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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
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22333A9022022-11-29029 November 2022 NRR E-mail Capture - Final Iolb RAI - Salem 1 and 2 LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG ML22318A1062022-11-14014 November 2022 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000272/2023011 and 05000311/2023011 ML22290A2202022-10-17017 October 2022 NRR E-mail Capture - Final RAI - Salem 1 and 2 LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG ML22055A0702022-02-22022 February 2022 NRR E-mail Capture - Final RAI - Salem 1-Relief Request Associated with Fourth Inservice Inspection (ISI) Interval Limited Examinations (L-2021-LLR-0085) ML22006A3212022-01-0606 January 2022 NRR E-mail Capture - Final RAI - Hope Creek - Revise TS Limits for Ultimate Heat Sink ML21300A0222021-10-27027 October 2021 Notification of Conduct of a Fire Protection Team Inspection ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21068A4142021-03-0909 March 2021 NRR E-mail Capture - Final RAI for Salem Unit 1 LAR to Revise and Relocate Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report ML21041A3972021-02-18018 February 2021 Request for Additional Information Revise Low Pressure Safety Limit to Address General Electric Part-21 Safety Communications (Non-Proprietary) ML21043A1442021-02-11011 February 2021 NRR E-mail Capture - Salem - Final RAI Alternative for Examination of ASME Section XI, Category B-B, Item Number B2.11and B2.12 (L-2020-LRR-0103) ML21021A2592021-01-21021 January 2021 NRR E-mail Capture - Final RAI - Salem 1 - Steam Generator Tube Inspection Report ML20295A4922020-10-21021 October 2020 NRR E-mail Capture - Hope Creek - Final RAI Revise ECCS TS with Respect to HPCI System Inoperability (L-2020-LLA-0131) ML20281A5172020-10-13013 October 2020 Notification of Conduct of a Fire Protection Team Inspection ML18267A1712018-09-21021 September 2018 NRR E-mail Capture - Final RAI from PRA Branch: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140) ML18264A0122018-09-20020 September 2018 NRR E-mail Capture - Final RAI from I&C Branch: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140) ML18263A1442018-09-12012 September 2018 NRR E-mail Capture - Final RAI from Apla: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18250A3132018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140) ML18250A3142018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18171A3212018-06-20020 June 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Adopt TSTF-411 and 418 (L-2017-LLA-0442) ML18150A6912018-05-30030 May 2018 NRR E-mail Capture - Hope Creek - Final RAI Revise TS to Adopt TSTF-542 ML18120A2482018-04-27027 April 2018 Information Request for the Cyber-Security Inspection, Notification to Perform Inspection 05000354/2018403 ML18094B0832018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to P. Duke RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for Salem and Hope Creek, and Peach Bottom ISFSIs Docket Nos. 72-48 and 72-29) ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML17349A0812017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Reactor Systems Branch (Srxb) - Hope Creek Mur ML17348A9972017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17348A6242017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Human Factors Associated with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17331A0072017-11-21021 November 2017 E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate ML17348A6282017-11-21021 November 2017 NRR E-mail Capture - Draft Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17324A2602017-11-17017 November 2017 NRR E-mail Capture - Final Request for Additional Information - Hope Creek Mur Electrical Instrumentation and Controls ML17320A2152017-11-16016 November 2017 NRR E-mail Capture - Hope Creek Measurement Uncertainty Recapture Application Review - Electrical Engineering (Eeob) Request for Additional Information (L-2017-LLS-0002) ML17290B0132017-10-17017 October 2017 NRR E-mail Capture - Hope Creek Mur Request for Additional Information for Apla and Snpb ML17222A1652017-08-10010 August 2017 NRR E-mail Capture - Hope Creek: Final Request for Information, Pressure-Temperature Limit Report Request (MF9502) ML17212B1152017-07-31031 July 2017 Request for Additional Information - Salem Units 1 and 2 - Containment Fan Coil Unit Allowed Outage Time Amendment Request (CACs MF9364 and MF9365) ML17199A1122017-07-18018 July 2017 Request for Additional Information - Salem Units 1 and 2 - Accident Monitoring Instrumentation License Amendment Request (CAC Nos. MF8859 & MF8860) ML17192A1672017-07-11011 July 2017 Request for Additional Information - Salem Unit 1 - Steam Generator Tube Inspection Report ML17181A1352017-06-29029 June 2017 NRR E-mail Capture - Request for Additional Information Related to Hope Creek and Salem Emergency Action Level Scheme Change License Amendment Request (MF9268/69/70) ML17164A4062017-06-13013 June 2017 NRR E-mail Capture - Hope Creek - Final Request for Additional Information Concerning ILRT (MF8462) ML17115A4032017-05-0909 May 2017 Request for Additional Information Regarding Relief Request SC-14R-171 - Use of Code Cases N-695-1 and N-696-1 ML17027A3282017-02-27027 February 2017 Request for Additional Information Regarding License Amendment Request to Permanently Extend Type a and Type C Leak Rate Test Frequencies ML16321A4642016-11-21021 November 2016 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding License Amendment Request to Remove Certain Training Requirements ML16277A5142016-11-0303 November 2016 Request for Additional Information Regarding License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling ML16271A2052016-11-0202 November 2016 Request for Additional Information Regarding Request to Delete Technical Specifications Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves ML16231A4272016-08-24024 August 2016 Request for Additional Information Regarding Relief Request VR-02, Associated with the Fourth 10-Year Inservice Test Interval ML16217A4302016-08-17017 August 2016 Request for Additional Information Regarding Digital Power Range Neutron Monitoring System Upgrade ML16218A0052016-08-11011 August 2016 Request for Additional Information Concerning Request for an Extension to Enforcement Guidance Memorandum 12-001 ML16195A4492016-07-14014 July 2016 Request for Additional Information Regarding Chilled Water System Modifications ML16188A4152016-07-0707 July 2016 Request for Additional Information Aging Management Program Plan for Reactor Vessel Internals ML16007A1742016-05-31031 May 2016 Request for Additional Information Regarding Review of Post-EPU Steam Dryer Stress Calculation Acoustic Circuit Model Software Error ML16089A0792016-05-0505 May 2016 Request for Additional Information Regarding Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, Associated with the Fourth 10-Year Inservice Test Interval 2022-02-22
[Table view] |
Text
January 5, 2010 Mr. Thomas Joyce, President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING SCOPING OF METAL FATIGUE FOR THE SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2, AND THE HOPE CREEK GENERATING STATION
Dear Mr. Joyce:
By letter dated August 18, 2009, as supplemented by letter dated January 23, 2009, Public Service Enterprise Group Nuclear, LLC (PSEG), submitted an application pursuant to Title 10 of the Code of Federal Regulations, Part 54 (10 CFR Part 54) for renewal of Operating License Nos. DPR-70, DPR-75, and NPF-57 for Salem Nuclear Generating Station (SALEM), Units 1 and 2, and Hope Creek Generating Station (HCGS), respectively. The staff of the U.S. Nuclear Regulatory Commission (the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. During its review, the staff has identified areas where additional information is needed to complete the review. The staffs requests for additional information are included in the enclosure. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Mr. John Hufnagel, of the License Renewal Project staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-3191 or by e-mail at Donnie.Ashley@nrc.gov.
Sincerely,
/RA/
Donnie J. Ashley, Senior Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-272, 50-311, and 50-354
Enclosure:
As stated cc w/encl: See next page
ML093360238 OFFICE PM:RPB1:DLR LA:RPOB:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME D. Ashley S. Figueroa B. Pham D. Ashley (Signature)
DATE 12/03/09 12/03/09 12/03/09 01/05/10 Letter to Thomas Joyce from Donnie J. Ashley dated January 5, 2010
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING SCOPING OF FIRE PROTECTION AND METAL FATIGUE FOR THE SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 AND THE HOPE CREEK GENERATING STATION DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RdsNrrDlrRer1 Resource RidsNrrDlrRer2 Resource RidsOgcMailCenter Resource DPelton DAshley JRobinson REnnis MModes, RI JBrand, RI RConte, RI RBellamy, RI PBamford, RI MMcLaughlin, RI
Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. Robert Braun Mr. Paul Bauldauf, P.E., Asst. Director Station Vice President - Salem Radiation Protection Programs PSEG Nuclear LLC NJ Department of Environmental One Alloway Creek Neck Road Protection and Energy, CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. John Perry Mr. Brian Beam Station Vice President - Hope Creek Board of Public Utilities PSEG Nuclear 2 Gateway Center, Tenth Floor P.O. Box 236 Newark, NJ 07102 Hancocks Bridge, NJ 08038 Regional Administrator, Region I Mr. Carl Fricker U.S. Nuclear Regulatory Commission Vice President - Operations Support 475 Allendale Road PSEG Nuclear LLC King of Prussia, PA 19406 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Senior Resident Inspector Salem Nuclear Generating Station Mr. Jeffrie J. Keenan, Esquire U.S. Nuclear Regulatory Commission Manager - Licensing Drawer 0509 PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Senior Resident Inspector Hope Creek Generating Station Mr. William Mattingly U.S. Nuclear Regulatory Commission Manager - Salem Regulatory Assurance Drawer 0509 PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Michael Gallagher Vice President - License Renewal Projects Mr. Michael Gaffney Exelon Nuclear LLC Manager - Hope Creek Regulatory 200 Exelon Way Assurance Kennett Square, PA 19348 PSEG Nuclear LLC One Alloway Creek Neck Road Mr. Ed Eilola Hancocks Bridge, NJ 08038 Plant Manager - Salem PSEG Nuclear LLC Township Clerk One Alloway Creek Neck Road Lower Alloways Creek Township Hancocks Bridge, NJ 08038 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Mr. Larry Wagner Plant Manager - Hope Creek PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038
Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. Paul Davison Director - Nuclear Oversight PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Ms. Christine Neely Director - Regulator Affairs PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Ali Fakhar Manager, License Renewal Salem PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. James Stavely Manager, License Renewal Hope Creek PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079
REQUEST FOR ADDITIONAL INFORMATION REGARDING SCOPING OF METAL FATIGUE FOR SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2, AND HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (LRA)
RAI S 4.4.3-1 In the Salem Nuclear Generating Station (Salem) LRA, the background information on leak-before-break (LBB) analysis in Section 4.4.3 does not contain enough information to evaluate the application for this analysis.
Please provide the following information:
- 1. References for the original LBB reports for the LBB-approved piping for both units.
- 2. Besides the primary loop piping, identify any other piping systems that have been approved for LBB for both units.
RAI S 4.4.3-2 On Page 4-49 of the Salem LRA, the applicant discussed 60-year LBB analyses which were based on the steam generator snubber elimination program, steam generator replacement, power uprate, Tavg operating window, and the mechanical stress improvement process application.
Please provide the following information:
- 1. Reference the report that contains the 60-year analyses.
- 2. It is not clear whether the 60-year LBB analyses were performed following the same methodology as that of the original LBB analyses or were a study to determine the impact on the LBB piping from various load changes due to changes in operating conditions. Describe in detail the 60-year LBB analyses or submit the analyses for staff review.
RAI S 4.4.3-3 On page 4-50 of the Salem LRA, the applicant stated that the piping systems include cast austenitic stainless steel piping components. Identify each of the cast austenitic stainless steel piping components that are part of the LBB-approved piping.
RAI S 4.4.3-4 Nickel-based Alloy 600/82/182 material in the pressurized water reactor environment has been shown to be susceptible to primary water stress corrosion cracking (PWSCC).
ENCLOSURE
Please provide the following information:
- 1. Identify any Alloy 82/182 weld metal and Alloy 600 components used in the LBB-approved piping for both units.
- 2. If LBB piping, identified in the Salem LRA, contains Alloy 600/82/182 material, discuss any measures (such as weld overlays or mechanical stress improvement) that have been or will be implemented to reduce the susceptibility of PWSCC in the LBB piping components.
- 3. Discuss the inspection history and future inspection frequency of the Alloy 82/182 dissimilar metal butt welds.
RAI S 4.4.3-5 As part of reviewing the Salem Time-Limited Aging Analysis (TLAA) of the LBB-approved piping, please provide the following information regarding the maintenance of the structural integrity of the LBB piping:
- 1. Discuss the inspection history and results of the LBB-approved piping.
- 2. If indications or flaws are remained in service in the LBB piping, discuss how the indications and flaws are monitored to ensure the structural integrity of the pipe to the end of the period of extended operation.
- 3. Discuss future inspection schedules for each of the LBB pipes, including the inspection of the existing flaws.
RAI S 4.4.3-6 On page 4-50 of the Salem LRA, the applicant stated that the numbers of design cycles assumed in the LBB analyses bound the numbers of design cycles projected for 60 years of operation. Discuss how the design cycles assumed in the LBB analysis are verified to ensure that they bound the numbers of design cycles projected for 60 years of operation.
RAI S 4.4.3-7 On page 4-50 of the Salem LRA, under Disposition: Validation, the applicant stated that The
[LBB] analyses remain valid for the period of extended operation Discuss how the LBB analyses are verified to demonstrate that they remain valid for the period of extended operation.