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MONTHYEARML0318204582003-06-23023 June 2003 Draft Information Input Faxed on June 23, 2003, (50-498 and 50-499) STP Units 1 and 2 - MB9098 and MB0999 Project stage: Draft Other ML0317607712003-06-25025 June 2003 Relief, American Society of Mechanical Engineers Code Requirements for Approval of ASME Section IX Code Cases 2142-1 and 2143-1 for the Second 10-year Inspection Interval, MB9098 and MB9099 Project stage: Other 2003-06-23
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Category:Code Relief or Alternative
MONTHYEARML24201A0462024-07-26026 July 2024 Authorization and Safety Evaluation for Alternative Request No. RR-ENG-4-07 ML24040A1962024-02-13013 February 2024 Authorization and Safety Evaluation for Alternative Request No. RR-ENG-4-06 ML22245A0012022-09-12012 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) 2024-07-26
[Table view] Category:Letter
MONTHYEARML24304B0512024-10-30030 October 2024 Cycle 26 Core Operating Limits Report IR 05000498/20244022024-10-23023 October 2024 Security Baseline Inspection Report 05000498/2024402 and 05000499/2024402 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function ML24295A0772024-10-21021 October 2024 Licensed Operator Positive Fitness-for-Duty Test 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24290A1162024-10-16016 October 2024 Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan ML24255A0322024-09-30030 September 2024 The Associated Independent Spent Fuel Storage Installation - Notice of Consideration of Approval of Direct Transfer of Licenses and Opportunity to Request a Hearing (EPID L-2024-LLM-0002) - Letter ML24269A1762024-09-25025 September 2024 Tpdes Permit Renewal Application WQ0001 908000 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps ML24271A3022024-09-18018 September 2024 STP-2024-09 Post-Exam Comments - Redacted ML24274A0902024-09-16016 September 2024 Written Response - EA-24-026 STP Operator - Redacted ML24250A1882024-09-11011 September 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators IR 05000498/20240052024-08-22022 August 2024 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2024005 and 05000499/2024005) IR 05000498/20240022024-08-0909 August 2024 Integrated Inspection Report 05000498/2024002 and 05000499/2024002 IR 05000498/20240102024-08-0808 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010 ML24218A1462024-07-26026 July 2024 2. EPA Comments on South Texas Project Exemption Ea/Fonsi ML24207A1782024-07-25025 July 2024 Licensed Operator Positive Fitness-For-Duty Test 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24137A0882024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual ML24136A2842024-05-15015 May 2024 Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24128A1572024-05-0707 May 2024 Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000498/20240012024-05-0606 May 2024 Integrated Inspection Report 05000498/2024001 & 05000499/2024001 ML24120A3762024-04-29029 April 2024 Annual Dose Report for 2023 ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water ML24117A1602024-04-24024 April 2024 2023 Radioactive Effluent Release Report ML24102A2452024-04-23023 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24113A3122024-04-22022 April 2024 Cycle 24 Core Operating Limits Report ML24097A0072024-04-0606 April 2024 Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75 05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24088A3022024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update ML24081A3972024-03-21021 March 2024 Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24080A2902024-03-19019 March 2024 Nuclear Liability Certificates of Insurance NOC-AE-240040, Nuclear Liability Certificates of Insurance2024-03-19019 March 2024 Nuclear Liability Certificates of Insurance ML24066A2002024-03-0606 March 2024 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML24079A1312024-03-0505 March 2024 Nuclear Insurance Protection ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 IR 05000498/20230062024-02-28028 February 2024 Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006) IR 05000498/20240132024-02-27027 February 2024 Design Basis Assurance Inspection (Programs) Commercial Grade Dedication IR 05000498/2024013 and 05000499/2024013 ML24022A2252024-02-20020 February 2024 Issuance of Amendment Nos. 227 and 212 to Authorize the Revision of the Alternative Source Term Dose Calculation ML24050A0082024-02-19019 February 2024 Evidence of Financial Protection ML24045A0922024-02-16016 February 2024 Response to STP FOF Move Letter (2024) 2024-09-30
[Table view] |
Text
June 25, 2003 Mr. William T. Cottle President and Chief Executive Officer STP Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, TX 77483
SUBJECT:
SOUTH TEXAS PROJECT, UNITS 1 AND 2 - REQUEST FOR RELIEF, RR-ENG-2-31, FROM AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE REQUIREMENTS FOR APPROVAL OF ASME SECTION IX CODE CASES 2142-1 AND 2143-1 FOR THE SECOND 10-YEAR INSPECTION INTERVAL (TAC NOS. MB9098 AND MB9099)
Dear Mr. Cottle:
By letter dated May 15, 2003, STP Nuclear Operating Company ( STPNOC or the licensee),
requested relief from the requirements of the 1989 Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Article IWA-4000. The licensee proposed to follow the guidelines of ASME Code Case 2142-1, F-Number Grouping for Ni-Cr-Fe, Classification UNS N06052 Filler Metal, Sections III, IX, and XI and Code Case 2143-1, F-Number Grouping for Ni-Cr-Fe, Classification UNS W86152 Welding Electrode, Sections III, IX, and XI.
STPNOC requested relief from the requirements of ASME Code Section XI, Article IWA-4000 in accordance with Section 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations in order to perform repair welds and installation welds for replacement items. The ASME Section III codes applied to the original construction and the corresponding ASME Section II material codes for most South Texas Project (STP) components do not address the welding materials specified in Code Cases 2142-1 and 2143-1. STPNOC requested that the U.S. Nuclear Regulatory Commission (NRC) approve the use of ASME Code Cases 2142-1 and 2143-1 at STP, Units 1 and 2 on the basis that it provides an acceptable level of quality and safety.
Code Cases 2142-1 and 2143-1 have classified the welding filler material group number as F-No. 43 for the Alloy 690 shielded metal arc welding electrode designated as UNS W86152 and the bare filler wire designated as UNS N06052. Since these weld filler materials are similar in welding characteristics to many other Code nickel-based filler weld materials and have metallurgical properties similar to the base metals, separate procedure and performance qualifications for these materials are not warranted. Affirming this Code F-number designation for Code Cases 2142-1 and 2143-1 permits the specified filler weld material to be used in previously qualified weld procedures, thus eliminating the need for creating new procedures and performance qualifications.
On the basis of its evaluation, the NRC staff concludes that the proposed alternative to use Alloy 690 (Inconel 52/152) as weld material in accordance with the Code Cases 2142-1 and 2143-1 for the repair of instrument nozzle welds will provide an acceptable level of quality and
W. Cottle safety. Therefore, the use of the Code Cases 2142-1 and 2143-1 as requested in the Relief Request RR-ENG-2-31, is authorized pursuant to Section 10 CFR 50.55a(a)(3)(i) at STP, Units 1 and 2, for the second 10-year inservice inspection interval. When these code cases are approved by reference in Regulatory Guide (RG) 1.85, "Materials Code Case Acceptability -
ASME Section III, Division 1," the licensee is to follow all provisions in the code cases with limitations issued in RG 1.85, if any, as discussed with Mr. John T. Conly, Licensing, STPNOC, in the telephone conversation on June 23, 2003.
The NRC staffs evaluation and conclusions are contained in the enclosed safety evaluation.
Sincerely,
/RA/
Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
Safety Evaluation cc w/encl: See next page
ML031760771 OFFICE PDIV-1 PM PDIV-1/PM PDIV-1/LA EMCB/SC OGC PDIV-1/SC NAME BVaidya MThadani* MMcAllister SCoffin* APH* RGramm DATE 6/25/03 06/24/03 6/24/03 06/24/03 06/24/03 6/25/03 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF NO. RR-ENG-2-31 USE OF AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE CASES 2142-1 AND 2143-1 SOUTH TEXAS PROJECT NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499
1.0 INTRODUCTION
By letter dated May 15, 2003, STP Nuclear Operating Company (STPNOC or the licensee),
requested relief from the requirements of the 1989 Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Article IWA-4000. The licensee has proposed to follow the guidelines of ASME Code Case 2142-1, F-Number Grouping for Ni-Cr-Fe, Classification UNS N06052 Filler Metal, Sections III, IX, and XI and Code Case 2143-1, F-Number Grouping for Ni-Cr-Fe, Classification UNS W86152 Welding Electrode, Sections III, IX, and XI as an alternative to the requirements in the ASME Code. Code Cases 2142-1 and 2143-1 provide criteria for weld material F-number group classifications.
2.0 BACKGROUND
The inservice inspection (ISI) of ASME Code Class 1, 2, and 3 components is to be performed in accordance with Section XI of the ASME Code and applicable edition and addenda as required by Section 50.55a(g) of Title 10 of the Code of Federal Regulations (10 CFR), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). The regulation in Section 10 CFR 50.55a(a)(3) states in part that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if the licensee demonstrates that: (i) the proposed alternatives 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 the preservice examination requirements, set forth in the ASME Code,Section XI, Rules for Inservice Regulation required that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by the limitations and modifications listed therein. The Code of record for the second 10-year ISI interval at STP, Units 1 and 2, is the 1989 Edition of Section XI and the ASME Code.
ASME Code Section XI, Article IWA-4120(a) states that repairs shall be performed in accordance with the Owners Design Specification and the original Construction Code of the component or system. Later editions and addenda of the Construction Code or of Section III, either in their entirety or portions thereof, and code cases may be used.
STPNOC requested approval under the provisions of 10 CFR 50.55a(a)(3)(i) to use Alloy 690 (Inconel 52/152) weld materials in accordance with ASME Code Cases 2142-1 and 2143-1.
The Alloy 690 weld materials would be used for repairing the bottom mounted instrument nozzles in the Unit 1 Reactor Pressure Vessel. The referenced code cases introduce and classify new nickel-base weld metals that are compatible with Alloy 690 base material. Code Case 2142-1 establishes welding classifications and other requirements for a bare filler material. Code Case 2143-1 establishes welding classifications and other requirements for coated electrodes. These two code cases have not been incorporated by reference into the regulation and, therefore, their use requires NRC approval.
Thus, the licensees request consists of two issues:
- 1. The use of Alloy 690 (Inconel 52/152) as weld material for repairing the instrument nozzles in lieu of Alloy 600 (Inconel 82/182) as welding material,
- 2. The use of two ASME code cases that group the new weld materials in the same weld categories as other commonly employed nickel-base weld materials. This allows the use of appropriate existing welding procedures and performance qualifications with the new weld materials.
The Code of Record to be used to repair the instrument nozzle at STP is ASME Code,Section XI, 1989 Edition with no Addenda. This code allows by reference the use of Alloy 600 (Inconel 82/182) as weld material, but does not include the use of Alloy 690 (Inconel 52/152) weld materials. Industry studies indicate that Alloy 690 (Inconel 52/152) as weld materials are less susceptible to intergranular stress corrosion cracking than the Alloy 600 (Inconel 82/182) weld materials.
3.0 EVALUATION OF RELIEF REQUEST APPROVAL OF ASME SECTION IX CODE CASES 2142-1 AND 2143-1 FOR THE SECOND 10-YEAR INSPECTION INTERVAL.
3.1 The Items for which Relief is Requested:
Components, component supports, or other items that are fabricated from Alloy 690 (Inconel 52/152) material and requiring the use of Universal Numbering System (UNS) N06052 filler metal or UNS W86152 electrodes for welding operations.
3.2 Code Requirement:
The applicable ASME Code Edition and Addenda are ASME Code,Section XI, 1989 Edition with no Addenda. ASME Code,Section XI, Article IWA-4000, Code of Record for STP, Units 1
and 2, requires that repair welds and installation welds for replacement items meet the requirements of the original construction codes, or later approved code, including materials requirements. The ASME Section III codes are applicable codes for the original construction and the corresponding Section II material codes for most STP components do not address the welding materials specified in Code Cases 2142-1 and 2143-1.
3.3 Reason for the Request (as stated):
STP Nuclear Operating Company (STPNOC) requests relief to employ the alternative welding materials of ASME Section IX Code Cases 2142-1 and 2143-1 as necessary during the second ten-year inservice inspection interval of South Texas Project Units 1 and 2. The immediate need for these Code Cases is for repairing the bottom mounted instrument nozzles in the Unit 1 reactor vessel.
3.4 Licensees Proposed Alternative and Basis for Use (as stated):
Industry studies have demonstrated that Alloy 690 (Inconel 52/152) weld materials possess a high resistance to primary water corrosion. The use of Alloy 690 (Inconel 52/152) weld materials has been previously approved for other applications at several operating nuclear power plants.
Code Cases 2142-1 and 2143-1 introduce and classify nickel-based weld materials that closely match and are intended for welding Alloy 690 (Inconel 52/152). Code Case 2142-1 establishes welding classifications and other requirements for bare filler metal. Code Case 2143-1 establishes welding classifications and other requirements for coated electrodes. The Code Cases were approved by ASME on June 5, 1995, and published in the 1995 Edition of the ASME Boiler and Pressure Vessel Code, Code Cases Supplement No.1.
Code Case 2142-1 lists the American Welding Society (AWS) specification A5.14 and Universal Numbering System (UNS) designation N06052 for a filler metal conforming to Inco 52 (Inconel 52). It establishes this weld metal as F-No. 43 for both procedure and performance qualification purposes. Code Case 2143-1 lists appropriate AWS specification A5.11 and UNS specification W86152 for a coated electrode conforming to Inco 152 (Inconel 152) and establishes F-No. 43 for this material for welding purposes. By this set of specifications and F-No. assignments, the materials are completely described for welding purposes as similar in their welding characteristics to many other Code nickel-based weld metals. These materials are similar in composition and mechanical and thermal properties to approved metals; thus, existing welding procedures may be used with the Inco 52 or 152 (Inconel 52/152) type weld metals.
STPNOC has determined that the proposed alternative to employ the alternative welding materials of Code Cases 2142-1 and 2143-1 provides an acceptable level of quality and safety.
3.5 Duration of Proposed Alternative (as stated):
This relief request will be implemented during the second ten-year inservice inspection interval of South Texas Project Units 1 and 2.
3.6 Evaluation
3.6.1 Use of Alloy 690 Weld Materials:
The licensee stated that the industry studies have demonstrated that Alloy 690 (Inconel 52/152) weld materials possess a high resistance to primary water corrosion. This is due to the presence of higher chromium content of the as deposited weld metal of Alloy 690 (Inconel 52/152) weld material. The licensee has proposed the use of alternative Inconel Alloy 690 (Inconel 52/152) weld materials for the repair weld of the bottom head instrument nozzle. Laboratory test data have shown that Inconel Alloy 690 (Inconel 52/152) weld materials are resistant to stress corrosion cracking in simulated Pressurized Water Reactor (PWR) environments. The NRC staff has approved the use of Alloy 690 (Inconel 52/152) in the replacement of steam generators (SGs) for a number of PWRs including: V.C. Summer; St. Lucie, Unit 1; McGuire Nuclear Station, Units 1 and 2; Catawba Nuclear Station, Unit 1; and Oconee Nuclear Station Units 1, 2, and 3 and also for new construction and other repair activities.
Therefore, on the basis of above discussion, the NRC staff concludes that the use of Alloy 690 (Inconel 52/152) weld materials in the repair of bottom head nozzle at STP, Units 1 and 2 as proposed by the licensee, is acceptable because it will provide an acceptable level of quality and safety.
3.6.2 Use of Code Cases 2142-1 and 2143-1:
The purpose of a weld metal code case is to establish the weld metal classification based on the welding characteristics of the welding materials. The welding characteristics classification is defined in ASME Section IX as a "F-No. Weld materials with similar characteristics are grouped together under the same F-No. in order to reduce the duplication of welding procedure and welder qualifications.
Code Case 2142-1 lists AWS specification (AWS 5.14) and UNS designation (UNS N06052) as conforming to Inconel 52. It establishes the F-No. of this weld metal as F-No. 43 for both procedure and performance qualification purposes. Code Case 2143-1 lists appropriate AWS specification (AWS 5.11) and UNS designation (UNS W86152) for a coated electrode matching Inconel 152 and establishes F-No. 43 for welding purposes. Weld filler materials that are similar to Alloy 690 (Inconel 52/152) were approved by the Code on June 5, 1995, in Code Cases 2142-1 and 2143-1. These code cases were reaffirmed July 22, 1998. The code cases established the F-No. 43 for the specified weld filler material under nickel-base alloys. By allowing the licensee to use Code Cases 2142-1 and 2143-1, the NRC staff is affirming the Code designation of F-No. 43. Affirming this Code designation for Code Cases 2142-1 and 2143-1 permits the specified filler weld material to be used in previously qualified weld procedures, thus eliminating the need for creating new procedures and performance qualifications. Since the specified filler weld materials are similar in its welding characteristics
to many other Code nickel base filler weld materials and have metallurgical properties similar to the base metals, the NRC staff has concluded that separate procedure and performance qualifications for these materials are not warranted. The use of previously qualified procedure and performance standards for welding with the filler weld metals described in Code Cases 2142-1 and 2143-1 will provide an acceptable level of quality and safety. Adoption on these code cases will enable the licensee to use Alloy 690 (Inconel 52/152) weld materials on code welds.
The NRC staff finds that these two code cases appropriately specify and classify the necessary weld metal characteristics and are acceptable for use. The NRC staff has approved the use of Alloy 690 (Inconel 52/152) weld materials in the replacement of SGs for a number of PWRs including: V.C. Summer; St. Lucie, Unit 1; McGuire Nuclear Station, Units 1 and 2; Catawba Nuclear Station, Unit 1; and Oconee Nuclear Station, Units 1, 2, and 3.
4.0 CONCLUSION
On the basis of its evaluation, the NRC staff concludes that the proposed alternative to use Alloy 690 weld materials in accordance with the Code Cases 2142-1 and 2143-1 for the repair of instrument nozzle welds will provide an acceptable level of quality and safety. Therefore, the use of the Code Cases 2142-1 and 2143-1 as requested in the Relief Request RR-ENG-2-31, is authorized pursuant to Section 10 CFR 50.55a(a)(3)(i) at STP, Units 1 and 2, for the second 10-year inservice inspection interval. When these code cases are approved by reference in Regulatory Guide (RG) 1.85, "Materials Code Case Acceptability - ASME Section III, Division 1," the licensee is to follow all provisions in the code cases with limitations issued in RG 1.85, if any, as discussed with Mr. John T. Conly, Licensing, STPNOC, in the telephone conversation on June 23, 2003.
Principal Contributor: Ganesh Cheruvenki Date: June 25, 2003
South Texas, Units 1 & 2 cc:
Mr. Cornelius F. OKeefe A. H. Gutterman, Esq.
Senior Resident Inspector Morgan, Lewis & Bockius U.S. Nuclear Regulatory Commission 1111 Pennsylvania Avenue, NW P. O. Box 910 Washington, DC 20004 Bay City, TX 77414 Mr. T. J. Jordan, Vice President A. Ramirez/C. M. Canady Engineering & Technical Services City of Austin STP Nuclear Operating Company Electric Utility Department P. O. Box 289 721 Barton Springs Road Wadsworth, TX 77483 Austin, TX 78704 S. M. Head, Manager, Licensing Mr. L. K. Blaylock Nuclear Quality & Licensing Department Mr. W. C. Gunst STP Nuclear Operating Company City Public Service Board P. O. Box 289, Mail Code: N5014 P. O. Box 1771 Wadsworth, TX 77483 San Antonio, TX 78296 Environmental and Natural Resources Mr. C. A. Johnson/A. C. Bakken Policy Director AEP Texas Central Company P. O. Box 12428 P. O. Box 289 Austin, TX 78711-3189 Mail Code: N5022 Wadsworth, TX 77483 Jon C. Wood Matthews & Branscomb INPO 112 East Pecan, Suite 1100 Records Center San Antonio, TX 78205 700 Galleria Parkway Atlanta, GA 30339-3064 Arthur C. Tate, Director Division of Compliance & Inspection Regional Administrator, Region IV Bureau of Radiation Control U.S. Nuclear Regulatory Commission Texas Department of Health 611 Ryan Plaza Drive, Suite 400 1100 West 49th Street Arlington, TX 76011 Austin, TX 78756 D. G. Tees/R. L. Balcom Brian Almon Texas Genco, LP Public Utility Commission P. O. Box 1700 William B. Travis Building Houston, TX 77251 P. O. Box 13326 1701 North Congress Avenue Judge, Matagorda County Austin, TX 78701-3326 Matagorda County Courthouse 1700 Seventh Street Bay City, TX 77414 May 2003
Susan M. Jablonski Office of Permitting, Remediation and Registration Texas Commission on Environmental Quality MC-122 P.O. Box 13087 Austin, TX 78711-3087 Mr. Terry Parks, Chief Inspector Texas Department of Licensing and Regulation Boiler Division P. O. Box 12157 Austin, TX 78711 Mr. Ted Enos 4200 South Hulen Suite 630 Ft. Worth, Texas 76109