Letter Sequence Other |
---|
|
|
MONTHYEARNOC-AE-19003684, Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Essential Cooling Water (Ecw) System Class 3 Buried Piping in Accordance with 10 CFR 50.55a(z)(1)2019-09-26026 September 2019 Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Essential Cooling Water (Ecw) System Class 3 Buried Piping in Accordance with 10 CFR 50.55a(z)(1) Project stage: Request 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. Project stage: Request ML19309F1412019-11-0404 November 2019 Supplemental Information Request - Proposed Alternative to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping (EPID L 2019-LLR-0096) (Draft) Project stage: Draft Other ML19312A0962019-11-13013 November 2019 Supplemental Information Needed for Acceptance of Requested Licensing Action Proposed Alternative to ASME Requirements for Repair of Essential Cooling Water Class 3 Buried Piping Project stage: Acceptance Review NOC-AE-19003696, Supplemental Information for Proposed Alternative to ASME Code Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24) EPID: L 2019-LLR-0096)2019-11-26026 November 2019 Supplemental Information for Proposed Alternative to ASME Code Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24) EPID: L 2019-LLR-0096) Project stage: Supplement ML19344A0092019-12-0909 December 2019 NRR E-mail Capture - South Texas Project - Acceptance of Requested Licensing Action - Proposed Alternative to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping Project stage: Acceptance Review ML20036F5862020-02-0404 February 2020 Request for Additional Information - Proposed Alternative to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping (EPID L-2019-LLR-0096)Redacted Project stage: RAI NOC-AE-20003716, Request for Additional Information for Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping2020-03-0909 March 2020 Request for Additional Information for Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping Project stage: Request ML20069L4992020-03-0909 March 2020 Request for Additional Information for Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping Project stage: Request NL-20-039, (04/29/2020) E-mail from R. Gaston to R. Guzman, Exemption Request from Requirements of 10 CFR Part 73, Appendix B, Section VI, Subsection C.3.(l)(1)2020-04-29029 April 2020 (04/29/2020) E-mail from R. Gaston to R. Guzman, Exemption Request from Requirements of 10 CFR Part 73, Appendix B, Section VI, Subsection C.3.(l)(1) Project stage: Other ML20128J8432020-05-15015 May 2020 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML20142A5202020-05-21021 May 2020 Exemption Request Due to COVID-19 Pandemic Project stage: Other NL-20-0620, SNC Requests a Temporary Exemption from the Quarterly Fire Brigade Drills and Annual Live Fire Fighting Training Requirements of the Regulation2020-05-22022 May 2020 SNC Requests a Temporary Exemption from the Quarterly Fire Brigade Drills and Annual Live Fire Fighting Training Requirements of the Regulation Project stage: Other NL-20-0640, Response to Request for Additional Information for Exemption Request2020-05-27027 May 2020 Response to Request for Additional Information for Exemption Request Project stage: Response to RAI ULNRC-06587, Supplement to Security Training Exemption Request Due to COVID-192020-06-17017 June 2020 Supplement to Security Training Exemption Request Due to COVID-19 Project stage: Supplement NOC-AE-20003749, Response to Request for Additional Information for Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24)2020-07-15015 July 2020 Response to Request for Additional Information for Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24) Project stage: Response to RAI ML20197A2612020-07-15015 July 2020 Response to Request for Additional Information for Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24) Project stage: Response to RAI ML20177A6452020-07-15015 July 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020 Project stage: Approval ML20212L5682020-07-30030 July 2020 Supplement to Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24) Project stage: Supplement NOC-AE-20003755, Supplement to Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24)2020-07-30030 July 2020 Supplement to Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24) Project stage: Supplement ML20232D1442020-08-26026 August 2020 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML20227A3852020-09-0303 September 2020 Nonproprietary - Proposed Alternative RR-ENG-3-24 to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping Project stage: Other 2020-05-15
[Table View] |
|
---|
Category:Code Relief or Alternative
MONTHYEARML22245A0012022-09-12012 September 2022 Relief from the Requirements of the ASME Code ML20227A3852020-09-0303 September 2020 Nonproprietary - Proposed Alternative RR-ENG-3-24 to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping NOC-AE-20003702, Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-03)2020-01-22022 January 2020 Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-03) ML19142A3072019-08-13013 August 2019 Request for Relief Request RR-ENG-3-23 to Extend Volumetric Examination Interval for Reactor Vessel Closure Head Nozzles NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23)2019-02-28028 February 2019 Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) ML18303A2062018-11-0707 November 2018 Request for Relief from ASME Code to Extend the Inservice Inspection Interval for Category B-N-2 and B-N-3 Examinations NOC-AE-18003598, Response to Request for Additional Information Request for Relief from the Third 10-Year Interval ISI Program ASME Section Xl Code Requirements for Category B-N-2 and B-N-3 Welds (Relief Request RR-ENG-3-16)2018-09-26026 September 2018 Response to Request for Additional Information Request for Relief from the Third 10-Year Interval ISI Program ASME Section Xl Code Requirements for Category B-N-2 and B-N-3 Welds (Relief Request RR-ENG-3-16) ML18177A4252018-07-24024 July 2018 Relief from the Requirements of the Asme Code Regarding the Third 10-Year Inservice Inspection Interval ML18187A1492018-07-24024 July 2018 Relief Request RR-ENG-3-22 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography NOC-AE-18003578, Request for Relief from the Third 10-Year Interval ISI Program ASME Section Xl Code Requirements for Category B-N-2 and B-N-3 Welds (Relief Request RR-ENG-3-16)2018-06-25025 June 2018 Request for Relief from the Third 10-Year Interval ISI Program ASME Section Xl Code Requirements for Category B-N-2 and B-N-3 Welds (Relief Request RR-ENG-3-16) NOC-AE-18003547, Proposed Alternative to Reactor Vessel Inservice Inspection Intervals (Relief Request RR-ENG-3-14)2018-02-15015 February 2018 Proposed Alternative to Reactor Vessel Inservice Inspection Intervals (Relief Request RR-ENG-3-14) ML16174A0912016-06-30030 June 2016 Relief Request RR-ENG-3-20, Use of ASME Code Case N-770-1, Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, for the Third 10-Year Inservice Inspection Interval ML15218A3672015-08-21021 August 2015 Relief Request RR-ENG-17, Relief from Code Case N-770-1, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, Third 10-Year ISI Interval ML13102A1262013-04-23023 April 2013 Withdrawal of Relief Request RR-ENG-3-12 from ASME Code Requirements for Periodic Inspection of Reactor Coolant Pressure Boundary Check Valve with Seal Cap, Third 10-year Inservice Inspection Interval ML13087A5172013-04-12012 April 2013 Relief Request RR-ENG-3-09, Request for Relief from ASME Code Requirements; Deferral of Code Repair of Essential Cooling Water System Piping Until April 2013 Refueling Outage ML13004A3392013-03-12012 March 2013 Relief Request RR-ENG-3-10, Reactor Pressure Vessel Head Flange O-Ring Leakoff Lines Non-Destructive Examination, for the Third 10-Year Inservice Inspection Interval NOC-AE-12002939, Request for Relief from ASME Section XI Code Requirements for Periodic Inspection of Reactor Coolant Pressure Boundary Check Valves with Seal Cap Enclosures (Relief Request RR-ENG-3-12)2013-02-0707 February 2013 Request for Relief from ASME Section XI Code Requirements for Periodic Inspection of Reactor Coolant Pressure Boundary Check Valves with Seal Cap Enclosures (Relief Request RR-ENG-3-12) NOC-AE-12002956, Response to Request for Additional Information Regarding Relief Request RR-ENG-3-09 for the Essential Cooling Water System2013-01-31031 January 2013 Response to Request for Additional Information Regarding Relief Request RR-ENG-3-09 for the Essential Cooling Water System ML12243A3432012-09-10010 September 2012 RR RE-ENG-3-04 to Apply Alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Requirements for Examination of Class 1 and 2 Piping Welds ML12235A3472012-08-28028 August 2012 Relief Request RR-ENG-3-06 from ASME Code Requirements for Leak Testing Boundaries of Class 1 Pressure-Retaining Components, Third 10-Year Inservice Inspection Interval (TAC ME7053-ME7054) ML12201A2562012-08-16016 August 2012 Relief Request RR-ENG-3-08, Deferral of Code Repair of Flaws in U2 Essential Cooling Water Class 3 Piping Until Restart from Current Refueling Outage Scheduled for Mid-April 2012 NOC-AE-12002837, Response to Request for Additional Information: Application of an Alternative to Requirements for Examination of Class 1 and Class 2 Piping Welds (Relief Request RR-ENG-3-04)2012-05-0909 May 2012 Response to Request for Additional Information: Application of an Alternative to Requirements for Examination of Class 1 and Class 2 Piping Welds (Relief Request RR-ENG-3-04) NOC-AE-12002807, Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for the Essential Cooling Water System (Relief Request RR-ENG-3-08)2012-03-12012 March 2012 Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for the Essential Cooling Water System (Relief Request RR-ENG-3-08) ML1118605352011-07-29029 July 2011 Relief Request RR-ENG-2-55 from ASME Code Requirements for Weld Examinations, Second 10-Year Inservice Inspection Interval 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 ML1108109482011-04-0707 April 2011 Request for Relief RR-ENG-3-03 from ASME Code Requirements for Pump Casing Inservice Inspection Examination, Third 10-Year Inservice Inspection Interval ML1108400762011-04-0505 April 2011 Request for Relief RR-ENG-3-02 from ASME Code Requirements for Reactor Pressure Vessel Flange Insert Non-Destructive Examination, Third 10-Year Inservice Inspection Interval NOC-AE-10002600, Request for Relief from ASME Section XI Requirements for Ultrasonic Examination of Reactor Pressure Vessel Shell-to-Flange Welds (RR-ENG-3-05)2010-10-18018 October 2010 Request for Relief from ASME Section XI Requirements for Ultrasonic Examination of Reactor Pressure Vessel Shell-to-Flange Welds (RR-ENG-3-05) NOC-AE-10002594, Request for Relief from ASME Section XI Code Requirements for Pump Casing Inservice Inspection Examination (Relief Request RR-ENG-3-03)2010-09-20020 September 2010 Request for Relief from ASME Section XI Code Requirements for Pump Casing Inservice Inspection Examination (Relief Request RR-ENG-3-03) ML1021500772010-09-0202 September 2010 Relief Request Nos. VRR-01, PRR-03, PRR-02, and PRR-01 for Third 10-year Interval Inservice Testing Program for Pumps and Valves (TAC Nos. ME3515 Through ME3522) ML1006208692010-03-24024 March 2010 Authorization of Relief Request RR-ENG-2-53, Alternative to Inservice Inspection Requirements for Ultrasonic Exam of Reactor Pressure Vessel Shell-to-Flange Weld ML1005395882010-03-12012 March 2010 Relief Request RR-ENG-2-52 from ASME Code, Section XI Requirements for Essential Cooling Water System Code Repair NOC-AE-09002399, Request for Relief from ASME Boiler and Pressure Vessel Code Section XI Requirements for the Essential Cooling Water System (Relief Request RR-ENG-2-52)2009-03-12012 March 2009 Request for Relief from ASME Boiler and Pressure Vessel Code Section XI Requirements for the Essential Cooling Water System (Relief Request RR-ENG-2-52) ML0827502202008-12-0909 December 2008 Relief Request RR-ENG-2-30, Request for Relief to Use ASME Code Case N-516-3, Underwater Welding, Section XI, Division 1 ML0827707852008-11-12012 November 2008 Authorization of Relief Request RR-ENG-2-51 from ASME Code Case N-498-4, on 10-Year System Hydrostatic Testing for Class 1, 2, and 3 Systems ML0824901602008-09-26026 September 2008 Relief Request RR-ENG-2-49, Second 10-Year Inservice Inspection Interval, Deferral of Code Repair in the Essential Cooling Water System Piping ML0735410722008-01-10010 January 2008 Request for Relief No. RR-ENG-2-48 from ASME Code Case N-638-1 Requirements Regarding Start Time for 48-Hour Hold Period Before Non-Destructive Examination of Weld Overlay Repair ML0731204462007-11-30030 November 2007 Relief Request RR-ENG-2-47 for Approval of Temporary Non-code Repair and Deferral of Code Repair Upgraded Essential Cooling Water System Piping NOC-AE-07002211, Relief Request (RR-ENG-2-50) for the Second 10 Year ISI Interval from 10 CFR 50.55a for the Purpose of Invoking Code Case N-698, Design Stress Intensities and Yield Strength Values For...2007-10-0202 October 2007 Relief Request (RR-ENG-2-50) for the Second 10 Year ISI Interval from 10 CFR 50.55a for the Purpose of Invoking Code Case N-698, Design Stress Intensities and Yield Strength Values For... ML0708510082007-04-30030 April 2007 Relief Request No. RR-ENG-2-44 on Deferral of Code Repair of Essential Cooling Water System Indication ML0708102642007-04-0202 April 2007 Relief, Request for Relief No. RR-ENG-2-43 for Remainder of Second 10-year Inservice Inspection Interval Application of Weld Overlays in Pressurizer Nozzle Safe End Welds (TAC Nos. MD1414 - MD1423) ML0706500752007-03-15015 March 2007 Request to Use 2001 Edition Through 2003 Addenda of ASME Code for Operations and Maintenance for Remainder of Second 10-Year Inservice Testing Program Interval ML0704400592007-03-0101 March 2007 Request for Relief No. RR-ENG-2-45 for Remainder of Second 10-year Inservice Inspection Interval Use of Penetrameters in Radiography Examination ML0622303092006-10-26026 October 2006 Response to Relief Request RR-ENG-2-42 for Approval Non-Code Repair and Deferral of Code Repair of Essential Cooling Water System Piping, TAC MC8804 NOC-AE-06002031, Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for Use of Penetrameters in Radiographic Examinations2006-06-14014 June 2006 Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for Use of Penetrameters in Radiographic Examinations ML0610907542006-05-25025 May 2006 Relief, Relief Request RR-ENG-2-39 and RR-ENG-2-40 for Approval of Temporary Non-code Repair and Deferral of Code Repair of Essential Cooling Water System Piping, Trains 1B and 1C ML0609702402006-05-12012 May 2006 Relief, RR-ENG-2-41 TAC No. MC8279 NOC-AE-05001899, Request for Relief from ASME Boiler and Pressure Vessel Code, Section Xl Requirements for the Essential Cooling Water System (Ecw Train 1 C) (Relief Request RR-ENG-2-40)2005-07-19019 July 2005 Request for Relief from ASME Boiler and Pressure Vessel Code, Section Xl Requirements for the Essential Cooling Water System (Ecw Train 1 C) (Relief Request RR-ENG-2-40) ML0506205052005-03-15015 March 2005 Request for Relief from Requirements of ASME and Pressure Vessel Code RR-ENG-IWE-07 NOC-AE-04001817, Revised Request for Authorization to Use an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Requirements (Relief Request VRR-05)2004-11-0909 November 2004 Revised Request for Authorization to Use an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Requirements (Relief Request VRR-05) 2022-09-12
[Table view] Category:Letter
MONTHYEARML24029A2752024-01-29029 January 2024 Request to Reschedule Evaluated Force-on-Force Drill IR 05000498/20230042024-01-29029 January 2024 Integrated Inspection Report 05000498/2023004 and 05000499/2023004 ML24024A1162024-01-24024 January 2024 STP Unit 2 Request for Information IR 05000498/20244042024-01-18018 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000498/2024404; 05000499/2024404 IR 05000498/20230032023-12-28028 December 2023 Acknowledgment of Reply to a Notice of Violation (NRC Inspection Report 05000498/2023003 and 05000499/2023003) ML23360A1692023-12-26026 December 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the South Texas Project Medical Services Drill Evaluated on August 31, 2023 NOC-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 ML23326A2592023-12-0505 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23339A1902023-12-0505 December 2023 Update Foreign Ownership, Control, or Influence (FOCI) IR 05000498/20234012023-12-0404 December 2023 Security Baseline Inspection Report 05000498/2023401 and 05000499/2023401 ML23324A0102023-11-16016 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23310A2282023-11-13013 November 2023 Integrated Inspection Report 05000498/2023003 and 05000499/2023003, and Notice of Violation ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23298A0002023-11-0101 November 2023 the Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 226 and 211 Related to Order Approving Indirect Transfer of Licenses and Conforming License Amendments ML23303A0782023-10-30030 October 2023 Submittal of Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments ML23279A0342023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Letter) IR 05000498/20234032023-10-26026 October 2023 Material Control and Accounting Program Inspection Report 05000498/2023403 and 05000499/2023403 (Cover Letter) ML23317A1262023-10-12012 October 2023 South. Texas Project Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 26 ML23279A1382023-10-0505 October 2023 Responses to Requests for Additional Information Related to Application for Order Approving Indirect Transfer of Control of Licenses ML23271A1942023-10-0303 October 2023 Notification of Commercial Grade Dedication Inspection (05000498/2024013 and 05000499/2024013) and Request for Information ML23270B2592023-09-27027 September 2023 Update Foreign Ownership, Control, or Influence ML23263B1132023-09-20020 September 2023 Operator Licensing Examination Schedule Revision 1 IR 05000498/20243012023-09-0707 September 2023 Notification of NRC Initial Operator Licensing Examination 05000498/2024301; 05000499/2024301 IR 05000498/20233012023-09-0101 September 2023 NRC Examination Report 05000498/2023301 and 05000499/2023301 ML23243B0562023-08-31031 August 2023 Supplemental Information to Application for Order Approving Indirect Transfer of Control of Licenses ML23236A6042023-08-24024 August 2023 Annual Dose Report for 2022 IR 05000498/20230052023-08-22022 August 2023 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023005 and 05000499/2023005) - Mid Cycle Letter ML23229A5262023-08-17017 August 2023 Inservice Inspection Summary Report - 1 RE24, ML23229A5892023-08-17017 August 2023 Voluntary Response to Regulatory Issue Summary (RIS) 2023-02, Scheduling Information for the Licensing of Accident Tolerant, Increased Enrichment, and Higher Burnup Fuels ML23229A4992023-08-17017 August 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) ML23228A2102023-08-15015 August 2023 Closure of Investigation (OI 4-22-19) ML23222A0322023-08-10010 August 2023 Report of Changes Made to Quality Assurance Program for Radioactive Material Packages ML23221A3002023-08-0909 August 2023 RE22 Inspection Summary Report for Steam Generator Tubinq, Rev. 1 (Epld L-2023-LRO-0029) ML23222A2792023-08-0909 August 2023 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) IR 05000498/20230022023-07-28028 July 2023 Integrated Inspection Report 05000498/2023002 and 05000499/2023002 ML23198A0532023-07-24024 July 2023 Request for Withholding Information from Public Disclosure ML23188A1612023-07-14014 July 2023 the Associated ISFSI - Notice of Consideration of Approval of Indirect Transfer of Licenses and Conforming Amendments and Opportunity to Request a Hearing (EPID L-2023-LLM-0004) - Letter ML23193A9932023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) ML23192A0482023-07-11011 July 2023 NRC Initial Operator Licensing Examination Approval 05000498/2023301; 05000499/2023301 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) ML23180A2822023-06-29029 June 2023 Operator Licensing Examination Schedule ML23177A2522023-06-26026 June 2023 Units 1, 2 & Independent Spent Fuel Storage Installation - Biennial Submittal of Technical Specification Bases Changes, Commitment Changes, 10 CFR 50.59 Evaluation Summary, and 10 CFR 72.48 Evaluation Summary ML23166B0802023-06-14014 June 2023 Update Foreign Ownership, Control, or Influence (FOCI) ML23163A1762023-06-12012 June 2023 Application for Order Approving Indirect Transfer of Control of Licenses 2024-01-29
[Table view] Category:Safety Evaluation
MONTHYEARML23279A0342023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Letter) ML23279A0482023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Enclosure 4 -Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Nonproprietary Safety Evaluation) ML23015A0012023-02-0606 February 2023 Issuance of Amendment Nos. 225 and 210 to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML22300A2492022-12-0606 December 2022 Approval for Alternate Disposal Procedures for Very Low-Level Radioactive Material (EPID: L?2021?LLL?0022) ML22245A0012022-09-12012 September 2022 Relief from the Requirements of the ASME Code ML21319A3552021-12-0909 December 2021 Issuance of Amendment Nos. 224 and 209 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML21320A0022021-12-0808 December 2021 Issuance of Amendment Nos. 223 and 208 to Revise Technical Specification 3.6.3 and to Remove the Technical Specifications Index NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 22021-05-11011 May 2021 Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 ML21033A2392021-04-0808 April 2021 Issuance of Amendment Nos. 222 and 207 to Revise Technical Specifications to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil 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 ML20227A3852020-09-0303 September 2020 Nonproprietary - Proposed Alternative RR-ENG-3-24 to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping ML20199M1622020-07-21021 July 2020 Proposed Alternatives PRR-01, PRR-02, PRR-03, and PRR-04 to the Requirements of the ASME OM Code (Epids L-2020-LLR-0007 to L-2020-LLR-0010) ML20141L6122020-05-28028 May 2020 Issuance of Amendment No. 219 to Revise Technical Specifications to Reduce Safety Injection Accumulators Minimum Pressures (Exigent Circumstances) ML19322A7192019-12-0909 December 2019 Issuance of Amendment Nos. 218 and 204 to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML19217A0602019-10-24024 October 2019 Issuance of Amendment Nos. 217 and 203 Revision to Technical Specification Tables to Change Terminology for the P-13 Permissive Interlock Description ML19213A1472019-08-20020 August 2019 Issuance of Amendment Nos. 216 and 202 Standby Diesel Generator Surveillance Requirements ML19142A3072019-08-13013 August 2019 Request for Relief Request RR-ENG-3-23 to Extend Volumetric Examination Interval for Reactor Vessel Closure Head Nozzles ML19067A2222019-06-0606 June 2019 Issuance of Amendment Nos. 215 and 201 Adoption of TSTF-522 Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML18303A2062018-11-0707 November 2018 Request for Relief from ASME Code to Extend the Inservice Inspection Interval for Category B-N-2 and B-N-3 Examinations ML18177A4252018-07-24024 July 2018 Relief from the Requirements of the Asme Code Regarding the Third 10-Year Inservice Inspection Interval ML18187A1492018-07-24024 July 2018 Relief Request RR-ENG-3-22 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML18159A2122018-07-19019 July 2018 Issuance of Amendment Nos. 214 and 200 Emergency Response Organization Time Augmentation and Staffing Chances to the Emergency Plan (CAC Nos. MG0024 and MG0025; EPID L-2017-LLA-0265) ML18128A3422018-06-0707 June 2018 Issuance of Amendment Nos. 213 and 199 to Revise TSs for Administrative Changes and to Relocate Fxy Exclusion Zones to the Colrs(Cac Nos. MG0253 and MG0254, EPID-L-2017-LLA-0300) ML17038A2232017-07-11011 July 2017 Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 ML17019A0022017-07-11011 July 2017 Safety Evaluation, Enclosure 3 to Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 ML16319A0102016-12-21021 December 2016 Issuance of Amendment No. 211, Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies ML16174A0912016-06-30030 June 2016 Relief Request RR-ENG-3-20, Use of ASME Code Case N-770-1, Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, for the Third 10-Year Inservice Inspection Interval ML16116A0072016-04-29029 April 2016 Issuance of Amendment Nos. 210 and 197, Revise Technical Specification 6.8.3.j, Containment Leakage Rate Testing Program, to Extend Integrated Leak Rate Test Interval from 10 to 15 Years ML15342A0032015-12-28028 December 2015 Issuance of Amendment Nos. 209 and 196, Adopt Technical Specification Task Force (TSTF)-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (CAC MF6178-MF6179) ML15343A1282015-12-11011 December 2015 Issuance of Amendment No. 208, Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Unit 1 Cycle 20 (Emergency Circumstances) ML15209A6412015-09-22022 September 2015 Issuance of Amendment Nos. 207 and 195, Revise Updated Final Safety Analysis Report Table 15.6-17 to Correct Radiological Doses Resulting from Calculation Error Performed in Support of Amendments 182 and 169 ML15218A3672015-08-21021 August 2015 Relief Request RR-ENG-17, Relief from Code Case N-770-1, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, Third 10-Year ISI Interval ML15201A1952015-08-20020 August 2015 Issuance of Amendment Nos. 206 and 194, Revise the Emergency Action Level Scheme to the NRC-endorsed Scheme Contained in NEI-99, Revision 6 ML15075A1462015-04-29029 April 2015 Issuance of Amendment Nos. 205 and 193, Request to Revise Technical Specification 3.3.1, Functional Unit 20, Reactor Trip Breakers, for Required Actions and Allowed Outage Times ML15049A1292015-02-27027 February 2015 Issuance of Amendment Nos. 204 and 192, Revise Technical Specification 6.9.1.6, Core Operating Limits Report, with Respect to Analytical Methods Used to Determine Core Operating Limits ML14339A1702015-02-13013 February 2015 Issuance of Amendment Nos. 203 and 191, Revise Fire Hazards Analysis Report and Fire Protection Program License Conditions Related to Alternate Shutdown Capability ML14281A0652015-01-29029 January 2015 Issuance of Amendment Nos. 202 and 190, Revise Operating License Conditions Related to Cyber Security Plan Milestone 8 Full Implementation Date ML13221A0042013-09-0909 September 2013 Issuance of Amendment Nos. 201 and 189, Revise TS 5.0, Design Features, to Reflect Removal of Visitor'S Center Building and References to Emergency Operations Facility ML13142A1602013-06-0606 June 2013 Safety Assessment in Response to Information Request Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment ML13008A5282013-04-25025 April 2013 Issuance of Amendment Nos. 200 and 188, Revise Technical Specification 3.3.3.6, Accident Monitoring Instrumentation ML13087A5172013-04-12012 April 2013 Relief Request RR-ENG-3-09, Request for Relief from ASME Code Requirements; Deferral of Code Repair of Essential Cooling Water System Piping Until April 2013 Refueling Outage ML13004A3392013-03-12012 March 2013 Relief Request RR-ENG-3-10, Reactor Pressure Vessel Head Flange O-Ring Leakoff Lines Non-Destructive Examination, for the Third 10-Year Inservice Inspection Interval ML13007A1362013-01-31031 January 2013 Review of Operations Quality Assurance Plan, Revision 20 ML12243A3432012-09-10010 September 2012 RR RE-ENG-3-04 to Apply Alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Requirements for Examination of Class 1 and 2 Piping Welds ML12235A3472012-08-28028 August 2012 Relief Request RR-ENG-3-06 from ASME Code Requirements for Leak Testing Boundaries of Class 1 Pressure-Retaining Components, Third 10-Year Inservice Inspection Interval (TAC ME7053-ME7054) ML12201A2562012-08-16016 August 2012 Relief Request RR-ENG-3-08, Deferral of Code Repair of Flaws in U2 Essential Cooling Water Class 3 Piping Until Restart from Current Refueling Outage Scheduled for Mid-April 2012 ML12152A2452012-08-14014 August 2012 Issuance of Amendment Nos. 199 and 187, Revise Applicability of Risk-Managed Technical Specifications (TS) to TS 3.7.7, Control Room Makeup and Cleanup Filtration System ML1124402222011-11-17017 November 2011 Issuance of Amendment Nos. 198 and 186, Revise Technical Specifications 5.3.1 and 6.9.1.6 to Allow Fuel Assemblies with Optimized Zirlo Cladding ML1126500712011-10-14014 October 2011 Relief Request RR-ENG-3-05, from Requirements for Ultrasonic Examination of Reactor Pressure Vessel Shell-to-Flange Welds for Third 10-Year Inservice Inspection ML1118605352011-07-29029 July 2011 Relief Request RR-ENG-2-55 from ASME Code Requirements for Weld Examinations, Second 10-Year Inservice Inspection Interval 2023-02-06
[Table view] |
Text
OFFICIAL USE ONLY PROPRIETARY INFORMATION September 3, 2020 Mr. G. T. Powell President and Chief Executive Officer STP Nuclear Operating Company P.O. Box 289 Wadsworth, TX 77483
SUBJECT:
SOUTH TEXAS PROJECT, UNITS 1 AND 2 - PROPOSED ALTERNATIVE RR-ENG-3-24 TO ASME CODE REQUIREMENTS FOR THE REPAIR OF ESSENTIAL COOLING WATER SYSTEM CLASS 3 BURIED PIPING (EPID L-2019-LLR-0096)
Dear Mr. Powell:
By letter dated September 26, 2019, as supplemented by letters dated November 26, 2019, March 9, 2020, July 15, 2020, and July 30, 2020, STP Nuclear Operating Company (the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components, requirements at South Texas Project (STP) Units 1 and 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(z)(1), the licensee requested to use the proposed Alternative RR-ENG-3-24 to use a carbon fiber reinforced polymer composite system to repair the internal surface of buried essential cooling water piping as an alternative to the repair and replacement requirements of the ASME Code, Section Xl, paragraph IWA-4221, Construction Code and Owners Requirements, subparagraph (b) (i.e., to meet the original Construction Code requirements for the buried essential cooling water piping), during the third and fourth 10-year inservice inspection intervals at STP Units 1 and 2 on the basis that the proposed alternative provides an acceptable level of quality and safety.
The NRC staff has reviewed the subject requests and concludes, as set forth in the enclosed safety evaluation, that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) and demonstrated that the proposed alternatives provide an acceptable level of quality and safety. Therefore, the NRC staff authorizes the use of proposed Alternative RR-ENG-3-24 for the third and fourth 10-year inservice inspection interval at STP Units 1 and 2.
Enclosure 1 to this letter contains sensitive unclassified non-safeguards information. When separated from Enclosure 1, this document is DECONTROLLED.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION G. Powell All other requirements in ASME Code,Section XI, for which relief or an alternative was not specifically requested and approved as part of this subject request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
The NRC staff has determined that the safety evaluation provided in Enclosure 1 contains proprietary information pursuant to 10 CFR Section 2.390, Public inspections, exemptions, requests for withholding. Accordingly, the NRC staff has prepared a non-proprietary version, which is provided in Enclosure 2.
If you have any questions, please contact the Project Manager, Dennis Galvin at 301-415-6256 or via e-mail at Dennis.Galvin@nrc.gov.
Sincerely, Digitally signed by Jennifer L. Jennifer L. Dixon-Herrity Date: 2020.09.03 Dixon-Herrity 13:34:08 -04'00' Jennifer L. Dixon-Herrity, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosures:
- 1. Safety Evaluation (proprietary)
- 2. Safety Evaluation (non-proprietary) cc w/o Enclosure 1: Listserv OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION ENCLOSURE 2 (NON-PROPRIETARY)
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION PROPOSED ALTERNATIVE RR-ENG-3-24 TO ASME CODE SECTION XI REQUIREMENTS FOR REPAIR/REPLACEMENT OF ESSENTIAL COOLING WATER PIPING STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499 Proprietary information pursuant to Title 10 of Code of Federal Regulations, Section 2.390 has been redacted from this document.
Redacted information is identified by blank space enclosed within double brackets, as shown here: (( )).
OFFICIAL USE ONLY PROPRIETARY INFORMATION SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION PROPOSED ALTERNATIVE RR-ENG-3-24 TO ASME CODE SECTION XI REQUIREMENTS FOR REPAIR/REPLACEMENT OF ESSENTIAL COOLING WATER PIPING STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499
1.0 INTRODUCTION
By letter dated September 26, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19274C393), as supplemented by letters dated November 26, 2019, March 9, 2020, July 15, 2020, and July 30, 2020 (ADAMS Accession Nos. ML19331A202, ML20069L499, ML20197A261, and ML20212L568, respectively), STP Nuclear Operating Company (the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components, requirements at South Texas Project (STP) Units 1 and 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.55a(z)(1), Acceptable level of quality and safety, the licensee requested to use the proposed Alternative RR-ENG-3-24 to use a carbon fiber reinforced polymer (CFRP) composite system to repair the internal surface of buried essential cooling water (ECW) piping as an alternative to the repair and replacement requirements of the ASME Code, Section Xl, paragraph IWA-4221, Construction Code and Owners Requirements, subparagraph (b)
(i.e., to meet the original Construction Code requirements for the buried ECW piping), during the third and fourth 10-year inservice inspection (ISI) intervals at STP Units 1 and 2 on the basis that the proposed alternative provides an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
The NRC regulations in 10 CFR 50.55a(g)(4), Inservice inspection standards requirement for operating plants, state, in part, that ASME Code Class 1, 2, and 3, components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI.
The regulations in 10 CFR 50.55a(z), Alternatives to codes and standards requirements, state, in part, that alternatives to the requirements of 10 CFR 50.55a(f) may be used, when authorized by the NRC, if the licensee demonstrates (1) the proposed alternatives would provide an OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION acceptable level of quality and safety or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Based on the above regulations, the NRC staff concludes that regulatory authority exists to authorize an alternative to ASME Code,Section XI, as requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 The Licensees Proposed Alternative 3.1.1 ASME Code Components Affected The affected component is the buried ASME Code Class 3 ECW piping. The piping sections that will be repaired using the proposed CFRP composite are specified in Enclosure 2 to the letter dated September 26, 2019, hereafter referred to as the alternative request. The ECW piping consists of 30-inch ECW system intake piping and fittings from the intake structure to the mechanical auxiliary building and the discharge piping from the mechanical auxiliary building to the discharge structure. The ECW piping was designed and installed in accordance with the 1974 Edition through 1975 Winter Addenda of the ASME Code,Section III, Rules for Construction of Nuclear Facility Components, Subsection ND, Class 3 Components.
The subject piping is below grade and buried, and has long straight runs with minimal bends and elbows. The exterior surface of the pipe is coated with coal-tar with an impressed current cathodic protection system to mitigate corrosion. The licensee stated that it has not identified degradation of the exterior surface of the pipe. The licensee further stated that the soil has high resistive characteristics further reducing the possibility of corrosion on the piping exterior surface. The piping is fabricated of aluminum-bronze material conforming to American Society of Testing and Materials (ASTM) International SB169, Standard Specification for Aluminum Bronze Sheet, Strip and Rolled Bar, Alloy CA-614. The subject piping has no pumps, valves, expansion joints, flange joints, or threaded connections included in the scope of work.
3.1.2 Applicable ASME Code Edition and Addenda The ASME Code of Record for the third ISI interval at STP Units 1 and 2 is the ASME Code, Section Xl, 2004 Edition with no Addenda. The ASME Code of Record for the fourth ISI interval at STP Units 1 and 2 is the ASME Code, Section Xl, 2013 Edition.
3.1.3 Applicable ASME Code Requirement ASME Code, Section Xl, Article IWA-4000, Repair/Replacement Activities, subparagraph IWA-4221(b), states that, An item to be used for repair/replacement activities shall meet the Construction Code specified in accordance with [subparagraphs IWA-4221(b)(1),
IWA-4221(b)(2), or IWA-4221(b)(3)].
Subparagraph IWA-4221(b)(1) states that, When replacing an existing item, the new item shall meet the Construction Code to which the original item was constructed.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION 3.1.4 Reason for Request The licensee will perform ISI of the ECW piping in the fall of 2020 and is proactively requesting approval to use the proposed CFRP composite as a contingency to address any potential degradation within the ECW pipe wall. The licensee stated that the most likely internal degradation mechanism is flow induced erosion, and that buried ECW piping is not susceptible to selective leaching due to pipe material composition.
The licensee stated that the NRC approved the use of the CFRP composite system on the interior of concrete encased, buried safety-related carbon steel piping at the Surry Power Station in 2018 with the upgrade program continuing through 2024 as shown in an NRC letter to Virginia Electric and Power Company, dated December 20, 2017 (ADAMS Accession No. ML17303A068).
3.1.5 Proposed Alternative The licensee proposed to repair the internal surface of the ECW piping using the CFRP composite system as discussed in proposed Alternative RR-ENG-3-24.
3.1.6 Basis for Use 3.1.6.1 General Information
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
In addition, the licensee discussed the ISIs of the CFRP-repaired ECW piping.
3.1.6.2 Design Criteria The design criteria, including objectives, approach, methodologies, applicable standards, technical criteria, loads, load combinations, applicable design factors, and effective safety factors, are discussed in Enclosure 5, Attachment A, of the alternative request. The various aspects of the design criteria are grouped into strength, reliability, durability, and design approach as discussed below.
Strength
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
Reliability
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
Durability
((
))
Design Approach
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
3.1.6.3 Design Loads
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
Load Combinations for Design LSs
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
Failure Modes and Effects Analysis
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
An overview of the calculation procedure for LS1 through LS9 was discussed above, and detailed calculations are presented in Enclosure 5, Attachment C, of the alternative request.
3.1.6.4 Material Controls of the alternative request discusses material manufacturing, qualification and testing, and watertightness testing as summarized below.
Material Manufacturing
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
Material Qualification and Testing
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
Material Watertightness Testing
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
3.1.6.5 Installation Controls of the alternative request specifies the installation controls, which include pre-installation preparation, installation, in-process inspection, in-process repair, acceptance examination, and pressure testing, as summarized below.
Pre-Installation Preparation
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
Installation
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
In the July 15, 2020, letter, the licensee provided additional information regarding tensile tests of the CFRP layers. ((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
In the letter dated July 15, 2020, the licensee provided additional information regarding curing of the CFRP layers. The licensee stated that:
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
In-Process Inspection
((
))
In-Process Repair
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
Acceptance Examination
((
))
Pressure Testing In the supplement dated March 9, 2020, the licensee stated that System start-up testing will be in accordance with [ASME Code, Section Xl, IWA-5244(b)(2)], which directs that the system pressure test for non-isolable buried components shall consist of a test to confirm that flow during operation is not impaired. This testing will demonstrate and document performance of flow tests on the ECW System flow paths that support the required safety functions.
3.1.6.6 Inservice Examination The licensee stated that ISI activities will include system flow testing performed in accordance with each stations system pressure test plans and ASME Code, Section Xl, subparagraph IWA-5244(b)(2), at least once each ISI interval, for the remaining life of the plant, to verify adequate flow through the ECW piping.
The licensee will also (a) determine the extent of biological fouling, sediment buildup, and corrosion, including microbiologically-induced corrosion, (b) assess the effectiveness of biofouling control mechanisms and protective coating technologies, and (c) monitor the material integrity of metallic components and protective coating, and installed expansion ring seals. The licensee stated that corrosion inspection criteria to be identified and quantified includes localized pitting, general pipe wall thinning, and microbiologically influenced corrosion. Biological inspection criteria include inspecting for typical biological growth and species including hydroid and bryozoan growth, and clams in the ECW intake structure pump bays.
In addition, the licensee stated in its alternative request that it will inspect buried ECW piping in each 10-year ISI interval, beginning with the 10-year ISI interval prior to extended operation of the renewed operating license in accordance with criteria set forth in the STP Updated Final Safety Analysis Report (UFSAR), Chapter 19A, License Renewal, Section 19A.1.18, Buried Piping and Tanks Inspection (ADAMS Accession No. ML18130A044).
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION 3.1.6.7 Quality Controls
((
))
3.1.6.8 Duration of Proposed Alternative The licensee plans to install the CFRP composite on the ECW piping at STP Units 1 and 2 during the third and fourth 10-year ISI intervals of each STP unit.
For STP Unit 1, the third 10-year ISI interval began on September 25, 2010, and ends on September 24, 2020, and the fourth 10-year ISI interval begins on September 25, 2020, and ends on September 24, 2030. For STP Unit 2, the third ISI interval began on October 19, 2010, and ends on September 24, 2020, and the fourth 10-year ISI interval begins on September 25, 2020, and ends on September 24, 2030.
The licensee stated in its alternative request that the CFRP composite will remain in place for the life of plant and the repaired piping is to remain in service for the life of the repair. The licensee further stated that any repair/replacement and/or inspections of the repaired piping will be conducted in accordance with the applicable edition of the ASME Code,Section XI, or alternative thereto, at the time of the repair/replacement or inspection.
3.2 NRC STAFF EVALUATION The NRC staff evaluated the proposed CFRP system in the areas of design, material, installation, examination, and quality control.
3.2.1 Design The NRC staff reviewed the licensees plant-specific stress calculation summaries for repairs proposed in the alternative request provided by the licensee. ((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
The NRC staff notes that the licensees calculations have considered the appropriate load combinations in analyzing the repaired pipes of 30-inch diameter. The NRC staff also notes that the licensee used results from Water Research Foundations research program primarily developed for nonsafety-related applications. These included full-scale field experiments of prestressed concrete cylinder pipe (PCCP) subjected to the combined effects of internal pressure and external loads to study modes and loads at failure; laboratory scale experiments to determine shear bond strength; and development of simplified and reliable design formulas.
The research program also included investigation using finite element analysis of CFRP-lined buried PCCP to analyze the combined effects of gravity loads and pressures to validate the accuracy and conservatism of simplified design formulas for LSs including pressure, bending, and stability (buckling). In such analyses, stresses in the CFRP system and its buckling load resulting from interaction of the CFRP system, host pipe, and surrounding soil were calculated as the host pipe continues to degrade during its service life.
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
The NRC staff concludes that the licensee has performed an acceptable failure modes and effects analysis, because the licensee has considered significant potential failure modes and demonstrated that the CFRP system is designed to mitigate or prevent the potential failures.
The NRC staff notes that CFRP has been used in aerospace, automotive, marine, and sports industries because of its advantage of high strength combined with low weight. The NRC staff also notes that the NRC regulations do not address the AWWA guidance. The NRC staff evaluated the proposed alternative based on the merits of its technical basis in lieu of the AWWA guidance or proposed ASME Code Case under development. The NRC staff notes that research results, in and of themselves, do provide reasonable assurance of the performance of the proposed CFRP system.
Terminations
((
))
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION Factor of Safety (Allowable Stress Design versus Load and Resistance Factor Design)
((
))
Allowable Stress Design Methodology in ASME Code, Subsection NC/ND Classes 2 and 3
((
))
The following table is a summary of the calculated ASD methodology values:
ASD Methodology Summary:
Computed / Allowable 1 or Allowable/Computed 1 Codes Prior to 1999 Codes After 1999 With FS = 4 With FS = 3.5 With FS = 10 Values up to 1981 (Ductile) (Ductile) (Brittle)
Longitudinal (Rows 3-7) Effective FSeff FSeff FSeff Normal (Level-A) k=1 4 3.5 10 Upset (Level-B) k=1.2 3.33 2.92 8.33 OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION Codes Prior to 1999 Codes After 1999 With FS = 4 With FS = 3.5 With FS = 10 Values up to 1981 (Ductile) (Ductile) (Brittle)
Emergency (Level-C) k=1.8 2.22 1.94 5.56 Faulted (Level-D) k=2.4 1.67 1.46 4.17 Thermal stresses (if 7000 2.67 2.33 6.67 cycles) 1.5 Sh approx.
((1.25Sc+0.25Sh)
Hoop Direction 4 3.5 10 With FS = 4 With FS = 3.5 With FS = 10 Values after 1981 (Ductile) (Ductile) (Brittle)
Longitudinal (Rows 3-7) FSeff FSeff FSeff Normal (Level-A) k=1.5 2.67 2.33 6.67 Upset (Level-B) k=1.8 2.22 1.94 5.56 Emergency (Level-C) k=2.25 1.78 1.56 4.44 Faulted (Level-D) k=3 1.33 1.17 3.33 Thermal stresses (if 7000 2.67 2.33 6.67 cycles) 1.5 Sh a Hoop Direction 4 3.5 10
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
Results of Effective FSs for End Use and Their Acceptability For degraded Aluminum-Bronze piping, the ECW system safety-related Class 3 buried 30-inch diameter piping at STP Units 1 and 2 will be repaired using CFRP composite. The following tables summarize the results of FSeff. ((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
Based on the NRC staff review and evaluation as described above, it is concluded that CFRP repair is structurally adequate as the evaluations for the various LSs demonstrated that the effective FSs meet the minimum acceptable values providing reasonable assurance regarding the structural integrity of the proposed repair.
The NRC staffs review of licensees calculations as described above indicates that the CFRP system design provided in the alternative request satisfies the acceptance criteria for the applicable LSs. Therefore, the NRC staff finds that there is reasonable assurance that the OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION proposed repair of degraded ECW system using CFRP composite including the terminations overlapping with the host Aluminum-Bronze piping will maintain structural integrity. The NRC staff concludes that the CFRP design used for the repair of degraded piping at STP Units 1 and 2 is acceptable.
Failure Modes and Effects Analysis The NRC staff concludes that the licensee has performed an adequate failure modes and effects analysis because the licensee has considered potential, credible failure modes of the installed CFRP layers, discussed the basis of why the failure mode is not possible, and provided solutions to either prevent or minimize the failure modes. Therefore, the NRC staff finds that the licensees failure modes and effect analysis is acceptable.
The NRC staff finds that the proposed CFRP composite satisfies the design criteria of the subject piping such that the CFRP layers will be able to support the existing pipe loads without considering the host pipe base metal except at the terminations. The CFRP terminations act as interface to transfer loads from the repaired sections with intact host pipe. The NRC staff concludes that the terminations are adequately designed to maintain their structural integrity.
3.2.2 Material
((
))
3.2.3 Installation
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
)) The NRC staff finds that the licensee has provided adequate specifications for the curing and tensile testing of the cured CFRP layers as part of the installation procedures.
The NRC staff finds acceptable that the licensee will provide training to the installers and inspectors on the knowledge, skills, and abilities needed to perform the assigned duties. The installers will be trained by installing the actual CFRP system on a mockup, and the inspectors will be trained by examining the mockup with CFRP layers installed. The NRC staff finds that the licensee has provided adequate and necessary requirements and procedures for the installation of the CFRP systems.
3.2.4 Examinations
((
))
For the ISI, the NRC staff determined that the licensee will perform system flow testing in accordance with the ASME Code, Section Xl, paragraph IWA-5244(b)(2), at least once each ISI interval for the remaining life of the plant to verify adequate flow through the ECW piping.
((
)) The NRC staff notes that the licensee will inspect for localized pitting, general pipe wall thinning, microbiologically influenced corrosion, hydroid and bryozoan growth, and clams in the ECW intake structure pump bays.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION The NRC staff notes that the licensee will inspect buried ECW piping in each 10-year ISI interval, beginning with the 10-year ISI interval prior to extended operation of the renewed operating license in accordance with criteria set forth in the STP UFSAR, Chapter 19A, Section 19A.1.18.
The NRC staff concludes that the proposed acceptance examination and ISIs will ensure structural integrity of the repaired subject piping with the CFRP system and are, therefore, acceptable.
3.2.5 Quality Control The NRC staff finds that the design controls, material controls, installation, and QA and QC of the proposed CFRP composite system satisfy the requirements of 10 CFR Part 50, Appendix B, and are, therefore, acceptable.
4.0 CONCLUSION
As set forth above, the NRC staff finds that Proposed Alternative RR-ENG-3-24 described in the letter dated September 26, 2019, as supplemented by letters dated November 26, 2019, March 9, 2020, July 15, 2020, and July 30, 2020, for use of a CFRP composite system to repair the internal surface of buried ECW piping is acceptable on the basis that the proposed alternative provides an acceptable level of quality and safety. The NRC staff finds that the proposed alternative will provide reasonable assurance of the structural integrity and leaktightness of the buried ECW piping. Accordingly, the NRC staff concludes that the licensee has adequately addressed the regulatory requirements in 10 CFR 50.55a(z)(1). Therefore, the NRC staff authorizes the use of Alternative RR-ENG-3-24 for the third and fourth 10-year lSI interval at STP Units 1 and 2.
All other requirements in ASME Code,Section XI, for which relief or an alternative was not specifically requested and approved as part of this subject request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributors: Chakrapani Basavaraju John Tsao Date September 3, 2020 OFFICIAL USE ONLY PROPRIETARY INFORMATION