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Category:Letter
MONTHYEARIR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval IR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 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 IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 ML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers 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 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 ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement 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 IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 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) IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report 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) IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) 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 IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration 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 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) 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-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 IR 05000354/20230012023-04-26026 April 2023 Integrated Inspection Report 05000354/2023001 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 LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains 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 2024-02-05
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4 PSEG Nuclear LLC P.O. Box 236, Hancocks Bndge, New Jersey 08038-0236 LRN-02-0318 United States Nuclear Regulatory Commission SEP 1 0 2002 PSEG Document Control Desk Washington, DC 20555 NuclearLLC Gentlemen:
REQUEST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST SH-RR-W01 SALEM GENERATING STATIONS UNIT I and 2 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSES DPR-70, DPR-75 and NPF-57 DOCKET NOS. 50-272, 50-311 AND 50-354 By letter dated April 1, 2002, PSEG Nuclear LLC (PSEG) submitted the subject request for relief from the requirements for welding and brazing procedure qualifications as stated in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, for Salem Generating Station, Units 1 and 2, and Hope Creek Generating Station. The request also included relief for all Procedure Qualification Records (PQR) supporting alternative procedures in accordance with ASME,Section XI, IWA-4500.
The Nuclear Regulatory Commission staff discussed the subject relief request with PSEG staff by telephone on September 4, 2002, and requested additional clarification on information provided. Pursuant to that request, PSEG is submitting the enclosed response to the request for additional clarification.
Should you have any questions regarding this request, please contact Mr. Howard Berrick at 856-339-1862.
Sin rell Manager - Nuclear Safety and Licensing Enclosure 95-2168 REV 7/99
Document Control Desk ' SEP 1 0 2002 LRN-02-0318 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 U.S. Nuclear Regulatory Commission ATTN: Mr. G. Wunder Licensing Project Manager - Hope Creek Mail Stop 08B1 Washingtorn DC 20555-001 USNRC Senior Resident Inspector - Salem (X24)
USNRC Senior Resident Inspector - Hope Creek (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625
Document Control Desk ENCLOSURE LRN 0318 ADDITIONAL INFORMATION SALEM NUCLEAR GENERATING STATIONS, UNITS NO. I AND 2 HOPE CREEK GENERATING STATION By letter dated April 1, 2002, PSEG Nuclear LLC (PSEG) submitted the subject request for relief from the requirements for welding and brazing procedure qualifications as stated in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, for Salem Generating Station, Units 1 and 2, and Hope Creek Generating Station. The request also included relief for all Procedure Qualification Records (PQR) supporting alternative procedures in accordance with ASME,Section XI, IWA-4500.
The Nuclear Regulatory Commission staff discussed the subject relief request with PSEG staff by telephone on September 4, 2002. The NRC requested that additional clarification be provided regarding why PSEG Nuclear LLC, in its request for approval to utilize ASME Section Xl, Code Case N-573, Transferof Procedure QualificationRecords Between Owners, specifically only referenced ASME Section Xl, 1995 Edition, 1996 Addenda and articles IWA 4440 and IWA-4600. Pursuant to that request, PSEG is submitting the enclosed response.
PSEG Response: PSEG Nuclear LLC operating licenses include the Salem Unit 1, Salem Unit 2 and Hope Creek plants. For the individual plant's respective Inservice Inspection (ISI) programs, Salem Unit 1 is presently committed to ASME Section Xl, 1995 Edition, 1996 Addenda; Salem Unit 2 is committed to ASME Section Xl, 1986 Edition; and Hope Creek is committed to ASME Section XI, 1989 Edition.
Unlike the individual ISI programs, the PSEG Nuclear LLC Repair Program, which implements ASME Section XI Repair and Replacement requirements, is applicable to Salem Unit 1, Salem Unit 2, and Hope Creek and is commonly scoped to meet ASME Section Xl, 1995 Edition, 1996 Addenda. The Repair Program has been developed in this manner in order to unify and simplify the requirements for the engineering and maintenance organizations that support the day-to-day implementation of the ASME Section Xl Repair and Replacement requirements.
The adoption of a later code edition for Repairs and Replacements is authorized in ASME Section Xl, Code Case N-389-1, Alternative Rules for Repairs, Replacements or Modifications. The code case states, in part, "that editions and addenda of ASME Section Xl subsequent to those referenced in the plants In-Service Inspection may be used for repairs, replacements and modifications", provided the subsequent edition and addenda have been accepted by the Regulatory and Jurisdictional authorities having jurisdiction at the plant site. The NRC has accepted Code Case N-389-1 without exception via Regulatory Guide 1.147, In-Service Inspection Code Case Acceptability, ASME Section Xl, Division 1.
Therefore, PSEG Nuclear LLC was able, within the parameters of both Code Case N-389-1 and Regulatory Guide 1.147, to update the basis for its common Repair Program to a single version of the ASME Section Xl Code, which is 1995 Edition, 1996 Addenda.
Since ASME Section XI, Code Case N-573, Transferof Procedure QualificationRecords Between Owners, addresses welding related functions which are activities controlled by ASME Section Xl, IWA-4000 Repair I Replacement requirements, it is appropriate to cite the single edition and addenda (i.e., 1995 Edition, 1996 Addenda) of ASME Section XI that was referenced in the PSEG Nuclear relief request submittal letter LRN-02-0115, dated April 1, 2002.