Letter Sequence Approval |
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EPID:L-2022-LLR-0029, E-mail Dated 11/10/2022 Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps (Approved, Closed) |
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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 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 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-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 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 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
MONTHYEARNMP1L3570, 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 IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 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)) 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 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 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 NMP1L3564, 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 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 NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 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 NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations 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 NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . 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 IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 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 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 NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined 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 IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:Safety Evaluation
MONTHYEARML23305A1402023-12-13013 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 ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML19301B0052019-11-25025 November 2019 Issuance of Amendment No. 239 Administrative Edits to the Technical Specifications ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques 2023-08-21
[Table view] |
Text
December 21, 2022 Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Rd Warrenville, IL 60555
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 1 - RELIEF REQUEST ASSOCIATED WITH PUMP PERIODIC VERIFICATION TESTS OF CORE SPRAY SYSTEM PUMPS (EPID L-2022-LLR-0029)
Dear Mr. Rhoades:
By letter dated March 2, 2022 (Agencywide Documents and Access Management System (ADAMS) Accession Number ML22061A057), as supplemented by letter dated August 5, 2022, and docketed email dated November 10, 2022 (ML22217A004 and ML22314A226, respectively), Constellation Energy Generation, LLC (the licensee) submitted Alternative Request CS-PR-02 to the U.S. Nuclear Regulatory Commission (NRC) proposing a testing approach for specified pumps as an alternative to certain Inservice Testing (IST) requirements in the 2012 Edition of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (OM Code) for the fifth 10-year IST program interval at Nine Mile Point Nuclear Station, Unit 1 (NMP1).
Specifically, pursuant to subparagraph (1) in paragraph (z) in Part 50 to Title 10 of the Code of Federal Regulations (10 CFR 50.55a(z)(1)), the licensee requested to use the proposed alternative in CS-PR-02 related to the core spray system (CSS) pumps at NMP1 on the basis that the alternative provides an acceptable level of quality and safety.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for Alternative Request CS-PR-02. Therefore, the NRC staff authorizes the use of Alternative Request CS-PR-02, as supplemented, for the fifth 10-year IST program interval at NMP1, which began on January 1, 2019, and is currently scheduled to end on December 31, 2028.
All other ASME Code, Section XI, requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
D. Rhoades If you have any questions, please contact the Nine Mile Point Project Manager, Richard V.
Guzman, at (301) 415-1030 or Richard.Guzman@nrc.gov.
Sincerely, Digitally signed by Hipolito J. Hipolito J. Gonzalez Date: 2022.12.21 Gonzalez 13:56:48 -05'00' Hipólito J. González, 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 ALTERNATIVE REQUEST CS-PR-02 FIFTH 10-YEAR INTERVAL INSERVICE TESTING PROGRAM CONSTELLATION ENERGY GENERATION, LLC NINE MILE POINT NUCLEAR STATION, UNIT 1 DOCKET NO. 50-220
1.0 INTRODUCTION
By letter dated March 2, 2022 (Agencywide Documents and Access Management System (ADAMS) Accession Number ML22061A057), as supplemented by letter dated August 5, 2022, and docketed email dated November 10, 2022 (ML22217A004 and ML22314A226, respectively), Constellation Energy Generation, LLC (Constellation, the licensee) submitted Alternative Request CS-PR-02 to the U.S. Nuclear Regulatory Commission (NRC) proposing a testing approach for specified pumps as an alternative to certain Inservice Testing (IST) requirements in the 2012 Edition of the American Society of Mechanical Engineers (ASME)
Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (OM Code) at Nine Mile Point Nuclear Station, Unit 1 (NMP1).
Specifically, pursuant to subparagraph (1) in paragraph (z) in Part 50 to Title 10 of the Code of Federal Regulations (10 CFR 50.55a(z)(1)), the licensee requested to use the proposed alternative in CS-PR-02 related to the core spray system (CSS) pumps at NMP1 on the basis that the alternative provides an acceptable level of quality and safety. The NRC staff describes its review of the proposed alternative in CS-PR-02 for NMP1 in this safety evaluation (SE).
The NMP1 fifth 10-Year IST program interval began on January 1, 2019, and is currently scheduled to end on December 31, 2028.
2.0 REGULATORY EVALUATION
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 10 CFR 50.55a(f) 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.
3.0 TECHNICAL EVALUATION
3.1 Licensees Alternative Request CS-PR-02
Applicable Code Edition and Addenda
The applicable Code of Record for the NMP1 fifth 10-Year IST program interval is the 2012 Edition of the ASME OM Code, which is incorporated by reference in 10 CFR 50.55a.
ASME Code Components Affected In its submittal, the licensee proposed alternative testing for the following CSS pumps:
Table 1: Alternative Request CS-PR CSS Pumps Affected Pump ID Description Type of Pump Class Group PMP-81-04 CSS Pump #122 Vertical Line Shaft Centrifugal 2 B PMP-81-24 CSS Pump #112 Vertical Line Shaft Centrifugal 2 B PMP-81-49 CSS Topping Pump #112 Centrifugal 2 B PMP-81-52 CSS Topping Pump #122 Centrifugal 2 B
Applicable Code Requirement
The IST requirements in the ASME OM Code, as incorporated by reference in 10 CFR 50.55a, related to this alternative request are as follows:
ASME OM Code, Division 1, Subsection ISTB, Inservice Testing of Pumps in Light-Water Reactor Nuclear Power Plants - Pre-2000 Plants.
Paragraph ISTB-1400, Owners Responsibility, subparagraph (d), specifies that the Owners responsibility includes:
establishing a pump periodic verification test program in accordance with Division 1, Mandatory Appendix V.
ASME OM Code, Division 1, Mandatory Appendix V, Pump Periodic Verification Test Program, paragraph V-2000, Definitions, provides the following definition of a pump periodic verification test (PPVT):
a test that verifies a pump can meet the required (differential or discharge) pressure as applicable, at its highest design basis accident flow rate.
ASME OM Code, Division 1, Mandatory Appendix V, paragraph V-3000, General Requirements, subparagraph (b), requires the Owner to perform a PPVT at least once every 2 years.
ASME OM Code, Subsection ISTB, paragraph ISTB-3000, General Testing Requirements, and Table ISTB-3000-1, Inservice Test Parameters, define and compare parameters (e.g.,
pressure, flow rate, and vibration) measured during Group A tests, Group B tests, and comprehensive pump tests (CPTs).
Paragraph ISTB-3510, General, subparagraph (a), Accuracy, states, in part, that instrument accuracy shall be within the limits of Table ISTB-3510-1, Required Instrument Accuracy.
Table ISTB-3510-1 requires that comprehensive and preservice test pressure instrument accuracy be within +/- 0.5 percent.
Paragraph ISTB-5100, Centrifugal Pumps (Except Vertical Line Shaft Centrifugal Pumps),
specifies the requirements for Group A test, Group B test, and CPT procedures for those pump types.
Table ISTB-5121-1, Centrifugal Pump Test Acceptance Criteria, provides Group A test, Group B test, and CPT acceptable range, alert range, and required action range for various parameters (i.e., flow, differential pressure, and vibration) when testing centrifugal pumps.
Paragraph ISTB-5200, Vertical Line Shaft Centrifugal Pumps, specifies the requirements for Group A test, Group B test, and CPT procedures for those pump types.
Table ISTB-5221-1, Vertical Line Shaft Centrifugal Pump Test Acceptance Criteria, provides Group A test, Group B test, and CPT acceptable range, alert range, and required action range for various parameters (i.e., flow, differential pressure, and vibration) when testing vertical line shaft centrifugal pumps
Reason for Request
In Alternative Request CS-PR-02 (as supplemented), the licensee states that the 2012 Edition of the ASME OM Code requires that a PPVT for the CSS pumps at NMP1 be performed every 2 years at the pumps highest design basis accident flow rate. The two sets of pumps (CSS pump and CSS topping pump) specified in table 1 of this SE have the capability to pump demineralized water from the condensate storage tanks into the reactor pressure vessel at the design basis accident flow rate. The licensee proposes to perform the PPVTs of these two pump sets at an extended interval of 48 months on a staggered basis (one train tested each outage) instead of every 24 months (2 years) specified in the ASME OM Code. The licensee states that the basis of their proposed alternative request is the good performance of the CSS pumps over a period of time. In particular, the licensee reported that testing of the CSS pumps over the last 12 years has shown no signs of mechanical or hydraulic degradation as indicated by consistent performance of the CSS pumps within ASME OM Code acceptance criteria and only needing minor routine maintenance. In its supplement dated August 5, 2022, the licensee provided CPT results for the CSS pumps. In the August 5, 2022, supplement, the licensee also described the testing and acceptance criteria used to demonstrate the operational readiness of the CSS pumps during quarterly tests performed in accordance with Technical Specification (TS) Surveillance Requirement (SR) 4.1.4, and the IST Program at NMP1. The licensee notes that the implementation of a division-based outage strategy will allow testing of a single division per outage.
Proposed Alternative In Alternative Request CS-PR-02 (as supplemented), the licensee proposes to perform the PPVTs to meet ASME OM Code, Mandatory Appendix V, for the CSS pumps (CSS pumps and CSS topping pumps) at NMP1 listed in Table 1 at an alternate interval of 48 months in lieu of the Code-required interval of 24 months. In its supplement dated August 5, 2022, the licensee states that one pump train will be tested each outage under the staggered approach specified in Alternative Request CS-PR-02, as supplemented. The CSS pump sets will continue to be tested quarterly in accordance with the ASME OM Code, Subsection ISTB, paragraph ISTB- 5200 for the CSS pumps, and paragraph ISTB-5100 for the CSS topping pumps (as stated in the docketed email dated November 10, 2022). As indicated in the supplement dated August 5, 2022, the CPTs for the CSS pumps will continue to be performed every 2 years. The CSS pump operability and performance testing is performed in accordance with the NMP1 TS SR 4.1.4 and the IST Program.
3.2 NRC Staff Evaluation Mandatory Appendix V, paragraph V-3000(a), of the ASME OM Code requires that pumps with specific design-basis accident flow rates in the licensees credited safety analysis be included in the PPVT program. If the pumps CPT or Group A flow rates do not bound the design-basis accident flow rate, the PPVT must be performed to verify that the pump can meet the required (differential or discharge) pressure as applicable, at its highest design basis accident flow rate.
Mandatory Appendix V, paragraph V-3000(b), requires that PPVT tests shall be performed once every 2 years (24 months).
In Alternative Request CS-PR-02 (as supplemented), the licensee proposes to perform the PPVTs for the CSS pumps at NMP1 with an alternate interval of 48 months in lieu of the Code-required interval of 24 months. In its supplement dated August 5, 2022, the licensee states that one pump train will be tested each outage under a staggered approach. The licensee states that each CSS loop (CSS pump and CSS topping pump) was designed for full flow rated conditions. Data on flows and pressures at various points in the flow lines for each CSS pump are obtained during testing and are used to create the field validated pump performance curves.
The licensee states that these tests for each CSS pump set meet the design-basis accident flow conditions.
As stated by the licensee in its docketed email dated November 10, 2022, the CSS pump sets will continue to be tested quarterly in accordance with the ASME OM Code, Subsection ISTB, paragraph ISTB-5200 for the CSS pumps, and paragraph ISTB-5100 for the CSS topping pumps. The CSS pump operability and performance testing is performed in accordance with the NMP1 TS SR 4.1.4 and the IST Program.
The CPTs for the CSS pumps are performed biennially to meet the ASME OM Code requirements as specified in Subsection ISTB, paragraphs ISTB-5100 and ISTB-5200. At NMP1, each CSS loop (i.e., the CSS pump and CSS topping pump) is designed for full flow rated conditions to meet the design-basis accident flow. In its supplemental letter dated August 5, 2022, the licensee provided CPT results for the CSS pumps at NMP1 in support of the pumps good performance.
The licensee obtains test data for the pump set flow rates and pressures for each CSS loop for comparison with the previously established normal conditions in accordance with the IST Program at NMP1. Testing and baselining of the pump performance test acceptance criteria are
reperformed following major maintenance of the CSS pumps in accordance with ISTB-3300, Reference Values. Testing of the CSS pumps at a flow rate of approximately 2900 gallon per minute utilizing the existing test return line flow path provides for substantial flow testing in a stable region of the pump curve. Testing over the last 12 years has shown no signs of mechanical or hydraulic degradation as indicated by consistent performance of the CSS pumps within the ASME OM Code acceptance criteria.
The licensee stated that the completed maintenance and the IST results for the CSS pumps and CSS topping pumps have identified the need for only minor maintenance. As a result, the pumps have retained their operational readiness with no signs of mechanical or hydraulic degradation. In its supplemental letter dated August 5, 2022, the licensee stated that minor maintenance includes re-painting and oil changes performed as part of preventative maintenance.
The licensee reported that performance monitoring conducted for the CSS pumps includes pump-motor bearing housing temperatures, vibration monitoring, and periodic sampling of the lube oil. Performance monitoring indicates that the CSS pumps remain capable of meeting their design function without degradation. The licensee will implement actions to address pump performance if measured parameters are found to be outside the normal operating range or determined to be trending toward an unacceptable degraded condition. These actions include monitoring additional parameters, review of specific information to identify the cause of the degradation, and potential removal of the pump from service to perform necessary maintenance. Continued testing in a stable flow range combined with the additional pump performance monitoring provides overall reliable performance monitoring beyond the requirements prescribed in the Code that validates the ability of each pump to meet the design-basis accident flow rates. The testing is effective for detecting mechanical and hydraulic degradation as required by ASME OM Code, Subsection ISTB.
Based on its review, the NRC staff finds the licensees proposal in Alternative Request CS-PR-02 to extend the required PPVT interval on a staggered basis for the CSS pumps listed in table 1 of this SE from 24 months to 48 months (with one pump train tested each outage) provides an acceptable level of quality and safety in providing reasonable assurance of the operational readiness of the CSS pumps within the scope of this request in accordance with 10 CFR 50.55a(z)(1) for the fifth 10-Year IST program interval at NMP1.
4.0 CONCLUSION
S As described above, the NRC staff finds that the licensees proposed testing approach described in Alternative Request CS-PR-02, as supplemented, to extend the required PPVT interval for the CSS pumps at NMP1 listed in table 1 of this SE from 24 months to 48 months on a staggered basis (i.e., one pump train tested each outage) will provide an acceptable level of quality and safety in achieving reasonable assurance of the operational readiness of the CSS pumps within the scope of this request. Accordingly, the NRC staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for Alternative Request CS-PR-02, as supplemented. Therefore, the NRC staff authorizes the use of Alternative Request CS-PR-02, as supplemented, for the fifth 10-Year IST program interval at NMP1, which began on January 1, 2019, and is currently scheduled to end on December 31, 2028.
All other ASME OM Code requirements as incorporated by reference in 10 CFR 50.55a for which relief or an alternative was not specifically requested, and granted or authorized (as appropriate), in the subject request remain applicable.
Principal Contributors: G. Bedi Y. Wong T. Scarbrough Date: December 21, 2022
ML22339A058 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DEX/EMIB/BC NAME RGuzman KEntz SBailey DATE 12/05/2022 12/05/2022 11/28/2022 OFFICE NRR/DORL/LPL1/BC NRR/DORL/LPL1/PMC NAME HGonzález RGuzman DATE 12/21/2022 12/21/2022