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MONTHYEARML1006401202010-02-22022 February 2010 Inservice Testing Program Description for the Third 10-Year Interval Project stage: Request ML1009605152010-04-0606 April 2010 Acceptance Review Email, Relief Request Nos. VRR-01, PRR-03, PRR-02, and PRR-01 for the Third 10-Year Inservice Testing Program Interval Project stage: Acceptance Review ML1013205642010-05-12012 May 2010 Request for Additional Information, Relief Requests VRR-01, PRR-03, PRR-02, and PRR-01 for Third 10-Year Interval Inservice Testing Program for Pumps and Valves (TACs ME3515 Through ME3522) Project stage: RAI NOC-AE-10002562, Response to Request for Additional Information: Inservice Testing Program Description for the Third 10-Year Interval2010-06-16016 June 2010 Response to Request for Additional Information: Inservice Testing Program Description for the Third 10-Year Interval Project stage: Response to RAI 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) Project stage: Other 2010-05-12
[Table View] |
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)ML102150077 |
Person / Time |
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Site: |
South Texas ![STP Nuclear Operating Company icon.png](/w/images/9/9c/STP_Nuclear_Operating_Company_icon.png) |
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Issue date: |
09/02/2010 |
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From: |
Markley M Plant Licensing Branch IV |
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To: |
Halpin E South Texas |
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Thadani, M C, NRR/DORL/LPL4, 415-1476 |
References |
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PRR-01, PRR-02, PRR-03, TAC ME3515, TAC ME3516, TAC ME3517, TAC ME3518, TAC ME3519, TAC ME3520, TAC ME3521, TAC ME3522, VRR-01 |
Download: ML102150077 (12) |
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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 STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 2, 2010 Mr. Edward D. Halpin President and Chief Executive Officer STP Nuclear Operating Company South Texas Project P. O. Box 289 Wadsworth, TX 77483
SUBJECT:
SOUTH TEXAS PROJECT, UNITS 1 AND 2 - RELIEF REQUEST NOS.
VRR-01, PRR-01, PRR-02, AND PRR-03 FOR THE THIRD 10-YEAR INSERVICE TESTING PROGRAM INTERVAL (TAC NOS. ME3515, ME3516, ME3517, ME3518, ME3519, ME3520, ME3521, AND ME3522)
Dear Mr. Halpin:
By letter dated February 22, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100640120), STP Nuclear Operating Company (the licensee) submitted to Nuclear Regulatory Commission (NRC) its 10-year Inservice Testing (1ST) program for third 1O-year 1ST interval, for South Texas Project (STP), Units 1 and 2. The licensee's submittal included Relief Request Nos. VRR-01, PRR-01, PRR-02, and PRR-03. In its relief requests, the licensee requested NRC's authorization to use alternative examination or testing in place of certain requirements of the 2004 American Society of Mechanical Engineers (ASME)
Code for Operation and Maintenance of Nuclear Power Plants (OM Code). The licensee provided additional information in its letter dated June 16, 2010 (ADAMS Accession No. ML101750035).
The Code of record for the STP, Units 1 and 2, third 10-year 1ST program interval is the 2004 Edition of the OM Code. The 1ST program has been developed by the licensee in accordance with the requirements of the OM Code, 2004 Edition, with no addenda. The licensee stated that STP, Units 1 and 2, will comply with the limitations and modifications to the requirements in Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(b) related to implementation of the 2004 OM Code. The licensee has elected to upgrade both operating units simultaneously and, by taking extensions, aligned the STP, Unit 2's third 10-year 1ST interval to commence in September 2010 to coincide with STP, Unit 1's 1ST interval. Thus the proposed third 10-year 1ST interval for STP, Units 1 and 2, would extend from September 25, 2010, through September 25,2020.
The NRC staff has reviewed the licensee's submittals for its third 10-year 1ST program interval requests for authorization of alternatives as described in the relief requests VRR-01, PRR-01, PRR-02, and PRR-03. Based on that review, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(i), and is in compliance with the requirements in the OM Code. The NRC staff concludes that the proposed alternatives provide an acceptable level of quality and safety; and are acceptable.
Accordingly, the NRC authorizes the use of the alternatives as requested in the licensee's relief
E. Halpin -2 requests VRR-01, PRR-01, PRR-02, and PRR-03, for STP, Units 1 and 2, for the third 10-year 1ST program interval extending from September 25, 2010, through September 25, 2020.
A copy of the Safety Evaluation is enclosed. All other ASME Code requirements for which relief has not been specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
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:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO INSERVICE TESTING PROGRAM FOR THIRD 10-YEAR INTERVAL AND RELIEF REQUESTS. PRR-01! PRR-02, AND PRR-03 and VRR-01 STP NUCLEAR OPERATING COMPANY
1.0 INTRODUCTION
By letter dated February 22, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100640120), STP Nuclear Operating Company (the licensee) submitted to Nuclear Regulatory Commission (NRC) its 1O-year Inservice Testing (1ST) program for third 10-year 1ST interval, for South Texas Project (STP), Units 1 and 2. The licensee's submittal included Relief Request Nos. VRR-01, PRR-01, PRR-02, and PRR-03. In its relief requests, the licensee requested NRC's authorization to use alternative examination or testing in place of certain requirements of the 2004 American Society of Mechanical Engineers (ASME)
Code for Operation and Maintenance of Nuclear Power Plants (OM Code). The licensee provided additional information in its letter dated June 16, 2010 (ADAMS Accession No. ML101750035).
The Code of record for the STP, Units 1 and 2, third 1O-year 1ST program interval is the 2004 Edition of the OM Code. The 1ST program has been developed by the licensee in accordance with the requirements of the OM Code, 2004 Edition, with no addenda. The licensee stated that STP, Units 1 and 2, will comply with the limitations and modifications to the requirements in Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(b) related to implementation of the 2004 OM Code. The licensee has elected to upgrade both operating units simultaneously and, by taking extensions, aligned the STP, Unit 2's third 10-year 1ST interval to commence in September 2010 to coincide with STP, Unit 1's 1ST interval. Thus the proposed third 10-year 1ST interval for STP, Units 1 and 2, would extend from September 25,2010, through September 25,2020.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (CFR), Part 50, Section 50.55a(f), "Inservice testing requirements," requires, in part, that ASME Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to paragraphs 10 CFR 50.55a(a)(3)(i) or 10 CFR 50.55a(a)(3)(ii).
When proposing alternatives, a licensee must demonstrate that the proposed alternatives provide an acceptable level of quality and safety or that compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The NRC Enclosure
-2 would authorize alternatives to ASME OM Code requirements upon making necessary determinations under 10 CFR 50.55a.
The application of ASME code cases is addressed in 10 CFR 50.55a(b)(6) through reference to Regulatory Guide (RG) 1.192, "Operations and Maintenance Code Case Acceptability, ASME OM Code," Revision 0, dated June 2003, which lists acceptable and conditionally acceptable code cases for implementation in 1ST programs.
3.0 TECHNICAL EVALUATION
Th NRC staff evaluated the licensee's relief request. The NRC staff's evaluation is provided below.
3.1 Valve Alternative Request VRR-01 The licensee has requested NRC authorization to use Code Case OMN-1, "Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in LW
[light water] Reactor Power Plants," in lieu of the stroke-time provisions specified in TSTC-5120 for MOVs as well as the position verification testing in ISTC3700. This code case allows motor operated valves (MOVs) to be periodically exercised and diagnostically tested as an alternative to the OM Code stroke-time and position verification test requirements. The code of Record for STP, Units 1 and 2, third ten-year 1ST interval is the 2004 Edition of the OM Code. The Version of Code Case OMN-1 in the 2004 Edition of the OM states that, "the code case Expires on March 30, 2007." NRC authorization is required in accordance with 10 CFR 50.55a(a)(3) to use the version of Code Case OMN-1 in the 2004 Edition of the OM code beyond its stated expiration date.
The NRC staff has approved the use of Code Case OMN-1-1 in Regulatory Guide 1.192, "Operations and Maintenance Code Case Acceptability, ASME OM Code," Revision 0, dated June 2003. RG 1.192 currently approves the use of the version of Code Case OMN-1 that is in the 1999 Adenda of the OM Codel The Licensees are allowed to use the 1999 version of the Code Case OMN-1 without submitting a request for an alternative. !\IRC Authorization is required in accordance wqith 10 CFR 50.55(a)(3) to use versions of Code Case OMN-1 other that the 1999 version. The Licensee has requested NRC Authorization to use the version of the Code Case OMN-1 that is in the 2004 Edition of the OM Code.
NRC Evaluation of Proposed Alternative Application of code cases is addressed in 10 CFR 50.55a(b)(6) through reference to RG 1.192, Revision 0, which lists acceptable and conditionally acceptable code cases for implementation in 1ST programs. RG 1.192, Table 2, approves the use of Code Case OMN-1 (1999 Addenda) in lieu of provisions for stroke-time and position verification testing of MOVs in Subsection ISTC of the OM Code. Licensees are allowed the option of using Code Case (1999 Addenda) as an alternative to the OM Code requirements for MOV stroke-time and position verification testing.
The NRC staff notes that there are no significant differences between the version of Code Case OMN-1 that is in the 1999 Addenda of the OM Code currently approved for use in RG 1.192, Revision 0, and the Revision 1 of the Code Case (OMN-1-1) in 2009 Edition of the OM Code.
-3 There are recognized weaknesses in the stroke-time testing requirements for MOVs in the OM Code and the use of Code Case OMN-1-1 by a licensee resolves the weaknesses. Code Case OMN-1-1 permits licensees to replace stroke time and position verification testing of MOVs with a program of exercising MOVs every refueling outage (not to exceed 2 years) and diagnostically testing on longer intervals.
The NRC staff considers the proposed alternative to be acceptable because Code Case OMN-1-1 provides a superior method than the stoke-timing method required by the OM Code for assessing the operational readiness of MOVs. The NRC staff has recommended that licensees implement Code Case OMN-1 as an alternative to the MOV stroke-time and position verification testing provisions in the ASME Code. The NRC Staff also finds that there are no significant differences between the version of Code Case OWN-1 that is in the 1999 Addenda of the OM Code currently approved for use in RG 1.192 and the version of Code Case OMN-1 in the 2004 Edition of the OM Code.
Conclusion The NRC Staff concludes that the licensee has adequately demonstrated that the alternative provides an acceptable level of quality and safety, addresses all the regulatory requirement set forth in 10 CFR 50.55a(a)(3)(i), and is in compliance with the ASME OM Code's Requirements.
Based on the above discussion, the NRC staff concludes that the alternative in request VRR-01 is acceptable for STP, Units 1 and 2.
3.2 Pump Alternative Request PRR-01 The licensee has requested NRC authorization to use ASME Code Case OMN-18, "Alternative Testing Requirements for Pumps Tested Quarterly Within +/-20 percent of Design Flow," with the exception that a more limiting upper bound Acceptable Range value of 1.06 versus 1.10 for flow and differential pressure will be used.
The initial version of the Code Case OMN-18 is in the 2009 Edition of the OM Code. The Code Case allows the Licensee not to perform the instruments accuracy required for the comprehensive pump test. The licensee proposes to performs a quarterly Group A test in lieu of performing a biennial comprehensive pump test, utilizing the acceptance criteria associated with the Group A test. This code case has not yet been approved for use by NRC in RG 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code, "June 2003.
The licensee requested relief for NRC authorization to use Code Case OMN-18 of the 1ST for the following pumps:
Pump Description Class 3S141(2)MPA01 Auxiliary Feedwater Pump 3 3S141(2)MPA02 Auxiliary Feedwater Pump 3 3S141 (2)MPA03 Auxiliary Feedwater Pump 3 3S141(2)MPA04 Auxiliary Feedwater Pump 3
- 4 Pump Description Class 3R201 (2)NPA1(2)01 A Component Cooling Water Pump 3 3R201 (2)NPA1(2)01 B Component Cooling Water Pump 3 3R201 (2)NPA1(2)01 C Component Cooling Water Pump 3 3V111(2)VPA004 Essential Chilled Water Pump 3 3V111 (2)VPA005 Essential Chilled Water Pump 3 3V111 (2)VPA006 Essential Chilled Water Pump 3 3R281 (2)NPA1(2)01A Essential Cooling Water Pump 3 3R281 (2)NPA1(2)01 B Essential Cooling Water Pump 3 3R281 (2)NPA1(2)01 C Essential Cooling Water Pump 3 3R211 (2)NPA1(2)01A Spent Fuel Pool Cooling Pump 3 3R211 (2)NPA1(2)01 B Spent Fuel Pool Cooling Pump 3 The proposed alternative will provide more consistent trend results when comparing subsequent tests or test results in the aggregate because all tests are performed at the same flow and instrument accuracy. Deviations from actual pump performance indicative of impending degradations will be more easily recognized, and declaring pumps inoperable for reasons other than actual equipment degradation can be avoided.
Subsection ISTB of the OM Code requires pumps to be tested quarterly (Group A or B test) and biannually (comprehensive pump test). More accurate instrumentation is required for the biannual pump test than for the quarterly pump test. This can cause problems with trending because data obtained during tests with more accurate instrumentation are not always comparable with data obtained during the quarterly tests.
ISTB-3400, "Frequency of Inservice Tests," of the OM Code states that, "an inservice test shall be run on each pump as specified in Table ISTB-3400-1. This table requires a Group A or Group B test to be performed quarterly and a Comprehensive test to be performed biennially.
Table ISTB-3400-1, "Inservice Test Frequency," of the OM Code requires that, "Group A and Group B tests to be performed quarterly and a comprehensive pump test to be performed biennially."
NRC Evaluation of Proposed Alternative The licensee is proposing to perform 1ST for all the pumps listed above in accordance a modified Group A test procedure Code Case OMN-18 with the exception a more limiting upper bound Acceptable Range value 1.06 versus 1.10, flow, and differential pressure will be used.
This Code Case has not yet been approved by the NRCin RG 1.192. The licensee has proposed to use this alternative for pumps with full flow testing capability.
The ASME OM Code requires that for Group A pumps, a Group A test be performed every quarter, and a comprehensive test be performed biennially. The Group A test is performed within +/- 20% of the pump design flow rate and the pressure instrument accuracy is +/- 2%, and
-5 the upper limit for the acceptable range for flow rate and differential pressure is 110% of the reference values. There is no Alert Range for the Group A test. The comprehensive test is performed within +/- 20% of the pump design flow rate, the pressure instrument accuracy is
+/- 'Y2%, and the upper limit of the Acceptable Range for flow rate and differential pressure is 103% of the reference values. The upper limit of the Alert Range for flow rate is 94% of the reference values, and of differential pressure for the comprehensive test is 94% of the reference values. Vibration monitoring is performed during both the Group A test and comprehensive test.
The licensee proposes that for Group A pumps, a modified quarterly test be performed every quarter, and the biennial comprehensive test not be performed. The modified Group A quarterly test would be performed within +/- 20% of the pump design flow rate, using the more accurate pressure instrumentation that is required for a comprehensive test (+/- 'Y2% instead of +/- 2%).
This modified quarterly test would replace the comprehensive test. The Acceptable Range for the modified Group A quarterly test is narrower than the Acceptable Range for the Group A quarterly test.
The licensee will use a more limiting upper bound of 106% for the Acceptable Range for the Acceptable Range for flow and differential pressure in lieu of 110% that is required by the OM Code for Group A tests. Therefore, the pumps noted in the table above will be in the Required Action Range if they exceed 106% of the Acceptable Range for reference value of flow and differential pressure. This proposed upper bound of 106% is greater than the upper bound of 103% for the biennial comprehensive pump test.
The NRC staff considers the proposed alternative acceptable, because all all of the tests will be performed with pressure gauges with +/- 'Y2% accuracy. The elimination of the comprehensive pump test (with its more limiting Acceptable Range upper bound of 103%) is compensated for by using more accurate pressure gauges on every quarterly test. This will provide for better trending of pump performance. Instead of performing seven tests with pressure gauges with
+/- 2% accuracy, and then performing the eighth test with pressure gauges with +/- 'Y2% accuracy, all eight tests will be performed with the same +/- 'Y2% accurate gauges.
Conclusion Based on the above evaluation, the NRC staff concludes that the licensee's proposed alternative to the Code Group A testing requirements for the pumps listed above provides an acceptable level of quality and safety and is acceptable pursuant to 10 CFR 50.55a(a)(3)(i), on the basis that the alternative prOVides an acceptable level of quality and safety.
3.3 Pump Alternative Request PRR-02 The licensee has requested authorization to use ASME Code Case OMN-16, "Use of a Pump Curve For Testing." This code case allows the use of pump curves for pump 1ST when it is impractical to adjust a centrifugal or vertical line shaft pump to a specific reference value.
Section ISTA-3130, "Application of Code Cases," ISTA-3130(b) of the 2004 Edition of the OM Code states that, "Code Cases shall be applicable to the edition and addenda specified in the test plan." The Code of Record for STP, Units 1 and 2, third ten-year 1ST interval, is the 2004
-6 Edition of the OM Code. The initial version of Code Case OMN-16 is in the 2006 Addendum of the OM Code and is compatible with the 2004 Edition of the OM Code. The NRC staff has not approved the the use of Code Case OMN-16 in RG 1.192, Revision 0, RG 1.192 Revision 0, presently approves the use of code cases up through the 2001 Edition of the OM Code. The licensee requires NRC authorization in accordance with 10 CFR 50.55a(a)(3) to use Code Case OMN-16.
The licensee requested relief to use Code Case OMN-16 for the 1ST for the following pumps:
Pump Description Class 3R281 (2)NPA1(2)01A Essential Cooling Water Pump 3 3R281 (2)NPA1(2)01 B Essential Cooling Water Pump 3 3R281 (2)NPA1(2)01 C Essential Cooling Water Pump 3 The licensee stated that, the conditions imposed on OMN-9, "Use of Pump Curve for Testing as stated in RG1.192, Revision 0, has been incorporated in Code Case OMN-16.
NRC Evaluation of Proposed Alternative Application of code cases is addressed in 10 CFR 50.55a(b)(6) through reference to RG 1.192, which lists acceptable and conditionally acceptable code cases for implementation in 1ST programs. RG 1.192, Table 2, conditionally approves the use of Code Case OMN-9. Licensees are allowed to use Code Case OMN-9 as an alternative to the OM Code requirements for pump 1ST without obtaining NRC authorization in accordance with 10 CFR 50.55a(3). The NRC has reviewed Code Case OMN-16 and agrees with the licensee that the conditions imposed on OMN-9 as stated in RG 1.192 have been incorporated in Code Case OMN-16.
The NRC staff considers Code Case OMN-16 to be an acceptable method for assessing the operational readiness of pumps, and is consistent with the staff position in RG 1.192 that conditionally approved the use of Code Case OMN-9.
Conclusion Based on the above evaluation, the NRC staff concludes that the licensee's proposed alternative to the OM Code testing requirements for the pumps listed above is acceptable pursuant to 10 CFR 50.55a(a)(3)(i), on the basis that the alternative provides an acceptable level of quality and safety. The licensee's proposed alternative provides reasonable assurance of the operational readiness of the pumps listed above 3.4 Pump Alternative Request PRR-03 The licensee has requested NRC authorization to increase the Group A inservice test interval for the residual heat removal (RHR) pumps from every 3 months (quarterly) to every 6 months.
Table ISTB-3400-1, "Inservice Test Frequency," of the 2004 Edition of the OM Code requires that a Group A pump test be performed quarterly.
-7 The licensee has proposed an alternative to the Group A quarterly test interval requirement in Table ISTB-3400-1 for the following pumps:
Pump Description Class 2R161 (2)NPA1(2)01A RHR Pump A 2 2R161 (2)NPA1(2)0'1 B RHR Pump B 2 2R161 (2)NPA1(2)01 C RHR Pump C 2 The licensee stated that STP, Units 1 and 2, have three RHR pump trains used only for long term cooldown events following auxiliary feedwater operations. STP, Units 1 and 2, are unique in the design of its RHR system. Whereas other plants have two trains of RHR, STP, Units 1 and 2, have three trains of RHR. The RHR system does not serve the low head safety injection function, and is therefore, not critical to the immediate accident mitigation function. Less emphasis should be placed on the quarterly testing of these pumps at power due to the RHR system negligible impact on core damage frequency and large early release frequency.
The licensee referenced the NRC safety evaluation in NRC letter "Issuance of Amendment Nos.
59 and 47 to Facility Operating License Nos. NPF-76 and NPF-80 and Related Relief Request South Texas Project, Units 1 and 2 (TAC Nos. M76048 and M76049)" (ADAMS Accession No. ML021300134), dated February 17, 1994, for the explanation of defense-in-depth philosophy and how the alternative maintains sufficient safety margins. The licensee stated that the results of the of review in the safety evaluation dated February 17, 1994, indicate that the proposed changes in the RHR pump surveillance interval represent an insignificant change in system unavailability, and no change in core damage frequency. The RHR system, including the RHR pumps, continue to be used as designed with no change in function or performance. The risk metrics for the RHR pumps remain consistent with the values used in the original risk analysis.
The licensee stated that the performance measure strategies for monitoring the proposed alternative in PRR-03 include a Group A 1ST run on each RHR pump nominally every 6 months during normal plant operation. A Comprehensive test on each RHR pump will be performed every two years.
!\IRC Evaluation of Proposed Alternative The NRC stated in its letter dated February 17, 1994, that the licensee proposed to change technical specifications (TSs) to extend the RHR pump surveillance test interval to 6 months.
However, the licensee withdrew this TS proposal because the NRC staff recognized that relief from the quarterly ASME Code test requirements was needed before the changes could be allowed to the RHR pump 1ST interval. The licensee subsequently requested, in Relief Request (RR) -11 (Unit 1) and RR-12 (Unit 2), NRC authorization to increase the 1ST interval for the RHR pumps, from every 3 months to every 6 months. The NRC safety evaluation that originally authorized RR-11 and RR-12 is also contained in the February 17, 1994 letter.
The NRC safety evaluation for RR-11 and RR-12 stated that STP, Units 1 and 2, is unique in the design of the RHR system. Whereas two trains are normally installed for redundancy to
-8 ensure availability of at least one train, STP, Units 1 and 2, have three trains of RHR. The licensee's analysis in the February 17, 1994, letter was reviewed by the NRC with assistance of Brookhaven National Laboratory to check the licensee's 3-train analysis for the percent change in system unavailability and core damage frequency. The results of the review indicated that the licensee's proposed change in the RHR pump 1ST interval represents an insignificant change in system unavailability and no change in core damage frequency.
RG 1.175, "An Approach for Plant-Specific, Risk-Informed Decision-Making: lnservice Testing,"
August 1998, describes an acceptable alternative approach for applying risk insights from probabilistic risk assessment, in conjunction with established traditional engineering information, to make changes to a nuclear power plant's 1ST programs. The approach described in RG 1.175 addresses the high-level safety principles specified in RG 1.174, "An Approach For Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes To The Licensing Basis," Revision 1, November 2002, and attempts to strike a balance between defining an acceptable process for developing risk-informed 1ST programs without being overly prescriptive. It is intended that the approach presented in RG 1.175 should be regarded as an example of acceptable practice, and that licensees should have some degree of flexibility in satisfying regulatory requirements on the basis of their accumulated plant experience and knowledge.
ASME Code Case OMN-3, "Requirements for Safety Significance Categorization of Components Using Risk Insights for Inservice Testing of LWR Power Plants," is conditionally approved for use in RG 1.192, Revision O. The provisions in Code Case OMN-3allow extension of the test interval for pumps in the 1ST program provided certain criteria are met.
The licensee did not use Code Case OMN-3 for this alternative because applying Code Case OMN-3 to the RHR pumps test frequency would result in internally inconsistent risk-ranking classifications.
Although the risk-ranking methodology used by the licensee is not the same risk-ranking methodology used in Code Case OMN-3 that was conditionally approved by the NRC, the alternative in PRR-03 is similar to the criteria in Code Case OMN-3 for extending the test intervals for components in the 1ST program. The NRC considers the proposed alternative to be acceptable because it is consistent with defense-in-depth philosophy, safety margin, and performance monitoring strategies as discussed in RG 1.175.
4.0 CONCLUSION
As set forth above, the NRC staff has determined that the alternatives in Relief Requests VRR 01, PRR-01, PRR-02, and PRR-03 are acceptable for STP, Units 1 and 2. Accordingly, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(i), and is in compliance with the requirements in the OM Code.
-9 Accordingly, the NRC staff authorizes the alternatives proposed in Relief Requests VRR-01, PRR-01, PRR-02, and PRR-03 for STP, Units 1 and 2, for the proposed 3rd 1O-year 1ST interval. The authorization is based on the conclusion that the proposed alternatives provide and acceptable level of quality and safety. All other OM Code requirements for which an alternative was not specifically requested and authorized remain applicable.
Principal Contributor: S. Tingen Date: September 2,2010
E. Halpin -2 requests VRR-01, PRR-01, PRR-02, and PRR-03, for STP, Units 1 and 2, for the third 10-year 1ST program interval extending from September 25, 2010, through September 25, 2020.
A copy of the Safety Evaluation is enclosed. All other ASME Code requirements for which relief has not been specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Sincerely, I RAJ 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:
Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLIV r/f RidsAcrsAcnw_MailCTR Resource RidsNrrDciCptb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrPMSouthTexas Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource LTrocine, EDO RIV STingen, NRRIDCI/CPTB ADAMS Accession No. ML102150077 *SE memo dated OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/CPTB/BC NRR/APLAlBC NRR/LPL4/BC NRR/LPL4/PM NAME MThadani JBurkhardt AMcMurtray* DHarrison MMarkley MThadani DATE 9/2/10 8/6/10 6/29/10 8/26/10 9/2110 9/2/10 OFFICIAL AGENCY RECORD