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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 ML22194A8402022-07-15015 July 2022 Correction Letter of Relief Request No. HR-I4R-220 Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs ML22181A1252022-07-0505 July 2022 Issuance of Relief Request No. HR I4R-220 Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs 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 ML20091L9992020-04-13013 April 2020 Issuance of Relief Request HC-I4R-190 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 ML19220A1022019-09-0606 September 2019 Alternative Request VR-03 to Use ASME Code Case OMN-17, Alternative Rules for Testing ASME Class 1 Pressure Relief/Safety Valve for the Fourth 10-Year Inservice Test Interval ML19136A0262019-07-11011 July 2019 Issuance of Relief Request No. HC-I3R-08, Revision 0, Use of the ASME Code LR-N18-0087, Submittal of Relief Request Associated with the Third Inservice Inspection (ISI) Interval2018-09-24024 September 2018 Submittal of Relief Request Associated with the Third Inservice Inspection (ISI) 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 ML17223A4832017-08-17017 August 2017 Relief from the Requirements of the ASME Code for Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations ML17132A0052017-05-19019 May 2017 Alternative Request to Adopt American Society of Mechanical Engineers Code Case OMN-20 (CAC Nos. MF8313 and MF8314) ML16343A0572016-12-20020 December 2016 Requests for Relief GR-01, PR-01, PR-02, VR-01, and VR-02, for the Fourth Inservice Testing Interval ML15349A9562015-12-24024 December 2015 Relief from the Requirements of the ASME Code ML15281A1202015-11-0202 November 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 ML0824700632008-10-16016 October 2008 Safety Evaluation of Relief Requests for the Third 10-Year Interval of the Inservice Inspection Program for Hope Creek Generating Station 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 ML0515201772005-08-29029 August 2005 Evaluation of Relief Request HC-RR-I2-W01 ML0500302112005-08-0202 August 2005 Relief, HC-RR-12-30, MC5174 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 ML0420102502004-08-27027 August 2004 Evaluation of Relief Request HC-RR-12-023 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 ML0322504712003-08-26026 August 2003 Evaluation of Relief Request HC-RR-B08 ML0320902002003-07-28028 July 2003 Relief, Relief from ASME Code Requirements Related to the Salem Inservice Inspection Program, Relief Request S1-RR-F01, MB6098 ML0314204812003-05-15015 May 2003 Supplemental Information for Relief Request HC-RR-B11 ML0311300042003-04-14014 April 2003 Inservice Inspection Program Relief Request HC-RR-B12 ML0311300072003-04-14014 April 2003 Code Relief, Alternative to Required Volumetric Examination for Nozzles Where Plant Configuration Is Such That Visual Examination of Inner Radius May Be Performed on Essentially 100 Percent of Inner Radius 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 ML0305903472003-02-20020 February 2003 Inservice Inspection Program Relief Request HC-RR-B08 ML0306901772003-02-20020 February 2003 Inservice Inspection Program Relief Request HC-RR-F02 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 2023-02-02
[Table view] 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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PSEG Nuclear LLC P 0 Box 236, Hancocks Bridge, New Jersey 08038-0236 FEB 2 0 2003 LRN-03-0054 United States Nuclear Regulatory Commission Document Control Desk0 o PSE PsE" Washington, DC 20555-001 NuclearLLC INSERVICE INSPECTION PROGRAM RELIEF REQUEST HC-RR-A02 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSES NPF-57 DOCKET NOS. 50-354 Pursuant to 10 CFR 50.55a(a)(3)(i), PSEG Nuclear, LLC requests relief to incorporate the alternate examination requirements of ASME Code Case N-598, Alternative Requirements to Required Percentagesof Examinations,Section XI Division ', to determine the required percentage of examinations each inspection period for Class 1, 2, and 3 components and associated component supports at Hope Creek.
The attachment to this letter includes the proposed alternative and supporting justification for the relief. Based on the evaluation contained in the attachment, PSEG Nuclear has concluded that the proposed alternative provides an acceptable level of quality and safety. Accordingly, this proposal satisfies the requirements of 10 CFR 50.55a(a)(3)(i).
This relief request is applicable to PSEG Nuclear LLC Hope Creek Generating Station. PSEG Nuclear requests that the NRC approve this request by April 2003 in order to support Hope Creek refueling outage RFO1E1 scheduled to commence April 12, 2003. Similar relief has been granted for Salem Units I and 2 [Docket Numbers 50-272 and 50-311 via approved TAC numbers MB6086 and MB6087, respectively, dated October 4, 2002].
Should you have any questions regarding this request, please contact Mr.
Howard Berrick at 856-339-1862.
G. Salamon Manager - Nuclear Safety and Licensing
Attachment:
ISI Relief Request HC-RR-A02 AOV-7 95-2168 REV 7/99
Documept Control Desk LR-N03-0054 C Mr. H. Miller, Administrator Regional Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission ATTN: Mr. G. Wunder Licensing Project Manager - Hope Creek Mail Stop 08C2 Washington, DC 20555-001 USNRC Senior Resident Inspector - Hope Creek (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625 Page 2 of 4
Document Control Desk Attachment 1 LR-N03-0054 Relief Request HC-RR-A02
- 1. ASME Code Component(s) Affected ASME Section X1 Class 1, 2, 3 component and their component supports.
2. Applicable Code Edition and Addenda
The code of record for Hope Creek ISI Program is Section Xl of the ASME Code, 1989 Edition.
3. Applicable Code Requirement
For Hope Creek, ASME Xl 1986 Edition subparagraphs IWB-2412, IWC 2412, IWD-2412, IWF-2410; and Tables IWB IWB-2412-1, IWC-2412-1, IWD 2412-1 and Table -2410-2 of Code Case N-491-1 require approximately one third of the Code examinations be performed each inspection period and that 100 percent of the examinations be completed each inspection interval.
- 4. Proposed Alternative PSEG Nuclear, LLC proposes to fully implement the alternative requirements of Code Case N-598 for Class 1, 2, and 3 components, and their associated Component Supports.
- 5. Basis of Alternative for Providing Acceptable Level of Quality and Safety Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternative provides an acceptable level of quality and safety.
PSEG Nuclear, LLC requests relief to incorporate the alternate examination requirements of ASME Code Case N-598, titled 'Alternative Requirements to Required Percentages of Examinations, Section Xl Division 1V, to determine the required percentage of examinations each inspection period for Class 1, 2, and 3 components and associated component supports at Hope Creek.
Although Code Case N-598 also addresses Class MC components, relief is not being requested for scheduling of Class MC components in this Request for Alternative.
The ASME Code tables referenced above were originally established such that approximately one third of the non-deferred examinations would be performed each period. Over the past 20 years, it has become increasingly more difficult to meet these percentages. The emergence of longer fuel cycles increases the likelihood that one of the periods will only have one refueling outage in it. In addition, efforts to shorten refueling outages have limited the amount of time available to perform examinations. These factors have made it difficult to complete the Code required percentages of examinations in the allotted time.
Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
-- Alternative Provides Acceptable Level of Quality and Safety --
Page 3 of 4
Document Control Desk Attachment I ILR-N03-0054 Relief Request HC-RR-A02 Code Case N-598 was developed to address this issue. It expands the range of examination completion percentages to allow examinations to be distributed more evenly between outages. This minimizes the need to schedule an excessive number of examinations during one outage just to meet the percentages required by ASME,Section XI, Tables IWB-2412-1, IWC-2412-1, IWD-2412-1, and IWF-2410-2 (-2410-2). In addition, Code Case N-598 allows for a more uniform distribution between outages that is more conducive to performing quality examinations.
During the development cf Code Case N-598, two additional factors were considered when evaluating the impact of the Code Case on plant safety.
The first was that the existing tables allow up to 50 percent of the examinations to be performed in the second and third periods, but only 34 percent can be performed in the first period. Therefore, the Inspection Plan B schedule is biased towards delaying examinations until the end of the interval.
The more flexible percentages stated in Code Case N-598 allow for more examinations to be performed earlier in the interval. This should improve safety because any problems, should they exist, would be detected earlier in the interval.
The second factor that was considered when developing Code Case N-598 was that some minimum amount of examinations should be required in each period. To address this consideration, the Code Case, including Note (1), is structured such that examinations will be required during all three periods.
Due to the factors documented above, PSEG Nuclear, LLC considers that the alternative criteria of Code Case N-598 provide an acceptable, or improved, level of quality and safety during the Second Ten-Year Inspection Interval at Hope Creek Granting the proposed alternative will provide an acceptable level of quality and safety, and will not adversely impact the health and safety of the public.
- 6. Duration of Proposed Alternative Proposed alternative relief is requested for the duration of the second ten year ISI interval at Hope Creek. The use of the Code Case is requested until the NRC publishes the Code Case in a future revision of the applicable Regulatory Guide.
- 7. Precedents Previous relief has been granted for Salem Units 1 and 2 [Docket Numbers 50-272 and 50-311 via approved TAC numbers MB6086 and MB6087, respectively, dated October 4, 2002].
- 8. References None Proposed Alternative In Accorddnce with 10 CFR 50.55a(a)(3)(i)
- Alternative Provides Acceptable Level of Quality and Safety -
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