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MONTHYEARNOC-AE-10002592, Request for Relief from ASME Section Xl Code Requirements for Steam Generator Nozzle Non-Destructive Examination (Relief Request RR-ENG-3-01)2010-09-20020 September 2010 Request for Relief from ASME Section Xl Code Requirements for Steam Generator Nozzle Non-Destructive Examination (Relief Request RR-ENG-3-01) Project stage: Request ML1029900292010-10-25025 October 2010 Acceptance Review Email, Relief Request RR-ENG-3-01, RR-ENG-3-02, and RR-ENG-3-03 from ASME Code Requirements for Third 10-Year Inservice Inspection Interval (TAC ME4766-ME4767, ME4764-ME4765, ME4762-ME4763) Project stage: Acceptance Review ML1030103152010-10-28028 October 2010 Request for Additional Information Email, Relief Request RR-ENG-3-01, from ASME Code Requirements for Class 2 Piping for the Third 10-Year Inservice Inspection Interval Project stage: RAI ML1109803472011-04-20020 April 2011 Relief Request RR-ENG-3-01, from ASME Code Requirements for Steam Generator Main Steam Nozzle Non-Destructive Examination, Third 10-Year Inservice Inspection Interval Project stage: Other 2010-10-28
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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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Nuclear Operating Company South Texas Promect Electric Generat'n Station P.. Box 289 Wadsworth, Texas 77483 September 20, 2010 NOC-AE-10002592 File No.: G25 10 CFR 50.55a U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2746 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Request for Relief from ASME Section Xl Code Requirements for Steam Generator Nozzle Non-Destructive Examination (Relief Request RR-ENG-3-01)
In accordance with the provisions of 10 CFR 50.55a(g)(6)(i), the STP Nuclear Operating Company (STPNOC) requests relief from the ASME Section Xl code nondestructive examination requirements applicable to the South Texas Project steam generator main steam nozzle inside-radius sections. Due to their flow restrictor-type design, the South Texas Project steam generator main steam nozzles do not contain a high-stress inside-radius section for which the Section Xl volumetric examination is intended. Therefore, compliance with the Section Xl examination requirement is impractical.
There are no commitments in this correspondence.
STPNOC requests NRC review and approval of this relief request by March 1, 2011, to support implementation of the Unit 1 and Unit 2 Ten Year Inservice Inspection Plan for the third inspection interval.
If-there are any questions, please contact either Mr. Philip Walker at 361-972-8392 or me at 361-972-7904.
/Marc~o Ruai caba*
Manager, Test and Programs Engineering PLW
Attachment:
Request for Relief from ASME Section Xl Code Requirements for Steam Generator Nozzle Non-Destructive Examination (Relief Request RR-ENG-3-01)
STI: 32733139
NOC-AE-1 0002592 Page 2 of 2 cc: (paper copy) (electronic copy)
Regional Administrator, Region IV A. H. Gutterman, Esq.
U. S. Nuclear Regulatory Commission Morgan, Lewis & Bockius LLP 612 East Lamar Blvd., Suite 4004 Arlington, TX 76011-4125 Mohan C. Thadani U. S. Nuclear Regulatory Commission Mohan C. Thadani Peter Nemeth Senior Project Manager Crain Caton & James, P.C.
U.S. Nuclear Regulatory Commission One White Flint North (MS 8 G14) 11555 Rockville Pike C. Mele Rockville, MD 20852 City of Austin Senior Resident Inspector E. Alarcon U. S. Nuclear Regulatory Commission K. Polio P. 0. Box 289, Mail Code: MN1 16 Richard Pena.
Wadsworth, TX 77483 City Public Service Board C. M. Canady John Ragan City of Austin C. Callaway, Esq.
Electric Utility Department J. von Suskil 721 Barton Springs Road NRG South Texas LP Austin, TX 78704 Richard A. Ratliff Alice Rogers Texas Department of State Health Services
Attachment 1 NOC-AE-1 0002592 Page 1 of 2 SOUTH TEXAS PROJECT UNITS 1 AND 2 REQUEST FOR RELIEF FROM ASME SECTION Xl CODE REQUIREMENTS FOR STEAM GENERATOR NOZZLE NON-DESTRUCTIVE EXAMINATION (RELIEF REQUEST RR-ENG-3-01)
A. Components Affected (a) Component: Steam generator (b)
Description:
Main steam nozzle, inside-radius section (c) Class: ASME Code Class 2 B. Applicable Code Requirement The applicable code is ASME Section Xl, 2004 Edition (no addenda).
ASME Section Xl, Table IWC-2500-1, Code Category C-B, Item Number C2.22, requires that a volumetric examination of the inside-radius section of nozzles at terminal ends of piping runs be performed in accordance with Figure IWC-2500-4(a), (b), or (d) each inspection interval. The applicable nozzles include those welded to or integrally cast in vessels that connect to piping runs selected for examination under Examination Category C-F, excluding manways and handholes.
C. Basis for Relief from Code Requirements In accordance with the provisions of 10CFR50.55a(g)(5)(iii), the STP Nuclear Operating Company (STPNOC) requests relief from the Section XI code requirement for a volumetric examination of the inside-radius section of the Unit 1 and 2 steam generator main steam nozzles because compliance with the requirement is impractical.
D. Alternative Examination:
No alternative examination is proposed in lieu of the volumetric examination for which relief is requested.
E. Justification for Granting Relief The inside-radius section of main steam nozzles is considered susceptible to flaw initiation and growth due to the high thermal and mechanical stresses associated with the vessel and connected piping systems. Each South Texas Project steam generator main steam nozzle is a one-piece forging with a set of seven holes bored parallel to the nozzle centerline. The design does not correspond to Figure Nos. IWC-2500-4(a), (b), or (d) and does not have a "radius bend". Furthermore, the borehole orientation precludes a meaningful ultrasonic examination in the area of the inner radius. Because of this design configuration, the examination required by Section Xl would not provide any meaningful results. In addition, because the ligaments between the holes distribute the stresses throughout the nozzle forging, the South Texas Project steam generator main steam nozzles have no high-stress inside-radius section.
Attachment NOC-AE-10002592 Page 2 of 2 These design considerations make the code-required inservice inspection impractical for application at the South Texas Project.
F. Implementation Schedule STPNOC requests relief from ASME Section Xl nondestructive examination requirements for the steam generator main steam nozzle inside radius sections for the duration of the third ten-year inservice inspection interval of Units 1 and 2. The Nuclear Regulatory Commission is requested to review and approve this relief request by March 1, 2011, to support implementation of the Unit 1 and Unit 2 Ten Year Inservice Inspection Plan for the third interval.
G. Precedent Relief from this examination requirement was previously approved by the NRC for the South Texas Project second 10-year interval inservice inspection program by safety evaluation dated December 15, 1999 (ML993570106) for Relief Request RR-ENG-2-2.