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| | issue date = 04/05/2011 | | | issue date = 04/05/2011 |
| | title = 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 (TAC Nos. ME4764 and ME4765) | | | title = 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 (TAC Nos. ME4764 and ME4765) |
| | author name = Singal B K | | | author name = Singal B |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Halpin E D | | | addressee name = Halpin E |
| | addressee affiliation = South Texas Project Nuclear Operating Co | | | addressee affiliation = South Texas Project Nuclear Operating Co |
| | docket = 05000498, 05000499 | | | docket = 05000498, 05000499 |
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| ==1.0 INTRODUCTION== | | ==1.0 INTRODUCTION== |
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| By letter dated September 20,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No, ML 102700173), as supplemented by letter dated February 7,2011 (ADAMS Accession No. ML 110460034), STP Nuclear Operating Company (STPNOC, the licensee) submitted a request for relief (RR-ENG-3-02) from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, destructive examination requirements applicable to the South Texas Project (STP), Units 1 and 2, reactor pressure vessel (RPV) flange inserts. The licensee proposed the use of a straight beam ultrasonic examination of the vessel inserts from the top end of the vessel inserts as an alternate to the Code-required VT -1 visual examination pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50,55a(a)(3)(i), The request is for the third 10-year inservice inspection (lSI) interval for both units. For STP, Unit 1, the lSI interval began on September 25, 2010, and ends on September 24,2020; for STP, Unit 2, the lSI interval began on October 19, 2010, and ends on October 18, 2020. | | By letter dated September 20,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No, ML102700173), as supplemented by letter dated February 7,2011 (ADAMS Accession No. ML110460034), STP Nuclear Operating Company (STPNOC, the licensee) submitted a request for relief (RR-ENG-3-02) from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, destructive examination requirements applicable to the South Texas Project (STP), Units 1 and 2, reactor pressure vessel (RPV) flange inserts. The licensee proposed the use of a straight beam ultrasonic examination of the vessel inserts from the top end of the vessel inserts as an alternate to the Code-required VT -1 visual examination pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50,55a(a)(3)(i), The request is for the third 10-year inservice inspection (lSI) interval for both units. For STP, Unit 1, the lSI interval began on September 25, 2010, and ends on September 24,2020; for STP, Unit 2, the lSI interval began on October 19, 2010, and ends on October 18, 2020. |
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| ==2.0 REGULATORY EVALUATION== | | ==2.0 REGULATORY EVALUATION== |
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| As stated cc w/encl: Distribution via Listserv DISTRIBUTION: | | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: |
| PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDciCpnb resource RidsNrrDorlLpl4 Resource RidsNrrPMSouth Texas Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource JTrapp, EDO RIV CNove, NRR/DCI/CPNB ADAMS Accession No. ML 110840076 | | PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDciCpnb resource RidsNrrDorlLpl4 Resource RidsNrrPMSouth Texas Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource JTrapp, EDO RIV CNove, NRR/DCI/CPNB ADAMS Accession No. ML110840076 |
| * Memo dated 2/22/2011 ICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPNB/BC NRR/LPL4/BC NAME BSingal JBurkhardt TLupold* MMarkley DATE 4/4/11 4/4/11 2/22/11 4/5111 OFFICIAL RECORD COpy}} | | * Memo dated 2/22/2011 ICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPNB/BC NRR/LPL4/BC NAME BSingal JBurkhardt TLupold* MMarkley DATE 4/4/11 4/4/11 2/22/11 4/5111 OFFICIAL RECORD COpy}} |
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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
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 5,2011 Mr. Edward D. President and Chief Executive Chief Nuclear Officer STP Nuclear Operating Company South Texas Project P. O. Box 289 VVadsworth, TX 77483 SOUTH TEXAS PROJECT, UNITS 1 AND 2 -REQUEST FOR RELIEF RR-ENG-3-02 FROM ASME CODE REQUIREMENTS FOR REACTOR PRESSURE VESSEL FLANGE INSERT NON-DESTRUCTIVE EXAMINATION (TAC NOS. ME4764 AND ME4765)
Dear Mr. Halpin:
By letter dated September 20, 2010, STP Nuclear Operating Company (the licensee) submitted a request for relief (RR-ENG-3-02) from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, non-destructive examination requirements applicable to the South Texas Project (STP), Units 1 and 2, reactor pressure vessel (RPV) flange inserts. The request is for the third 10-year inservice inspection (lSI) interval for both units. For STP, Unit 1, the lSI interval began on September 25,2010, and ends on September 24,2020; for STP, Unit 2, the lSI interval began on October 19,2010, and ends on October 18, 2020. The U.S. Nuclear Regulatory Commission (NRC) staff has completed the review of the subject relief request. Based on the enclosed safety evaluation, the NRC staff concludes that the use of straight beam ultrasonic examination of the RPV flange inserts from the top end of the inserts will provide an equivalent or better examination of the entire length of the vessel insert for circumferential flaws than the Code-required visual examination.
Therefore, based on the above, the staff concludes the proposed alternative provides an acceptable level of quality and safety and the licensee's proposed alternative is authorized pursuant to paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations for the third 1 O-year lSI interval at STP, Units 1 and 2. All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
E. Halpin -If you have any questions, please contact the project manager, Balwant Singal, at 301-415-3016 or via e-mail at Balwant.singal@nrc.gov.
Sincerely, Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
As stated cc w/encl: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C, 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF FROM ASME CODE REQUIREMENTS FOR REACTOR PRESSURE VESSEL FLANGE INSERT NON-DESTRUCTIVE EXAMINATION DURING THIRD 10-YEAR INSERVICE INSPECTION INTERVAL SOUTH TEXAS PROJECT, UNITS 1 AND 2 STP NUCLEAR OPERATING COMPANY DOCKET NOS, 50-498 AND 50-499
1.0 INTRODUCTION
By letter dated September 20,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No, ML102700173), as supplemented by letter dated February 7,2011 (ADAMS Accession No. ML110460034), STP Nuclear Operating Company (STPNOC, the licensee) submitted a request for relief (RR-ENG-3-02) from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, destructive examination requirements applicable to the South Texas Project (STP), Units 1 and 2, reactor pressure vessel (RPV) flange inserts. The licensee proposed the use of a straight beam ultrasonic examination of the vessel inserts from the top end of the vessel inserts as an alternate to the Code-required VT -1 visual examination pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50,55a(a)(3)(i), The request is for the third 10-year inservice inspection (lSI) interval for both units. For STP, Unit 1, the lSI interval began on September 25, 2010, and ends on September 24,2020; for STP, Unit 2, the lSI interval began on October 19, 2010, and ends on October 18, 2020.
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50,55a{g) specify that lSI of nuclear power plant components shall be performed in accordance with the requirements of the ASME Code,Section XI, except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
The regulations in 10 CFR 50,55a(g)(6)(i) state that the Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest, given the consideration of the burden upon the licensee, Pursuant to 10 CFR 50.55a(a)(3), alternatives to the requirements of paragraph (g) may be used, when authorized by the U,S. Nuclear Regulatory Commission (NRC), if (i) the proposed alternatives Enclosure
-would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1,2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry.
and materials of construction of the components.
The regulations require that lSI of components and system pressure tests conducted during the first 1 O-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable ASME Code of record for the third 10-year lSI interval at STP, Units 1 and 2, is the 2004 Edition, No Addenda. The information provided by the licensee in support of the relief request has been evaluated by the NRC staff and the bases for disposition are documented below. 3.0 TECHNICAL EVALUATION 3.1 Applicable Code Edition and Addenda The Code of record for the third 10-year lSI program at STP, Units 1 and 2, is the ASNIE Code,Section XI, 2004 Edition, No Addenda. 3.2 Component(s) for Which Relief is Requested ASME Code,Section XI, IW8-2500, Table 2500-1, Code Category 8-G-1, Item Number 86.50, Class 1, Reactor Pressure Vessel Roto-Lok flange inserts (bushings).
There are 36 flange inserts per unit. 3.3 Applicable Code Requirement ASME Code,Section XI, 2004 Edition No Addenda, Code Category 8-G-1, Item 86.50, requires that all bushings receive a visual, VT-1 examination each inspection interval.
Examination of bushings and threads in flange base material is required only when the connections are disassembled.
8ushings may be inspected in place. 3.4 Licensee Proposed Alternative and 8asis for Use (as stated by the licensee)
Pursuant to 10 CFR 50.55a(a)(3)(i), STPNOC proposes to perform a straight beam ultrasonic examination of the vessel inserts from the top end of the vessel inserts as an alternative to the Code-required Visual, VT-1 examination.
The proposed alternative examination is to be performed concurrently with that of the vessel flange thread volumetric examination to inspect for radial-circumferential flaws.
-3 Roto-Lok flange inserts (see attached illustration
[attachment to letters dated September 20,2010, and February 7,2011]) consist of conventional threads on the outside surface and three rows of lugs on the inside surface. With the Lok flange inserts in place in the reactor vessel flange, portions of the lugs are not accessible for Visual, VT -1 examination.
Performing the examination concurrent with the vessel flange thread ultrasonic examination will reduce the total radiation exposure.
The ultrasonic technique will examine the entire length of the vessel insert and is superior to the VT-1 examination.
The straight beam ultrasonic examination procedure has been demonstrated to ensure examination adequacy.
3.5 NRC Staff Evaluation ASME Code,Section XI, 2004 Edition No Addenda, IW8-2500, Table IW8-2500-1, Code Category 8-G-1, Item 86.50, requires that all bushings receive a visual, VT -1 examination each inspection interval.
In accordance with 10 CFR 50.55a(a)(3)(i), the licensee proposes to perform straight beam ultrasonic examination of the RPV Roto-Lok flange inserts from the top end of the inserts as an alternative to the ASME Code-required VT-1 visual examination The proposed alternative is to be performed concurrently with that of the vessel flange thread volumetric examination to inspect for radial-circumferential flaws. The Roto-Lok flange inserts consist of conventional threads on the outside surface and three rows of lugs on the inside surface. With the Roto-Lok flange inserts in place in the reactor vessel flange, portions of the lugs are not accessible for VT-1 visual examination.
The straight beam ultrasonic examination procedure was demonstrated to ensure adequacy by the licensee; the initial demonstration was performed on December 7, 1998, in accordance with ultrasonic technical instructions.
The ultrasonic technical instructions were demonstrated at the Electric Power Research Institute in accordance with the requirements of ASME Code,Section XI, Appendix VIII as modified by the Performance Demonstration Initiative Program. The calibration block used for the demonstration was prepared in accordance with Table VI-2430-1 of the ASME Code,Section XI, Appendix VI, to examine the entire length of the vessel insert. The calibration block was fabricated from an actual spare RPV insert and included notches at different depths on both the inside and outside surfaces to ensure examination of flaws that would be found in-service.
The licensee stated that the demonstration confirmed that all inside and outside surface indications can be easily observed at scanning speeds. The manual, contact, pulse echo ultrasonic method was utilized with a 1-inch round, O-degree longitudinal wave transducer.
The inserts were examined from the top with the beam passing through the length of the insert. The NRC staff concludes that the use of straight beam ultrasonic examination of the RPV Lok flange inserts from the top end of the inserts will provide an equivalent or better examination of the entire length of the vessel insert for radial-circumferential flaws than the ASME
-4 required VT-1 visual examination.
Based on the above, the NRC staff concludes that an acceptable level of quality and safety will be maintained when using the licensee's proposed alternative examination.
4.0 CONCLUSION
The NRC staff concludes that the licensee's proposed alternative contained in Relief Request RR-ENG-3-02 to use ultrasonic examination in lieu of visual, VT -1 examination for Roto-Lok flange inserts provides an acceptable level of quality and safety. Therefore, pursuantto 10 CFR 50.55a(a)(3)(i), the proposed alternative is authorized for the third 10-year lSI interval which began on September 25,2010, and ends on September 24,2020, for STP, Unit 1, and which began on October 19,2010, and ends on October 18,2020, for STP, Unit 2. All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor:
Carol Nove Date: April 5, 2011 E. Halpin -2 If you have any questions, please contact the project manager, 8alwant Singal, at 301-415-3016 or via e-mail at Balwantsingal@nrc.gov.
Sincerely, IRAI Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
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- Memo dated 2/22/2011 ICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPNB/BC NRR/LPL4/BC NAME BSingal JBurkhardt TLupold* MMarkley DATE 4/4/11 4/4/11 2/22/11 4/5111 OFFICIAL RECORD COpy