Similar Documents at Salem |
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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: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: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 NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 September 19, 2011 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038 SAFETY EVALUATION OF RELIEF REQUESTS REGARDING PRESSURE TESTING OF SERVICE WATER SYSTEM BURIED PIPING -SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 (TAC NOS. ME4861 AND ME4862)
Dear Mr. Joyce:
By letter dated October 12, 2010, as supplemented by letter dated July 21, 2011, PSEG Nuclear LLC (PSEG) submitted relief requests S1-14R-102 and S2-13R-104 for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2, respectively.
The proposed reliefs would allow PSEG to use an alternative examination of buried piping in the service water system in lieu of system pressure tests required by American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, IWA-5244(b)(1).
The U.S. Nuclear Regulatory Commission staff has completed its review of the subject relief requests as documented in the enclosed Safety Evaluation (SE). Our SE concludes that the proposed alternative provides reasonable assurance of the structural integrity of the subject components.
Furthermore, the NRC staff concludes that the licensee's compliance with the ASME Code requirements would result in hardship without a compensating increase in the level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), the proposed alternative is authorized for the remainder of the fourth 1 O-year in service inspection (lSI) interval for Salem Unit No.1, and for the remainder of the third 10-year lSI interval for Salem Unit No.2. All other requirements of the ASME Code,Section XI for which relief has not been specifically requested remain applicable, including a third party review by the Authorized Nuclear Inservice Inspector.
T. Joyce -2 If you have any questions concerning this matter, please contact the Salem Project Manager, Mr. Richard Ennis, at (301) 415-1420.
7l' Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RELIEF REQUESTS S1-14R-102 and S2-13R-104 PSEG NUCLEAR LLC SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
By letter dated October 12,2010, as supplemented by letter dated July 21,2011 (Agencywide Documents Access and Management System (ADAMS)
Accession Nos. ML102920465 and ML112030205, respectively), PSEG Nuclear LLC (PSEG, the licensee) submitted relief request relief requests S1-14R-1 02 and S2-13R-1 04 for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2, respectively.
The proposed reliefs would allow PSEG to use an alternative examination of buried piping in the service water (SW) system in lieu of system pressure tests required by American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, IWA-5244(b)(1).
Relief request S 1-14R-1 02 is for the fourth 1 O-year inservice inspection (lSI) interval at Salem Unit No.1 which began on May 20, 2011, and is scheduled to end on May 20, 2021. Relief request S2-13R-1 04 is for the third 10-year lSI interval at Salem Unit No.2 which began on November 27,2003, and is scheduled to end on November 27,2013.
2.0 REGULATORY EVALUATION
The lSI of ASME Code Class 1, 2, and 3 components is to be performed in accordance with Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," of the ASME Code and applicable edition and addenda as required by Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(g), except where specific relief has been granted by the Nuclear Regulatory Commission (NRC or the Commission) pursuant to 10 CFR 50.55a(g)(6)(i).
Pursuant to 10 CFR 50.55a(a)(3), alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if the licensee demonstrates that: (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Enclosure
-2 Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) must meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, to the extent practical within the limitations of design, geometry, and materials of construction of the components.
The regulation requires that inservice examination of components and system pressure tests conducted during the first 10-year interval, and subsequent intervals, comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. As stated above, the subject relief requests are for the fourth 10-year lSI interval at Salem Unit No.1 and for the third 10-year lSI interval at Salem Unit No.2. The Code of Record for the Salem Unit No.1 fourth 10-year lSI interval is the ASME Code,Section XI, 2004 Edition, no Addenda. The Code of Record for the Salem Unit No.2 third 1 O-year lSI interval is the ASME Code,Section XI, 1998 Edition through 2000 Addenda. 3.0 LICENSEE'S PROPOSED ALTERNATIVES 3.1 System/Component(s}
For Which Relief Is Requested
==
Description:==
Buried portions of the 24" inside diameter 11 and 12 SW supply headers (Salem Unit No.1) and the 21 and 22 SW supply headers (Salem Unit No.2). The approximate lengths are: 11 SW Header Supply -642 feet 12 SW Header Supply -629 feet 21 SW Header Supply -635 feet 22 SW Header Supply -578 feet Code Class: 3 Examination Category:
D-B in Table IWD-2500-1 Item Number: D2.10 in Table IWD-2500-1 3.2 ASME Code Requirements ASME Code,Section XI, IWD-2500 states that all pressure-retaining components shall be tested at the frequency and examined by the methods specified in Table IWD-2500-1.
Table 2500-1, Examination Category D-B, Item D2.1 0, requires that a system leakage test be conducted with a VT -2 visual examination once each inspection period per IWD-5221. 5221 requires that the system be tested at the system pressure obtained while the system or portion of the system is in service performing its normal operating function or at the system pressure developed during a test conducted to verify system operability.
When a VT-2 visual examination cannot be performed on buried components, IWA-5244(b)(1) allows the examination requirements to be satisfied by either a system pressure test that determines the rate of pressure loss for components that are isolable by means of valves or, alternatively, by a test that determines the change in flow between the ends of the buried components.
-3 Licensee's Basis for Requesting Relief The pressure drop test and the alternative change in flow test required by IWA-5244(b)(1) cannot be performed on the SW system in its present configuration.
The valves installed in the SW system that would isolate the piping for pressure drop testing are butterfly valves and are not capable of the leak-tightness required to perform the test. Extensive modifications, including removing the system from operation and installing blind flanges to allow for system isolation for pressure testing, would be required.
In order to perform the change in flow test, flow measuring devices would need to be installed.
However, there are no locations available for installation of flow measuring devices near the buried portions of the SW system that would be capable of measuring flow with sensitivity adequate for comparing flow at the inlet and outlet of headers. Performance of either of these tests would require extensive system modifications and would constitute a hardship. Licensee's Proposed Alternative The licensee's letter dated October 12, 2010, stated that the proposed alternative for testing the buried portion of SW piping in lieu of performing the periodic test required by IWA-5244(b)(1) shall consist of: A visual examination of the ground surface areas (includes surfaces of asphalt or other pavement materials) above all SW piping buried in soil shall be performed during all current and subsequent inspection outages to detect evidence of through-wall leakage in the buried components.
The system shall have been in operation at nominal operating conditions for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to performing the visual examinations, in lieu of performing the periodic test required by IWA-5244(b)(1).
The ASME Section XI [CJode only requires a pressure test once each period. Since the SW system is in-service for extended periods of time, any leakage would be readily identified by plant personnel performing routine inspections during rounds. Visual examination of the inside surface of all SW buried piping are performed to ensure that piping is unobstructed and any evidence of piping degradation is identified and is evaluated or repaired.
The licensee requests approval of this alternative pursuant to 10 CFR 50.55a(a)(3)(ii). NRC STAFF EVALUATION Hardship Evaluation As discussed above in Section 3.2 of this Safety Evaluation (SE), when a VT-2 visual examination cannot be performed on buried components, IWA-5244(b)(1) allows the examination requirements to be satisfied by either a system pressure test that determines the rate of pressure loss for components that are isolable by means of valves or, alternatively, by a test that determines the change in flow between the ends of the buried components.
-4 In order to perform a test that determines the rate of pressure loss, the segment under test must be isolated.
The licensee states that the butterfly valves installed in the SW system are not capable of the leak-tightness required to perform a pressure drop test. As a result, the IWA-5244(b)(1) requirements to perform a pressure drop test cannot be met without extensive system modifications, including removing the system from operation and installing blind flanges. The NRC staff finds that the extensive system modifications required to meet the ASME Code pressure test requirements would present a hardship.
As an alternative to the pressure drop test, the ASME Code, IWA-5244(b)(1), allows measurement of the change in flow between the ends of the buried components using flow meters at each end of the buried segment.
The licensee states that there are presently no locations available for installation of flow measuring devices in the SW system near the buried portions that would be capable of measuring flow with sensitivity adequate for comparing flow at inlet and outlet of headers. The NRC staff finds that the extensive system modifications required to install flow meters to meet the ASME Code flow test requirements would present a hardship.
4.2 Proposed Alternative and Precedent As described in Section 3.4, the licensee has proposed an alternative to the system pressure test requirements for the piping segments listed in SE Section 3.1. In lieu of the ASME Code-required pressure drop or flow tests, the licensee proposes to perform visual examinations of the ground surface areas above all SW buried piping with the system having been in operation for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to performing the visual examination.
This examination is to be performed during all current and subsequent inspection outages to detect evidence of through-wall leakage. The licensee states that since the SW system is in-service for extended periods of time, any leakage would be readily apparent to plant personnel performing routine inspections during rounds. In addition to the visual examination of the ground surfaces, the licensee proposes to perform a remote visual inspection of the inside surface of the subject SW buried piping every 36 months (i.e., one of the two headers for each unit is inspected each refueling outage) to ensure that the piping is unobstructed and to identify any evidence of piping degradation.
In its letter dated July 21, 2011, the licensee stated that the visual inspection consists of accurately documenting visible deterioration along the pipe inside surface, with the location of as-found anomalies marked, photographed or videoed for future surveys and tracking.
The buried pipe internal visual inspections are focused on locating cracking of the inner concrete core. WEKO-Seals, which have been installed in the bell and spigot joints of all 4 SW supply nuclear headers, are inspected for nicks, tears, or any other damage indicative of deterioration.
The NRC staff notes that similar proposed alternatives have been authorized by the NRC staff, as noted in the licensee's relief request submission.
However, the previously-authorized alternatives have dealt with cast iron or carbon steel piping, and the subject piping is stressed concrete cylinder pipe (PCCP). The construction and properties, most significantly failure mode, of PCCP are significantly different than that of other piping materials.
Corrosion in carbon steel SW pipe is frequently the result of pitting where the pits are usually small in lateral dimension.
As a result, the pipe will leak significantly before the structural integrity of the pipe is challenged.
Such leakage can be readily detected by frequent walk downs. The walk downs
-5 have been credited by the NRC staff for inspection of Class 3 pipe where performance of pressure or flow tests would present a hardship.
Wall thinning of carbon steel pipe by generalized corrosion is a slow process that can be monitored by wall thickness measurements, allowing the structural integrity of the pipe to be ensured. In comparison, a dominant PCCP failure mode is corrosion of the pre-stressing wires outside of the metal cylinder, resulting in their failure and catastrophic pipe rupture without significant prior leakage (Reference 3). As a result, the precedents cited by the licensee do not directly support the proposed alternative for the subject PCCP. 4.3 Description of SW Piping In its letter dated July 21, 2011, the licensee stated that the subject SW piping primarily consists of lined cylinder pre-stressed concrete cylinder pipe (LC-PCCP) that was fabricated to American Water Works Association (AWWA) standard C-301-64, and also includes non-PCCP end pieces and fittings called "specials." LC-PCCP consists of a thin steel cylinder lined with centrifugally cast concrete.
The concrete core is pre-stressed by steel wire helically wrapped around the steel cylinder, and a cement mortar coating is applied around the pipe to protect the wire against corrosion.
In standard commercial PCCP, the internal pressure load is carried by the stressing wires and the steel cylinder only forms a barrier against leakage. The 16-foot sections (sticks) of PCCP with bell and spigot ends are connected with bell-bolt joints and external harness assemblies.
The external harness assemblies are located at 3 o'clock and 9 o'clock along the length of the pipe sections to help resist axial loads. The "specials" are stressed 1/2"-thick steel pipe with a nonstructural interior and exterior mortar coating for corrosion protection.
If several pre-stressing wires within a small area of the PCCP corrode and fail, the local load carrying capacity is compromised and sudden catastrophic rupture can occur with little prior leakage. Although the pre-stressing wires are protected from corrosion by the cement mortar coating on the outside of the pipe, in cases where soil corrosivity is high, corrosion of the stressing wires can occur. 4.4 Evaluation of Salem PCCP In its letter dated July 21, 2011, the licensee stated that the soil corrosivity has been evaluated using AWWA C-105 Soil Test Evaluation of the pH, sulfide, and moisture content readings.
The licensee stated that the results of this evaluation show that the soil has a very low corrosivity.
The NRC staff has evaluated the soil corrosivity using the values of pH, sulfide and moisture content supplied by the licensee and concludes that the soil has a very low corrosivity.
The licensee stated that the buried PCCP at Salem Unit Nos. 1 and 2 has no known history of failure or degradation due to pre-stressing wire breaks or cylinder degradation since it was installed in the 1972-1973 time span. In addition, there has been no degradation of external concrete coating discovered during excavations to date and only superficial degradation of internal concrete lining has been identified during Generic Letter 89-13 inspections.
The licensee's examination of the external surfaces of the carbon steel pipe wall penetration spool showed that the piping was in very good condition, and ultrasonic testing showed a minimum thickness reading of 0.531" or 1 06% of the nominal 0.500" wall, supporting the low soil
-6 corrosivity evaluation.
Based on the results of the licensee's examinations and the soil low corrosivity discussed above, the NRC staff concludes there is reasonable assurance of the structural integrity of the pre-stressing wires. The licensee stated that the subject PCCP sticks are fabricated with an upgraded 10 gauge (0.1345 inches) steel cylinder, as compared to a standard commercial grade 16 gauge (0.0598 inches) steel cylinder.
The 1 O-gauge steel cylinder alone nearly meets the ASME B31.1 design minimum wall requirement for operating pressure of the SW piping without considering the load carrying capacity of the pre-stressing wires. The licensee stated that there is a factor of safety of 2.24 against burst pressure for the 200 psi design pressure and a factor of safety of 2.99 for the 150 psi operating pressure for the steel cylinder alone. The NRC staff finds that although the SW piping at Salem Unit Nos. 1 and 2 is classified as PCCP, the properties and failure mode should more closely resemble those of traditional carbon steel pipe. The NRC staff notes that rupture of the subject SW pipe would require significant generalized corrosion of the steel cylinder, and the voluminous products from such corrosion would likely be readily apparent during visual examination of the concrete liner. Furthermore, the staff expects that there would be extensive water leakage prior to rupture and that leakage should be readily detected during normal walk downs. A previous NRC staff SE of the PCCP at Salem Unit No.1 (Reference
- 4) also concluded:
U[e]xtensive experience with this type of piping has shown that corrosion of the reinforcing tendons and 10 gauge steel liner would result in noticeable water leakage prior to rupture. Consequently, it is very unlikely that a piping failure would result in a total loss of service water before the licensee could initiate a controlled shutdown of the plant." The NRC staff concludes that the combination of low soil corrosivity, high load carrying capacity of the 10 gauge steel cylinder, a service history without failure or significant degradation, visual internal inspection on alternating trains each refueling outage, and periodic walk downs of the surface above the pipe provide reasonable assurance of structural integrity of the SW PCCP, and that performance of the ASME Code-required leak down or flow tests would require extensive modification of the SW system, resulting in hardship without a compensating increase in the level of quality and safety.
5.0 CONCLUSION
Based on the considerations discussed in SE Section 4.0, the NRC staff concludes that the proposed alternative provides reasonable assurance of the structural integrity of the subject components.
Furthermore, the NRC staff concludes that the licensee's compliance with the ASME Code requirements would result in hardship without a compensating increase in the level of quality and safety, Therefore, pursuant to 10 CFR 50,55a(a)(3)(ii), the proposed alternative is authorized for the remainder of the fourth 10-year lSI interval for Salem Unit No, 1, and for the remainder of the third 10-year lSI interval for Salem Unit No, 2. All other requirements of the ASME Code,Section XI for which relief has not been specifically requested remain applicable, including a third party review by the Authorized Nuclear Inservice Inspector.
-7 6.0 PSEG letter (LR-N1 0-0361) dated October 12, 2010, "Request for Relief from ASME Code Pressure Test for Service Water Supply Buried Piping" (ADAMS Package Accession No. ML102920465). PSEG letter (LR-N11-0163) dated July 21, 2011, "Response to Draft NRC Request for Additional Information Regarding Relief Request Nos. S1-14R-102 and S2-13R-104 for ASME Code Pressure Test for Service Water Supply Buried Piping" (ADAMS Accession No. ML112030205). AWWA Research Foundation report dated 2008, "Failure of Prestressed Concrete Cylinder Pipe," prepared by A. Romer, D. Ellison, G. Bell, B. Clark. NRC letter dated December 27,2001, "Salem Nuclear Generating Station, Unit No.1, Issuance of Amendment Re: Emergency Request For Change To Technical Specification (TS) 3/4.7.4, Service Water System (TAC No. MB3528)" (ADAMS Accession Number ML013540096).
Principal Contributor:
J. Wallace September 19, 2011 T. Joyce If you have any questions concerning this matter, please contact the Salem Project Mr. Richard Ennis, at (301) 415-1420.
Docket No. 50-272
Enclosure:
Safety Evaluation cc w/encl: Distribution via Lislserv DISTRIBUTION PUBLIC LPL 1-2 RIF RidsNrrDorlLpl1-2 Resource RidsNrrLAABaxter Resource RidsNrrPMSalem Resource ADAMS Accession No.: ML112420175 Sincerely, IRAI Harold K. Chernoff, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation JMcHale. EDO Region I RidsAcrsAcnw
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- SE dated 8/17/11 LPL1-2/PM LPL 1-2/LA CPNB/BC* LPL 1-2/BC REnnis ABaxter TLu old HChernoff 9/7/11 9/7/11 8/17/11 9/19/11 OFFICIAL RECORD COpy