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] |
Text
PSEG Nuclear LLC
-* P.O. Box 236, Hancocks Bndge, New Jersey 08038-0236 NOV, 2 20OZ UPSEG L Nuclear LLC LRN-02-0394 United States Nuclear Regulatory Commission Document Control Desk Washington, DC' 20555 Gentleman:
REQUEST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST SI-RR-B01 SALEM GENERATING STATION- UNIT I FACILITY OPERATING LICENSE DPR-70 DOCKET NOS. 50-272 By letter dated January 8, 2002, PSEG Nuclear LLC (PSEG) submitted two requests (S1-RR-B01 and S1-RR-C01) for relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section X1, for Salem Generating Station, Unit No. 1 (Salem 1). The requests for relief are for the second 10-year inservice inspection (ISI) interval in which Salem adopted the 1983 Edition of ASME Section XI, including Summer 1983 Addenda, as the Code of record.
The Nuclear Regulatory Commission staff discussed the subject relief requests with PSEG staff on October 18, 2002. In response to the Nuclear Regulatory Commission's request, PSEG Nuclear is providing written clarification of the material composition and configuration of piping associated with the pressurizer relief and spray lines and steam generator nozzle to cast stainless steel elbows.
The Pressurizer relief and spray line 'nozzle to safe-end' welds 6-PR-1 104-1 (Summary No. 023400), 6-PR-1103-1 (Summary No. 024600), 4-PS-1131-29 (Summary No.
033500) and 4-PR-1100-1 (Summary No. 025900) do not contain Alloy 600 type material as evidenced by Attachment I drawing and information.
The Steam Generator nozzle-to-elbow welds 31-RC-1 130-2R1 (Summary No. 039200),
29-RC-1130-5R1 (Summary No. 050210), and 29-RC-1120-5R1 (052600) contain a single bead of Alloy 600 material located on the outside of the pipe. The Alloy 600 material is not in contact with the primary reactor water coolant located on the inside of the piping as evidenced by Attachment 2 drawing and information.
95-2168 REV. 7/99
Document Control Desk NOV 1 2 2002 LRN-01 -0433 Should you have any questions regarding this information, please contact Mr. Howard Berrick at 856-339-1862.
Sinc rely G. Salamo /
Manager - uclear Safety and Licensing
Attachment:
I. Pressurizer Relief and Spray Lines Nozzle to safe-end Weld Configurations II. Steam Generator Nozzle to Cast Stainless Steel Elbow Weld Configurations 2
SDocument Control Desk LRN-02-0394 NOV 12 2002 C Mr. H. Miller Regional Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. Nuclear Regulatory Commission ATTN: Mr. R. Fretz Licensing Project Manager - Salem Mail Stop 08B2 Washington DC 20555-001 USNRC Senior Resident Inspector - Salem (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625 3
Document Control Desk LRN-02-0394 Attachment 1 Pressurizer Relief and Pressurizer Spray Lines Nozzle to Safe-end Weld Configurations I
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Document Control Desk LRN-02-0394 Attachment 2 Steam Generator Nozzle to Cast Stainless Steel Elbow Weld Configurations I
S4Z ., I "S/e * ,&P4,A I .uT PR/M, / -ZZL C, The new welds consists of SA 216 Gr WCC cast nozzle. Inconcl weld bnd 308L o14 weld from the hydro cap welded at Seabrook, 308L nArrow groove weld, v-t*u*u, thicknesses of old weld consisting of ER 316 root and E16-8-2 lur the rcnmuidu oii ill,
-NCL ,oNCL weld deposit welded to the cas elbow A351 CF8M The actuAl width ot the nlia,ih wet.
groove weld is 375, which has a cap weld of ER 308L, bridging the trAnibtiliaw IBA the nozzle and the elbow, measring an average of I 025" wide
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