Letter Sequence Supplement |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: ML110620203, ML11140A163, ML11224A265, ML11230A003, ML11318A121, ML11318A122, ML11318A123, ML11318A124, ML11318A125, ML11318A126, ML11318A127, ML11318A128, ML11318A129, ML11318A130, ML11318A131, ML11318A132, ML11318A133, ML11318A135, ML11318A136, ML11318A138, ML11318A139, ML11318A140, ML11318A141, ML11318A142, ML11318A143, ML11318A144, ML11318A145, ML11318A146, ML11318A147, ML11318A148, ML11318A149, ML11318A150, ML11318A151, ML11318A152, ML11318A153, ML11318A154, ML11318A155, ML11318A156, ML11318A157, ML11318A158, ML11318A159, ML11318A160, ML11318A161, ML11318A162, ML11318A163, ML11318A164, ML11318A165, ML11318A166, ML11318A167, ML11318A168... further results
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MONTHYEARML1106202032011-03-17017 March 2011 License Renewal Application Online Reference Portal Project stage: Other ML1108907642011-04-14014 April 2011 Request for Additional Information for the Review of the South Texas Project, License Renewal Application-Electrical Branch Scoping Project stage: RAI ML1108205792011-04-14014 April 2011 Request for Additional Information for the Review of the South Texas Project, License Renewal Application -Section 2.4 Structural (TAC Nos. ME4936, ME4937) Project stage: RAI ML1108309782011-04-14014 April 2011 Request for Additional Information for the Review of the South Texas Project, License Renewal Application, Fire Protection and Component Integrity (TAC Nos. ME4536 ME4637 Project stage: RAI NOC-AE-11002670, Response to Request for Additional Information for License Renewal Application2011-05-0505 May 2011 Response to Request for Additional Information for License Renewal Application Project stage: Response to RAI NOC-AE-11002672, Response to Request for Additional Information for Licence Renewal Application2011-05-12012 May 2011 Response to Request for Additional Information for Licence Renewal Application Project stage: Response to RAI ML11137A0922011-05-24024 May 2011 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application Future Consideration of Operating Experience Project stage: RAI ML11140A1632011-06-0606 June 2011 Plan for the Aging Management Program Regulatory Audit Regarding the South Texas Project, Units 1 and 2 License Renewal Application Review (TAC Nos. ME4936 and ME4937) Project stage: Other NOC-AE-11002681, Amendment 2 to the License Renewal Application2011-06-16016 June 2011 Amendment 2 to the License Renewal Application Project stage: Other NOC-AE-11002683, Response to Request for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937)2011-06-23023 June 2011 Response to Request for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Response to RAI ML11154A0132011-07-0606 July 2011 Summary of Telephone Conference Call Held on May 23, 2011, Between the NRC and STPNOC, Concerning Requests for Additional Information Pertaining to the South Texas Project, LRA-Future Consideration of Operating Experience Project stage: RAI ML11166A2392011-07-12012 July 2011 Letter Request for Additional Information for South Texas Project Electric Generating Station, Units 1 and 2 License Renewal Application - Scoping and Screening Balance of Plant (TAC Nos. ME4936 and ME4937) Project stage: RAI ML11201A0552011-07-28028 July 2011 Requests for Additional Information for the Review of the South Texas Project, License Renewal Application - Scoping and Screening Audit (TAC Nos. ME4936 and ME4937) Project stage: RAI NOC-AE-11002702, Response to Request for Additional Information for the Review of the South Texas Project License Renewal Application2011-08-0909 August 2011 Response to Request for Additional Information for the Review of the South Texas Project License Renewal Application Project stage: Response to RAI ML11214A0882011-08-15015 August 2011 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Programs Audit, Plant Systems (TAC ME4936 and ME4937) Project stage: RAI ML11214A0052011-08-15015 August 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Programs Audit, Structures/Electrical (TAC ME4936 and ME4937) Project stage: RAI ML11214A0272011-08-15015 August 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Programs Audit, Reactor Systems (TAC Nos. ME4936 and ME4937) Project stage: RAI NOC-AE-11002716, Response to Request for Additional Information for the South Texas Project License Renewal Application (TAC ME4936 and ME4937)2011-08-18018 August 2011 Response to Request for Additional Information for the South Texas Project License Renewal Application (TAC ME4936 and ME4937) Project stage: Response to RAI ML1123000162011-08-18018 August 2011 License Renewal - Errata in AMP RAI Package Project stage: RAI NOC-AE-11002714, Response to Request for Additional Information for the South Texas Project License Renewal Application (TAC ME4936 and ME4937)2011-08-23023 August 2011 Response to Request for Additional Information for the South Texas Project License Renewal Application (TAC ME4936 and ME4937) Project stage: Response to RAI ML11230A0032011-09-0606 September 2011 Scoping and Screening Audit Report Regarding the South Texas Project, Units 1 and 2 (TAC Nos. ME4936 and ME4937) Project stage: Other NOC-AE-11002730, Response to Request for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937)2011-09-15015 September 2011 Response to Request for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Response to RAI NOC-AE-11002731, Response to Requests for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937)2011-09-15015 September 2011 Response to Requests for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Response to RAI ML1124402012011-09-21021 September 2011 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Review, Set 2 (TAC Nos. ME4936, ME4937) Project stage: RAI ML11250A0432011-09-22022 September 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Review, Set 1 (TAC Nos. ME4936 and ME4937) Project stage: RAI ML11224A2652011-09-22022 September 2011 Aging Management Programs Audit Report Regarding the South Texas Project, Units 1 and 2, Station License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Other ML11258A1612011-09-22022 September 2011 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Review, Set 3 (TAC Nos. ME4936 and ME4937) Project stage: RAI ML11272A1652011-10-0404 October 2011 Summary of Telephone Conference Call Held on September 28, 2011, Between the NRC and STP Nuclear Operating Company, Concerning Request for Additional Information Pertaining to the South Texas Project, LRA (TAC Nos. ME4936 and ME4937) Project stage: RAI NOC-AE-11002732, Response to Requests for Additional Information for the License Renewal Application2011-10-10010 October 2011 Response to Requests for Additional Information for the License Renewal Application Project stage: Response to RAI ML11273A0172011-10-11011 October 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application - Aging Management Review, Set 5 (TAC Nos. ME4936 and ME4937) Project stage: RAI ML11273A0082011-10-11011 October 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application - Aging Management Review, Set 4 (TAC Nos. ME4936 and ME4937) Project stage: RAI NOC-AE-11002737, Supplement to License Renewal Application (TAC Nos. ME4936 and ME4937)2011-10-18018 October 2011 Supplement to License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Supplement ML11277A0472011-10-18018 October 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application - Aging Management Program, Set 6 Project stage: RAI ML11305A0762011-10-25025 October 2011 Response to Requests for Additional Information for License Renewal Application (TAC ME4936 and ME4937) Project stage: Response to RAI NOC-AE-11002756, Contact Information Change, License Renewal Application (TAC ME4936 and ME4937)2011-10-26026 October 2011 Contact Information Change, License Renewal Application (TAC ME4936 and ME4937) Project stage: Other ML11318A1792011-11-0303 November 2011 Drawing No. LR-STP-WL-7R309F90021#2, Rev. 1, Piping and Instrumentation Diagram Liquid Waste Processing System Project stage: Other ML11318A1802011-11-0303 November 2011 Drawing No. LR-STP-WS-6R329F05048#1, Rev. 1, Piping and Instrumentation Diagram Solid Waste Processing System Project stage: Other ML11318A1762011-11-0303 November 2011 Drawing No. LR-STP-WL-7R309F05024#2, Rev. 1, Piping and Instrumentation Diagram Liquid Waste Processing System Project stage: Other ML11318A1652011-11-0303 November 2011 Drawing No. LR-STP-PS9Z329Z00047#1, Rev. 1, Piping and Instrumentation Diagram Primary Sampling System. Project stage: Other ML11318A1642011-11-0303 November 2011 Drawing No. LR-STP-PS-5Z329Z00045#2, Rev. 1, Piping & Instrumentation Diagram Primary Sampling System. Project stage: Other ML11318A1782011-11-0303 November 2011 Drawing No. LR-STP-WL-7R309F90021#1, Rev. 1, Piping and Instrumentation Diagram Liquid Waste Processing System Project stage: Other ML11318A1682011-11-0303 November 2011 Drawing No. LR-STP-RC-5R149F05004#2, Rev. 1, Piping and Instrumentation Diagram Acs Pressurizer Relief Tank. Project stage: Other ML11318A1722011-11-0303 November 2011 Drawing No. LR-STP-WL-5R309F05022#2, Rev. 1, Piping and Instrumentation Diagram Liquid Waste Processing System. Project stage: Other ML11318A1702011-11-0303 November 2011 Drawing No. LR-STP-RM-5R279F05033#2, Rev. 1, Piping & Instrumentation Reactor Makeup Water System. Project stage: Other ML11318A1602011-11-0303 November 2011 Drawing No. LR-STP-IA-8Q119F05050#2, Rev. 1, Piping & Instrumentation Diagram Mechanical Aux. Building Instrument Air. Project stage: Other ML11318A1472011-11-0303 November 2011 Drawing No. LR-STP-ED-5Q069F90011#1, Revision 1, Piping & Instrumentation Diagram Radioactive Vent and Drain System Fuel Handling Building Gravity Drains. Project stage: Other ML11318A1742011-11-0303 November 2011 Drawing No. LR-STP-WL-5R309F05027#2, Rev. 1, Piping & Instrumentation Diagram Auxiliary Steam and Condensate Return System (Lwps) Project stage: Other ML11318A1462011-11-0303 November 2011 Drawing LR-STP-ED-5Q069F05030 #2, Rev. 17, Piping & Instrumentation Diagram Radioactive Vent & Drain System Sump Pumps. Project stage: Other ML11318A1552011-11-0303 November 2011 Drawing No. LR-STP-FP-7Q272F00046, Rev. 1, Piping and Instrumentation Diagram Fire Protection Loop. Project stage: Other ML11318A1482011-11-0303 November 2011 Drawing No. LR-STP-ED-5Q069F90011#2, Revision 1, Piping & Instrumentation Diagram Radioactive Vent and Drain System Fuel Handling Building Gravity Drains. Project stage: Other 2011-06-16
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Category:Letter type:NOC
MONTHYEARNOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-230039, Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/20230032023-12-12012 December 2023 Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/2023003 NOC-AE-230039, Submittal of Update Foreign Ownership, Control or Influence (FOCI)2023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) NOC-AE-220039, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 252023-02-0606 February 2023 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 25 NOC-AE-220038, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2022-06-23023 June 2022 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask NOC-AE-210038, Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 252022-01-0404 January 2022 Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 25 NOC-AE-21003858, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2021-12-0606 December 2021 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes NOC-AE-21003853, Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-12-0303 December 2021 Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003848, Unit 1 Cycle 24 Core Operating Limits Report2021-11-18018 November 2021 Unit 1 Cycle 24 Core Operating Limits Report NOC-AE-21003846, Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-11-0404 November 2021 Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003842, 10 CFR 50.59 Summary Report2021-09-23023 September 2021 10 CFR 50.59 Summary Report NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003832, Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-0909 September 2021 Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003812, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-08-10010 August 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003825, Update of Foreign Ownership, Control, or Influence Information (FOCI)2021-08-0505 August 2021 Update of Foreign Ownership, Control, or Influence Information (FOCI) NOC-AE-21003824, Update Foreign Ownership, Control, or Influence (FOCI)2021-07-29029 July 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003823, Update Foreign Ownership Control or Influence (FOCI)2021-07-28028 July 2021 Update Foreign Ownership Control or Influence (FOCI) NOC-AE-21003820, Nuclear Insurance Protection2021-07-20020 July 2021 Nuclear Insurance Protection NOC-AE-21003819, Inservice Inspection Summary Report - 2RE212021-07-15015 July 2021 Inservice Inspection Summary Report - 2RE21 NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report NOC-AE-21003814, Technical Specification Bases Control Program2021-06-24024 June 2021 Technical Specification Bases Control Program NOC-AE-21003810, Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy NOC-AE-21003811, Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval2021-05-20020 May 2021 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval NOC-AE-21003801, Annual Dose Report for 20202021-04-26026 April 2021 Annual Dose Report for 2020 NOC-AE-21003802, 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report2021-04-26026 April 2021 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report NOC-AE-21003804, Operator Licensing Examination Schedule2021-04-21021 April 2021 Operator Licensing Examination Schedule NOC-AE-21003800, Radioactive Effluent Release Report2021-04-19019 April 2021 Radioactive Effluent Release Report NOC-AE-21003799, Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2021-04-15015 April 2021 Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan NOC-AE-21003795, Cycle 22 Core Operating Limits Report2021-04-15015 April 2021 Cycle 22 Core Operating Limits Report NOC-AE-21003796, Update Foreign Ownership, Control, or Influence (FOCI)2021-04-15015 April 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003791, Financial Assurance for Decommissioning - 2021 Update2021-03-31031 March 2021 Financial Assurance for Decommissioning - 2021 Update NOC-AE-21003790, Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter)2021-03-31031 March 2021 Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter) NOC-AE-210037, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-21003792, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-200037, License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications2021-03-11011 March 2021 License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications NOC-AE-21003784, Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing2021-03-0808 March 2021 Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-21003786, Annual Fitness for Duty Performance Report for 20202021-03-0101 March 2021 Annual Fitness for Duty Performance Report for 2020 NOC-AE-21003785, Evidence of Financial Protection2021-02-23023 February 2021 Evidence of Financial Protection NOC-AE-21003781, Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts2021-01-27027 January 2021 Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts NOC-AE-21003780, Submittal of Update Foreign Ownership, Control, or Influence (FOCI)2021-01-0707 January 2021 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-20003778, Changes to South Texas Project Electric Generating Station Emergency Plan2020-12-17017 December 2020 Changes to South Texas Project Electric Generating Station Emergency Plan NOC-AE-20003777, STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency2020-12-10010 December 2020 STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency NOC-AE-20003766, Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan2020-12-0202 December 2020 Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan NOC-AE-20003767, Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-16016 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval2020-10-28028 October 2020 Inservice Testing Program Description for the Fourth Ten-Year Interval NOC-AE-20003764, 1 RE22 Inspection Summary Report for Steam Generator Tubing2020-10-0707 October 2020 1 RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-20003762, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen2020-09-22022 September 2020 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen NOC-AE-20003761, Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic2020-09-10010 September 2020 Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic NOC-AE-20003760, Update Foreign Ownership. Control. or Influence(FOCI)- Transmittal2020-09-0808 September 2020 Update Foreign Ownership. Control. or Influence(FOCI)- Transmittal 2023-07-11
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Text
Nuclear Operating Company South Tewas Project Electric Station PO. Box 289 Wadsworth.
Texas 77483 __A_--December 11, 2012 NOC-AE-12002933 10 CFR 54 STI: 33629992 File: G25 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555-0001 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Clarification to Requests for Additional Information for the South Texas Project License Renewal Application Aging Management Program, Set 13 (Supplemental) (TAC Nos. ME4936 and ME4937)
References:
- 1. STPNOC letter dated October 25, 2010, from G. T. Powell to NRC Document Control Desk, "License Renewal Application" (NOC-AE-1 0002607)(ML103010257)
- 2. STPNOC letter dated April 17, 2012 from D. W. Rencurrel to NRC Document Control Desk, "Response to Requests for Additional Information for the South Texas Project License Renewal Application Aging Management Program, Set 13 (Supplemental) and Set 15 (TAC Nos. ME4936 and ME4937)" (NOC-AE-12002830) (ML12114A231)
By Reference 1, STP Nuclear Operating Company (STPNOC) submitted a License Renewal Application (LRA) for South Texas Project (STP) Units 1 and 2. By Reference 2, STPNOC provided responses to requests for additional information by the Nuclear Regulatory Commission regarding the STP application.
Clarification to the response to request for additional information (RAI) Set 13 (Supplemental)
RAI 4.2.2-1 that was provided in Reference 2 is described in Enclosure 1 to this letter. Changes to LRA pages described in Enclosure 1 are depicted as line-in/line-out pages in Enclosure 2.There are no regulatory commitments in this letter.Should you have any questions regarding this letter, please contact either Arden Aldridge, STP License Renewal Project Lead, at (361) 972-8243 or Ken Taplett, STP License Renewal Project regulatory point-of-contact, at (361) 972-8416.
NOC-AE-12002933 Page 2 I declare under penalty of perjury that the foregoing is true and correct.Executed on /2 _Date Senior Vice President KJT
Enclosures:
- 1. STPNOC Clarification to Response to Request for Additional Information RAI 4.2.2-1 2. STPNOC LRA Changes with Line-in/Line-out Annotations NOC-AE-12002933 Page 3 cc: (paper copy)(electronic copy)Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 1600 East Lamar Boulevard Arlington, Texas 76011-4511 Balwant K. Singal Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North (MS 8B1)11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 289, Mail Code: MN116 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 John W. Daily License Renewal Project Manager (Safety)U.S. Nuclear Regulatory Commission One White Flint North (MS 011-Fl)Washington, DC 20555-0001 Tam Tran License Renewal Project Manager (Environmental)
U. S. Nuclear Regulatory Commission One White Flint North (MS O11F01)Washington, DC 20555-0001 A. H. Gutterman, Esquire Kathryn M. Sutton, Esquire Morgan, Lewis & Bockius, LLP John Ragan Chris O'Hara Jim von Suskil NRG South Texas LP Kevin Polio Richard Pena City Public Service Peter Nemeth Crain Caton & James, P.C.C. Mele City of Austin Richard A. Ratliff Alice Rogers Texas Department of State Health Services Balwant K. Singal John W. Daily Tam Tran U. S. Nuclear Regulatory Commission Enclosure 1 NOC-AE-1 2002933 Enclosure 1 STPNOC Clarification to Response to Request for Additional Information RAI 4.2.2-1 Enclosure 1 NOC-AE-12002933 Page 1 of 1 SOUTH TEXAS PROJECT, UNITS I AND 2 REQUEST FOR ADDITIONAL INFORMATION
-AGING MANAGEMENT, SET 13 (TAC NOS. ME4936 AND ME4937)
Reference:
STPNOC letter dated April 17, 2012 from D. W. Rencurrel to NRC Document Control Desk, "Response to Requests for Additional Information for the South Texas Project License Renewal Application Aging Management Program, Set 13 (Supplemental) and Set 15 (TAC Nos. ME4936 and ME4937)" (NOC-AE-12002830) (ML12114A231)
RAI 4.2.2-1 (059)In the referenced letter, a revision to Sections 4.2.2 and 4.2.3 of the South Texas Project License Renewal Application was provided.Section 4.2.2 provided discussion of the RTPTS values for both Unit 1 and Unit 2. In that discussion the limiting material was identified as the intermediate shell R1606-3 and the intermediate shell R2507-2 for Unit 1 and 2 respectively.
Clarification is necessary to assure differentiation between the beltline limiting material and the overall limiting material of the Inlet Nozzle R1613-4 and Outlet Nozzle R2012-1 for Unit 1 and 2, respectively.
Section 4.2.3 provided discussion of the Cv USE values for both Unit 1 and Unit 2. In that discussion the limiting material was identified.
Clarification is necessary to reflect the overall limiting material to be the intermediate shell R1606-2 for Unit 1 and the nozzle (upper) shell to intermediate shell circular weld and lower shell to lower head torus circular weld for Unit 2.LRA Sections 4.2.2 and 4.2.3 are revised to clarify the identification of the most limiting material with the highest RTPTS values.Enclosure 2 provides the line-in/line-out revisions to LRA Section 4.2.2 and 4.2.3.
Enclosure 2 NOC-AE-12002933 Enclosure 2 STPNOC LRA Changes with Line-in/Line-out Annotations Enclosure 2 NOC-AE-12002933 Page 1 of 5 List of Revised LRA Sections RAI Affected LRA Section 4.2.2-1 Section 4.2.2 4.2.2-1 Section 4.2.3 Enclosure 2 NOC-AE-12002933 Page 2 of 5 4.2.2 Pressurized Thermal Shock Summary Description 10 CFR 50.61(b)(1) provides rules for protection against pressurized thermal shock (PTS)events for pressurized water reactors.
Licensees are required to perform an updated assessment of the projected values of PTS reference temperature (RTPTS) whenever there is a significant change in projected values of RTPTS, or upon a request for a change in the expiration date for operation of the facility.The license renewal rule 10 CFR 54.4(a)(3) also requires that the licensee evaluate those structures, systems, and components (SSCs) relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for PTS.10 CFR 50.61(c) provides two methods for determining RTPTS. These methods are also described as Positions 1 and 2 in Regulatory Guide 1.99, Radiation Embrittlement of Reactor Vessel Materials.
Position 1 applies for material that does not have credible surveillance data available and Position 2 is used for material that does have two or more credible surveillance data sets available.
The adjusted reference temperatures are calculated for both Positions 1 and 2 by following the guidance in Regulatory Guide 1.99 (Sections 1.1 and 2.1, respectively), using the copper and nickel content of STP beltline materials, and the EOLE fluence projections.
10 CFR 50.61(b)(2) establishes screening criteria for RTPTs as 270'F for plates, forgings, and axial welds and 300°F for circumferential welds. If the RTPTs does not exceed the PTS screening criteria, then only the reactor pressure vessel is relied on to demonstrate compliance with the 10 CFR 50.61, the PTS rule.Analysis The original response to the issuance of the PTS rule, 10 CFR 50.61, by STP indicated that the projected RTPTs for both units do not exceed the PTS screening criteria (270°F for plates, forgings, and axial welds; and 300°F for circumferential welds), based on a 40 year, 32 EFPY life.The most recent coupon examination results for both units show that the shift in RTNDT in plate and weld materials are in good agreement with or less than the Regulatory Guide 1.99 Revision 2 predictions for Units 1 and 2. The results demonstrate that the Regulatory Guide 1.99 predictions provide a conservative means to satisfy the requirement of 10 CFR 50.61; thus providing assurance of the reactor vessel integrity.
Enclosure 2 NOC-AE-12002933 Page 3 of 5 Unit 1 The data from the most recently withdrawn surveillance capsule, Capsule V, were deemed credible.
RTPTS values were generated for beltline and extended beltline region materials of the Unit 1 reactor vessel for fluence values at EOLE (54 EFPY). The Unit 1 RTNDT results from Capsule V indicated measured mean 30 ft-lb transition temperatures of -12.17 0 F, 17.78°F, and -29.41 OF for longitudinal plate coupons, transverse plate coupons, and the weld metal respectively.
The Capsule V material is from intermediate shell R1 606-2.The RTPTS values for the Unit 1 beltline materials are provided in Table 4.2-2. The limiting beltline material for Unit 1 is the intermediate shell R1 606-3 with a projected EOLE RTPTS value of 83.6 0 F. The projected RTPTs values for EOLE meet the 10 CFR 50.61 screening criteria.The extended beltline materials that are expected to receive fluence values greater than 1 x 1017 n/cm 2 (E>1.0 MeV) were also evaluated.
The RTPTS values were shown to meet the 10 CFR 50.61 screening criteria.
The fluence projections for the nozzle (upper) shell to intermediate shell circular weld and lower shell to lower head torus circular weld bound the other materials above and below the beltline.The most limiting material for Unit 1 is the Inlet Nozzle R1613-4 with a proiected EOLE RTp-s value of 127.3 0 F.Unit 2 The data from the most recently withdrawn surveillance capsule, Capsule U, war were deemed credible.
RTPTS values were generated for beltline and extended beltline region materials of the Unit 2 reactor vessel for fluence values at EOLE (54 EFPY). The Unit 2 RTNDT results from Capsule U indicated measured mean 30 ft-lb transition temperatures of -10.49 0 F, 22.23 0 F, and 5.88°F for longitudinal plate coupons, transverse plate coupons, and the weld metal respectively.
The Capsule U material is from intermediate shell R2507-1.The RTpTs values for the Unit 2 beltline materials are provided in Table 4.2-3. The limiting beltline material for Unit 2 is the intermediate shell R2507-2 with a projected EOLE RTPTS value of 63.7 0 F. The projected RTPTS values for EOLE meet the 10 CFR 50.61 screening criteria.The extended beltline materials that are expected to receive fluence values greater than 1 x 1017 n/cm 2 (E>1.0 MeV) were also evaluated.
The RTPTS values were shown to meet the 10 CFR 50.61 screening criteria.
The fluence projections for the nozzle (upper) shell to intermediate shell circular weld and lower shell to lower head torus circular weld bound the other materials above and below the beltline.The most limitingq material for Unit 2 is the Outlet Nozzle R2012-1 with a proiected EOLE RTpTs value of 111.1 OF.
Enclosure 2 NOC-AE-12002933 Page 4 of 5 Disposition:
Projection, 10 CFR 54.21(c)(1)(ii)
The RTPTS values were revised with projections to the end of the period of extended operation.
Therefore, these TLAAs are dispositioned in accordance with 10 CFR 54.21(c)(1)(ii).
4.2.3 Upper-Shelf Energy (USE)Summary Description Per Regulatory Guide 1.99, Radiation Embrittlement of Reactor Vessel Materials, the Charpy upper-shelf energy (Cv USE) is assumed to decrease as a function of fluence and copper content. Figure 2 of the guide determines this magnitude of decrease when surveillance data is not used (Position 1.2). In addition, if surveillance data is to be used (Position 2.2), the decrease in upper shelf energy may be obtained by plotting the reduced plant surveillance data on Figure 2 of the guide and fitting the data with a line drawn parallel to the existing lines as the upper bound of all the data. This line can then be used in preference to the existing line. The Cv USE can be predicted using the corresponding
%T fluence projection, the copper content of the beltline materials, and the results of the capsules tested to date using Figure 2 of the guide. The fluence at the 1/4T depth (f) is determined using the clad / base metal fluence (f&s-_4) and the depth of the desired location in inches.10 CFR 50, Appendix G, Section IV.A.1.a requires that the reactor vessel beltline materials must have a Cv USE of no less than 75 ft-lb initially, and must maintain Cv USE throughout the life of the vessel of no less than 50 ft-lb unless it is demonstrated in a manner approved by the Director, Office of Nuclear Reactor Regulation, that lower values of Cv USE will provide margins of safety against fracture equivalent to those required by ASME Section XI, Rules for In-Service Inspection of Nuclear Power Plant Components, Appendix G.Analysis The most recent coupon examination results for both units show that the decline in Cv USE in plate and weld materials are less than originally predicted by Regulatory Guide 1.99 Revision 2 for Units 1 and 2. The results demonstrate that the Regulatory Guide 1.99 predictions provide a conservative means to satisfy the requirements of 10 CFR 50, Appendix G; thus providing assurance of the reactor vessel integrity.
Unit I The Cv USE results from Unit 1 surveillance Capsule V indicated a mean Charpy V-notch Cv USE of 131 ft-lbf, 106 ft-lbf and 86 ft-lbf for longitudinal plate coupons, transverse plate coupons, and the weld metal respectively.
The data were determined to be credible, however the data were not included in the EOLE Cv USE projections.
To support operation during the period of extended operation, these values were projected to 54 EFPY of operation.
The EOLE Cv USE values for the Unit 1 belt"Re reactor vessel Enclosure 2 NOC-AE-12002933 Page 5 of 5 materials are provided in Table 4.2-4. The limiting value was 71 ft-lbf for intermediate shell R1606-2.The extended beltline nozzle and shell materials that are expected to receive fluence values greater than 1 x 1017 n/cm 2 (E>1.0 MeV) were also evaluated and confirm an EOLE Cv USE that is greater than 50 ft-lbf. The ftueRe embrittlement projections for the Ie (-upp shell to intermediate shell circulair weld and lower shell to lower head torus circ'u!ar weld intermediate shell R1606-2 bounds the other materials above and below the beltline.Unit 2 The Cv USE results from Unit 2 surveillance Capsule U indicated a mean Charpy V-notch Cv USE of 138 ft-lbf, 98 ft-lbf, and 97 ft-lbf for longitudinal plate coupons, transverse plate coupons, and the weld metal respectively.
The Surveillance Capsule U results for Unit 2 were deemed credible, however the data were not included in the EOLE Cv USE projections.
To support operation during the period of extended operation, these values were projected to 54 EFPY of operation.
The EOLE Cv USE values for the Unit 2 beltUie reactor vessel materials are provided in Table 4.2-5. The limiting value was -7 72 ft-lbf for lowe-shel longitudinal weld E3.12 the nozzle (upper) shell to intermediate shell circular weld and lower shell to lower head torus circular weld.The extended beltline nozzle and shell materials that are expected to receive fluence values greater than 1 x 1017 n/cm 2 (E>1.0 MeV) were also evaluated and confirm an EOLE Cv USE that is greater than 50 ft-lbf. The bottom head torus, R3920 1, .A.s 4dentified to have a projected EGLE rV USE value of 76 ftlbf. The RT 6 is m ore ImitiRg than the beltline maeral HwGever the (CV USE still meets the FIR 50, Appendix G 540 ft Ibf criterion.
The embrittlement fhueRee-projections for the nozzle (upper) shell to intermediate shell circular weld and lower shell to lower head torus circular weld bound the other materials above and below the beltline.Disposition:
Projection, 10 CFR 54.21(c)(1)(ii)
The Cv USE values were re-evaluated with projections to the end of the period of extended operation.
Therefore, these TLAAs are dispositioned in accordance with 10 CFR 54.21(c)(1)(ii).
The re-evaluations demonstrated that the Cv USE in the limiting material of each unit will remain above the 10 CFR 50 Appendix G acceptance criteria of 50 ft-lbf.