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MONTHYEARML0206000762002-03-21021 March 2002 ASME Code Section XI Relief Request: RR-2-31 Regarding Surface Examination of the Reactor Vessel Closure Studs Project stage: Other 2002-03-21
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Category:Letter
MONTHYEARIR 05000266/20240022024-08-13013 August 2024 Integrated Inspection Report 05000266/2024002 and 05000301/2024002 L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24214A3092024-08-0202 August 2024 Confirmation of Initial License Examination ML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024 License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections IR 05000266/20244012024-07-23023 July 2024 Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401 ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024 Preparation and Scheduling of Operator Licensing Examinations L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal IR 05000266/20240102024-07-10010 July 2024 Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010 L-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024 License Amendment Request 300, Modify Containment Average Air Temperature Requirements L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024 Schedule for Subsequent License Renewal Environmental Review ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-093, Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision2024-06-10010 June 2024 Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision IR 05000266/20244202024-06-0505 June 2024 Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420 ML24149A1922024-05-28028 May 2024 Notification of NRC Baseline Inspection and Request for Information ML24141A1382024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000266/2024301; 05000301/2024301 L-2024-067, Annual Monitoring Report2024-04-26026 April 2024 Annual Monitoring Report ML24116A0402024-04-23023 April 2024 Periodic Update of the Updated Final Safety Analysis Report ML24071A0912024-04-22022 April 2024 Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval IR 05000266/20240012024-04-11011 April 2024 Integrated Inspection Report 05000266/2024001 and 05000301/2024001 L-2024-030, Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-03-27027 March 2024 Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-043, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-03-25025 March 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications IR 05000266/20230062024-02-28028 February 2024 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006) L-2024-020, Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections2024-02-22022 February 2024 Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections ML24053A3732024-02-22022 February 2024 Operator Licensing Examination Approval Point Beach, March 2024 ML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML24120A1582023-10-0606 October 2023 Ile Proposed Outline Submittal Letter 2024-08-09
[Table view] Category:Safety Evaluation
MONTHYEARML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML24200A1612024-07-19019 July 2024 Alternative CISI-03-01 ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter ML24068A2492024-04-22022 April 2024 – Authorization and Safety Evaluation for Alternative Request No. I6-RR-01 ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22193A1142022-09-12012 September 2022 Issuance of Amendment Nos. 270 and 272 Elimination of the Requirements to Maintain the Post-Accident Sampling System ML22140A1272022-05-25025 May 2022 Subsequent License Renewal Application Safety Evaluation Revision 1 Public ML22041A3342022-02-23023 February 2022 Transmittal Letter for Point Beach Final SE for SLRA Review to AA La 2-9 (3) ML22054A1082022-02-23023 February 2022 Subsequent License Renewal Application Safety Evaluation Public ML21148A2552021-07-21021 July 2021 Issuance of Amendment Nos. 269 and 271 Technical Specification Changes to Implement New Surveillance Methods for Transient Heat Flux Hot Channel Factor ML20363A1762021-02-23023 February 2021 Issuance of Amendment Nos. 268 and 270 Regarding Tornado Missile Protection Licensing Basis ML20241A0582020-09-25025 September 2020 Issuance of Amendment No. 267 for One-Time Extension of License Condition 4.I, Containment Building Construction Truss (EPID L-2020-LLA-0180 (COVID-19)) ML20036F2612020-03-0404 March 2020 Approval of Relief Request 1-RR-13 and 2-RR-13 Regarding Extension of Inspection Interval for Point Beach Unit 1 and Unit 2 Reactor Pressure Vessel Welds from 10 to 20 Years ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19339H7472019-12-13013 December 2019 Approval of Relief Request 2-RR-17 Regarding Steam Generator Primary Nozzle Dissimilar Metal Welds Inspection Interval ML19064A9042019-04-25025 April 2019 Issuance of Amendments to Extend Containment Leakage Rate Test Frequency ML19052A5442019-03-27027 March 2019 Issuance of Amendments 264 and 267 to Adopt TSTF-547, Clarification of Rod Position Requirements ML18289A3782018-11-26026 November 2018 Issuance of Amendments to Adopt Title 10 of Code of Federal Regulations 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18079A0452018-06-13013 June 2018 Issuance of Amendments Revision to the Point Beach Nuclear Plant Emergency Action Level Scheme (CAC Nos. MF9859 and MF9860 EPID L-2017-LLS-0278) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML17159A7782017-07-27027 July 2017 Issuance of Amendment to Approve H*: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17039A3002017-02-22022 February 2017 Issuance of Amendments -Removal of Completed License Conditions and Changes to the Ventilation Filter Testing Program ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16241A0002016-09-23023 September 2016 Mitigating Strategies and Spent Fuel Pool Instrumentation Safety Evaluation ML16196A0932016-09-0808 September 2016 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48 (C) ML16118A1542016-06-17017 June 2016 Issuance of Amendments ML16063A0582016-03-22022 March 2016 Approval of Relief Request 2-RR-11; Steam Generator Nozzle to Safe-End Dissimilar Metal (DM) Weld Inspection ML16035A5092016-03-0909 March 2016 Correction of Typographical Error in Safety Evaluation Associated with License Amendment Nos. 238 and 242 ML15293A4572015-11-25025 November 2015 Issuance of Amendments for the Steam Generator Technical Specifications, to Reflect Adoption of TSTF-510 ML15246A3052015-09-16016 September 2015 Evaluation of Relief Request RR-10 - Examination of Feedwater Nozzle Extension to Nozzle Weld Fifth 10-Year Inservice Program Interval ML15195A2012015-07-28028 July 2015 Issuance of Amendments Regarding Relocation of Surveillance Frequencies to Licensee Control ML15155A5392015-07-14014 July 2015 Issuance of Amendments Concerning Extension of Cyber Security Plan Milestone 8 ML15161A5352015-06-24024 June 2015 Relief Request VR-01; Alternatives to Certain Inservice Testing Requirements of the American Society of Mechanical Engineers (ASME) Code of Operation and Maintenance of Nuclear Power Plants ML15127A2912015-05-20020 May 2015 Relief Request RR-8, Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Examination of Buried Components ML15099A0182015-05-0707 May 2015 Relief Request RR-9, Proposed Alternative from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for System Leakage Test ML15014A2492015-01-27027 January 2015 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008-01, Managing Gas Accumulation (Tac Nos. MF4353 and MF4354) ML14343A0512014-12-10010 December 2014 Relief from the Requirements of the ASME Code for Re-Examination of the Reactor Pressure Vessel a Inlet Nozzle Weld for the Fifth Ten-Year Inservice Inspection Program Interval ML14293A0022014-10-21021 October 2014 Issuance of Safety Evaluation Regarding Relief Request RR-5 ML14126A3782014-06-30030 June 2014 Issuance of License Amendment Nos. 250 and 254 Regarding Change to Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report ML14058B0292014-05-0909 May 2014 Issuance of Amendment Nos. 249 and 253 Regarding Use of Optimized Zirlo Fuel Cladding Material ML14014A2052014-01-30030 January 2014 Issuance of Relief Request Regarding Risk-Informed Inservice Inspection Program for the Fifth 10-Year Inservice Inspection Interval ML13329A0422013-12-20020 December 2013 Relief from the Requirements of ASME Code, Section XI, for the Fourth 10-Year Inservice Inspection Interval (RR-4L3) ML13329A0312013-12-20020 December 2013 Relief from the Requirements of ASME B&PV Code, Section XI, for the Fourth 10-Year ISI Interval (RR-4L1) ML13346A0402013-12-18018 December 2013 Relief from the Requirements of ASME Code, Section XI, for the Fourth 10-Year Inservice Inspection Interval (RR-4L2) 2024-07-24
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March 21, 2002 Mr. Mark E. Warner Site Vice President Kewaunee and Point Beach Nuclear Plants Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 2 - RELIEF REQUEST RR-2-31 REGARDING SURFACE EXAMINATION OF THE REACTOR VESSEL CLOSURE STUDS (TAC NO. MB4063)
Dear Mr. Warner:
By letter dated September 19, 2001, Nuclear Management Company, LLC (the licensee) submitted Relief Request RR-2-31 for Point Beach Nuclear Plant (PBNP), Unit 2.
Relief Request RR-2-31, which was submitted pursuant to 10 CFR 50.55a(a)(3)(i), proposes to use the requirements of Performance Demonstration Initiative and Supplement 8 of Appendix VIII of the American Society of Mechanical Engineers (ASME) Code,Section XI, 1995 edition with addenda through 1996, as an alternative to the surface examination requirement for reactor pressure vessel closure studs in ASME Code,Section XI, Table IWB-2500-1, Code Category B-G-1, Item B6.30.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the proposed alternative, and has concluded that the use of Performance Demonstration Initiative and Supplement 8 of Appendix VIII of the 1995 edition of ASME Code,Section XI, with addenda through 1996, with the volumetric examination requirements provides an acceptable level of quality and safety for examination of the RPV closure studs. Therefore, the licensees proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for the remainder of the third ISI interval at PBNP, Unit 2.
Further details on the bases for the NRC staffs conclusions are contained in the enclosed safety evaluation. If you have any questions regarding this issue, please contact John G. Lamb, the Project Manager, at 301-415-1446.
Sincerely,
/RA/
William D. Reckley, Acting Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-301
Enclosure:
Safety Evaluation cc w/encl: See next page
ML020600076 Point Beach Nuclear Plant, Units 1 and 2 cc:
Mr. John H. ONeill, Jr. Ms. Sarah Jenkins Shaw, Pittman, Potts & Trowbridge Electric Division 2300 N Street, NW Public Service Commission of Wisconsin Washington, DC 20037-1128 P.O. Box 7854 Madison, WI 53707-7854 Mr. Richard R. Grigg President and Chief Operating Officer Mr. Roy A. Anderson Wisconsin Electric Power Company Executive Vice President and 231 West Michigan Street Chief Nuclear Officer Milwaukee, WI 53201 Nuclear Management Company, LLC 700 First Street Site Licensing Manager Hudson, WI 54016 Point Beach Nuclear Plant Nuclear Management Company, LLC Nuclear Asset Manager 6610 Nuclear Road Wisconsin Electric Power Company Two Rivers, WI 54241 231 West Michigan Street Milwaukee, WI 53201 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, WI 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241 May 2001
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE THIRD INSERVICE INSPECTION INTERVAL RELIEF REQUEST RR-2-31 NUCLEAR MANAGEMENT COMPANY, LLC POINT BEACH NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-301
1.0 INTRODUCTION
Inservice inspection (ISI) of the American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components is to be performed in accordance with the ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWB-2500-1, Examination Category B-G-1, Item B6.30 and applicable addenda as required by Code of Federal Regulations (10 CFR),
Section 50.55a(g), except where specific written relief has been granted by the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.55a(6)(g)(i). The regulation at 10 CFR 50.55a(a)(3) states that alternatives to the requirements of 10 CFR 50.55a(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 Inspection of Nuclear Power Plant Components, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that 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, which were incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. For Point Beach Nuclear Plant (PBNP), Unit 2, the applicable edition of Section XI of the ASME Code for the third 10-year ISI interval is the 1986 edition.
By letter dated September 19, 2001, Nuclear Management Company, LLC (the licensee),
submitted Relief Request RR-2-31, which requested relief from certain ASME Code,Section XI, ISI requirements. The information provided by the licensee in support of the request for relief has been evaluated and the basis for disposition is documented below.
ENCLOSURE
2.0 EVALUATION 2.1 Relief Request RR-2-31 Pursuant to 10 CFR 50.55a(a)(3)(i), the licensee requests relief from the requirements of Examination Category B-G-1, Item B6.30, as specified in the 1986 edition of ASME Code,Section XI.
2.2 Components for Which Relief is Requested Reactor pressure vessel (RPV) closure head studs.
2.3 ASME Code Requirement from Which Relief is Requested ASME Code,Section XI, 1986 edition, Table IWB-2500-1, Examination Category B-G-1, Pressure Retaining Bolting, Greater than 2 inches in Diameter, Item B6.30, "RPV closure head studs," which requires surface and volumetric examinations of all RPV closure head studs each interval.
2.4 Content of the Relief Request Relief is requested to perform only a volumetric examination of the RPV closure head studs in lieu of conducting both the surface and the volumetric examinations as required by the 1986 edition of ASME Code,Section XI, Table IWB-2500-1, Code Category B-G-1, Item B6.30.
2.5 Basis for Requesting Relief and Justification for Granting Relief The licensee states that 16 of the 48 studs at PBNP, Unit 2, have already been examined using surface techniques for the third 10-Year interval. The surface examinations of these studs have revealed only man-made indications, which were either scratches or dents, probably caused by handling. The surface examinations have not found any other type of indication.
2.6 Proposed Alternative Examination The licensee proposes to use the alternative requirements of a volumetric examination of the RPV closure head studs utilizing personnel and procedures qualified in accordance with the Performance Demonstration Initiative (PDI), and Supplement 8 of Appendix VIII of ASME Code,Section XI, with 1995 addenda through 1996. This alternative matches the proposed rule change to 10 CFR 50.55a dated August 3, 2001, that adopted ASME Code,Section XI, 1998 edition with addenda through 2000, and would be in compliance with all current rules for volumetric examination.
2.7 NRC Staff Evaluation The examination for RPV closure head studs require surface and volumetric examinations in accordance with the applicable Code (1986 edition of the ASME Code,Section XI). However, the licensee proposes to perform only the volumetric examination using an ultrasonic testing (UT) technique. In the case of the reactor vessel stud, a stress concentration occurs at the root of the thread and is, therefore, the most likely site for initiation of a crack which eventually will
propagate into the stud volume. During scanning of the stud from the ends, a circumferential crack emanating from the thread root will offer a large reflective surface to bounce back sound waves and is easily detectable with UT as a planar reflector. If scanning is done from the center hole of the stud, the crack tip will produce a reflection that lies between reflections from the inside surface and that of the thread root and is, therefore, detectable.
Demonstrated through procedure and performance qualification according the criteria of Supplement 8 to Appendix VIII of ASME Code,Section XI, the UT technique is designed to find cracks and other reflectors in a stud. The demonstration requires the detection of flaws located at the minimum and maximum metal path. The demonstration establishes personnel and procedures capabilities in reliability detecting cracks.
The licensee seeks relief from performing a surface examination which is required in addition to the volumetric examination. The NRC staff believes that both volumetric and surface examination methods are equally sensitive in the detection of cracks originating from the thread root. The performance of a surface examination in addition to a volumetric examination for this application is redundant. Therefore, the elimination of the surface examination will not reduce examination effectiveness and the sole use of a UT examination will provide an acceptable level of quality and safety.
2.8 NRC Staff Conclusion
Based on the above evaluation, the NRC staff concludes that the use of a volumetric examination of the RPV closure head studs utilizing personnel and procedures qualified in accordance with the PDI, and Supplement 8 of Appendix VIII of ASME Code,Section XI, 1995 edition with addenda through 1996, provides an acceptable level of quality and safety for examination of the RPV closure head studs. Therefore, the licensees proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for the third ISI interval at PBNP, Unit 2.
3.0 CONCLUSION
The NRC staff has concluded, based on the considerations discussed above, that there is reasonable assurance that the health and safety of the public will not be endangered by implementation of the proposed alternatives, and that such activities will be conducted in compliance with the Commission's regulations.
Principal Contributors: P. Patnaik J. Lamb Date: March 21, 2002