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MONTHYEARML20262H0322020-09-18018 September 2020 Acceptance Email of Requested Licensing Actions Concerning Surveillance Frequency for Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114) Project stage: Other ML20358A2602020-12-28028 December 2020 Changes to Draft Request for Additional Information Regarding License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency Project stage: Draft RAI ML20365A0092020-12-30030 December 2020 Request for Additional Information Concerning Review of License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114) Project stage: RAI ML21049A0242021-02-23023 February 2021 Alternative Request to the Requirements of the ASME OM Code for the Testing Intervals for the Instrument-Line Flow Check Valves Project stage: Other 2020-12-30
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Category:Code Relief or Alternative
MONTHYEARML23354A0032024-01-19019 January 2024 Authorization and Safety Evaluation for Alternative Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations 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 ML23104A3472023-04-14014 April 2023 Verbal Authorization for Relief Request I5R-14, Proposed Alternative Associated with N2E Dissimilar Metal Weld Overlay Repair with Laminar Indication ML22339A0582022-12-21021 December 2022 Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) NMP2L2777, Relief Request Associated with Excess Flow Check Valves2021-09-0808 September 2021 Relief Request Associated with Excess Flow Check Valves 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 ML21140A1532021-06-0303 June 2021 Correction to April 22, 2021 Safety Evaluation for Requests for Alternative to the Inservice Testing Requirements of the ASME OM Code for the Fifth 10-Year Program Interval ML21105A3382021-04-22022 April 2021 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Concerning Examination Coverage of Certain Class 1 and 2 Component Welds ML21109A2162021-04-22022 April 2021 Proposed Alternative to Inservice Testing Requirements of the ASME OM Code for the Fifth 10-Year Interval ML21049A0242021-02-23023 February 2021 Alternative Request to the Requirements of the ASME OM Code for the Testing Intervals for the Instrument-Line Flow Check Valves ML20294A4242020-10-20020 October 2020 Acceptance of Requested Licensing Action Relief Requests CTNSP-PR-01 and CS-PR-01 (EPIDs L-2020-LLR-0136 and L-2020-LLR-0137) 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 ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) 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 RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi)2020-02-28028 February 2020 Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) ML20036D9622020-02-0404 February 2020 Dresden Nuclear Power Station, Nine Mile Point Nuclear Station, Peach Bottom Atomic Power Station, & Quad Cities Nuclear Power Station - Proposed Alternative to Extend Reactor Pressure Vessel Safety Relief Valve Testing Frequency ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19046A1142019-02-25025 February 2019 Issuance of Relief Requests 154-04 and 14R-04 Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography 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 ML18334A2362018-12-21021 December 2018 Alternative to the Requirements of the ASME Code ML18332A0422018-12-12012 December 2018 Issuance of Relief Requests I5R-04 and I4R-04 Use of ASME Code Case N-513-4 in Lieu of Specific ASME Code Requirements ML18318A4222018-12-10010 December 2018 Issuance of Relief Request Use of ASME Code Case OMN-13 in Lieu of Specific ASME Code Requirements ML18275A1392018-11-13013 November 2018 Relief from the Requirements of the ASME Code (EPID L-2017-LLR-0145 Through EPID L-2017-LLR-0152) NMP1L3226, Submittal of Relief Requests Associated with the Fifth and Fourth Lnservice Inspection Intervals2018-06-0808 June 2018 Submittal of Relief Requests Associated with the Fifth and Fourth Lnservice Inspection Intervals 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 ML17331A1812017-12-0505 December 2017 Alternative to the Requirements of the American Society of Mechanical Engineers Code (CAC Nos. MF9381 and MF9382; EPID L-2017-LLR-0015) ML17297A5242017-11-0606 November 2017 R. E. Ginna - Request for Use of a Portion of a Later Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (CAC Nos. MG0079-MG0083; EPID L-2017-LLR-0061) ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML17136A1122017-05-30030 May 2017 Alternative to the Requirements of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants NMP1L3146, Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J2017-04-0606 April 2017 Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML16138A0212016-05-19019 May 2016 Proposed Alternative to Use Code Case N-789 (CAC Nos. MF7018-MF7022) ML16071A2332016-04-29029 April 2016 Relief Request Alternative Use of Boiling Water Reactor Vessel and Internals Project Guidelines in Lieu of Specific ASME Code Requirements ML13290A1722013-10-24024 October 2013 Relief from the Requirements of the ASME Code Request Number 2lSl-011, Rev. 00, Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for Implementation of a Risk-Informed, Safety-Base ML13052A3732013-03-15015 March 2013 ME5789-Authorization of Relief Request 1ISI-004, Revision 1 (NMP1 Relief Request) ML13084A2442013-03-14014 March 2013 Response to Request for Review of Draft NRC Safety Evaluation, Relief from Requirements of ASME Code, Section XI, Request No. 1ISI-004, Revision 1, Repair of Control Rod Drive Housing Penetrations ML12166A2692012-06-22022 June 2012 ME8534-Authorization of Relief Request No. RR-PTRR-02, Revision 1,Recirc Pump Seals Replacement ML1109503072011-03-25025 March 2011 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair of Control Rod Drive Housing Penetrations for the Remainder of the License Renewal Period of Extended Operation ML1007000342010-03-15015 March 2010 Request for Alternative 1ISI-003, Request to Use ASME Code Case N-716 Associated with the Fourth 10-year Inservice Inspection Interval ML0926300072009-09-23023 September 2009 Request for Alternative No. MSS-VR-02 Main Steam Safety Relief Valve Test Interval Extension ML0919804542009-08-0303 August 2009 Request to Utilize Alternative of Applying ASME Code Case 730 for Repair and ISI of Control Rod Drive Bottom Head Penetrations for the License Renewal Period of Extended Operation ML0831904942008-12-0101 December 2008 Relief Request 2ISI-007 and 2ISI-009 for Third 10-Year ISI Interval ML0633204612006-11-16016 November 2006 Request for Permanent Relief from Inservice Inspection Requirements of 10 CFR 50.55a(g) for the Volumetric Examination of Circumferential Reactor Pressure Vessel Welds ML0332400602003-11-21021 November 2003 Relief, Approval of Alternative Regarding Dissimilar Metal Welds ML0312200272003-05-0606 May 2003 Authorization of Alternative, Inservice Inspection (ISI) Relief Request ISI-23B, TAC MB5732 2024-01-19
[Table view] Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023 Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station 2024-09-04
[Table view] Category:Safety Evaluation
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation ML24145A1862024-05-30030 May 2024 Authorization and Safety Evaluation of Alternative Relief Request I5R-12 Concerning the Installation of a Full Structural Weld Overlay on RPV Recirculation Inlet Nozzle N2E ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 ML23156A6832023-06-22022 June 2023 Authorization and Safety Evaluation of Alternative Relief Request I5R-14 ML23156A6822023-06-22022 June 2023 Authorization and Safety Evaluation of Alternative Relief Request I5R-11 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23103A1912023-04-20020 April 2023 Request for Threshold Determination Under 10 CFR 50.80 ML23082A3502023-04-17017 April 2023 Issuance of Amendment No. 192, Revision of Surveillance Requirements Associated with Emergency Diesel Generator Testing ML23094A1422023-04-0505 April 2023 Approval of Alternative Request I5R-13 to Utilize Specific Provisions of Code Case N-716-3 ML23025A4122023-02-28028 February 2023 Issuance of Amendment No. 248 to Revise Alternative Source Term Calculation for Main Steam Isolation Valve Leakage and Non-MSIV Leakage ML22339A0582022-12-21021 December 2022 Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits 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) ML22061A0402022-03-11011 March 2022 Relief Request Associated with Excess Flow Check Valves ML22033A3102022-03-0404 March 2022 Issuance of Amendment No. 190, Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements 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) ML21295A7342021-11-15015 November 2021 Issuance of Amendment No. 187 Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21256A1792021-11-0202 November 2021 Issuance of Amendment No. 246 Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) 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 ML21166A1682021-06-25025 June 2021 ML21140A1532021-06-0303 June 2021 Correction to April 22, 2021 Safety Evaluation for Requests for Alternative to the Inservice Testing Requirements of the ASME OM Code for the Fifth 10-Year Program Interval ML21082A2212021-04-29029 April 2021 Issuance of Amendment No. 186, Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML21109A2162021-04-22022 April 2021 Proposed Alternative to Inservice Testing Requirements of the ASME OM Code for the Fifth 10-Year Interval ML21105A3382021-04-22022 April 2021 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Concerning Examination Coverage of Certain Class 1 and 2 Component Welds ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21049A0062021-03-16016 March 2021 Issuance of Amendment No. 245 for Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21049A0242021-02-23023 February 2021 Alternative Request to the Requirements of the ASME OM Code for the Testing Intervals for the Instrument-Line Flow Check Valves ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 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 ML20332A1152021-01-29029 January 2021 Issuance of Amendment No. 183 Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML21005A0612021-01-14014 January 2021 Proposed Alternatives to Extend the Safety Relief Valve Testing Interval (EPID L-2020-LLR-0014 Through L-2020-LLR-0018) ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20241A1902020-10-20020 October 2020 Issuance of Amendment No. 182 to Change Allowable Main Steam Isolation Valve Leak Rates 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 ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 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 ML20141L0532020-06-0202 June 2020 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts 2024-09-26
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February 23, 2021 Mr. David P. Rhoades Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 1 - ALTERNATIVE REQUEST TO THE REQUIREMENTS OF THE ASME OM CODE FOR THE TESTING INTERVALS FOR THE INSTRUMENT-LINE FLOW CHECK VALVES (EPID L-2020-LLR-0114)
Dear Mr. Rhoades:
By letter dated August 20, 2020 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML20233A435), as supplemented by letter dated January 22, 2021 (ADAMS Accession No. ML21022A010), Exelon Generation Company, LLC (Exelon, the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of alternatives to certain American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) requirements at Nine Mile Point Nuclear Station, Unit 1 (Nine Mile Point 1).
Specifically, pursuant to Section 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR), the licensee requested to use the proposed alternative on the basis that the alternative provides an acceptable level of quality and safety. The licensee requested implementation of Relief Request GV-RR-09 with respect to the inservice testing (IST) requirements for the testing intervals for the instrument-line flow check valves.
As set forth in the enclosed safety evaluation, the NRC staff has determined that proposed alternative GV-RR-09 provides an acceptable level of quality and safety for the valves at Nine Mile Point 1 listed in Table 1 of the enclosed safety evaluation. Accordingly, the NRC staff concludes that the licensee has adequately addressed the regulatory requirements specified in 10 CFR 50.55a(z)(1) for Relief Request GV-RR-09. Therefore, the NRC staff authorizes the use of Relief Request GV-RR-09 for the remainder of the fifth 10-year IST program interval at Nine Mile Point 1, which began on January 1, 2019, and is scheduled to end on December 31, 2028.
All other ASME OM Code requirements for which relief or an alternative were not specifically requested and approved as part of this request remain applicable.
D. Rhoades In its application, Exelon included a separate request for a proposed license amendment to change the technical specification required surveillance requirements for the instrument flow line check valves at Nine Mile Point 1. The NRC staff conducted a separate review of the license amendment request, and the result of that review will be communicated to Exelon in separate correspondence.
If you have any questions, please contact the Nine Mile Point Nuclear Station Project Manager, Michael Marshall, at (301) 415-2871.
Sincerely, Digitally signed by James G. James G. Danna Date: 2021.02.23 Danna 11:12:16 -05'00' James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
Safety Evaluation cc: Listserv
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RELIEF REQUEST GV-RR-09 NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, UNIT 1 DOCKET NO. 50-220
1.0 INTRODUCTION
By letter dated August 20, 2020 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML20233A435), as supplemented by letter dated January 22, 2021 (ADAMS Accession No. ML21022A010), Exelon Generation Company, LLC (Exelon, the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of alternatives to certain American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) requirements at Nine Mile Point Nuclear Station, Unit 1 (Nine Mile Point 1). In particular, the licensee requested implementation of Relief Request GV-RR-09 with respect to the inservice testing (IST) requirements for the testing intervals for the instrument-line flow check valves specified in the ASME OM Code, Division 1, OM Code, Section IST, for the IST program at Nine Mile Point 1 during the fifth 10-year IST program interval.
Pursuant to subparagraph (1) in paragraph (z), Alternatives to codes and standards requirements, of Section 55a, Codes and standards, in Part 50, Domestic Licensing of Production and Utilization Facilities, to Title 10, Energy, of the Code of Federal Regulations (10 CFR), the licensee requested to implement proposed alternative GV-RR-09 on the basis that the proposed alternative will provide an acceptable level of quality and safety.
2.0 REGULATORY REQUIREMENTS The NRC regulations in 10 CFR 50.55a(f)(4), Inservice testing standards requirement for operating plants, state, in part, that throughout the service life of a boiling or pressurized water-cooled nuclear power facility, pumps and valves that are within the scope of the ASME OM Code must meet the inservice test requirements (except design and access provisions) set forth in the ASME OM Code and addenda that become effective subsequent to editions and addenda specified in 10 CFR 50.55a(f)(2) and (3) and that are incorporated by reference in 10 CFR 50.55a(a)(1)(iv), to the extent practical within the limitations of design, geometry, and materials of construction of the components.
Enclosure
The NRC regulations in 10 CFR 50.55a(z) state, in part, that alternatives to the requirements of paragraph (f) of 10 CFR 50.55a may be used, when authorized by the NRC, if the licensee demonstrates (1) the proposed alternatives would provide an acceptable level of quality and safety or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The Nine Mile Point 1 fifth 10-year IST program interval began on January 1, 2019, and is scheduled to end on December 31, 2028. The applicable ASME OM Code edition for the Nine Mile Point 1 fifth 10-year IST program interval is the 2012 Edition, which is incorporated by reference in 10 CFR 50.55a with conditions.
3.0 TECHNICAL EVALUATION
3.1 Licensees Alternative Request The licensee requested an alternative to the valve testing requirements of the ASME OM Code, Subsection ISTC, Inservice Testing of Valves in Light-Water Reactor Nuclear Power Plants, paragraph ISTC-3522, Category C Check Valves.
Paragraph ISTC-3522, subparagraph (a), states, in part, During operation at power, each check valve shall be exercised or examined in a manner that verifies obturator travel by using the methods in para. ISTC-5221.
Subparagraph ISTC-3522(c) states, If exercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages.
The licensee requested use of its proposed alternative for valves specified in its request. These valves are listed in Table 1 below.
Table 1 Component System Code Class OM Category CKV-36-57 Emergency Cooling 1 C CKV-36-62 Emergency Cooling 1 C CKV-36-67 Emergency Cooling 1 C CKV-36-72 Emergency Cooling 1 C CKV-01-76 Main Steam SRV 1 C CKV-01-77 Main Steam 1 C CKV-01-78 Main Steam 1 C CKV-01-79 Main Steam 1 C CKV-32-100 Reactor Recirculation 1 C CKV-32-106 Reactor Recirculation 1 C CKV-32-112 Reactor Recirculation 1 C CKV-32-118 Reactor Recirculation 1 C CKV-32-125 Reactor Recirculation 1 C CKV-32-131 Reactor Recirculation 1 C CKV-32-138 Reactor Recirculation 1 C CKV-32-144 Reactor Recirculation 1 C CKV-32-151 Reactor Recirculation 1 C
Table 1 Component System Code Class OM Category CKV-32-157 Reactor Recirculation 1 C CKV-32-164 Reactor Recirculation 1 C CKV-32-170 Reactor Recirculation 1 C CKV-32-177 Reactor Recirculation 1 C CKV-32-183 Reactor Recirculation 1 C CKV-32-204 Reactor Recirculation 1 C CKV-32-210 Reactor Recirculation 1 C CKV-32-215 Reactor Recirculation 1 C CKV-32-221 Reactor Recirculation 1 C CKV-32-226 Reactor Recirculation 1 C CKV-32-232 Reactor Recirculation 1 C CKV-32-237 Reactor Recirculation 1 C CKV-32-243 Reactor Recirculation 1 C CKV-32-248 Reactor Recirculation 1 C CKV-32-254 Reactor Recirculation 1 C CKV-32-64 Reactor Recirculation 1 C CKV-32-70 Reactor Recirculation 1 C CKV-32-76 Reactor Recirculation 1 C CKV-32-82 Reactor Recirculation 1 C CKV-32-88 Reactor Recirculation 1 C CKV-32-94 Reactor Recirculation 1 C CKV-44.1-07 Reactor Recirculation 1 C CKV-44.1-12 Reactor Recirculation 1 C CKV-36-120 Reactor Vessel Instrumentation 1 C CKV-36-125 Reactor Vessel Instrumentation 1 C CKV-36-130 Reactor Vessel Instrumentation 1 C CKV-36-135 Reactor Vessel Instrumentation 1 C CKV-36-140 Reactor Vessel Instrumentation 1 C CKV-36-145 Reactor Vessel Instrumentation 1 C CKV-36-160 Reactor Vessel Instrumentation 1 C CKV-36-165 Reactor Vessel Instrumentation 1 C CKV-36-170 Reactor Vessel Instrumentation 1 C CKV-36-175 Reactor Vessel Instrumentation 1 C CKV-36-48 Reactor Vessel Instrumentation 1 C CKV-36-53 Reactor Vessel Instrumentation 1 C 3.2 Reason for Request The licensee currently tests all excess flow check valves (EFCVs) (referred to as instrument-line flow check valves at Nine Mile Point 1) every 24 months in accordance with the Surveillance Frequency Control Program. These valves are located on instrument lines, and the instruments on these lines are required to operate during normal plant operation and cold shutdown conditions. The licensee stated that
exercising these check valves requires removing the instruments from service, which could cause spurious instrument signal fluctuations to occur, that might result in the inadvertent automatic initiation or trip of systems if the check valves were tested during plant operation.
3.3 Proposed Alternative The licensee proposed that a representative sample (approximately 20 percent) of the EFCVs be tested every refueling outage with each EFCV tested at least once every 10 years.
In its letter dated August 20, 2020, the licensee stated:
Industry experience as documented in Boiling Water Reactor (BWR) Owners Group Licensing Topical Report (TR) NEDO-32977-A, Excess Flow Check Valve Testing Relaxation, dated June 2000, indicates that EFCVs have a very low failure rate. A review of the maintenance history for [Nine Mile Point 1]
EFCVs has shown that they have been highly reliable over the life of the plant.
The [Nine Mile Point 1] test experience is consistent with the findings in the NEDO document. The NEDO document indicates that many reported test failures at other plants were related to test methodologies and not actual EFCV failures. A detailed analysis of the maintenance history and a comparison to the acceptance criteria in NEDO-32977-A are provided in Attachments 1 and 2 to the License Amendment Request that this relief request is associated with. The analysis concludes the maintenance history for the [Nine Mile Point 1] EFCVs supports use of the representative sampling basis for determining the testing schedule for the EFCVs. Thus, the EFCVs at [Nine Mile Point 1], consistent with the industry, have exhibited a high degree of reliability, availability, and the alternate sampling approach justified by application of the NEDO-32977 analysis provides an acceptable level of quality and safety.
3.4 NRC Staff Evaluation The licensee's justification for proposed alternative GV-RR-09 relies on BWR Owners Group TR NEDO-32977-A, dated June 2000 (ADAMS Accession No. ML003729011). Based on the very low failure rate of EFCVs at the nuclear power plants participating in the BWR Owners Group study, the NRC staff accepted this TR and issued a safety evaluation (SE) on March 14, 2000 (ADAMS Accession No. ML003691722). In its SE, the NRC staff indicated the importance of the corrective action program (CAP) to address any EFCV failures when implementing the TR.
In its supplement dated January 22, 2021 (ADAMS Accession No. ML21022A010), the licensee stated that it will utilize the IST program as the means to track the performance of EFCVs in a manner similar to existing performance-based programs. In addition, the licensee stated that the field test procedures and the IST Program Plan will be revised to assure that each EFCV failure is entered into the CAP and evaluated against performance criteria with appropriate corrective actions taken based on the failure analysis and trend in failures. If failures exceed the performance criteria of less than or equal to one failure during a 24-month rolling average, the licensee stated that the IST Program Plan will require a cause evaluation and determination of additional testing requirements. The licensee also stated that the failed valves will be tested in the next refueling outage.
Exelon provided plant-specific failure rate analysis for Nine Mile Point 1 that is documented in GE Hitachi Nuclear Energy Report 006N1767, Revision 0 (Attachment 2 to its letter dated August 20, 2020). As described in GE Hitachi Nuclear Energy Report 006N1767, Revision 0, and BWR Owners Group Topical Report NEDO-32977-A, the Nine Mile Point 1 EFCV failure rate analysis data are consistent with the EFCV failure rate analysis for the 12 BWR nuclear power plants referenced in NEDO-32977-A.
Based on the acceptability of the methods used in GE Hitachi Nuclear Energy Report 006N1767, Revision 0, the plant-specific EFCV failure rate analysis, and the licensees failure feedback mechanism and CAP including the licensees plans to update the field test procedures and IST Program Plan as described in its supplement, the NRC staff has determined that the licensee's proposal to test approximately 20 percent of the EFCVs every refueling outage with each EFCV tested at least once every 10 years is an acceptable application of TR NEDO-32977-A at Nine Mile Point 1 . As a result, the NRC staff finds that the licensees proposed alternative Relief Request GV-RR-09 provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(z)(1).
4.0 CONCLUSION
As set forth above, the NRC staff has determined that proposed alternative GV-RR-09 provides an acceptable level of quality and safety for the valves at Nine Mile Point 1 listed in Table 1 of this SE. Accordingly, the NRC staff concludes that the licensee has adequately addressed the regulatory requirements specified in 10 CFR 50.55a(z)(1) for GV-RR-09. Therefore, the NRC staff authorizes the use of Relief Request GV-RR-09 for the remainder of the fifth 10-year IST program interval at Nine Mile Point 1 , which began on January 1, 2019, and is scheduled to end on December 31, 2028.
All other ASME OM Code requirements for which relief or an alternative were not specifically requested and approved as part of this request remain applicable.
Principal Contributor: R. Wolfgang, NRR Date: February 23, 2021
ML21049A024 *by safety evaluation dated OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DE/EMIB/BC(A)* NRR/DORL/LPL1/BC NAME MMarshall JBurkhardt TScarbrough JDanna DATE 02/19/2021 02/19/2021 02/11/2021 02/23/2021