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Category:Code Relief or Alternative
MONTHYEARML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML21299A0032021-10-28028 October 2021 and Waterford Steam Electric Station, Unit 3 - Approval of Request for Alternative EN-20-RR-003 from Certain Requirements of the ASME Code ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20099D9552020-04-17017 April 2020 Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19135A4442019-06-21021 June 2019 Issuance of Relief Request I4R-22 Relief from the Requirements of the ASME Code ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019 Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds JAFP-18-0076, End of Interval Relief Request Associated with the Fourth Ten-Year Lnservice Inspection (ISI) Interval2018-07-26026 July 2018 End of Interval Relief Request Associated with the Fourth Ten-Year Lnservice Inspection (ISI) Interval ML18039A8542018-05-30030 May 2018 Relief Requests I5R-02, I5R-03, I5R-04 from ASME Code Requirements for Reactor Vessel Internals, Ferretic Piping Repair/Replacement, and RPV Flange Welds, 5th 10-Year Inservice Inspection Interval (MG0116-MG0118; L-2017-LLR-0083 to 0085) JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018 Proposed Alternative to Utilize Code Cases N-878 and N-880 JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 ML18044A9932018-04-13013 April 2018 Request for Alternatives PRR-01, PRR-02, PRR-04, VRR-02, VRR-03, and VRR-04 from ASME OM Code Requirements for Various Pumps and Valves, Fifth 10-Year Inservice Testing Interval (CAC MG0052-MG0061; EPID L-2017-LLR-0067 to L-2017-LLR-0074) ML17289A0752017-12-12012 December 2017 Issuance of Relief Request for Proposed Alternative to Use ASME Code Case N-789-1 (CAC No. MF9692; EPID L-2017-LLR-0027) Note Correction Safety Evaluation See ML18003B382 ML17219A4282017-12-11011 December 2017 Issuance of Relief Request-Alternative to Certain Requirements of the ASME Code Regarding Use of ASME Code Case N-513-4 (CAC No. MF9641; EPID L-2017-LLR-0023) ML17223A2802017-08-10010 August 2017 Submittal of Relief Requests Associated with the Fifth Lnservice Inspection (ISI) Interval ML17090A1682017-04-12012 April 2017 Alternative to ASME Code Requirements for Weld Overlay Repair ML16355A4292017-01-0606 January 2017 Relief Request for Proposed Alternative for the Implementation of BWRVIP-05 ML16334A4402016-12-0606 December 2016 Relief from the Requirements of the ASME Code Case N-702 and BWRVIP-241 for Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii ML16270A0462016-10-0303 October 2016 Acceptance of Requested Licensing Action Relief Request for Proposed Alternative for the Implementation of BWRVIP-05 ML16253A3412016-09-14014 September 2016 Acceptance of Requested Licensing Action Relief Request for Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-241 ML16180A2892016-06-29029 June 2016 Inservice Inspection Program Alternative for Safety Relief Valves ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16077A3522016-03-22022 March 2016 Withdrawal of Relief Request No. 19 from the Fourth Inservice Inspection Interval JAFP-15-0122, Withdrawal of Application for Alternative Examination Requirements for James A. FitzPatrick Nuclear Power Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-2412015-11-20020 November 2015 Withdrawal of Application for Alternative Examination Requirements for James A. FitzPatrick Nuclear Power Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-241 ML15230A3502015-08-18018 August 2015 J.A Fitzpatrick Nuclear Power Plant - Requests Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1), Implementation of BWRVIP-05 (GL 98-05) CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015 Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division ML12279A2482012-10-17017 October 2012 Issuance of Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code JAFP-11-0112, Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP2011-10-0303 October 2011 Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP ML0803902232008-03-13013 March 2008 Relief Request No. 5, Use of Performance Demonstration Initiative in Lieu of ASME Code Section XI, Appendix Viii, Supplement 11 Requirement ML0803003072008-02-28028 February 2008 Relief Request No. RR-6, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals Components Inspection ML0803700802008-02-25025 February 2008 Relief Request No. 2 (RR-2) from the Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Appendix Viii, Supplement 10 ML0804204272008-02-22022 February 2008 Relief Request No. 3 (RR-3) Risk-Informed Inservice Inservice Inspection Program ML0520700472005-08-0909 August 2005 Relief Request for Temporary Non-Code Repair of a Shutdown Cooling Pipe JAFP-05-0105, Request for Approval of Relief Request No. RR-38, Proposed Alternative to Perform a Temporary Non-Code Repair in Accordance with 10 CFR 50.55a(a)(3)(ii)2005-07-0909 July 2005 Request for Approval of Relief Request No. RR-38, Proposed Alternative to Perform a Temporary Non-Code Repair in Accordance with 10 CFR 50.55a(a)(3)(ii) ML0427406642004-10-14014 October 2004 Relief Request Nos. R-33, R-71, R 3-40(A) and R-41, James A. FitzPatrick Nuclear Power Plant, Indian Point Nuclear Generating Unit Nos. 2 and No. 3 and Pilgrim Nuclear Power Station ML0420301572004-07-20020 July 2004 Relief, Relief Request No. 30 for Third 10-Year Inservice Inspection (ISI) Program Interval ML0410700882004-07-0606 July 2004 Relief Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-600 ML0417401842004-07-0606 July 2004 Relief Request, Nos. RR-34 and PRR for the Third 10-Year Inservice Inspection (ISI) Interval, MC1999 and MC2006 ML0405406932004-04-12012 April 2004 Relief Request Review, Relief Request VRR-08 Related to the Third 10-Year Inservice Testing (IST) Ubtervak JPN-03-020, Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-6002003-08-11011 August 2003 Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-600 JAFP-03-0111, Proposed Alternatives in Accordance with 10CFR50.55a(g)(6)(ii)(A)(5) and Relief from ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds Pursuant to 10 CFR 50.55a (g)(6)(i)2003-08-0404 August 2003 Proposed Alternatives in Accordance with 10CFR50.55a(g)(6)(ii)(A)(5) and Relief from ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds Pursuant to 10 CFR 50.55a (g)(6)(i) ML0306502552003-04-0101 April 2003 Relief Request Review, Third 10-Year Pump and Valve Inservice Testing Program, Revision of Relief Request VRR-04 ML0231804962002-11-14014 November 2002 Relief, Request for Relief No. RR-28 for the Third 10-Year Inservice Inspection Interval Program Plan for the FitzPatrick Power Plant JAFP-02-0194, Proposed Revision of Relief Request VRR-06 for In-Service Testing Program2002-09-30030 September 2002 Proposed Revision of Relief Request VRR-06 for In-Service Testing Program JPN-02-011, Request for Relief RR-29, Third 10-Year Inservice Inspection Interval Program Plan2002-05-0808 May 2002 Request for Relief RR-29, Third 10-Year Inservice Inspection Interval Program Plan JPN-02-010, Relief Request RR-28, Revision 1 for the Third 10-Year Inservice Inspection Interval Program Plan2002-05-0808 May 2002 Relief Request RR-28, Revision 1 for the Third 10-Year Inservice Inspection Interval Program Plan 2023-12-14
[Table view] Category:Letter
MONTHYEARIR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 ML24037A0102024-02-0606 February 2024 Requalification Program Inspection ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML24004A2302024-01-0808 January 2024 Project Manager Reassignment ML23356A0832024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0058 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines JAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) RS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis IR 05000333/20230052023-08-31031 August 2023 Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005) JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report ML23228A1342023-08-16016 August 2023 Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20230022023-08-0707 August 2023 Integrated Inspection Report 05000333/2023002 RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance ML23208A1622023-07-27027 July 2023 Operator Licensing Examination Approval IR 05000333/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000333/2023402 IR 05000333/20230112023-07-25025 July 2023 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000333/2023011 IR 05000333/20235012023-07-20020 July 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2023501 JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation IR 05000333/20234202023-06-26026 June 2023 Security Baseline Inspection Report 05000333 2023420 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23164A0322023-06-13013 June 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000333/2023010 ML23152A0042023-06-0101 June 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000333/2023401 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report IR 05000333/20230012023-05-0303 May 2023 Integrated Inspection Report 05000333/2023001 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report IR 05000333/20230122023-04-13013 April 2023 Quadrennial Fire Protection Inspection Report 05000333/2023012 ML23095A3722023-04-0505 April 2023 2023 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations IR 05000333/20220042023-03-20020 March 2023 Integrated Inspection Report 05000333/2022004 JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 2024-02-07
[Table view] Category:Safety Evaluation
MONTHYEARML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML22223A1412022-09-0101 September 2022 Issuance of Amendment No. 353 Adoption of TSTF - 505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22196A0612022-08-23023 August 2022 Issuance of Amendment No. 352 Adoption of 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22166A4302022-07-15015 July 2022 Issuance of Amendment No. 351 Removal of Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation ML22126A1962022-05-27027 May 2022 Issuance of Amendment No. 350 Adoption of TSTF-264, Revision 0 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML21364A0432022-02-28028 February 2022 Issuance of Amendment No. 348 Revising Surveillance Requirement 3.5.1.6 Involving Recirculation Pump Discharge Valves ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21300A3552021-11-16016 November 2021 Issuance of Amendment No. 345 Adoption of TSTF-582 ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21131A1272021-08-0909 August 2021 Issuance of Amendment No. 343 Modifications to Technical Specification 3.6.1.3, Primary Containment Isolation Valves (Pcivs) ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21162A0422021-06-14014 June 2021 Issuance of Amendment No. 342, One Time Extension of Completion Times to Support Residual Heat Removal Pump Motor Replacement (Emergency Circumstances) ML21049A3552021-04-28028 April 2021 Issuance of Amendment No. 341 Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20169A5102020-08-20020 August 2020 Issuance of Amendment No. 339 Changes to Technical Specifications Related to Primary Containment Hydrodynamic Loads ML20140A0702020-07-21021 July 2020 Issuance of Amendment No. 338 Application of Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20094G9032020-06-0202 June 2020 Issuance of Amendment No. 335 Adoption of TSTF-372, Addition of LCO 3.0.8, 'Inoperability of Snubbers' ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20024C6612020-03-0202 March 2020 Issuance of Amendment No. 332 Adopt TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line Item Improvement Process ML19295G7832019-12-19019 December 2019 Issuance of Amendment No. 331 Regarding Change to Technical Specifications to Remove Ultimate Heat Sink Bar Rack Heaters ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19189A0842019-08-19019 August 2019 Issuance of Amendment No. 326 Adoption of TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19157A2032019-07-11011 July 2019 Issuance of Amendment No. 325 Reactivity Anomalies Surveillance ML19135A4442019-06-21021 June 2019 Issuance of Relief Request I4R-22 Relief from the Requirements of the ASME Code ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML18360A6352019-02-25025 February 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4464; EPID No. L-2014-JLD-0049) ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18289A4322018-11-28028 November 2018 Issuance of Amendment No. 323 Revision to the Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 ML18214A7062018-09-19019 September 2018 Issuance of Amendment No. 322, Revise Technical Specification 2.1.1, Reactor Core Sls, to Change Cycle 24 Safety Limit Minimum Critical Power Ratio Numeric Values ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18180A3722018-07-19019 July 2018 Issuance of Amendment No. 319, Revise Technical Specification Surveillance Requirement 3.6.4.1.3 to Allow Opening of Inner and Outer Secondary Containment Access Openings (CAC MG0239; EPID L-2017-LLA-0298) ML18039A8542018-05-30030 May 2018 Relief Requests I5R-02, I5R-03, I5R-04 from ASME Code Requirements for Reactor Vessel Internals, Ferretic Piping Repair/Replacement, and RPV Flange Welds, 5th 10-Year Inservice Inspection Interval (MG0116-MG0118; L-2017-LLR-0083 to 0085) ML18044A9932018-04-13013 April 2018 Request for Alternatives PRR-01, PRR-02, PRR-04, VRR-02, VRR-03, and VRR-04 from ASME OM Code Requirements for Various Pumps and Valves, Fifth 10-Year Inservice Testing Interval (CAC MG0052-MG0061; EPID L-2017-LLR-0067 to L-2017-LLR-0074) ML17289A1752018-03-26026 March 2018 Issuance of Amendment No. 318, Revise Emergency Plan for Emergency Response Organization Requalification Training Frequency Consistent with Exelon Fleet (CAC MG0026; EPID L-2017-LLA-0273) ML18003B3822018-01-0303 January 2018 Correction to the Safety Evaluation to James A. Fitzpatrick Nuclear Power Plant Issuance of Relief Request for Proposed Alternative to Use ASME Code Case N-789-1 (CAC No. MF9692; EPID L-2017-LLR-0027) (Original Safety Evaluation: ML17289A07 ML17342A0062017-12-18018 December 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17289A0752017-12-12012 December 2017 Issuance of Relief Request for Proposed Alternative to Use ASME Code Case N-789-1 (CAC No. MF9692; EPID L-2017-LLR-0027) Note Correction Safety Evaluation See ML18003B382 2023-05-01
[Table view] |
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February 28, 2008 Vice President, Operations Entergy Nuclear Operations, Inc James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - RELIEF REQUEST NO. RR-6, IMPLEMENTATION OF BWRVIP GUIDELINES IN LIEU OF ASME CODE, SECTION XI REQUIREMENTS ON REACTOR VESSEL INTERNALS COMPONENTS INSPECTION (TAC NO. MD4758)
Dear Sir or Madam:
By letter dated February 27, 2007, as supplemented by letters dated August 20, 2007 and December 4, 2007, Entergy Nuclear Operations, Inc. (Entergy or the licensee) submitted Relief Request No. RR-6 for James A. FitzPatrick Nuclear Power Plant (JAFNPP). The licensees submittal proposed to use various Boiling Water Reactor Vessel and Internals Project (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for inservice inspection (ISI) of reactor vessel internal components. The request was made pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(a)(3)(i).
As documented in the enclosed safety evaluation (SE), the Nuclear Regulatory Commission (NRC) staff reviewed your submittal and concluded that, with the exception of the proposed uses of BWRVIP-41, Revision 1 and BWRVIP-138, the proposed alternative to the ASME Code requirements is acceptable. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), relief is authorized for the fourth 10-year interval ISI program.
If you have any questions regarding this matter, please contact Adrian Muniz at 301-415-4093.
Sincerely,
/RA/
Mark G. Kowal, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
As stated cc w/encl: See next page
February 28, 2008 Vice President, Operations Entergy Nuclear Operations, Inc James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - RELIEF REQUEST NO. RR-6, IMPLEMENTATION OF BWRVIP GUIDELINES IN LIEU OF ASME CODE, SECTION XI REQUIREMENTS ON REACTOR VESSEL INTERNALS COMPONENTS INSPECTION (TAC NO. MD4758)
Dear Sir or Madam:
By letter dated February 27, 2007, as supplemented by letters dated August 20, 2007 and December 4, 2007, Entergy Nuclear Operations, Inc. (Entergy or the licensee) submitted Relief Request No. RR-6 for James A. FitzPatrick Nuclear Power Plant (JAFNPP). The licensees submittal proposed to use various Boiling Water Reactor Vessel and Internals Project (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for inservice inspection (ISI) of reactor vessel internal components. The request was made pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(a)(3)(i).
As documented in the enclosed safety evaluation (SE), the Nuclear Regulatory Commission (NRC) staff reviewed your submittal and concluded that, with the exception of the proposed uses of BWRVIP-41, Revision 1 and BWRVIP-138, the proposed alternative to the ASME Code requirements is acceptable. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), relief is authorized for the fourth 10-year interval ISI program.
If you have any questions regarding this matter, please contact Adrian Muniz at 301-415-4093.
Sincerely,
/RA/
Mark G. Kowal, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
As stated cc w/encl: See next page Distribution:
PUBLIC GCheruvenki RidsNrrLASLittle RidsNrrPMAMuniz LPL 1-1 Reading RidsNrrDciCvib RidsNrrPMJBoska RidsOGCMailCenter RidsAcrsAcnw&mMailCenter RidsNrrDorlLpla Accession Number: ML080300307 *With Comments OFFICE LPL3-1\PM LPL1-1/PM LPL1-1\LA CVIB/BC OGC LPL1-1\BC NAME AMuniz JBoska SLittle MMitchell JAdler NLO MKowal DATE 2/13/08 2/25/08 2/27/08*
Official Record Copy
FitzPatrick Nuclear Power Plant cc:
Senior Vice President Mr. Paul Tonko Entergy Nuclear Operations, Inc. President and CEO P.O. Box 31995 New York State Energy, Research, and Jackson, MS 39286-1995 Development Authority 17 Columbia Circle Vice President Oversight Albany, NY 12203-6399 Entergy Nuclear Operations, Inc.
P.O. Box 31995 Mr. John P. Spath Jackson, MS 39286-1995 New York State Energy, Research, and Development Authority Senior Manager, Nuclear Safety & Licensing 17 Columbia Circle Entergy Nuclear Operations, Inc. Albany, NY 12203-6399 P.O. Box 31995 Jackson, MS 39286-1995 Mr. Paul Eddy New York State Dept. of Public Service Senior Vice President and COO 3 Empire State Plaza Entergy Nuclear Operations, Inc. Albany, NY 12223-1350 440 Hamilton Avenue White Plains, NY 10601 Oswego County Administrator Mr. Steven Lyman Assistant General Counsel 46 East Bridge Street Entergy Nuclear Operations, Inc. Oswego, NY 13126 440 Hamilton Avenue White Plains, NY 10601 Supervisor Town of Scriba Manager, Licensing Route 8, Box 382 Entergy Nuclear Operations, Inc. Oswego, NY 13126 James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Mr. James H. Sniezek Lycoming, NY 13093 BWR SRC Consultant 5486 Nithsdale Drive Regional Administrator, Region I Salisbury, MD 21801-2490 U.S. Nuclear Regulatory Commission 475 Allendale Road Mr. Michael D. Lyster King of Prussia, PA 19406 BWR SRC Consultant 5931 Barclay Lane Resident Inspector's Office Naples, FL 34110-7306 James A. FitzPatrick Nuclear Power Plant U. S. Nuclear Regulatory Commission Mr. John Doering P.O. Box 136 BWR SRC Consultant Lycoming, NY 13093 P.O. Box 189 Parker Ford, PA 19457 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RELIEF REQUEST NO. RR-6 FOR THE FOURTH 10-YEAR INTERVAL OF THE INSERVICE INSPECTION PROGRAM ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
1.0 INTRODUCTION
By letter dated February 27, 2007, as supplemented by letters dated August 20, 2007, and December 4, 2007, Entergy Nuclear Operations, Inc. (Entergy or the licensee) submitted its fourth 10-year interval inservice inspection (ISI) program plan Request for Relief No. RR-6 for James A. FitzPatrick Nuclear Power Plant (JAFNPP). The licensees submittal proposes to use various Boiling Water Reactor Vessel and Internals Project (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for ISI of reactor vessel internal (RVI) components.
2.0 REGULATORY REQUIREMENTS ISI of ASME Code Class 1, 2, and 3 components is performed in accordance with Section XI of the ASME Code as required by Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g),
except where specific relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). 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: (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 pre-service examination requirements, set forth in the ASME Code,Section XI, "Rules for ISI 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 incorporated by reference in 10 CFR 50.55a(b),
Enclosure
twelve months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable ASME Code of record for the fourth 10-year ISI interval for JAFNPP is the 2001 Edition with 2003 Addenda of the ASME Code,Section XI.
3.0 TECHNICAL EVALUATION
3.1 Components for Which Relief is Requested ASME Code,Section XI, Class 1, Examination Categories B-N-1 and B-N-2.
Code item Numbers:
B13.10, Vessel Interior B13.20, Interior Attachments within Beltline Region B13.30, Interior Attachments beyond Beltline Region B13.40, Core Support Structures 3.2 Examination Requirements from which Relief is Requested ASME Code, Section Xl requires the visual examination (VT) of certain RVI components. These examinations are included in Table IWB-2500-1, Categories B-N-1 and B-N-2, and identified with the following item numbers:
- B13.10 - Examine accessible areas of the RV interior each period using a technique which meets the requirements for a VT-3 examination, as defined in paragraph IWA-2213 of the ASME Code,Section XI.
- B13.20 - Examine interior attachment welds within the beltline region each interval using a technique which meets the requirements for a VT-1 examination as defined in paragraph IWA-2211 of the ASME Code,Section XI.
- B13.30 - Examine interior attachment welds beyond the beltline region each interval using a technique which meets the requirements for a VT-3 examination, as defined in paragraph IWA-2213 of the ASME Code,Section XI.
- B13.40 - Examine surfaces of the core support structure each interval using a technique which meets the requirements for a VT-3 examination, as defined in paragraph IWA-2213 of the ASME Code,Section XI.
These examinations are performed to assess the structural integrity of the RVI components.
3.3 Applicable ASME Code Edition and Addenda The ASME Code of Record for the fourth 10-year ISI interval for JAFNPP is the 2001 Edition with 2003 Addenda, of ASME Code,Section XI.
3.4 Licensees Basis The licensee concluded that the alternative inspections (described below) will maintain an adequate level of quality and safety of the affected welds and will not adversely impact the health and safety of the public. As part of its justification for the relief, the licensee stated that boiling-water reactors (BWRs) now examine RVI components in accordance with BWRVIP guidelines. These guidelines have been written to address the examination of safety significant RVI components using appropriate methods and reexamination frequencies. The licensee also noted that the NRC has agreed with the BWRVIP approach, in principle, and has issued safety evaluations (SEs) for these guidelines. [Note: in principle means that, for some reports, final SE reports have been written, but the final BWRVIP acceptance reports which incorporate these SEs for some of the reports may not have been issued]. Relief from examinations in Table IWB-2500-1 of the ASME Code are requested pursuant to 10 CFR 50.55a(a)(3)(i).
3.5 Alternative Examination In lieu of the requirements of the 2001 Edition with 2003 Addenda of the ASME Code, Section Xl, the licensee proposed to examine the RVI components in accordance with BWRVIP Guideline requirements. The licensee stated that the particular guidelines that are applicable to the various RVI components are:
- BWRVIP-41, Revision 1, BWRVIP Jet Pump Assembly Inspection and Flaw Evaluation Guidelines
- BWRVIP-47-A, BWR Lower Plenum Inspection and Flaw Evaluation Guidelines
- BWRVIP-48-A, Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines
- BWRVIP-76, BWR Core Shroud Inspection and Flaw Evaluation Guidelines
- BWRVIP-138, BWRVIP Updated Jet Pump Beam Inspection and Flaw Evaluation Guidelines The licensee made a commitment to incorporate the requirements of the BWRVIP-94 Report, "Program Implementation Guideline," at JAFNPP. The BWRVIP-94 Report states that where guidance in existing BWRVIP documents has been supplemented or revised by subsequent correspondence approved by the BWRVIP Executive Committee, the most current approved guidance will be implemented.
In addition to the BWRVIP reports noted above, the licensee identified NUREG-0619 BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking, as the basis for its proposed alternative examinations for the feedwater sparger tee welds and the feedwater sparger piping and brackets.
The licensee, in its submittal dated February, 27, 2007, provided a comparison of the required ASME Code,Section XI Category B-N-1 and B-N-2 examination requirements with the above current BWRVIP Guideline requirements that are applicable to JAFNPP. In response to the NRC staffs request for additional information (RAI) (2B), by licensee letter dated August 20, 2007, the licensee provided RVI component inspection histories including results from the last inspections performed during the most recent refueling outage (RO17, October 2006). Furthermore, the licensee identified the applicable inspection program for the RVI components and the total number of welds in each of the RVI components. The licensee, as an example, provided additional information regarding the BWRVIP inspection requirements for the following welds of the RVI components and their subcomponents representing each of the aforementioned ASME Code,Section XI category/item numbers (Item Numbers B13.10, B13.20, B13.30, and B13.40).
- Vessel Attachment Welds (e.g., steam dryer hold-down brackets, guide rod brackets, and surveillance specimen holders The licensee claimed that these examples demonstrated that the inspection techniques that are recommended by the BWRVIP inspection guidelines are superior to the inspection techniques mandated by the ASME Code,Section XI ISI program. Additionally, these examples proved that the BWRVIP inspection guidelines require more frequent inspections of the RVI components than the corresponding ASME Code,Section XI ISI program. The licensee claimed that by implementing the BWRVIP inspection guidelines the aging degradation of the RVI components can be identified in a timely manner so that proper corrective action can be taken to restore the integrity of the applicable RVI component. Therefore, the licensee concluded that implementation of the BWRVIP inspection guidelines for the JAFNPPs RVI components would provide an acceptable level of quality and safety. The licensees proposed alternative for the RVI components and subcomponents covered under the scope of this Relief Request is summarized in the Attachment to this SE.
3.6 NRC Staff Evaluation The NRC staff reviewed the information provided by the licensee in its submittal dated February 27, 2007, regarding its proposed alternatives to the ASME Code,Section XI ISI requirements and the technical bases for the licensees proposed alternatives. The NRC staff reviewed the status of each of the referenced BWRVIP guidance documents and the applicability of the information provided in NUREG-0619. The NRC staff found all of the referenced BWRVIP reports (with the exception of the BWRVIP-41, Revision 1 and BWRVIP-138 reports) to be acceptable, with any additional conditions associated with the implementation of the subject BWRVIP reports outlined in the corresponding NRC staff SE for that report. The NRC staff also confirmed the applicability of the information given in NUREG-0619 to supporting the licensees proposed alternative for the feedwater sparger tee welds and the feedwater sparger piping and brackets. The NRC staff did, however, identify some issues which required additional clarification by the licensee or which required the licensee to modify its proposed alternatives. The following paragraphs address the NRC staffs RAIs, the licensees responses, and the NRC staffs evaluation of the RAIs.
To ensure that the attachments in this relief request were properly identified, in the RAI letter dated August 1, 2007, the NRC staff requested that the licensee indicate attachment numbers 2, 3, 4, and 5 on relevant pages of the relief request. In a letter dated August 20, 2007, consistent with the NRC staffs request, the licensee revised the relevant pages. The NRC staff accepts the licensees revised version and, therefore, considers its concern resolved.
In RAI letter dated August 1, 2007, the NRC staff stated that Section 4.1, item 5 of the BWRVIP-100-A Report, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds, dated August 2006, indicates that fracture toughness values of stainless steel materials that are exposed to neutron fluence levels greater than 1 X 1021 n/cm2 (E > 1 MeV) are lower than those used in Appendix C of the BWRVIP-76 Report. The NRC staff requested that the applicant confirm that the planned inspections of the JAFNPP core shroud and/or core shroud repair hardware for the units fourth ISI interval are consistent with both BWRVIP-76 and BWRVIP-100-A reports. In a letter dated August 20, 2007, the licensee stated that for core shroud and core shroud repair hardware it will comply with the requirements specified in the BWRVIP-76 and BWRVIP-100-A reports. The NRC staff finds this response acceptable and, therefore, considers its concern resolved.
In Attachment 5 of the licensees response dated August 20, 2007, the licensee indicated that the core plate hold-down bolts will be inspected in accordance with the requirements specified in the ASME Code,Section XI ISI program during the fourth 10-year ISI interval. In the NRC staffs SE (ADAMS Accession Number ML072110136, dated July 31, 2007) for the JAFNPP license renewal application (LRA), the NRC staff accepted a licensee commitment (LRA Commitment #
- 23) in which it stated that one of the following options will be implemented 2 years prior to the license renewal period:
Option # 1 - Install core plate wedges Option # 2 - Complete plant-specific analysis per the BWRVIP-25 report to ensure maintenance of structural integrity of the core plate and provide inspection plan for the core plate hold-down bolts Based on the aforementioned commitment, the NRC staff determined that during the fourth 10-year ISI interval, the licensee will be implementing the ASME Code,Section XI ISI requirements up until 2 years prior to the license renewal period. At that time, the licensee will be using the inspection guidelines specified in the BWRVIP-25 report in lieu of the ASME Code,Section XI ISI requirements. In a conference call on October 2, 2007, the NRC staff discussed this issue with the licensee, and in its letter dated December 4, 2007, stated that it plans to perform VT-3 inspections of approximately 25 percent of the core plate hold-down bolts prior to implementing its LRA Commitment 23. The NRC staff finds this response acceptable because these inspections will provide information regarding the condition of the core plate hold-down bolts.
Additionally, implementation of LRA Commitment 23 during the fourth 10-year ISI interval will provide reasonable assurance that the radiation induced stress relaxation of the core plate hold-down bolts is adequately monitored during the fourth 10-year ISI interval and beyond.
Consistent with the determination that was made in the NRC staffs SEs which approved each of the cited BWRVIP reports (with the exception of the BWRVIP-41, Revision 1 and BWRVIP-138 reports), the BWRVIP inspection requirements (as supplemented by the NUREG-0619
requirements) incorporated into the licensees proposed alternative will identify aging degradation of the RVI components in a timely manner. Therefore, the NRC staff has concluded that the implementation of the inspection requirements specified in the licensees proposed alternative will ensure that the integrity of the RVI components will be maintained with an acceptable level of quality and safety.
By letter dated July 18, 2007, the EPRI BWRVIP withdrew the BWRVIP-41, Revision 1 and BWRVIP-138 reports from the NRC review process. Therefore, the licensees proposed alternative inspection requirements which rely on the technical bases established by the BWRVIP-41, Revision 1 and BWRVIP-138 are not authorized for the fourth ten-year interval.
The licensee shall follow the applicable ASME Code,Section XI requirements.
The NRC staff, however, notes that a subsequent relief request will be required if the licensee decides to take exceptions to, or deviations from, the NRC staff-approved BWRVIP inspection guidelines (specifically, those inspection requirements listed in the Attachment to this SE) or the ASME Code,Section XI ISI requirements in the future.
Therefore, based on the information in the licensees submittals dated February 27, 2007, August 20, 2007, and December 4, 2007, the NRC staff has confirmed that the licensees proposed alternatives (as documented in the Attachment to this SE) are consistent with the technical bases documented in NUREG-0619 and the BWRVIP Reports cited in Section 3.0 of this SE.
4.0 CONCLUSION
Based on the information provided in the licensee's submittal, the NRC staff concludes that the alternatives proposed in Request for Relief RR-6 (except for the proposed alternatives that rely on the technical bases established by the BWRVIP-41, Revision 1 and BWRVIP-138), and as summarized in the Attachment to this SE, will ensure that the integrity of the RVI components is maintained with an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the licensees proposed alternatives (except for the proposed alternatives that rely on the technical bases established by the BWRVIP-41, Revision 1 and BWRVIP-138), are authorized for the fourth 10-year inspection interval. All other requirements of the ASME Code,Section XI for which relief has not been specifically requested remain applicable, including third party review by the Authorized Nuclear Inservice Inspector. Any components that are not included in this relief request will continue to be inspected in accordance with the ASME Code,Section XI requirements.
Attachment:
Tables Principal Contributor: G. Cheruvenki Date: February 28, 2008
James A. FitzPatrick Comparison of ASME Category B-N-1 and B-N-2 Requirements With BWRVIP Guidance Requirements (1)
ASME Item No. Component ASME Exam ASME ASME Applicable BWRVIP BWRVI BWRVIP Frequency Table IWB-2500-1 Scope Exam Frequency BWRVIP Exam P Exam Document Scope B13.10 Reactor Vessel Interior Accessible VT-3 Each BWRVIP-18-A, 25, In accordance with applicable BWRVIP (Note 2) Areas period 26-A, 27-A, 38, document.
(Non- 47-A, 48-A, and 76.
specific)
B13.20 Interior Attachments Within Accessible VT-1 Each 10- BWRVIP-48-A Riser Brace EVT-1 100% in first 12 years Beltline - Jet Pump Riser Welds year Table 3-2 Attachment (with 50% to be Braces Interval inspected in the first 6 years); 25% during each subsequent 6 years Lower Surveillance BWRVIP-48-A Bracket VT-1 Each 10-year Interval Specimen Holder Brackets Table 3-2 Attachment Attachment
ASME Item No. Component ASME Exam ASME ASME Applicable BWRVIP BWRVIP BWRVIP Frequency Table IWB-2500-1 Scope Exam Frequency BWRVIP Exam Exam Document Scope B13.30 Interior Attachments Beyond Accessible VT-3 Each 10- BWRVIP-48-A Bracket VT-3 Each 10-year Interval Beltline - Steam Dryer Hold- Welds year Table 3-2 Attachment down Brackets Interval Guide Rod Brackets BWRVIP-48-A Bracket VT-3 Each 10-year Interval Table 3-2 Attachment Steam Dryer Support BWRVIP-48-A Bracket EVT-1 Each 10-year Interval Brackets Table 3-2 Attachment Feedwater Sparger Brackets BWRVIP-48-A Bracket EVT-1 Each 10-year Interval Table 3-2 Attachment Core Spray Piping Brackets BWRVIP-48-A Bracket EVT-1 Every 4 Refueling Table 3-2 Attachment Cycles Upper and Middle BWRVIP-48-A Bracket VT-3 Each 10-year Interval Surveillance Specimen Table 3-2 Attachment Holder Brackets Shroud Support (Weld H9) BWRVIP-38 Weld H9 EVT-1 or Maximum of 6 years 3.1.3.2, Figure UT for one sided EVT-1, 3-5 Maximum of 10 years for UT Weld H12 Not Applicable Not Not Not Applicable Applicable Applicable
ASME Item No. Component ASME Exam ASME ASME Applicable BWRVIP BWRVIP BWRVIP Frequency Table IWB-2500-1 Scope Exam Frequency BWRVIP Exam Scope Exam Document B13.40 Integrally Welded Core Accessible VT-3 Each 10- BWRVIP-38 Weld H9 EVT-1 or Maximum 6 years for Support Structure - Shroud Surfaces year 3.1.3.2, 3.2.1, and Gusset UT one-sided EVT-1, 10 Support Interval Figures 3-5 and Attachments years for UT 3-6 Shroud BWRVIP-76 Vertical and EVT-1 or Maximum 10 years Figures 3-3 and Top Guide UT (per designer 3-4 Ring recommendations)
Segment Welds BWRVIP-76 Tie-rod VT-3 All 10 tie rods within 3.5 and 3.6 Repair and 10 years EVT-1 Note (1) This Table provides only an overview of the requirements. For more details, refer to the ASME Code,Section XI, Table IWB-2500-1, and the appropriate BWRVIP document.
Note (2) Per New York Port Authority (NYPA) letter to NRC (JPN-97-013), Core Spray Internals Inspection, dated March 24, 1997, JAFNPP informed the NRC of a new commitment to perform Core Spray System piping and spargers inspections inside the RPV in accordance with the BWRVIP-18 guidelines.