Letter Sequence Other |
---|
|
|
MONTHYEARML1126500712011-10-14014 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 Project stage: Other 2011-10-14
[Table View] |
|
---|
Category:Letter
MONTHYEARML24250A1882024-09-11011 September 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000499/LER-2024-001, 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 05000498/20243012024-08-27027 August 2024 NRC Initial Operator Licensing Examination Approval 05000498/2024301; 05000499/2024301 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 NOC-AE-240040, Application for Order Consenting to Direct Transfer of Licenses2024-07-31031 July 2024 Application for Order Consenting to Direct Transfer of Licenses 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 ML24184C0832024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators ML24183A1742024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump ML24179A3412024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24171A0112024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function IR 05000498/20244042024-06-0303 June 2024 Cyber Security Inspection Report 05000498/2024404 (Cover Letter) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual ML24137A0882024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 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 ML24116A3172024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report 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 ML24092A1902024-04-0101 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 NOC-AE-240040, Financial Assurance for Decommissioning - 2024 Update2024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update 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 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 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) ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 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) ML24017A2972024-02-15015 February 2024 Project Manager Assignment ML24039A1602024-02-0808 February 2024 Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation ML24039A1112024-02-0808 February 2024 Operator Licensing Examination Schedule Revision 2 ML24038A3342024-02-0707 February 2024 Change to South Texas Project Electric Generating Station (Stepgs) Emergency Plan ML24033A3002024-02-0707 February 2024 Summary of Regulatory Audit Regarding a Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML24029A2752024-01-29029 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 2024-09-11
[Table view] Category:Safety Evaluation
MONTHYEARML24201A0462024-07-26026 July 2024 Authorization and Safety Evaluation for Alternative Request No. RR-ENG-4-07 ML24022A2252024-02-20020 February 2024 Issuance of Amendment Nos. 227 and 212 to Authorize the Revision of the Alternative Source Term Dose Calculation 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) 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 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 ML18177A4252018-07-24024 July 2018 Relief from the Requirements of the Asme Code Regarding the Third 10-Year Inservice Inspection Interval 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) ML17019A0022017-07-11011 July 2017 Safety Evaluation, Enclosure 3 to Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 ML17038A2232017-07-11011 July 2017 Issuance of 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 2024-07-26
[Table view] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 October 14, 2011 Mr. Edward D. President and Chief Executive Chief Nuclear Officer STP Nuclear Operating Company South Texas Project P. O. Box 289 VVadsworth,TX 77483 SOUTH TEXAS PRO ..IECT, UNITS 1 AND 2 -REQUEST FOR RELIEF RR-ENG 05 FROM ASME CODE, SECTION XI REQUIREMENTS FOR ULTRASONIC EXAMINATION OF REACTOR PRESSURE VESSEL SHELL-TO-FLANGE VVELDS (TAC NOS. ME4975 AND ME4976)
Dear Mr. Halpin:
By letter dated October 18,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 102950166), STP Nuclear Operating Company (the licensee) submitted request RR-ENG 05 in which it requested relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements applicable to ultrasonic (UT) examinations to be conducted in accordance with Section XI, Appendix I of the ASME Code, pursuant to paragraph 50.55a(a)(3){i) of Title 10 of the Code of Federal Regulations (10 CFR) for South Texas Project (STP), Units 1 and 2. Article IVVA-2232 of the ASME Code,Section XI, requires that UT examinations be conducted in accordance with Section XI, Appendix I of the ASME Code. Appendix I, Article 1-2110(b) requires that UT examinations of the reactor pressure vessel (RPV) shell-to-flange welds be examined in accordance with ASME Code,Section V, Article 4. The licensee has proposed an alternative using the performance-based methods of ASME Code,Section XI, Appendix VIII, Supplements 4 and 6, as modified by 10 CFR 50.55a(b)(2)(xxiv). The request is for the third 10-year inservice inspection (lSI) interval for STP, which ends on September 25,2020, for Unit 1, and October 19, 2020, for Unit 2. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's request and determined that the proposed alternative provides an acceptable level of quality and safety. Based on the enclosed safety evaluation, the NRC staff concludes that procedures, personnel, and equipment qualified in accordance with the ASME Code,Section XI, Appendix VIII, demonstrate a high probability of detecting flaws and increase the reliability of examinations of weld configurations within the scope of the Performance Demonstration Initiative program. Therefore, pursuant to 10 CFR 50.55a(a){3)(i), the NRC staff authorizes the use of the proposed alternative for the third 10-year lSI interval for STP, Units and 2. All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in the subject requests for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
E. Halpin -2 If you have any questions, please contact the project manager, Balwant K. Singal, at 301-415-3016 or via e-mail at Balwant.Singal@nrc.gov. Sincerely, Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
As stated cc w/encl: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF FROM ASME SECTION XI CODE REQUIREMENTS FOR ULTRASONIC EXAMINATION OF REACTOR PRESSURE VESSEL SHELL-TO-FLANGE WELDS THIRD 10-YEAR INSERVICE INSPECTION INTERVAL STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499
1.0 INTRODUCTION
By letter dated October 18, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 102950166), STP Nuclear Operating Company (the licensee) submitted a request for relief (RR-ENG 05) from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements from ultrasonic (UT) examinations to be conducted in accordance with Section XI, Appendix I of the ASME Code pursuant to paragraph 50.55a{a)(3)(i) of Title 10 of the Code of Federal Regulations (10 CFR) for South Texas Project (STP), Units 1 and 2. Article IWA-2232 of the ASME Code,Section XI, requires that UT examinations be conducted in accordance with Section XI, Appendix I of the ASME Code. Appendix I, Article 1-2110(b) requires that UT examinations of the reactor pressure vessel (RPV) shell-to-flange welds be examined in accordance with ASME Code,Section V, Article 4. The licensee has proposed an alternative using the performance-based methods of ASME Code,Section XI, Appendix VIII, Supplements 4 and 6, as modified by 10 CFR 50.55a(b)(2)(xxiv). The request is for the third 10-year inservice inspection (lSI) interval for STP, which ends on September 25,2020, for Unit 1, and October 19, 2020, for Unit 2.
2.0 REGULATORY EVALUATION
Inservice inspection of ASME Code Class 1,2, and 3 components is performed in accordance with Section XI of the ASME Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific relief has been granted by the U.S. Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.55a(g)(6)(i). The regulations in 10 CFR 50.55a(a)(3) state that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if: Enclosure
-2 (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 SO.SSa(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 Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulation requires 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 reference in 10 CFR SO.SSa(b) 12-months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable Code of record for the third 10-year interval lSI program at STP, Units 1 and 2 is the 2004 Edition of the ASME Code,Section XI, without Addenda.
3.0 TECHNICAL EVALUATION
3.1 Component Identification RR-ENG 0S addresses the ASME Code Class 1, Examination Category B-A, Item No. B1.30 RPV shell-to-flange welds at STP, Units 1 and 2. 3.2 Code Requirements The 2004 Edition of the ASME Code,Section XI, IWA-2232 requires that UT examinations be conducted in accordance with the ASME Code,Section XI, Appendix I. Appendix I, 1-2110(b) requires UT examinations of RPV shell-to-flange welds to be conducted in accordance with the ASME Code,Section V, Article 4. Appendix I, 1-211 O(b) also requires that these examinations be further supplemented by Appendix I, Table 1-2000-1. The required examination volume for RPV shell-to-flange welds is provided in the ASME Code,Section XI, Figure IWB-2S00-4, as specified in the ASME Code,Section XI, Table IWB-2S00-1 for these Examination Category B-A Item No. 81.30 welds. 3.3 Basis for Relief and Proposed Alternative (as stated by the licensee) The RPV shell-to-flange weld is the only circumferential shell weld in the RPV not examined according to ASME [Code,] Section XI, Appendix VIII, Supplements 4 and 6 UT techniques [Article 1-2110(a)]. Procedures, equipment, and personnel qualified by the Appendix VIII Performance Demonstration Initiative (PDI) Programs for Supplements 4 and 6 have demonstrated a high probability of detecting flaws, and are generally considered superior to those qualified under the [ASME Code,] Section V, Article 4 criteria.
-3.4 Proposed Alternative and Basis for Relief (as stated by the licensee) The RPV shell-to-flange weld will be examined in accordance with the performance-based methods of ASME [Code,] Section XI, 2001 Edition (no Addenda), Appendix VIII, Supplements 4 and 6, as modified by 10 CFR SO. SSa(b )(2)(xxiv). ASME [Code,] Section XI, 2004 Edition 200S Addenda, Appendix I, Article 2600(a) states that for components to which Appendix VIII is not applicable, examination procedures, personnel, and equipment qualified in accordance with Appendix VIII may be applied, provided such components, materials, sizes, and shapes are within the scope of the qualified examination procedure. Industry experience has shown that the Appendix VIII PDI approach for UT examinations equals or surpasses the UT examination techniques of the ASME Code,Section V, Article 4 for detection and characterization of flaws in reactor pressure vessels. The procedure requires the examiner to evaluate all indications determined to be flaws regardless of their amplitude. The proposed qualification approach is more conservative. Therefore, the use of the proposed alternative will provide an acceptable level of quality and safety. 3.S NRC Staff Evaluation The 2004 Edition of the ASME Code,Section XI, IWA-2232 states that UT examinations shall be conducted in accordance with the ASME Code,Section XI, Appendix I. Appendix I, 1-2110(b) states that UT examination of RPV shell-to-flange welds, closure head-to-flange welds, and integral attachment welds shall be conducted in accordance with the ASME Code,Section V, Article 4, as supplemented by Appendix I, Table 1-2000-1. The ASME Code,Section V, Article 4 provides a prescriptive process for qualifying UT examination procedures and the scanning requirements for examinations. UT examinations performed in accordance with the ASME Code,Section V, Article 4 use detailed criteria for setting up and calibrating equipment, calculating coverage, and detecting indications. The capability of an ASME Code,Section V, Article 4 UT examination is demonstrated with calibration blocks made from representative material containing holes and notches. In lieu of the ASME Code,Section V, Article 4 angle-beam UT examination requirements, the licensee proposed to perform the RPV shell-to-flange weld examination at STP, Units 1 and 2, using examination procedures, personnel, and equipment qualified in accordance with the ASME Code,Section XI, Appendix VIII, Supplements 4 and 6, as modified by 10 CFR SO.SSa(b)(2)(xxiv). The regulations in 10 CFR SO.SSa(b)(2)(xxiv) limit the use ofthe ASME Code,Section XI, Appendix VIII to the 2001 Edition of the ASME Code with no Addenda. The ASME Code,Section XI, Appendix VIII is a performance-based UT examination method. Performance-based UT examination requires that detailed criteria be used for performance demonstration tests. The results for the tests are compared against statistically developed screening criteria. The tests are performed on representative mockups containing flaws similar to those found in operating plants. The performance-based tests demonstrate the of UT examination procedures, personnel, and In accordance with 10 CFR 50.55a(b)(2)(xv)(G), UT examinations performed using personnel, and equipment qualified in accordance with the ASME Code, Section Appendix VIII, Supplements 4 and 6, shall follow the following examination The clad to base metal interface, including a minimum of 15 percent T (measured from the clad to base metal interface), must be examined from four orthogonal directions using procedures and personnel qualified in accordance with Supplement 4 to Appendix VIII. If the clad-to-base-metal-interface procedure demonstrates detectability of flaws with a tilt angle relative to the weld centerline of at least 45 degrees, the remainder of the examination volume is considered fully examined if coverage is obtained in one parallel and one perpendicular direction. This must be accomplished using a procedure and personnel qualified for single-side examination in accordance with Supplement 6. Subsequent examinations of this volume may be performed using examination techniques qualified for a tilt angle of at least 10 degrees. The examination volume not addressed by paragraph (b)(2)(xv)(G)(1) of this section is considered fully examined if coverage is obtained in one parallel and one perpendicular direction, using a procedure and personnel qualified for single sided examination when the conditions in paragraph (b)(2)(xv)(G)(2) are met. UT examination procedures, personnel, and equipment qualified in accordance with the ASME Code,Section XI, Appendix VIII, following the examination coverage stated above, demonstrate a high probability of detecting flaws and increase the reliability of examinations of weld configurations within the scope of the PDI program. Therefore, the NRC staff concludes that proposed alternative provides an acceptable level of quality and safety. CONCLUSION The NRC staff has reviewed the licensee's proposed alternative to apply the ASME Code,Section XI, Appendix VIII performance demonstration requirements for UT examinations of the RPV shell-to-flange welds at STP, Units 1 and 2, and determined that the proposed alternative provides an acceptable level of quality and safety. The NRC staff concludes that procedures, personnel, and equipment qualified in accordance with the ASME Code,Section XI, Appendix VIII demonstrate a high probability of detecting flaws and increase the reliability of examinations of weld configurations within the scope of the PDI program. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff authorizes the use of the proposed alternative for the third 10-year lSI interval for STP, which ends on September 25, 2020, for Unit 1 and October 19,2020, for Unit 2.
-5 All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in the subject requests for relief remain applicable, including third-party review by the authorized Nuclear Inservice Inspector. Principal Contributor: Chris Sydnor, NRRIDCI/CVIB Date: October 14, 2011 E. Halpin -2 If you have any questions, please contact the project manager, Balwant K. Singal. at 301-415-3016 or via e-mail at Balwant.Singal@nrc.gov. Sincerely, IRAI Michael 1. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPLIV Reading RidsAcrsAcnw lVlailCTR Resource RidsNrrDciCvib Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrPMSouth Texas Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource JMcHale, EDO RIV CSydnor, NRR/DCI/CVIB ADAMS Accession No. ML 112650071 *Memo dated 9/19/11 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRRIDCI/CVIB/BC (A) NRR/LPL4/BC NAME BSingal ,IBurkhardt MMitchell (SSheng for)* MMarkley DATE 10/11/11 10/5/11 9/19/11 10/14/11 OFFICIAL RECORD COpy