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Category:Code Relief or Alternative
MONTHYEARML22194A8402022-07-15015 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 ML20091L9992020-04-13013 April 2020 Issuance of Relief Request HC-I4R-190 for the Fourth 10-Year Inservice Inspection 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 ML17223A4832017-08-17017 August 2017 Relief from the Requirements of the ASME Code for Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations 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 ML15281A1202015-11-0202 November 2015 Relief from the Requirements of the ASME Code 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 ML0515201772005-08-29029 August 2005 Evaluation of Relief Request HC-RR-I2-W01 ML0500302112005-08-0202 August 2005 Relief, HC-RR-12-30, MC5174 ML0420102502004-08-27027 August 2004 Evaluation of Relief Request HC-RR-12-023 ML0322504712003-08-26026 August 2003 Evaluation of Relief Request HC-RR-B08 ML0314204812003-05-15015 May 2003 Supplemental Information for Relief Request HC-RR-B11 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 ML0311300042003-04-14014 April 2003 Inservice Inspection Program Relief Request HC-RR-B12 ML0306901772003-02-20020 February 2003 Inservice Inspection Program Relief Request HC-RR-F02 ML0305903472003-02-20020 February 2003 Inservice Inspection Program Relief Request HC-RR-B08 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 2022-07-05
[Table view] Category:Letter
MONTHYEARIR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval 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 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 ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 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 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 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-N23-0065, 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 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) 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 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-N23-0042, 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 IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations 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) 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 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 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-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes 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 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 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 05000354/20220062023-03-0101 March 2023 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2022006) 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-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023 Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges 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 IR 05000354/20220042023-01-24024 January 2023 Integrated Inspection Report 05000354/2022004 LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023 In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments ML22335A0412022-12-0101 December 2022 Notification of Commercial Grade Dedication Inspection (05000354/2023011) and Request for Information IR 05000354/20220032022-11-0303 November 2022 Integrated Inspection Report 05000354/2022003 2024-02-01
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PSEG Nuclear LLC "P.O.Box 236, Hancocks Brndge, New Jersey 08038-0236 FEB 2 0 2003 LRN-03-0068 United States Nuclear Regulatory Commission 0 PSEG NuclearLLC Document Control Desk Washington, DC 20555-001 INSERVICE INSPECTION PROGRAM RELIEF REQUEST HC-RR-B08 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 is submitting inservice relief request HC-RR-B08 for NRC approval.
This relief request is for the ultrasonic examination of the Reactor Pressure Vessel (RPV) nozzle to vessel welds and is expected to reduce personnel radiation exposure and examination time, which translates to significant cost savings while still providing an acceptable level of quality and safety.
PSEG Nuclear, LLC requests to reduce the examination volume to one half inch from the widest part of the RPV nozzle to vessel weld in lieu of the examination volume requirements of Figures IWB-2500-7 (a) and (b) ASME Section XI, 1989 Edition, which is tV2.
The NRC Final Rule amending 10CFR50.55a establishes the requirements for the conduct of the ultrasonic examination and requires PSEG Nuclear to implement Appendix VIII titled "Performance Demonstration for Ultrasonic Examination Systems,"
American Society of Mechanical Engineers (ASME) Section Xl, Division 1, 1995 Edition with the 1996 Addenda, with modifications as stated in the Final Rule.
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 inorder to support Hope Creek refueling outage RFO11 scheduled to commence April 12, 2003.
Similar relief was granted for Salem Units I and 2 [Docket Numbers 50-272 and 50-311 via approved TAC numbers MB1228 and MB3048, dated April 26, 2001 and December 26, 2001, respectively].
Should you have any questions regarding this request, please contact Mr. Howard Berrick at 856-339-1862.
S in r I Manager - Nuclear Safety and Licensing
Attachment:
ISI Relief Request HC-RR-B08 95-2168 REV 7/99
FEB 2 0 2003 Documernt Control Desk LRN-03-0068 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 I LRN-03-0068 Relief Request HC-RR-B08
- 1. ASME Code Component(s) Affected Hope Creek, ASME Section Xl, Class 1, Reactor Pressure Vessel (RPV) Nozzle-to Vessel welds
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
ASME Code, Section Xl, 1989 Edition; Table IWB-2500-1, Examination Category B D Full Penetration Welds of Nozzles in Vessels. Code Item B3.90, Figure IWB-2500 7 (a) & (b), for defining the examination volume requirements, and ASME Code Section Xl 1995 Edition, 1996 Addenda Appendix 1 as required by 10CFR.50.55a for the UT examination requirements.
- 4. Proposed Alternative Pursuant to 1 OCFR50.55a(a)(3)(i), PSEG Nuclear LLC (PSEG) requests relief from the ts/2 examination volume requirements of Figures IWB-2500-7 (a) and (b). PSEG Nuclear proposes to use the reduced volume to one-half (1/2) inch from the widest part of the weld, in lieu of requirements of ASME Section XI Figures IWB-2500-7 (a) and (b).
The following proposed alternatives provide an acceptable level of quality and safety:
- 1) PSEG Nuclear proposes to use the reduced examination volume defined above in lieu of the required volume specified in Table IWB-2500-1 Category B-D of the 1989 Edition of ASME Xl.
- 2) Perform examinations in accordance with ASME Code, Section Xl, Div. 1, 1995 Edition, 1996 Addenda, Appendix VIII Supplement VII
- 3) Periodic system pressure tests per Category B-P, Table IWB-2500-1
- 5. Basis of Alternative for Providing Acceptable Level of Quality and Safety PSEG Nuclear, Hope Creek is currently required to perform inservice examinations of selected welds in accordance with the requirements of 10CFR50.55a, Plant Technical Specifications, and the 1989 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Xl, Rules for In-Service Inspection of Nuclear Power Plant Components.
ProposedAltemative 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 1 LRN-03-0068 Relief Request HC-RR-B08 The Code invokes the (ts/2) examination volume requirements of Figures IWB-2500-7 (a) and IWB-2500-7 (b).
The examination volume for the RPV pressure retaining nozzle-to-vessel welds extend far beyond the weld into the base metal, and is unnecessarily large. This increases the examination time significantly, and results in no net increase in safety, as the area being examined is base metal region which is not prone to inservice cracking and has been extensively examined during construction, preservice examination and during the first inservice examinations with acceptable results. Creation of flaws during plant service is unlikely due to the low stresses in the base metal away from the weld.
Stresses caused by welding are concentrated at and near the weld. 'This relief request would reduce the examination volume next to the widest part of the weld from one half of the vessel wall thickness to one half (1/2") inch.
The reduction of the examination will reduce examination time, which translates to significant cost savings and reduce personnel radiations exposure.
The UT examination of the RPV vessel to nozzle welds will be performed as they have been in previous examinations, from the vessel shell. The examination will utilize Appendix VIII Supplements 4, 6 & 7 as modified by 1 OCFR50.55a.
- 6. Duration of Proposed Alternative Proposed alternative relief is requested for the duration of the second ten year ISI interval at Hope Creek.
- 7. Precedents Previous relief has been granted for Salem Units 1 and 2 [Docket Numbers 50-272 and 50-311 via approved TAC numbers MB1228 and MB3048, dated April 26, 2001 and December 26, 2001, respectively].
ProposedAlternative In Accordance with 10 CFR 50.55a(a)(3)(i)
-- Alternative ProvidesAcceptable Level of Quality and Safety -
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