paragraph NB-7300. (UFSAR 5.2.2)
Piping, valves, and associated equipment used for overpressure protection are classified in accordance with ANSI NI 8.2, "Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants." (UFSAR 5.2.2.6)
NOC-AE-03001454 Attachment 1 Page 5 of 7 NUREG-0800, Section 5.2.2, "Overpressure Protection" states:
The acceptance criteria for the overpressure protection system are based on meeting the relevant portions of the following regulations:
General Design Criterion 15 - "Reactor coolant system design."
The reactor coolant system and associated auxiliary control, and protection systems shall be designed with sufficient margin to assure that the design conditions of the reactor coolant pressure boundary are not exceeded during any condition of normal operation, including anticipated operational occurrences.
General Design Criterion 31 - "Fracture prevention of reactor coolant pressure boundary."
The reactor coolant pressure boundary shall be designed with sufficient margin to assure that when stressed under operating, maintenance, testing, and postulated accident conditions (1) the boundary behaves in a nonbrittle manner and (2) the probability of rapidly propagating fracture is minimized.
Licensees must meet the recommendations of Task Action Plan item II.D. of NUREG-0737, which required that licensees and applicants conduct testing to qualify the RCS safety valves under expected operating conditions for design basis transients and accidents.
Other specific acceptance criteria necessary to meet the requirements of GDC 15 and 31 are as follows:
Safety valves shall be designed with sufficient capacity to limit the pressure to less than 110% of the reactor coolant pressure boundary design pressure during the most severe abnormal operational transient with reactor scram.
Reference 3 submitted reports that show the valves, piping arrangements, and fluid inlet conditions for STP Units 1 and 2 are bounded by the values and test parameters of the EPRI Safety and Relief Test Program. The EPRI tests confirmed the ability of the safety valves to open and close under the expected operating fluid conditions. The NRC confirmed the conclusions drawn by STP (Reference 4).
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.
NOC-AE-03001454 Attachment I Page 6 of 7
6.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10CFR20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10CFR51.22(c)(9).
Therefore, pursuant to 10CFR51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
7.0 REFERENCES
- 1. Letter, E. D. Halpin to NRC, "Licensee Event Report 01-002 - Pressurizer Safety Valves Setpoints Discovered Outside Required Tolerances," December 12, 2001 (NOC-AE-01001228)
- 2. Letter, J. J. Sheppard to NRC, "Technical Specifications Associated with a 1.4% Core Power Uprate," August 22, 2001 (NOC-AE-01001162)
- 3. Letter, M. R. Wisenburg to NRC, "Responses to DSER/FSAR Items Regarding Chapter 7A, Item Il.D.1," October 31, 1985 (ST-HL-AE-1466)
- 4. NUREG-078 1, Supplement 4, "Safety Evaluation Report Related to the Operation of South Texas Project, Units 1 and 2," Appendix W, July 1987
NOC-AE-03001454 Attachment 1 Page 7 of 7 TABLE 1 REACTOR COOLANT SYSTEM NOMINAL PRESSURE SETTINGS Psi g Hydrostatic Test Pressure 3,107 110% Design Pressure 2,735 Pressurizer Safety Valves Begin to Open (with + 2%tolerance) 2,535 Design Pressure and Pressurizer Safety Valve Set Pressure 2, 485 Pressurizer Safety Valves Begin to Open (with - 2% tolerance) 2,435 Pressurizer Safety Valves Begin to Open (with - 3% tolerance) 2,410 High Pressure Reactor Trip 2,380 Power Operated Relief Valves Begin to Open 2,335 High Pressure Alarm / Pressurizer Spray Valves Full Open 2,310 Pressurizer Spray Valves Begin to Open 2,260 Pressurizer Proportional Heaters Begin to Operate 2,250 Pressurizer Proportional Heaters Full Operation 2,220 Low Pressure Alarrn / Pressurizer Backup Heaters Energize 2,210 Low Pressure Reactor Trip 1,870
NOC-AE-03001454 Attachment 2 Proposed Technical Specification Changes (Mark-up)
REACTOR COOLANT SYSTEM OPERATING LIMITING CONDITION FOR OPERATION 3.4.2.2 All pressurizer Code safety valves shall be OPERABLE with a lift setting' of 2485 psig +-2%2 2%, - 3%. 2 APPLICABILITY: MODES 1, 2, and 3.
ACTION:
With one pressurizer Code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.2.2 No additional requirements other than those required by Specification 4.0.5.
'The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
2The as left lift setting shall be within +/-1% following valve testing.
SOUTH TEXAS - UNITS 1 & 2 3/4 4-8 Unit 1 - Amendment No. 5, 78 Unit 2 - Amendment No. 47, 67
NOC-AE-03001454 Attachment 3 Proposed Technical Specification Page (Retyped) For Information Only
REACTOR COOLANT SYSTEM OPERATING LIMITING CONDITION FOR OPERATION 3.4.2.2 All pressurizer Code safety valves shall be OPERABLE with a lift setting' of 2485 psig + 2%, - 3% 2 APPLICABILITY: MODES 1, 2, and 3.
ACTION:
With one pressurizer Code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.2.2 No additional requirements other than those required by Specification 4.0.5.
'The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
2 The as left lift setting shall be within +/-1% following valve testing.
SOUTH TEXAS- UNITS 1 & 2 3/4 4-8 Unit 1 - Amendment No.
Unit 2 - Amendment No.
NOC-AE-03001454 Attachment 4 Bases (For Information Only)
FOR INFORMATION ONLY REACTOR COOLANT SYSTEM BASES SAFETY VALVES The pressurizer Code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. Each safety vialve is designed to relieve 504,950 lbs. per hour of saturated steam at the valve setpoinit of 2500 psia.
During Modes 1, 2, and 3, all pressurizer Code safety valves must be OPERABLE to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss-of-load assuming no Reactor trip until the first Reactor Trip System Trip Setpoint is reached (i.e., no credit is taken for a direct Reactor trip on the turbine trip resulting from loss-of-load) and also assuming no operation of the power-operated relief valves or steam dump valves.
Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section Xl of the ASME Boiler and Pressure Code.