Letter Sequence RAI |
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TAC:ME1834, Control Room Habitability (Approved, Closed) TAC:ME1836, Control Room Habitability (Approved, Closed) |
Results
Other: LR-N16-0144, Completion of Activities to Support Entry Into the Period of Extended Operation, ML092400531, ML092400532, ML092430231, ML092460442, ML092470039, ML092520185, ML092650382, ML092660174, ML092660447, ML100850459, ML102280211, ML102430586, ML11125A024
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MONTHYEARLR-N09-0192, Information to Support NRC Staff Review of the Application for Renewed Operating License2009-08-18018 August 2009 Information to Support NRC Staff Review of the Application for Renewed Operating License Project stage: Request LR-N09-0161, PSEG Nuclear, Salem Nuclear Generating Station, Units 1 and 2, Transmittal of License Renewal Application2009-08-18018 August 2009 PSEG Nuclear, Salem Nuclear Generating Station, Units 1 and 2, Transmittal of License Renewal Application Project stage: Request ML0924005312009-08-18018 August 2009 PSEG Nuclear, Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application, Volume 2 of 3 Project stage: Other ML0924302312009-08-18018 August 2009 PSEG Nuclear, Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application, Volume 1 of 3 Project stage: Other ML0924005322009-08-18018 August 2009 PSEG Nuclear, Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application, Volume 3 of 3 Project stage: Other ML0924604422009-09-0303 September 2009 Delaware Citizen Comment on Salem Hope Creek License Renewal Application Project stage: Other ML0924700392009-09-0404 September 2009 Comment on Salem - Hope Creek License Renewal Applications from Citizen Project stage: Other ML0926601742009-09-0707 September 2009 Comment on License Renewal for Salem and Hope Creek Power Plants - Goodman Project stage: Other ML0925201852009-09-0808 September 2009 Comments About Relicensing Salem and Hope Creek Reactors in Nj, Steven Hegedus Project stage: Other ML0926503822009-09-0808 September 2009 Citizen Comment on Salem Hope Creek License Renewal Application Project stage: Other ML0926604472009-09-23023 September 2009 Hope Creek, E-mail from Ruth Panella Comments on License Renewal Project stage: Other ML1008502062010-03-24024 March 2010 Task Order No. 004 Under Delivery Order No. NRC-DR-03-09-061 Project stage: Acceptance Review ML1008504592010-04-0606 April 2010 Project Manager Change for the License Renewal of Salem Nuclear Generating Station, Units 1 and 2 (TAC No. ME1834 and ME1836) Project stage: Other ML1007606612010-04-14014 April 2010 RAI Regarding Balance of Plant Scoping and Screening Results for the Salem Nuclear Generating Station Units 1 & 2 (Tac Nos. ME1834 and ME1836) Project stage: RAI ML1013805112010-05-24024 May 2010 Request for Additional Information for the Salem Generating Station, Units 1 and 2, License Renewal Application, Section 3.3.2 (TAC Nos ME1836 and ME1834) Project stage: RAI LR-N10-0191, Response to NRC Request for Additional Information Dated April 30, 2010, Regarding Scoping and Screening Methodology for License Renewal Application2010-05-28028 May 2010 Response to NRC Request for Additional Information Dated April 30, 2010, Regarding Scoping and Screening Methodology for License Renewal Application Project stage: Response to RAI ML1014600612010-06-0707 June 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application Regarding Section 3.5 (TAC Nos. ME1834 and ME1836) Project stage: RAI ML1014400812010-06-10010 June 2010 Request for Additional Information for the Review of the Salem Generating Station, Unit 1 and Unit 2, License Renewal Application Identified During the Audit (TAC ME1836 and ME1834) Project stage: RAI ML1014600772010-06-10010 June 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC ME1832 and ME1836) Project stage: RAI ML1014810092010-06-11011 June 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application Project stage: RAI ML1015504712010-06-11011 June 2010 RAI for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application Sections 3.1.2 and 3.3.2 (TAC No ME1834/ME1836) Project stage: RAI ML1014801892010-06-14014 June 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application Regarding Sections 4.3 and 4.4 (TAC Nos. ME1834 and ME1836) Project stage: RAI ML1013905372010-06-17017 June 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application(Tac Nos ME1834, ME1836) Project stage: RAI ML1016201902010-06-25025 June 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2, License Renewal Application (Tac ME1834/ME1836) Project stage: RAI ML1016804022010-06-29029 June 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2, License Renewal Application Regarding Subsection 3.1.2.2.14 (TAC ME1834/ME1836) Project stage: RAI ML1014807262010-06-30030 June 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application Regarding Section B.3.1.1 (TAC Nos. ME1834 and ME1836) Project stage: RAI ML1017203642010-07-12012 July 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1&2 LRA Regarding ASME Section XI ISI, Subsections Iwb,Iwc, and Iwd (TAC Nos. ME1834/ME1836) Project stage: RAI LR-N10-0243, Response to NRC Request for Additional Information Dated June 14, 2010, Related to Sections 4.3 and 4.4 License Renewal Application2010-07-13013 July 2010 Response to NRC Request for Additional Information Dated June 14, 2010, Related to Sections 4.3 and 4.4 License Renewal Application Project stage: Response to RAI ML1019504872010-07-19019 July 2010 Request for Additional Information for the Salem Generating Station, Unit 1 and Unit 2, License Renewal Application, Section 4.6 (TAC Nos. ME1834 and ME1836) Project stage: RAI ML1019606342010-07-23023 July 2010 Request for Additional Information for the Salem Generating Station, Unit 1 and Unit 2, License Renewal Application (TAC ME1834 and ME1836) Project stage: RAI ML1019304962010-07-30030 July 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC No. ME1834 and Me 1836) Project stage: RAI ML1019504792010-08-0303 August 2010 Request for Additional Information Regarding ASME Section XI, Subsection IWE for the Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC Nos. ME1834 and ME1836) Project stage: RAI ML1019704742010-08-0303 August 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application Regarding Bolting Integrity (TAC Nos. ME1834 and ME1836) Project stage: RAI ML1015402422010-08-0606 August 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application for Buried Piping Inspection Program (TAC Nos. ME1834 and ME1836) Project stage: RAI ML1020004042010-08-0909 August 2010 Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC Nos. ME1834 and ME1836) Project stage: RAI LR-N10-0295, Responses to NRC Requests for Additional Information Dated July 12, 2010, July 19, 2010 and July 23, 2010 Related to Various Sections of License Renewal Application2010-08-10010 August 2010 Responses to NRC Requests for Additional Information Dated July 12, 2010, July 19, 2010 and July 23, 2010 Related to Various Sections of License Renewal Application Project stage: Response to RAI ML1020304172010-08-19019 August 2010 RAI Regarding the Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC ME1834 & ME1836) Project stage: RAI ML1022802112010-08-25025 August 2010 Scoping and Screening Audit Summary Regarding the Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application Project stage: Other LR-N10-0313, Responses to Request for Additional Information Dated 08/03/10, Related to Bolting Integrity and 07/30/10 to Steam Generators and Question Posed During Region 1 Inspection, Regarding License Renewal Application2010-08-26026 August 2010 Responses to Request for Additional Information Dated 08/03/10, Related to Bolting Integrity and 07/30/10 to Steam Generators and Question Posed During Region 1 Inspection, Regarding License Renewal Application Project stage: Response to RAI LR-N10-0322, Response to NRC Request for Additional Information, Dated August 6, 2010 Related to the Buried Piping Inspection Program Associated with License Renewal Application2010-09-0707 September 2010 Response to NRC Request for Additional Information, Dated August 6, 2010 Related to the Buried Piping Inspection Program Associated with License Renewal Application Project stage: Response to RAI ML1024600782010-09-29029 September 2010 RAI for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC Nos. ME1834 and ME1836) Project stage: RAI ML1026003402010-10-12012 October 2010 RAI for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application for Buried Piping Inspection Program (TAC No. ME1834 and ME1836) Project stage: RAI ML1029102492010-10-25025 October 2010 Request for Additional Information for Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application on Structures Monitoring (TAC No. ME1834 and ME1836) Project stage: RAI ML1029300492010-11-0404 November 2010 Request for Additional Information for Salem Nuclear Generating Station, Units 1 and 2, LRA on Primary Water Stress Corrosion Cracking in Steam Generator Tube-to-Tube Sheet Welds Project stage: RAI ML1030101002010-11-0404 November 2010 Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station, Units 1 and 2 Project stage: Approval ML1031201722010-11-0404 November 2010 Safety Evaluation Report with Open Items Related to the License Renewal of Salem Nuclear Generating Station, Units 1 and 2 Project stage: Approval ML1024305862010-11-0909 November 2010 Audit Report Regarding the Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application (TAC Nos. ME1834 and ME1836) Project stage: Other ML1028101942010-11-22022 November 2010 RAI for Salem Nuclear Generating Station Units 1 and 2 LRA for Use of Westems Program in Metal Fatigue Analysis Project stage: RAI ML1032700762010-12-10010 December 2010 RAI for Salem Nuclear Generating Station Units 1 and 2 LRA Project stage: RAI LR-N10-0414, Response to NRC Request for Additional Information, Dated October 25, 2010, Related to Structures Monitoring Associated with License Renewal Application2010-12-14014 December 2010 Response to NRC Request for Additional Information, Dated October 25, 2010, Related to Structures Monitoring Associated with License Renewal Application Project stage: Response to RAI 2010-06-11
[Table View] |
Similar Documents at Salem |
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Category:Letter
MONTHYEARIR 05000272/20240022024-07-30030 July 2024 Integrated Inspection Report 05000272/2024002 and 05000311/2024002 LR-N24-0012, Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding2024-07-24024 July 2024 Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding ML24145A1772024-07-15015 July 2024 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary IR 05000272/20245012024-06-12012 June 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Emergency Preparedness Biennial Exercise Inspection Report 05000354/2024501, 05000272/2024501 and 05000311/2024501 ML24099A1572024-05-29029 May 2024 Issuance of Amendment Nos. 348 and 330 Permanent Extension of Type a and Type C Containment Leak Rate Test Frequencies ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024 Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response IR 05000272/20240102024-05-16016 May 2024 Fire Protection Team Inspection Report 05000272/2024010 and 05000311/2024010 IR 05000272/20240012024-05-0707 May 2024 Integrated Inspection Report 05000272/2024001 and 05000311/2024001 LR-N24-0039, Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage2024-05-0606 May 2024 Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024 Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary IR 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 IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 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 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-N23-0035, 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 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 2024-07-30
[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) 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 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 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) ML18250A3132018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140) ML18171A3212018-06-20020 June 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Adopt TSTF-411 and 418 (L-2017-LLA-0442) ML18094B0832018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to P. 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MF8859 & MF8860) ML17192A1672017-07-11011 July 2017 Request for Additional Information - Salem Unit 1 - Steam Generator Tube Inspection Report 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 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 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 ML16124A5802016-05-0303 May 2016 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Redacted - Request for Additional Information Review of Security Plan Revision 17 Changes ML16013A1592016-02-17017 February 2016 Request for Additional Information Regarding Chilled Water System Modifications ML15287A1412015-11-0202 November 2015 Request for Additional Information License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems ML15287A1052015-11-0202 November 2015 Request for Additional Information License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling) (CAC Nos. 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MF3384, MF3385 and MF3386) ML14168A2422014-06-28028 June 2014 Request for Additional Information Regarding Flooding Hazard Reevaluation ML14135A2912014-06-0202 June 2014 RAI Regarding Request for Relief SC-I4R-140 from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI Requirements Regarding the Reactor Vessel Head Flange Seal Leak Detection ML14086A6362014-04-30030 April 2014 Request for Additional Information Regarding Core Operating Limits Report ML14066A2952014-03-0606 March 2014 Licensed Operator Positive Fitness-For-Duty-Test (FY14) ML13330A5672013-11-22022 November 2013 Request for Additional Information: Salem Units 1 and 2 - Relief Request SC-14R-133 Repair of Service Water Piping (TAC MF1375 & 1376) ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13304B9362013-10-29029 October 2013 Request for Additional Information: Salem Units 1 and 2 - Relief Request SC-14R-133 Repair of Service Water Piping (TAC MF1375 & 1376) ML13270A4142013-10-17017 October 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation (TAC Nos. MF0913 and Mf ML13249A0112013-09-0505 September 2013 Weko Seal Relief Request RAI ML13196A3382013-07-15015 July 2013 2013 Decommissioning Fund Report RAI ML13192A2322013-07-11011 July 2013 Draft Request for Additional Information Overall Integrated Plan in Response to Order EA-12-051, Reliable Spent Fuel Pool Instrumentation. ML13186A1672013-07-11011 July 2013 Request for Additional Information Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML13179A3032013-06-28028 June 2013 RAIs for Salem Regarding Response to Order EA-12-051 (SFP Instrumentation) ML13137A4882013-06-0505 June 2013 Request for Additional Information Relief Request SC-l4R-133 ML13149A0862013-06-0505 June 2013 Request for Additional Information Decommissioning Funding Status Report ML13102A2752013-04-25025 April 2013 Request for Additional Information Change to PSEG Emergency Plan to Remove the Backup R45 Plant Vent Radiation Monitor Indications ML13063A7172013-03-11011 March 2013 Second Request for Additional Information Deletion of Condition for Inoperable Control Area Air Condition System/Control Room Emergency Air Conditioning System Isolation Dampers 2022-02-22
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 22, 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 FOR SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION FOR USE OF WESTEMS PROGRAM IN METAL FATIGUE ANALYSIS (TAC NO. ME1834 AND ME1836)
Dear Mr. Joyce:
By letter dated August 18,2009, Public Service Enterprise Group Nuclear, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 for renewal of Operating License Nos. DPR-70 and DPR-75 for Salem Nuclear Generating Station, Units 1 and 2, respectively. The staff of the U.S. Nuclear Regulatory Commission (NRC or 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 staff's request for additional information is included in the Enclosure. Further requests for additional information may be issued in the future.
Items in the enclosure were provided to John Hufnagel and other members of your 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 301-415-2981 or bye-mail at bennett. brady@nrc.gov.
Sincerely, Bennett M. Brady, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION FOR METAL FATIGUE ANALYSES (TAC NOS. ME1834 AND ME 1836)
RAI4.3-07:
Background:
Section 4.3.1 of the Salem Nuclear Generating Station, Units 1 and 2, (Salem) license renewal application (LRA) mentions that data from the WESTEMS fatigue monitoring software were reviewed with respect to pressurizer heatups and cooldowns. Section 4.3.4.2 of the Salem LRA credits the WESTEMS code for evaluation of fatigue for the pressurizer and surge line locations. Sections A.3.1.1 and B.3.1.1 of the Salem LRA identify that WESTEMS computes cumulative usage factors for select locations under a discussion of the Metal Fatigue of Reactor Pressure Boundary Program. Section A.4.3.4.2 of the Salem LRA mentions that WESTEMS was used to evaluate pressurizer insurge/outsurge transients and surge line stratification on the pressurizer.
The staff is not clear on the specific use of WESTEMS at Salem. In addition, the staff has identified concerns regarding the results determined by the WESTEMS program as a part of the ASME Code fatigue evaluation process. For example, Westinghouse's response to NRC questions regarding the AP1000 Technical Report (see ADAMS Accession No. ML102300072, dated August 13, 2010). describes the ability of users to modify intermediate data (peak and valley stresses/times) used in the analyses. In addition. a response provided on August 20.
2010 (ADAMS Accession No. ML102350440) describes different approaches for summation of moment stress terms. These items can have significant impacts on calculated fatigue cumulative usage factor (CUF). The potential impact for modifications such as these formed the basis for the staff's conclusions in Regulatory Issue Summary (RIS) 2008-30, "Fatigue Analysis of Nuclear Power Plant Components," dated December 16, 2008, where it was noted that simplification of the analysis requires a great deal of judgment by the analyst to ensure that the simplification still provides a conservative result. The staff recognizes that WESTEMS has been developed under a formal Quality Assurance Program with supporting Technical Bases; however, it is difficult to ascertain the accuracy or conservatism of a location-specific application of WESTEMS given that a variety of analyst judgments may still be applied to the software outputs by the user on a case-specific basis.
Request:
The staff requests that the licensee provide clarification on the use of WESTEMS at Salem, as follows:
- Please clarify how WESTEMS is used at each Salem unit, especially with regard to the Metal Fatigue of Reactor Pressure Boundary Program. Specifically, what transients and locations are monitored by WESTEMS, what WESTEMS stress modules are used.
and are the stress models used at each Salem unit identical?
ENCLOSURE
-2
- Please describe whether the issues raised in ADAMS Accession Nos. ML102300072 dated August 13,2010, and ML102350440 dated August 20,2010, are applicable to each Salem WESTEMS monitored location. If not, please describe the reasons those issues are not applicable.
- For each location monitored by WESTEMS, please describe the historical fatigue analyses of record starting from the original ASME Code,Section III design basis fatigue analysis of record. For each follow-on analysis, please describe the reason for the re analysis, whether the evaluation was referenced in the current licensing basis (CLB),
and whether an updated ASME Code,Section III Design Specification and Code Reconciliation were performed in accordance with ASME Code, Section 1/1 requirements.
Please describe how these analyses are reflected in the results tabulated in Tables 4.3.1-1,4.3.4-1,4.3.7-1 and 4.3.7-2.
- Please describe the environmentally-assisted fatigue (EAF) analyses performed for each monitored location, if any.
- Please describe the differences between the stress models used in WESTEMS and the stress models used in the currently governing fatigue analysis of record and the EAF analysis of record (if any) for each monitored location.
- Please describe how the transient counting results tabulated in Tables 4.3.1-3 and 4.3.1 4 are incorporated into the fatigue results shown in Tables 4.3.7-1 and 4.3.7-2.
In addition, the staff requests benchmarking evaluations for two of the limiting locations monitored in the Salem WESTEMS application using the same input parameters and assumptions as those used in traditional, ASME Code,Section III CUF calculations for each location. If such calculations do not exist for either of the selected locations, they should be developed using techniques that allow independent comparison with the WESTEMS results.
The intent of this benchmarking evaluation is to confirm that the results of the WESTEMS models, including any analyst judgments, are acceptable and comparable to traditional ASME Code,Section III analyses for the selected monitored locations.
For the pressurizer surge nozzle and the 1.5" BIT line locations that Salem has indicated are monitored in WESTEMS, provide a summary of the benchmarking evaluation that includes the following information:
- A comparison of the calculated stresses and CUF using WESTEMS to the same results from the ASME Code,Section III CUF calculations for all transient pairs representing at least 75 percent of the total CUF from the ASME Code,Section III CUF calculations. One comparison for each unique stress model used in WESTEMS for each selected location is sufficient
- Describe the differences in the results between the WESTEMS evaluation and the ASME Code,Section III CUF calculations for each selected location, and provide a justification for acceptability of the differences.
-3 RAI4.3-08
Background:
By letter dated July 13, 2010, the applicant responded to RAI 4.3-05. In its response to request 1, the applicant provided a discussion on the methodology used to determine the locations that required environmentally assisted fatigue analyses, consistent with NUREG/CR-6260. In its response to request 3, the applicant stated that the correction temperature, T, and transformed oxygen content parameter, 0*, were set to values of zero, therefore, the Fen is maximized when these two terms are set equal to zero. The applicant also stated that its primary water chemistry specification for dissolved oxygen during normal operations is less than 0.005 ppm. Furthermore, a review of the Units 1 and 2 reactor coolant system (RCS) quarterly dissolved oxygen data indicated that the dissolved oxygen content was less than 0.05 ppm since 2000, except for short periods of time during start-up and shutdown conditions.
GALL AMP X.M1 states the impact of the reactor coolant environment on a sample of critical components should include the locations identified in NUREG/CR-6260, as a minimum, or propose alternatives based on plant configuration. The staff noted that the applicant's plant-specific configuration may contain locations that should be analyzed for the effects of reactor coolant environment, other than those generic locations identified in NUREG/CR-6260. The staff noted this may include locations, for example, (1) that are limiting or bounding for a particular plant-specific configuration or (2) that have calculated CUF values that are greater than those for the locations identified in NUREG/CR-6260.
The staff noted that the statement "Fen is maximized when these two terms are set equal to zero" is not accurate because the last term in the Fen expression can be less than zero (thus subtracting a negative value and providing a higher value of Fen and the use of T equal to zero in the second term of the Fen expression is not technically correct). The staff also noted that setting the transformed oxygen content parameter, 0*, to a value of zero is based on the assumption that the applicant has always operated with dissolved oxygen less than 0.05 ppm since initial plant start-up. However, the applicant's response only confirmed the dissolved oxygen content for the time period since the year 2000. The staff also noted that it is not clear how much time elapses during the short periods of time during start-up and shutdown conditions when dissolved oxygen content is greater than 0.05 ppm.
Request:
- 1. Confirm and justify that the locations selected for environmentally assisted fatigue analyses, consistent with NUREG/CR-6260, are the most limiting and bounding for the plant. If these locations are not the most limiting and bounding for the plant, clarify the locations that require an environmentally assisted fatigue analysis and the actions that will be taken for these additional locations. If the most limiting location consists of nickel alloy, NUREG/CR-6909 methodology for nickel alloy will be used.
- 2. Justify the statement "Fen is maximized when these two terms are set equal to zero" made in response to RAI4.3-05.
- 3. Clarify whether dissolved oxygen content has always been maintained less than 0.05 ppm since initial plant start-up, and provide justification to support this clarification. If not, justify why the Fen values provided in LRA Tables 4.3.7-1 and 4.3.7-2 do not account for these
-4 periods of time in which dissolved oxygen content was not maintained less than 0.05 ppm, including the "short periods of time during start-up and shutdown conditions."
'.. ML102810194 OFFICE LA:DLR PM:DLR:RPB1 BC:DLR:RPB1 PM:DLR:RPB1 NAME IKing B. Brady B. Pham (BBrady for) B. Brady DATE 10/13/10 11/22110 11/22/10 11/22110 Letter to T. Joyce from B. Brady dated November 22, 1010.
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION FOR BURIED PIPING INSPECTION PROGRAM (TAC NOS. ME1834 AND ME1836)
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