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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
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 10, 2018 Mr. Bryan C. Hanson 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, UNITS 1 AND 2- ISSUANCE OF RELIEF REQUEST RE: USE OF ASME CODE CASE OMN-13 IN LIEU OF SPECIFIC ASME CODE REQUIREMENTS (EPID L-2018-LLR-0052)
Dear Mr. Hanson:
By letter dated April 10, 2018 (Agencywide Documents Access and Management System Accession No. ML18100A299), Exelon Generation Company, LLC (the licensee) submitted an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) associated with snubber examination at the Nine Mile Point Nuclear Station, Units 1 and 2 (Nine Mile Point 1 and 2).
This request was submitted for the fifth and fourth 10-year inservice testing intervals at Nine Mile Point 1 and 2, respectively, and is applicable to all snubbers within the scope of the Nine Mile Point 1 and 2 snubber programs.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(z)( 1),
the licensee requested to use the proposed alternative on the basis that the alternative provides an acceptable level of quality and safety. The fifth and fourth 10-year intervals for Nine Mile Point, Units 1 and 2, will begin on January 1, 2019, and are currently scheduled to conclude on December 31, 2028.
The U.S. Nuclear Regulatory Commission staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the alternative proposed by the licensee will ensure an acceptable level of quality and safety for the snubbers is maintained and the alternative has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1). Therefore, pursuant to 10 CFR 50.55a(z)(1), the licensee's proposed alternative is authorized for the fifth and fourth 10-year inservice testing intervals at Nine Mile Point 1 and 2, respectively.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable.
B. Hanson If you have any questions, please contact Jennifer Tobin by telephone at 301-415-2328 or by e-mail to Jennifer.Tobin@nrc.gov.
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<Jes G. Danna, Chief Plant Licensing Branch 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-41 O
Enclosure:
Safety Evaluation cc: Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ALTERNATIVE REQUEST SR SNUBBER INSPECTION AND TESTING EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-220 AND 50-410
1.0 INTRODUCTION
By letter dated April 10, 2018 (Agencywide Documents Access and Management System Accession No. ML18100A299), Exelon Generation Company, LLC (the licensee) submitted an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) associated with snubber examination at the Nine Mile Point Nuclear Station, Units 1 and 2 (Nine Mile Point 1 and 2).
The request was submitted for the fifth and fourth 10-year inservice testing (1ST) intervals at Nine Mile Point 1 and 2, respectively, and is applicable to the snubber examination requirements of the ASME OM Code for all snubbers within the scope of the Nine Mile Point 1 and 2 snubber programs. Specifically, pursuant to Title 1O of the Code of Federal Regulations (10 CFR) Section 50.55a(z)(1), the licensee requested to use the proposed alternative on the basis that the alternative provides an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
The 1ST of ASME Code Class 1, 2, and 3 components is to be performed in accordance with certain provisions of ASME OM Code and applicable edition and addenda as required by 10 CFR 50.55a(f). Pursuant to 10 CFR 50.55a(z), alternatives to the requirements of paragraph (f) may be used when authorized by the NRG if: (1) the proposed alternatives woul.d 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.
Pursuant to 10 CFR 50.55a(f)( 4 ), pumps and valves within the scope of the ASME OM Code must meet the inservice test requirements, except the design and access provisions set forth in the ASME OM Code, 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 1ST 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(a)(1 )(ii), 12 months prior to the start of the 120-month interval, subject to the conditions listed in 10 CFR 50.55a(b )(3).
Enclosure
Nine Mile Point 1 is currently in the fourth 10-year 1ST interval. The fifth interval will begin on January 1, 2019, and is scheduled to end on December 31, 2028. Nine Mile Point 2 is currently in the third 10-year 1ST interval. The fourth interval will begin on January 1, 2019, and is scheduled to end on December 31, 2028.
3.0 TECHNICAL EVALUATION
3.1 Background The licensee requested an alternative to the snubber examination requirements of the ASME OM Code for all snubbers within the scope of the Nine Mile Point 1 and 2 snubber programs.
3.2 ASME Code Requirements The ASME OM Code requires certain snubber examination frequencies as identified below:
- ISTD-4252, "Subsequent Examination Intervals," (c), states, "The duration of examination intervals following the completion of the second refueling outage shall be in accordance with Table ISTD 4252 1."
- ISTA-3130, "Application of Code Cases," (b), states, "Code Cases shall be applicable to the edition and addenda specified in the test plan."
3.3 Applicable ASME Code Edition and Addenda The applicable ASME OM Code edition and addenda for Nine Mile Point 1 and 2 fifth and fourth 10-year 1ST intervals, respectively, is the 2012 Edition with no Addenda.
3.4 Licensee's Proposed Alternative In its April 10, 2018, letter, the licensee stated:
ISTA-3130(b) states, "Code Cases shall be applicable to the edition and addenda specified in the test plan." ASME has approved CC [Code Case] OMN-13
["Performance-Based Requirements for Extending Snubber lnservice Visual Examination Interval at LWR Power Plants"], Revision 2. This CC is unconditionally approved for use in Regulatory Guide (RG) 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 2. The NMPNS [Nine Mile Point Nuclear Station] code of record for the 5th interval for Unit 1 and the 4th interval for Unit 2 is the ASME OM-2012 Edition. However, CC OMN-13, Revision 2, states in the Applicability section that it is applicable to ASME OM Code 1995 Edition through 2011 Addenda. NMPNS will be implementing the ASME Code OM-2012 Edition and proposes to also implement CC OMN-13, Revision 2, for extending the examination interval for snubbers.
3.6 Licensee's Basis for Use of Alternative The licensee proposed to use ASME OM Code Case OMN-13, Revision 2, with the 2012 Edition of the ASME OM Code in lieu of the 1995 Edition through 2011 Addenda of the ASME OM Code, as stated in the applicability section of Code Case OMN-13, Revision 2. The proposed alternative will be utilized for the fifth 1ST 10-year interval for Nine Mile Point 1, and the fourth 1ST 10-year interval for Nine Mile Point 2, which are both currently scheduled to start on January 1, 2019.
3.7 Duration of Proposed Alternative The licensee submitted this request for the fifth and fourth 1ST intervals for the Nine Mile Point 1 and 2, respectively. The fifth and fourth 1ST intervals are scheduled to begin January 1, 2019, and conclude on December 31, 2028.
4.0 NRC STAFF EVALUATION The NRC staff reviewed the information provided by the licensee in its submittal regarding its proposed alternative to the ASME OM Code and the technical basis for the licensee's proposed alternative. The 2012 Edition of the ASME OM Code, Section ISTD-4252(c), requires snubber examination intervals following the second refueling outage to be in accordance with intervals specified in Table ISTD-4252-1. The snubber visual examination interval can be extended up to 48 months by meeting the requirements as specified in Table ISTD-4252-1 and its notes.
ASME OM Code Case OMN-13, Revision 2, allows extension of the visual examination interval beyond the interval allowed in Table ISTD-4252-1. ISTA-3130(b) requires that Code cases shall be applicable to the edition and addenda specified in the test plan. The licensee proposed to use ASME OM Code Case OMN-13, Revision 2, to extend the visual examination interval beyond the interval allowed by Table ISTD-4252-1 for all snubbers in the 1ST program.
Specifically, the licensee proposed to apply ASME OM Code Case OMN-13, Revision 2, to the 2012 Edition of the ASME OM Code in lieu of the 1995 Edition through 2011 Edition, to extend the visual inspection frequency of snubbers in the 1ST program.
Application of ASME OM Code cases is addressed in 10 CFR 50.55a(b )(6) through references to NRC Regulatory Guide 1.192, Revision 2, "Operation and Maintenance Code Case Acceptability, ASME OM Code," which lists acceptable and conditionally acceptable Code cases for implementation in the 1ST program and snubber program. Code Case OMN-13, Revision 2, is in Table 1 of Regulatory Guide 1.192, Revision 2, which means that it is acceptable for use without conditions. Code Case OMN-13, Revision 2, was published with the 2012 Edition of the ASME OM Code, and is applicable to the 1995 Edition through the 2011 Addenda of the ASME OM Code. There is no technical reason for prohibiting the use of Code Case OMN-13, Revision 2, with the 2012 Edition of the ASME OM Code. Further, NRC staff review of the 2012 Edition of the ASME OM Code and Code Case OMN-13, Revision 2, confirmed that there are no changes in the applicable Code sections referenced within Code Case OMN-13, Revision 2. Therefore, the NRC staff concludes that the licensee's proposed alternative provides an acceptable level of quality and safety.
5.0 CONCLUSION
As set forth above, the NRC staff concludes that the licensee's proposed alternative to extend the examination interval for the snubbers included in the ASME OM Code provides an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(z)(1), the licensee's proposed alternative is authorized for the fifth and fourth 10-year 1ST intervals at Nine Mile Point 1 and 2, respectively.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable.
Principal Contributor: G. Bedi Date: December 10, 2018
B. Hanson
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2- ISSUANCE OF RELIEF REQUEST RE: USE OF ASME CODE CASE OMN-13 IN LIEU OF SPECIFIC ASME CODE REQUIREMENTS (EPID L-2018-LLR-0052)
DATED DECEMBER 10, 2018 DISTRIBUTION:
PUBLIC PM File Copy RidsACRS_MailCTR Resource RidsNrrDorlLpl1 Resource RidsNrrDeEmib Resource RidsNrrLALRonewicz Resource RidsNrrPMNineMilePoint Resource RidsRgn1 MailCenter Resource JBowen, OEDO CCook, OEDO LBurkhart, OEDO GBedi, NRR ADAMS Access1on No.: ML18318A422 *b1y e-ma1*1 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/LA NRR/DE/EMIB*
NAME JTobin LRonewicz SBailev DATE 12/03/18 12/04/18 11/02/18 OFFICE NRR/DORL/LPL 1/BC NRR/DORL/LPL 1/PM NAME JDanna JTobin DATE 12/09/18 12/10/18 OFFICIAL RECORD COPY
