Similar Documents at Salem |
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Category:Code Relief or Alternative
MONTHYEARML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping LR-N21-0052, Request for Relief from ASME Code Defect Removal for Service Water Buried Piping2022-04-0707 April 2022 Request for Relief from ASME Code Defect Removal for Service Water Buried Piping ML21145A1892021-06-10010 June 2021 Authorization and Safety Evaluation for Alternative Request No. SC-I4R-200 ML20099E2332020-04-20020 April 2020 Issuance of Alternative Request S1-I4R-191 for the Fourth 10-Year Inservice Inspection Interval LR-N19-0084, Proposed Alternative for Examination of ASME Section XI, Steam Generator and Pressurizer Nozzle Inside Radius Sections, Per Inservice Inspection Relief Request SC-I4R-1922019-09-10010 September 2019 Proposed Alternative for Examination of ASME Section XI, Steam Generator and Pressurizer Nozzle Inside Radius Sections, Per Inservice Inspection Relief Request SC-I4R-192 LR-N19-0083, Request for Relief S1-I4R-191 from Alloy 690 PWR Reactor Vessel Head Inspection Interval, Fourth 10-year Interval2019-09-10010 September 2019 Request for Relief S1-I4R-191 from Alloy 690 PWR Reactor Vessel Head Inspection Interval, Fourth 10-year Interval ML17219A1862017-08-17017 August 2017 Safety Evaluation of Relief Request SC-I4R-171 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program ML17132A0052017-05-19019 May 2017 Alternative Request to Adopt American Society of Mechanical Engineers Code Case OMN-20 (CAC Nos. MF8313 and MF8314) ML15349A9562015-12-24024 December 2015 Relief from the Requirements of the ASME Code ML15195A4952015-07-28028 July 2015 Relief from the Requirements of the ASME Code ML14153A1462014-06-23023 June 2014 Safety Evaluation of Relief Request No. S2-14R-131 Regarding the Fourth Ten-Year Inservice Inspection Interval (Tac ME2442) ML13088A2192013-04-18018 April 2013 Safety Evaluation of Relief Request No. S2-14R-123 Regarding the Fourth Ten-Year Inservice Inspection Interval Code Edition LR-N12-0157, Submittal of Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval Code Edition2012-06-0707 June 2012 Submittal of Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval Code Edition ML1124201752011-09-19019 September 2011 Safety Evaluation of Relief Requests Regarding Pressure Testing of Service Water System Buried Piping - Salem Nuclear Generating Station, Unit Nos. 1 and 2 LR-N10-0380, Request for Authorization to Continue Using a Risk-Informed Inservice Inspection Alternative to the ASME Boiler and Pressure Vessel Code Section XI Requirements for Class 1 and 2 Piping2010-10-21021 October 2010 Request for Authorization to Continue Using a Risk-Informed Inservice Inspection Alternative to the ASME Boiler and Pressure Vessel Code Section XI Requirements for Class 1 and 2 Piping ML0936500862010-01-0707 January 2010 Safety Evaluation of Relief Requests for the Third 10-Year Interval of the Inservice Inspection Program for Salem Nuclear Generating Station, Unit Nos. 1 and 2 ML0920304642009-08-11011 August 2009 Safety Evaluation of Relief Requests for the Fourth 10-Year Interval of the Inservice Testing Program for Salem Nuclear Generating Station, Unit 1 & 2 (TAC ME0322, ME0323, ME0324, ME0325, ME0326, ME0327, ME0328, ME0329, ME0330, ME0331, ME03 LR-N09-0126, Relief Requests to Extend the Inservice Interval for Reactor Vessel Weld Examination2009-06-11011 June 2009 Relief Requests to Extend the Inservice Interval for Reactor Vessel Weld Examination ML0825502182008-10-10010 October 2008 Safety Evaluation of Relief Requests for the Third 10-Year Interval of the Inservice Testing Program for Salem Nuclear Generating Station, Unit Nos. 1 and 2 LR-N05-0446, ASME Code Relief Request Salem Units 1 and 22005-11-16016 November 2005 ASME Code Relief Request Salem Units 1 and 2 LR-N04-0473, Relief Request SC-13-RR-A14 Synchronization of Salem Units 1 and 2 ISI Programs Ten-Year Inservice Inspection Intervals2005-10-31031 October 2005 Relief Request SC-13-RR-A14 Synchronization of Salem Units 1 and 2 ISI Programs Ten-Year Inservice Inspection Intervals ML0525802662005-09-30030 September 2005 Evaluation of Relief Requests S1-RR-04-V01 and S1-RR-04-V02 Related to the Third 10-Year Interval Inservice Testing Program ML0511803442005-05-0404 May 2005 Evaluation of Relief Request S2-13-RR-F01 ML0511503792005-04-29029 April 2005 Evaluation of Relief Request S2-13-RR-A06 ML0428005542004-10-0606 October 2004 Request for Additional Information Relief Requests S1-RR-04-V01 and V02 ML0409203612004-04-23023 April 2004 Evaluation of Relaxation Request No. S1-RR-13-B22, First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors ML0320902002003-07-28028 July 2003 Relief, Relief from ASME Code Requirements Related to the Salem Inservice Inspection Program, Relief Request S1-RR-F01, MB6098 ML0305902162003-02-20020 February 2003 Inservice Inspection Program Relief Request HC-RR-A02 ML0305902072003-02-20020 February 2003 Inservice Inspection Program Relief Request HC-RR-A06 ML0224704092003-02-0303 February 2003 Relief, Use of ASME Code Case N-532-1, Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission, MB6089 ML0301607502003-01-16016 January 2003 Relief, ASME Code Requirements Related to the Salem Inservice Inspection Program, Relief Request S1-RR-B01 and S1-RR-C01 ML0228105402002-11-27027 November 2002 Relief Request, Evaluation of Relief Request SC-RR-E01 and SC-RR-L01 ML0228307152002-11-27027 November 2002 Relief Request, Evaluation of Relief Request SC-RR-A01, TAC Nos. MB5569 & MB5570 ML0232302982002-11-12012 November 2002 Request for Additional Information Inservice Inspection Program Relief Request S1-RR-B01 ML0226004852002-10-30030 October 2002 Relief Request, Relief from ASME Code Requirements Related to the Salem Inservice Inspection Program, Relief Request SC-RR-F02, ML0225506812002-10-0707 October 2002 Code Relief, ASME Code Section XI, Inservice Inspection Program Requirements Related to Pressure Testing of Class 3 Components ML0225504352002-10-0404 October 2002 Relief, ASME Code Requirements Related to the Salem Inservice Inspection Programs, MB6086 & MB6087 ML0206100052002-03-21021 March 2002 Generation Station, Units 1 and 2, Code Relief, Inservice Inspection Requirements of Reactor Pressure Vessel Nozzle Inner Radius Sections, MB4071 and MB4072 ML0205304402002-03-21021 March 2002 Code Relief, Relief from ASME Code Requirements Related to the Inservice Inspection Program, Second 10-Year Interval, Relief Request S2-RR-B04 ML0205904012002-02-11011 February 2002 Inservice Inspection Program Relief Request S2-RR-B04, Inspection of Reactor Pressure Vessel (RPV) Flange-to-Shell Weld 2023-02-02
[Table view] Category:Letter
MONTHYEARIR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000272/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401 ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000272/20230032023-11-13013 November 2023 Integrated Inspection Report 05000272/2023003 and 05000311/2023003 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20230052023-08-31031 August 2023 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005) ML23233A0762023-08-21021 August 2023 Requalification Program Inspection ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report IR 05000272/20230012023-05-0303 May 2023 Integrated Inspection Report 05000272/2023001 and 05000311/2023001 ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator IR 05000272/20233012023-05-0101 May 2023 Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301 LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML23044A1052023-03-13013 March 2023 Issuance of Amendment Nos. 345 and 326 Relocate Technical Specifications Requirements for Reactor Head Vents to Technical Requirements Manual ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report IR 05000272/20230112023-03-0707 March 2023 Comprehensive Engineering Team Inspection Report 05000272/2023011 and 05000311/2023011 IR 05000272/20220062023-03-0101 March 2023 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2022006 and 05000311/2022006) LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 ML23034A1532023-02-0909 February 2023 Operator Licensing Examination Approval ML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023 Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211 2024-02-05
[Table view] Category:Safety Evaluation
MONTHYEARML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership ML23044A1052023-03-13013 March 2023 Issuance of Amendment Nos. 345 and 326 Relocate Technical Specifications Requirements for Reactor Head Vents to Technical Requirements Manual ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report ML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping ML22130A7912022-05-24024 May 2022 Issuance of Relief Request No. S1-I4R-210 Fourth Inservice Inspection Interval Limited Examinations ML22061A0302022-04-0404 April 2022 Issuance of Amendment Nos. 343 and 324 Revise Technical Specifications Surveillance Requirements for Auxiliary Feedwater ML22012A4352022-02-14014 February 2022 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Nos. 230, 342, and 323 Delete Definition in 10 CFR 20 and Figures of Site and Surrounding Areas ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21295A2292021-11-15015 November 2021 Issuance of Amendment Nos. 340 and 321 Revise Technical Specifications to Adopt TSTF 569, Revision of Response Time Testing Definitions ML21230A0182021-10-0808 October 2021 Issuance of Amendment No. 339 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report ML21202A0782021-09-0303 September 2021 Issuance of Amendment Nos. 338 and 320 Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21195A0622021-08-0303 August 2021 Issuance of Amendment No. 319 One-Time Request to Revise Technical Specification Action for Rod Position Indicators ML21110A0522021-07-19019 July 2021 Issuance of Amendment Nos. 337 and 318, Revise Technical Specifications to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML21145A1892021-06-10010 June 2021 Authorization and Safety Evaluation for Alternative Request No. SC-I4R-200 ML20338A0382021-02-23023 February 2021 Issuance of Amendment Nos. 336 and 317 Leak-Before-Break for Accumulator, Residual Heat Removal, Safety Injection, and Pressurizer Surge Lines ML20224A2982020-08-20020 August 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20191A2032020-08-0606 August 2020 Issuance of Amendment Nos. 335 & 316-Revise Minimum Required Channels, Mode Applicability, & Actions for Source Range/Intermediate Range Neutron Flux Reactor Trip System Instrumentation ML20104A1862020-04-20020 April 2020 Issuance of Alternative Request SC-I4R-192 for Examination of ASME Code, Section XI, Steam Generator and Pressurizer Nozzle Inside Radius Sections ML20099E2332020-04-20020 April 2020 Issuance of Alternative Request S1-I4R-191 for the Fourth 10-Year Inservice Inspection Interval ML20091K7302020-04-13013 April 2020 Issuance of Relief Request SC-I4R-190 for the Fourth 10-Year Inservice Inspection Interval ML20034E6172020-02-27027 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 222, 333, and 314 Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer ML19352F2312020-02-18018 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2; Issuance of Amendment Nos. 221, 332, and 313 Revise Emergency Plan Staffing Requirements ML19330F1562020-01-14014 January 2020 Issuance of Amendment Nos. 331 and 312 Revise Technical Specifications to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19275D6942019-11-18018 November 2019 Issuance of Amendment Nos. 330 and 311 Revise Technical Specifications to Adopt TSFT-547, Clarification of Rod Position Requirements ML19105B1712019-05-31031 May 2019 Issuance of Amendment Nos. 329 and 310 Revise Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation, Main Steam Isolation Valves, and Add New TS ML19077A3362019-04-11011 April 2019 Issuance of Amendment Nos. 328 and 309 Revise Technical Specifications to Extend Refueling Water Storage Tank Allowed Outage Time ML19044A6272019-03-0606 March 2019 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 214, 327, and 308 Revise Technical Specifications to Adopt TSTF-529 ML19050A3702019-03-0606 March 2019 Alternative to Reactor Vessel Nozzle Welds Examinations Inspection Interval (EPID-L-2018-LLR-0110) ML19009A4772019-01-25025 January 2019 Issuance of Amendment Nos. 326 and 307 Revise Technical Specifications to Increase Vital Instrument Bus Inverter Allowed Outage Time ML18318A2662018-12-19019 December 2018 Issuance of Amendment Nos. 325 and 306 Revise TS Reactor Trip System Instrumentation and Engineered Safety Features Actuation System Instrumentation Test Times and Completion Times ML18142B1262018-05-29029 May 2018 Use of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Inservice Inspection Activities ML18040A7782018-04-18018 April 2018 Issuance of Amendment Nos. 323 and 304 Relocation of Reactor Coolant System Pressure Isolation Valve Tables ML18085B1982018-04-18018 April 2018 Issuance of Amendment Nos. 324 and 305 Revise Technical Specification Actions for Rod Position Indicators ML17355A5702018-02-16016 February 2018 Issuance of Amendment Nos. 322, 303, & 210, to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 (CAC Nos. MF9268/MF9269/MF9270; EPID L-2017-LLA-0173) ML17349A1082018-01-18018 January 2018 Issuance of Amendments Containment Fan Coil Unit Allowed Outage Time Extension (CAC Nos. MF9364 and MF9365; EPID L-2017-LLA-0212) ML17227A0162017-11-14014 November 2017 Issuance of Amendments Accident Monitoring Instrumentation ML17304A9432017-11-0101 November 2017 Use of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Inservice Inspection Activities ML17219A1862017-08-17017 August 2017 Safety Evaluation of Relief Request SC-I4R-171 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program ML17172A5872017-07-17017 July 2017 Safety Evaluation of Relief Request S1-I4R-160 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program ML17165A2142017-06-28028 June 2017 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule App. to Section 5.5 Testing ML17132A0052017-05-19019 May 2017 Alternative Request to Adopt American Society of Mechanical Engineers Code Case OMN-20 (CAC Nos. MF8313 and MF8314) ML17093A8702017-05-16016 May 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Revised PSEG Nulcear LLC Cyber Security Plan Milestone 8 Implementation Schedule ML17012A2922017-02-0606 February 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Issuance of Amendments ML16351A1822017-01-19019 January 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16229A5192016-09-29029 September 2016 Issuance of Amendments Correct Non-Conservative Technical Specifications and Other Discrepancies ML16137A5792016-06-29029 June 2016 Issuance of Amendments Extension of Implementation Period for Salem, Unit No. 1, License Amendment No. 311, and Salem, Unit No. 2 License Amendment No. 292 2023-08-14
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 19, 2017 Mr. Peter P. Sena, Ill President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 -
ALTERNATIVE REQUEST TO ADOPT AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE CASE OMN-20 (CAC NOS. MF8313 AND MF8314)
Dear Mr. Sena:
By letter dated August 30, 2016 (Agencywide Documents Access and Management System Accession No. ML16243A233), PSEG Nuclear LLC (the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of alternatives to certain inservice testing (IST) requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) at the Salem Nuclear Generating Station, Unit Nos. 1 and 2, for the fourth 10-year IST interval.
Specifically, pursuant to Title 1O of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee requested to use an alternative on the basis that complying with the specified requirement would result in hardship or unusual difficulty, without a compensating increase in the 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 all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Therefore, the NRC staff authorizes the proposed alternative request for the remainder of the fourth 10-year IST interval at the Salem Nuclear Generating Station, Units 1 and 2, which is currently scheduled to end on August 30, 2019.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable.
P.Sena If you have any questions, please contact the Project Manager, Rick Ennis, at 301-415-1420 or Rick.Ennis@nrc.gov.
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7 James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosure:
Safety Evaluation cc w/enclosures: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST G-01 RELATED TO THE INSERVICE TESTING PROGRAM FOR THE FOURTH 10-YEAR INTERVAL PSEG NUCLEAR LLC EXELON GENERATION COMPANY, LLC SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 311
1.0 INTRODUCTION
By letter dated August 30, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16243A233), PSEG Nuclear LLC (the licensee), submitted Relief Request G-01 to the U.S. Nuclear Regulatory Commission (NRC or the Commission). The licensee proposed alternatives to certain inservice testing (IST) requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), for the fourth 10-year IST program at the Salem Generating Station (Salem), Unit Nos. 1 and 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee requested to use the proposed alternative in Relief Request G-01, since compliance with the ASME OM Code requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.55a(f), "lnservice testing requirements," require, in part, that IST of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized by the NRC pursuant to paragraphs (z)(1) or (z)(2) of 10 CFR 50.55a.
In proposing alternatives, a licensee must demonstrate that the proposed alternative provides an acceptable level of quality and safety (10 CFR 50.55a(z)(1 )) or compliance would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety (10 CFR 50.55a(z)(2)). Section 50.55a allows the NRC to authorize alternatives to ASME OM Code requirements upon making necessary findings.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request, and the Commission to grant, the relief requested by the licensee.
Enclosure
3.0 TECHNICAL EVALUATION
3.1 Licensee's Relief Request G-01 3.1.1 Applicable Code Requirements The Salem, Unit Nos. 1 and 2, code edition and addenda that are applicable to the program interval are the ASME OM Code-2001 through the ASME OMb Code 2003 Addenda. The current interval for Salem, Unit Nos. 1 and 2, ends on August 30, 2019. This request relates to ASME OM Code Case OMN-20, "lnservice Test Frequency," which specifies the test frequency requirements for pumps and valves applicable to ASME OM Division 1, Section IST 2009 Edition through OMa-2011 Addenda and all earlier editions and addenda of the ASME OM Code. This request is applicable to the accelerated test frequencies specified in Code Case OMN-20.
3.1.2 Components for Which Relief is Requested The request applies to pumps and valves specified in ASME OM Division 1, Section IST 2009 Edition through OMa-2011 Addenda, and all earlier editions and addenda of the ASME OM Code (i.e., all pumps and valves contained within the Salem IST program scope).
3.1.3 Reason for Requesting Relief ASME OM Code Section IST establishes the IST frequency for all components within the scope of the code. The frequencies (e.g., quarterly) have always been interpreted as "nominal" frequencies, and owners routinely applied the surveillance extension time period (i.e., grace period) contained in the plant technical specification (TS) surveillance requirements (SRs). The TSs typically allow for a less than or equal to 25 percent extension of the surveillance test interval to accommodate plant conditions that may not be suitable for conducting a TS surveillance (SR 3.0.2). However, in Regulatory Issue Summary 2012-10, "NRC Staff Position on Applying Surveillance Requirements 3.0.2 and 3.0.3 to Administrative Controls Program Tests" (ADAMS Accession No. ML12079A393), and Enforcement Guidance Memorandum 12-001, "Dispositioning Noncompliance with Administrative Controls Technical Specifications Programmatic Requirements that Extend Test Frequencies and Allow Performance of Missed Tests" (ADAMS Accession No. ML11258A243), the NRC staff states that items related to extending the surveillance periods of the TS IST program were inappropriately added to the TSs and may not be applied to non-TS support components tested under 10 CFR 50.55a(f).
The lack of a tolerance band (i.e., extension, grace period) on the ASME OM Code IST frequency restricts operational flexibility. The lack of a tolerance band applied to the ASME OM Code testing places an unusual hardship on the plant to adequately schedule work tasks without operational flexibility. Therefore, just as with TS-required surveillance testing, some tolerance is requested to allow adjusting ASME OM Code testing intervals to suit the plant conditions and other maintenance and testing activities. This assures operational flexibility when scheduling IST that would minimize the conflicts between the need to complete the testing and plant conditions.
The licensee proposed to use ASME OM Code Case OMN-20, for determining acceptable tolerances for pump and valve test frequencies. The proposed alternative will be utilized for the
fourth 10-year interval and will apply to the various frequency specifications of the ASME OM Code for all pumps and valves contained within the IST program scope.
3.1.4 Licensee's Proposed Alternative ASME OM, Division 1, Section IST, and earlier editions and addenda of the ASME OM Code specify component test frequencies based either on elapsed time periods (e.g., quarterly, 2 years, etc.) or on the occurrence of plant conditions or events (e.g., cold shutdown, refueling outage, upon detection of a sample failure, following maintenance, etc.).
a) Components whose test frequencies are based on elapsed time periods shall be tested at the frequencies specified in Section IST with a specified time period between tests as shown in the table below.
Frequency Specified Time Period Between Tests Quarterly 92 days (or everv 3 months)
Semiannually 184 days (or every 6 months)
Annually 366 days (or everv vear) x calendar years x Years where 'x' is a whole number of years :;:: 2 The specified time period between tests may be reduced or extended as follows:
- 1) For periods specified as less than 2 years, the period may be extended by up to 25 percent for any given test.
- 2) For periods specified as greater than or equal to 2 years, the period may be extended by up to 6 months for any given test.
- 3) All periods specified may be reduced at the discretion of the Owner (i.e., there is no minimum period requirement).
Period extension is used to facilitate test scheduling and considers plant operating conditions that may not be suitable for performance of the required testing (e.g.,
performance of the test would cause an unacceptable increase in the plant risk profile due to transient conditions or other ongoing surveillance, test, or maintenance activities).
Period extensions are not intended to be used repeatedly merely as an operational convenience to extend test intervals beyond those specified. Period extensions may also be applied to accelerated test frequencies (e.g., pumps in Alert Range) and other less than 2-year test frequencies not specified in the table above. Period extensions may not be applied to the test frequency requirements specified in ASME OM Code Subsection ISTD, "Preservice and lnservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-water Reactor Nuclear Power Plants," as Subsection ISTD contains its own rules for period extensions.
b) Components whose test frequencies are based on the occurrence of plant conditions or events may not have their period between tests extended except as allowed by the ASME OM Code.
3.2 NRC Staff Evaluation Historically, licensees have applied, and the NRC staff has accepted, the Standard TS definitions for IST intervals (including allowable interval extensions) to ASME OM Code-required testing (see Section 3.1.3 of NUREG-1482, Revision 2, "Guidelines for lnservice Testing at Nuclear Power Plants: lnservice Testing of Pumps and Valves and lnservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants," October 2013 (ADAMS Accession No. ML13295A020)). Recently, the NRC staff reconsidered the allowance of using TS testing intervals and interval extensions for IST. As noted in Regulatory Issue Summary 2012-10, the NRC determined that programmatic test frequencies cannot be extended to all IST described in the ASME OM Code in accordance with TS SR 3.0.2.
The lack of a tolerance band on the ASME OM Code IST frequency restricts operational flexibility. The NRC staff recognized that, just as with TS-required surveillance testing, some tolerance is needed to allow adjusting ASME OM Code testing intervals to suit the plant conditions and other maintenance and testing activities. To provide operational flexibility when scheduling IST that minimize the conflicts between the need to complete the testing and plant conditions, the NRC staff sponsored and co-authored an ASME OM Code inquiry and Code Case to modify the ASME OM Code to include TSs like test interval definitions and interval extension criteria. The resultant Code Case OMN-20 was approved by the ASME Operation and Maintenance Standards Committee on February 15, 2012, with the NRC representative voting in the affirmative. Code Case OMN-20 was subsequently published in conjunction with the ASME OM Code, 2012 Edition. The licensee proposes to adopt Code Case OMN-20 as described in Section 3.1.4 above.
Requiring the licensee to meet the ASME OM Code requirements without an allowance for defined frequency and frequency extensions for IST of pumps and valves results in a hardship, without a compensating increase in the level of quality and safety. Based on the prior acceptance by the NRC staff of the similar TS test interval definitions and interval extension criteria, the staff concludes that implementation of the test interval definitions and interval extension criteria contained in ASME OM Code Case OMN-20 is acceptable. Allowing usage of Code Case OMN-20 provides reasonable assurance of operational readiness of pumps and valves subject to the ASME OM Code IST.
4.0 CONCLUSION
As set forth above, the NRC staff determined that the proposed alternative provides reasonable assurance that the affected components are operationally ready. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(z)(2). Therefore, the NRC staff authorizes the proposed alternative request for the remainder of the fourth 10-year IST interval at Salem, Unit Nos. 1 and 2, which is currently scheduled to end on August 30, 2019.
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: Y. Huang Date: May 19, 2017
ML17132A005 *Safety Evaluation by e-mail OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/LA NRR/DE/EPNB/BC*
NAME MMarshall REnnis LRonewicz DAiiey DATE 05/16/2017 05/16/2017 05/15/2017 03/17/2017 OFFICE DORL/LPL 1/BC DORL/LPL 1/PM NAME JDanna MMarshall DATE 05/19/2017 05/19/2017