Letter Sequence RAI |
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Results
Other: LR-N09-0162, PSEG Nuclear, Hope Creek Generating Station, Transmittal Letter, License Renewal Application, LR-N10-0234, 10 CFR 54.21(b) Review to Identify Any Current Licensing Basis (CLB) Changes Made Since Submittal of the License Renewal Application (LRA), ML092430373, ML092430374, ML092430384, ML092430386, ML092430387, ML092430388, ML092430389, ML092430390, ML092430484, ML092460442, ML092520185, ML092650382, ML092660174, ML092660447, ML100850462, ML101660452, ML102100544, ML111090416
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MONTHYEARLR-N09-0191, 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 ML0924303742009-08-18018 August 2009 PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 2 of 3 Project stage: Other ML0924303892009-08-18018 August 2009 PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3, Appendix E Project stage: Other ML0924303842009-08-18018 August 2009 PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3 Through Appendix a Project stage: Other ML0924303862009-08-18018 August 2009 PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3, Appendix B Project stage: Other ML0924303872009-08-18018 August 2009 PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3, Appendix C Project stage: Other ML0924303902009-08-18018 August 2009 PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3, Appendix F Project stage: Other ML0924304842009-08-18018 August 2009 PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3 of 3 Project stage: Other ML0924303882009-08-18018 August 2009 PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3, Appendix D Project stage: Other LR-N09-0162, PSEG Nuclear, Hope Creek Generating Station, Transmittal Letter, License Renewal Application2009-08-18018 August 2009 PSEG Nuclear, Hope Creek Generating Station, Transmittal Letter, License Renewal Application Project stage: Other ML0924303732009-08-18018 August 2009 PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 1 of 3 Project stage: Other ML0924604422009-09-0303 September 2009 Delaware Citizen Comment on Salem Hope Creek License Renewal Application Project stage: Other ML0926601742009-09-0707 September 2009 Comment on License Renewal for Salem and Hope Creek Power Plants - Goodman Project stage: Other ML0926503822009-09-0808 September 2009 Citizen Comment on Salem Hope Creek License Renewal Application Project stage: Other ML0925201852009-09-0808 September 2009 Comments About Relicensing Salem and Hope Creek Reactors in Nj, Steven Hegedus Project stage: Other ML0926604472009-09-23023 September 2009 Hope Creek, E-mail from Ruth Panella Comments on License Renewal Project stage: Other ML1007704192010-03-17017 March 2010 Task Order No. 005 Under Delivery Order No. NRC-DR-03-09-061 Project stage: Acceptance Review ML1008504622010-04-0606 April 2010 Project Manager Change for the License Renewal of Hope Creek Generating Station Project stage: Other ML1009703502010-04-14014 April 2010 License Renewal Application - Request for Additional Information for Section 2.2.5, Boral Monitoring Program Project stage: RAI ML1007503312010-04-15015 April 2010 Request for Additional Information Regarding Scoping and Screening Results for the Hope Creek Generating Station (Tac ME1832) Project stage: RAI ML1010205112010-04-27027 April 2010 License Renewal Application - Request for Additional Information for Section 2.1, Scoping and Screening Methodology Project stage: RAI ML1010601552010-05-14014 May 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application Identified During the Audit Project stage: RAI ML1013803162010-06-0101 June 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application Section 3.3.2 Project stage: RAI ML1013806202010-06-0101 June 2010 Request for Additional Information Regarding Sections 4.6 and 4.7 of the Hope Creek Generating Station License Renewal Application Project stage: RAI ML1014501792010-06-0303 June 2010 Letter Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application Project stage: RAI ML1013801492010-06-0707 June 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Section 3.5 Project stage: RAI ML1013705592010-06-0909 June 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Review Application 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 ML1013707612010-06-14014 June 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application Project stage: RAI ML1016104482010-06-22022 June 2010 RAI for the Review of the Hope Creek Generating Station License Renewal Application for Fire Protection Project stage: RAI LR-N10-0234, 10 CFR 54.21(b) Review to Identify Any Current Licensing Basis (CLB) Changes Made Since Submittal of the License Renewal Application (LRA)2010-06-24024 June 2010 10 CFR 54.21(b) Review to Identify Any Current Licensing Basis (CLB) Changes Made Since Submittal of the License Renewal Application (LRA) Project stage: Other ML1016601502010-06-25025 June 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Open Cycle Cooling Water System Program and Structures Project stage: RAI ML1015906752010-06-25025 June 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Section 4.3 Project stage: RAI ML1017500242010-06-29029 June 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Fiberglass Doors Project stage: RAI LR-N10-0211, Response to NRC Request for Additional Information, Dated June 3, 2010, Related to Sections 3.2.2, 3.3.2 and B.2.2.2 of License Renewal Application2010-06-30030 June 2010 Response to NRC Request for Additional Information, Dated June 3, 2010, Related to Sections 3.2.2, 3.3.2 and B.2.2.2 of License Renewal Application Project stage: Response to RAI ML1015804812010-06-30030 June 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Metal Fatigue of Reactor Coolant Pressure Boundary Program Project stage: RAI LR-N10-0242, Response to NRC Request for Additional Information, Dated June 9, 2010, Related to Sections 3.1.2 and 3.3.2 of License Renewal Application2010-07-0606 July 2010 Response to NRC Request for Additional Information, Dated June 9, 2010, Related to Sections 3.1.2 and 3.3.2 of License Renewal Application Project stage: Response to RAI LR-N10-0248, Response to NRC Request for Additional Information, Dated June 22, 2010, Related to Fire Protection License Renewal Application2010-07-19019 July 2010 Response to NRC Request for Additional Information, Dated June 22, 2010, Related to Fire Protection License Renewal Application Project stage: Response to RAI ML1020002932010-08-0303 August 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Bolting and Flow Element Project stage: RAI ML1015400542010-08-0606 August 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Buried Piping Inspection Program Project stage: RAI ML1020303982010-08-18018 August 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Primary Containment Valve Material Project stage: RAI ML1021005442010-08-19019 August 2010 Scoping and Screening Audit Summary Regarding Hope Creek Generating Station License Renewal Application Project stage: Other LR-N10-0317, Response to NRC Request for Additional Information Dated August 3, 2010, Related to Bolting and Flow Element, and Update to PSEG July 6, 2010, Response to NRC RAI Associated with RPV Leak Detection Line - License Renewal Application2010-08-26026 August 2010 Response to NRC Request for Additional Information Dated August 3, 2010, Related to Bolting and Flow Element, and Update to PSEG July 6, 2010, Response to NRC RAI Associated with RPV Leak Detection Line - License Renewal Application Project stage: Response to RAI ML1016604522010-09-0303 September 2010 Audit Report Regarding the Hope Creek Generating Station License Renewal Application Project stage: Other ML1027804222010-10-12012 October 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Buried Piping Project stage: RAI ML1032805742010-12-13013 December 2010 Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for One Time Inspection and Selective Leaching Project stage: RAI ML1110904162011-05-0505 May 2011 Project Manager Change for the License Renewal of Hope Creek Generating Station Project stage: Other ML11144A2452011-06-10010 June 2011 Schedule Revision for the Review of the Hope Creek Generating Station License Renewal Application Project stage: Approval ML11117A2062011-07-20020 July 2011 Notice of Issuance of Renewed Facility Operating License No. NPF-57 for an Additional 20-Year Period Project stage: Request ML11116A1482011-07-20020 July 2011 Issuance of Renewed Facility Operating License No. NPF-57 for Hope Creek Generating Station Project stage: Approval 2010-06-24
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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
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22006A3212022-01-0606 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 ML21041A3972021-02-18018 February 2021 Request for Additional Information Revise Low Pressure Safety Limit to Address General Electric Part-21 Safety Communications (Non-Proprietary) 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) 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) ML18250A3142018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) 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) 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) 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) 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 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 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 ML15055A3772015-03-10010 March 2015 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information Request to Update Appendix B to Renewed Facility Operating License DPR-70, DPR-75 and NPF-57 ML14197A6192014-07-24024 July 2014 and Salem Nuclear Generating Station, Units 1 and 2 - Request for Additional Information Regarding Cyber Security Plan Milestone 8 Implementation Schedule (Tac Nos. MF3384, MF3385 and MF3386) ML14168A2352014-07-0202 July 2014 Request for Additional Information Regarding Flooding Hazard Reevaluation ML13309B5922013-11-22022 November 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 ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13168A2762013-08-12012 August 2013 Peach Bottom, Units 2 and 3, Request for Additional Information Decommissioning Funding Status Report (TAC No. MF2202; MF2227; MF2228) ML13193A2912013-07-22022 July 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) TAC MF1031 ML13204A2532013-07-19019 July 2013 Draft RAIs - Decommissioning Funding Status Report for Hope Creek and Peach Bottom ML13190A2212013-07-0202 July 2013 RAIs for Hope Creek Regarding Response to Order EA-12-051 ML13154A4952013-06-0404 June 2013 Rai'S Following Ifib Analysis of Pseg'S 2013 Decommissioning Funding Status Report for Hope Creek Generating Station ML12334A3102012-12-0505 December 2012 Request for Additional Information Request to Correct Technical Specification and Facility Operating License Editorial Items ML12310A1672012-11-0101 November 2012 Draft RAI to License Amendment Request Regarding Average Power Range Monitoring Operability Requirements in Operational Condition 5 ML1227901012012-10-0505 October 2012 Clarifying Information for Question No. 4 (with Attachment) ML12212A1032012-08-0808 August 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information ML12216A1792012-08-0303 August 2012 Draft RAI Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule ML12213A6162012-07-30030 July 2012 Draft Request for Additional Information Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule ML1209002372012-03-29029 March 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic 2022-01-06
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Text
June 25, 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 THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION FOR SECTION 4.3 (TAC NO ME1832)
Dear Mr. Joyce:
By letter dated August 18, 2009, as supplemented by letter dated January 23, 2009, Public Service Enterprise Group Nuclear, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54) for renewal of Operating License No. NPF-57 for the Hope Creek Generating Station. 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 by e-mail at bennett.brady@nrc.gov. Sincerely,
/RA/ Bennett M. Brady, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
As stated
cc w/encl: See next page
ML101590675 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME BBrady SFigueroa BPham BBrady DATE 6/22/10 6/9/10 6/25/10 6/25/10 Letter to T. Joyce from B. Brady dated June 25, 2010
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION FOR SECTION 4.3 (TAC NO ME1832)
DISTRIBUTION
HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RdsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsOgcMailCenter Resource ------------- BPham BBrady CEccleston REnnis CSanders BHarris, OGC ABurritt, RI RConte, RI MModes, RI DTifft, RI NMcNamara, RI Hope Creek Generating Station cc: Mr. Robert Braun Senior Vice President Nuclear PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Brian Booth Director Nuclear Oversight PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. John Perry Station Vice President - Hope Creek PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Larry Wagner Plant Manager - Hope Creek PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038
Mr. Michael Gallagher Vice President - License Renewal Projects Exelon Nuclear LLC 200 Exelon Way Kennett Square, PA 19348
Mr. Jeffrie J. Keenan, Esquire Manager - Licensing PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Gregory Sosson Director Corporate Engineering PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038Mr. Michael Gaffney Manager - Hope Creek Regulatory Assurance PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038
Mr. Ali Fakhar Manager, License Renewal PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Township Clerk Lower Alloways Creek Township Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy, CN 415 Trenton, NJ 08625-0415
Mr. Brian Beam Board of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102
Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
Mr. Paul Davison Vice President, Operations Support PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038
Hope Creek Generating Station cc: Ms. Christine Neely Director - Regulator Affairs PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Senior Resident Inspector Hope Creek Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079 REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION (HCGS) LICENSE RENEWAL APPLICATION (LRA) FOR SECTION 4.3 (TAC NO ME1832)
RAI 4.3-01
Background:
Pursuant to 10 CFR 54.21(c)(1)(i) - (iii), an applicant must demonstrate one of the following: (i) the analyses remain valid for the period of extended operation, (ii) the analyses have been projected to the end of the extended period of operation, or (iii) the effects of aging on the intended function(s) will be adequately managed for the period of extended operation.
Issue (Part 1):
LRA Table 4.3.1-1 states that the limiting number of cycles for loss of feed water (FW) heaters (turbine trip with 100% steam bypass and partial FW heater bypass) is 23. In UFSAR Table 3.9-1a, the loss FW heaters transient is separated into two transients for turbine trip with 100% steam bypass and for partial FW heater bypass with three and 20 limiting numbers of cycles, respectfully. It is not clear to the staff whether (i) in the fatigue analyses for the FW nozzles these transients were accounted for as two separate transients and (ii) they should be included into the Metal Fatigue of Reactor Coolant Pressure Boundary Program as two transients with three and 20 limiting numbers of cycles.
Request (Part 1):
Clarify whether (i) in the fatigue analyses for the FW nozzles, the loss of FW heaters transients were accounted for as two separate transients and (ii) they should be included in the Metal Fatigue of Reactor Coolant Pressure Boundary Program as two transients with three and 20 limiting numbers of cycles.
Issue (Part 2):
LRA Table 4.3.1-1 states that the limiting number of cycles for scram (turbine generator trip-feedwater on-isolation valves stay open and all other) is 136. In UFSAR Table 3.9-1, the scram transient is separated into two transients for turbine generator trip-feedwater on-isolation valves stay open and other scrams with 40 and 140 limiting numbers of cycles respectfully. It is not clear to the staff whether (i) in the fatigue analyses for the reactor vessel (RV) and its components other than FW nozzles these transients were accounted for as two separate transients and (ii) should be included into the Metal Fatigue of Reactor Coolant Pressure Boundary Program as two transients.
Request (Part 2):
Clarify whether (i) in the fatigue analyses for the reactor vessel (RV) and its components other than FW nozzles, scrams transients were accounted for as two separate transients and (ii) should be included in the Metal Fatigue of Reactor Coolant Pressure Boundary Program as two transients.
RAI 4.3-02
Background:
Pursuant to 10 CFR 54.21(c)(1)(i) - (iii), an applicant must demonstrate one of the following: (i) the analyses remain valid for the period of extended operation, (ii) the analyses have been projected to the end of the extended period of operation, or (iii) the effects of aging on the intended function(s) will be adequately managed for the period of extended operation.
Issue: LRA Section 4.3.1 states that 40- and 60-year cycles projections are based on the number of transients experienced at HCGS from plant startup and up to 12/31/2007 and the trends from the last twelve years of plant operation. However, LRA Section 4.3.1 does not provide sufficient information for the staff to conclude that the projection methodology used by the applicant is acceptable and would produce conservative values for 40- and 60-year cycle projections.
Request: Clarify whether the applicant has been tracking (counting) the number of design basis transient occurrences at Hope Creek from the time when the initial operations of the unit had commenced. For those transients that are required to be tracked and monitored in accordance with Technical Specifications, or applicable design basis criteria, identify how many times the transients have occurred during the time period between December 31, 1995 and December 31, 2007. Clarify whether your assumption that the number of transients occurring during those 12 years of operations remains as a valid basis for calculating the 60-year transient projections for this time limiting aging analysis (TLAA). For these transients, identify all technical bases and assumptions that have been used to inform your conclusion that the cycle accumulation trends during the last twelve years of operation provide a conservative basis for projecting the cycle occurrences for these transients through the expiration of the period of extended operation.
RAI 4.3-03
Background:
Pursuant to 10 CFR 54.21(c)(1)(i) - (iii), an applicant must demonstrate one of the following: (i) the analyses remain valid for the period of extended operation, (ii) the analyses have been projected to the end of the extended period of operation, or (iii) the effects of aging on the intended function(s) will be adequately managed for the period of extended operation.
Issue:
LRA Section B.3 states that as a result of the high pressure coolant injection (HPCI) event experienced in October 2004, the number of injection cycles exceeded the assumed number of cycles in the core spray nozzle fatigue analysis. The corrective action was invoked to evaluate this event, resulting in an analysis indicating that the core spray nozzle cumulative fatigue usage (CUF) was 0.815. LRA Section 4.3.1 states that the applicant performed re-analysis for the core spray nozzle in accordance with ASME B&PV,Section III, 2001 Edition including 2003 Addenda. This re-analysis resulted in the core spray nozzle 40-year CUF of 0.063. It is not clear to the staff what assumptions used in the core spray nozzle re-analysis resulted in reduction of CUF by a factor of 13. Further, the staff identified an inconsistency in the reported 60-year projected CUF value for the core spray nozzle in that the LRA Table 4.3.1-2 lists the value as 0.065 and LRA Table 4.3.5-1 reports the value as 0.0202.
Request: Explain and justify why the LRA lists two different 60-year projected CUF values for the core spray nozzles. Identify and justify which 60-year non-environmental effects CUF value should be used for the core spray nozzles in LRA Table 4.3.1-2 and 4.3.5-1. Identify the assumptions that were used to reduce the CUF for the core spray nozzle by a factor of 13 in the reanalysis of the component.
RAI 4.3-04
Background:
Pursuant to 10 CFR 54.21(c)(1)(i) - (iii), an applicant must demonstrate one of the following: (i) the analyses remain valid for the period of extended operation, (ii) the analyses have been projected to the end of the extended period of operation, or (iii) the effects of aging on the intended function(s) will be adequately managed for the period of extended operation.
Issue:
UFSAR Section 3.9.1.1.4 states that the transients and the number of cycles specified in UFSAR Table 3.9-1 were considered in 40-year fatigue analyses of the reactor pressure vessel internals. LRA Section 4.3.2 states that the applicant derived 60-year CUF values for reactor pressure vessel components by multiplying 40-year CUFs values by a factor of 1.5, which represent an increase in the plant life from 40 to 60 years. However, for some transients used in the reactor pressure vessel components fatigue analyses, the 40-year cycle projection summarized in LRA Table 4.3.1-1 exceed the values reported in UFSAR Table 3.9-1.
Therefore, to project the reactor pressure vessel internals CUFs to 60 years, the fatigue analyses for these components need to be updated based on the 60-year cycle projections.
However, LRA Section 4.3.2 does not provide sufficient information for staff to determine whether the 60-year reactor CUF values for the core support plate, top guide beams, and core differential pressure sensing line (as based on a simple multiplication of the design basis values by a factor of 1.5) are conservative relative to those that would be calculated for these components if the 60-year projections were based on the 60-year cycle projections for the transients that were analyzed in the design basis CUF calculations of these components.
Request: Provide the basis and justify why the 60-year projected CUF values that have been provided for these components (as based on a simple multiplication of the design basis CUF values by a factor of 1.5) are considered to be conservative relative to those that would be calculated using the actual 60-year cycle projections for the transients that are within the scope of the CUF calculations for these components.
RAI 4.3-05
Background:
Pursuant to 10 CFR 54.21(c)(1)(i) - (iii), an applicant must demonstrate one of the following: (i) the analyses remain valid for the period of extended operation, (ii) the analyses have been projected to the end of the extended period of operation, or (iii) the effects of aging on the intended function(s) will be adequately managed for the period of extended operation.
Issue (1):
LRA Section 4.3.5 states that the applicant identified the plant-specific components for the NUREG/CR-6260 sample locations and equivalent HCGS locations that bound those of NUREG/CR-6260 sample locations (LRA Table 4.3.5-1). Further, the applicant performed environmentally assisted fatigue (EAF) calculation for these equivalent HCGS locations to evaluate the effects of the reactor coolant system environment on fatigue life. However, LRA does not provide sufficient information on the methodology used in determining equivalent HCGS locations that bound those of NUREG/CR-6260 sample locations and the basis for performing EAF calculations for these locations in place of EAF calculation for identified NUREG/CR-6260 plant-specific components.
Request (1):
Explain the methodology used in determining equivalent HCGS locations that bound those of NUREG/CR-6260 sample locations. Identify the technical bases that have been used to confirm that the equivalent HCGS locations bound those of NUREG/CR-6260 sample locations. Provide all technical bases for performing EAF calculation for these locations in place of EAF calculation for identified NUREG/CR-6260 plant-specific components.
Issue (2):
The locations identified and analyzed in NUREG/CR-6260 include typical limiting locations but does not consider all plant-specific components and configurations.
Request (2):
Clarify whether any other plant-specific locations at HCGS are more limiting than those identified in NUREG/CR-6260. If other HCGS plant-specific locations exceed those from NUREG/CR-6260, provide EAF calculations for those locations.
RAI 4.3-06
Background:
Pursuant to 10 CFR 54.21(c)(1)(i) - (iii), an applicant must demonstrate one of the following: (i) the analyses remain valid for the period of extended operation, (ii) the analyses have been projected to the end of the extended period of operation, or (iii) the effects of aging on the intended function(s) will be adequately managed for the period of extended operation.
Issue: LRA Section 4.3.5 does not provide sufficient information on the basis for assumptions used in the environmental fatigue multipliers (Fen) calculations for the NUREG/CR-6260 sample locations.
Request:
Identify all assumptions used (e.g., sulfur content, temperature, strain rate) in the Fen calculations for the NUREG/CR-6260 sample locations. Provide the basis why the assumptions applied to the Fen calculations (including those for dissolved oxygen level) are reasonable or conservative for determining Fen factors for application to the Hope Creek environmentally-assisted fatigue calculations.
RAI 4.3-07
Background:
Pursuant to 10 CFR 54.21(c)(1)(i) - (iii), an applicant must demonstrate one of the following: (i) the analyses remain valid for the period of extended operation, (ii) the analyses have been projected to the end of the extended period of operation, or (iii) the effects of aging on the intended function(s) will be adequately managed for the period of extended operation.
Issue: LRA Section 4.3.5 states that Fen factor of 1.49 was used for the Alloy 600 component (control rod drive penetration and core spray nozzle). Also, the LRA does not provide sufficient information to determine what methodology was used in obtaining Fen. Note that NUREG/CR-6909 incorporates more recent fatigue data using a larger database than prior reports for determining the Fen factor of nickel alloys. The basis methodology for the Fen of nickel alloys described in NUREG/CR-6909 is considered by the staff to represent the most up-to-date method for determining the Fen factor for nickel alloys for license renewal considerations.
Request: (a) Justify using the value of 1.49 for the Fen factor if it is not a bounding/conservative value for the Alloy 600 component when compared to the Fen factor calculated based on NUREG/CR-6909 for nickel alloys. (b) Describe the current or future planned actions to update the CUF calculation with Fen factor for the Alloy 600 component only, consistent with the methodology in NUREG/CR-6909. If there are no current or future planned actions to update the CUF calculation with Fen factor for the Alloy 600 component consistent with the methodology in NUREG/CR-6909, provide a justification for not performing the update.