Letter Sequence RAI |
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TAC:MD3002, Control Room Habitability (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
|
MONTHYEARML0733004532003-11-27027 November 2003 Schedule and Response to PSEG Letter (LR-N07-0274) Dated October 23, 2007, Plans Related to Steam Dryer Evaluation Regarding Request for Extended Power Uprate Project stage: Other ML0626900642006-09-0101 September 2006 Attachment 26, C.D.I. Report No. 06-16NP, Rev 1, Estimating High Frequency Flow Induced Vibration in the Main Stream Lines at Hope Creek Unit 1: a Subscale Four Line Investigation of Standpipe Behavior. Project stage: Request LR-N06-0286, Request for License Amendment Extended Power Uprate2006-09-18018 September 2006 Request for License Amendment Extended Power Uprate Project stage: Request ML0626900442006-09-30030 September 2006 Attachment 21, C.D.I. Report No. 06-27, Rev 0, Stress Analysis of Hope Creek Unit 1 Steam Dryer at CLTP and EPU Conditions Using 1/8th Scale Model Pressure Measurement Data. Project stage: Request ML0631101672006-09-30030 September 2006 Attachment 2 - CDI Technical Memo 06-23P (Non-Proprietary) Comparison of Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions, Revision 0, Dated September 2006 Project stage: Request LR-N06-0413, Supplement to License Amendment Request for Extended Power Uprate2006-10-10010 October 2006 Supplement to License Amendment Request for Extended Power Uprate Project stage: Supplement ML0628303692006-10-13013 October 2006 Supplement to Application for Extended Power Uprate Project stage: Other ML0629003222006-10-18018 October 2006 Extended Power Uprate Accpetance Review Results Project stage: Other LR-N06-0418, Supplement to License Amendment Request for Extended Power Uprate, to Increase the Maximum Authorized Power Level to 3840 Megawatts Thermal2006-10-20020 October 2006 Supplement to License Amendment Request for Extended Power Uprate, to Increase the Maximum Authorized Power Level to 3840 Megawatts Thermal Project stage: Supplement ML0628304722006-11-0808 November 2006 PSEG Nuclear LLC, Withholding from Public Disclosure, NEDC-33076P, Revision 2, Safety Analysis Report for Hope Creek Constant Pressure Power Uprate, Class III, MD3002 Project stage: Other ML0628304532006-11-21021 November 2006 PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance ML0633301432006-12-15015 December 2006 11/13-14/2006 Summary of Category 1 Meeting with PSEG Nuclear LLC, Regarding Application for Extended Power Uprate for Hope Creek Project stage: Meeting ML0703002772007-01-26026 January 2007 E-Mail Shea-NRR,to Duke, PSEG, Group1 Draft EPU RAI Project stage: Draft Other ML0716303072007-01-31031 January 2007 C.D.I. Technical Note No. 07-01NP, EPU Conditions in the Main Steam Lines at Hope Creek Unit 1: Additional Subscale Four Line Tests. Project stage: Request LR-N07-0034, C.D.I. Technical Memorandum No. 06-23NP, Revision 1, Comparison of the Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions.2007-01-31031 January 2007 C.D.I. Technical Memorandum No. 06-23NP, Revision 1, Comparison of the Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions. Project stage: Request LR-N07-0026, Supplemental to License Amendment Request for Extended Power Uprate2007-02-14014 February 2007 Supplemental to License Amendment Request for Extended Power Uprate Project stage: Supplement LR-N07-0029, Supplement to License Amendment Request for Extended Power Uprate2007-02-16016 February 2007 Supplement to License Amendment Request for Extended Power Uprate Project stage: Supplement ML0703304152007-02-16016 February 2007 Request for Additional Information Regarding Request for Extended Power Uprate Project stage: RAI ML0706606192007-02-20020 February 2007 Draft Request for Additional Information Hope Creek EPU Grp 5 Project stage: Draft RAI ML0706601992007-02-20020 February 2007 Draft Request for Additional Information Hope Creek EPU Grp 4 Project stage: Draft RAI ML0704602432007-02-23023 February 2007 Ltr Request for Additional Information Related to the Request for Extended Power Uprate Project stage: RAI ML0706606382007-02-23023 February 2007 Draft Request for Additional Information Hope Creek EPU Grp 6 Project stage: Draft RAI ML0706803142007-02-28028 February 2007 Hope Creek, Supplement to License Amendment Request for Extended Power Uprate Project stage: Supplement ML0708103652007-02-28028 February 2007 C.D.I. Report No. 07-01NP, Rev. 0, Revised Hydrodynamic Loads on Hope Creek Unit 1 Steam Dryer to 200 Hz. Project stage: Request ML0706006112007-03-0202 March 2007 Request for Additional Information Regarding Request for Extended Power Uprate Project stage: RAI ML0709200252007-03-0202 March 2007 Slides for Summary of March 2, 2007 Meeting with PSEG Nuclear LLC on an Application for Extended Power Uprate for Hope Creek Generating Station Regarding Steam Dryer Margin Project stage: Meeting ML0706803062007-03-13013 March 2007 Request for Additional Information Regarding Request for Extended Power Uprate Project stage: RAI LR-N07-0035, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate2007-03-13013 March 2007 Response to Request for Additional Information Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0055, Supplement to License Amendment Request for Extended Power Uprate2007-03-13013 March 2007 Supplement to License Amendment Request for Extended Power Uprate Project stage: Supplement ML0708004302007-03-29029 March 2007 Summary of March 2, 2007, Meeting with PSEG Nuclear, LLC, on an Application for Extended Power Uprate for Hope Creek Generating Station Regarding Steam Dryer Margin Project stage: Meeting LR-N07-0060, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate2007-03-30030 March 2007 Response to Request for Additional Information Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0069, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate2007-03-30030 March 2007 Response to Request for Additional Information Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0070, Response to Request for Additional Information on Request for License Amendment - Extended Power Uprate2007-04-13013 April 2007 Response to Request for Additional Information on Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0084, Supplement to License Amendment Request for Extended Power Uprate, Revised No Significant Hazards Consideration2007-04-18018 April 2007 Supplement to License Amendment Request for Extended Power Uprate, Revised No Significant Hazards Consideration Project stage: Supplement ML0711400912007-04-20020 April 2007 Request for Additional Information Regarding Request for Extended Power Uprate (TAC MD3002) - NON-PROPRIETARY Project stage: RAI ML0713603772007-04-30030 April 2007 C.D.I. Report No. 06-16NP, Rev. 2, Estimating High Frequency Flow Induced Vibration in the Main Steam Lines at Hope Creek, Unit 1: a Subscale Four Line Investigation of Standpipe Behavior. Project stage: Request LR-N07-0099, Response to Request for Additional Information Request for License Amendment, Extended Power Uprate2007-04-30030 April 2007 Response to Request for Additional Information Request for License Amendment, Extended Power Uprate Project stage: Response to RAI ML0710104492007-05-0303 May 2007 Explanation of Hope Creek Nuclear Generating Station Extended Power Uprate and Conclusion of Informal Consultation Project stage: Other ML0712404872007-05-0909 May 2007 PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance LR-N07-0102, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate2007-05-10010 May 2007 Response to Request for Additional Information Request for License Amendment - Extended Power Uprate Project stage: Response to RAI ML0712404112007-05-14014 May 2007 RAI, Request for Additional Information Regarding Request for Extended Power Uprate Project stage: RAI ML0712405052007-05-15015 May 2007 Summary of Meeting with PSEG Nuclear LLC, Regarding Technical Aspects of the Licensee'S Application for an Extended Power Uprate (EPU) at the Hope Creek Generating Station (Hope Creek) Project stage: Meeting ML0712404612007-05-17017 May 2007 PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance ML0628605302007-05-17017 May 2007 Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance ML0713707002007-05-17017 May 2007 Request for Additional Information (RAI) Regarding Request for Extended Power Uprate Project stage: RAI ML0712405102007-05-17017 May 2007 PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance LR-N07-0123, Response to Request for Additional Information, Request for License Amendment - Extended Power Uprate2007-05-18018 May 2007 Response to Request for Additional Information, Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0113, Supplement to Request for License Amendment Extended Power Uprate Steam Dryer Limit Curves2007-05-18018 May 2007 Supplement to Request for License Amendment Extended Power Uprate Steam Dryer Limit Curves Project stage: Supplement LR-N07-0122, Supplement to Request for License Amendment Re Extended Power Uprate & C.D.I. Technical Note No. 07-012007-05-24024 May 2007 Supplement to Request for License Amendment Re Extended Power Uprate & C.D.I. Technical Note No. 07-01 Project stage: Supplement ML0717203702007-05-31031 May 2007 Attachment 2, C.D.I. Technical Note No. 07-19NP, Revision 0, Hope Creek, Unit 1, Extended Power Uprate Limit Curve Analysis for Dryer Stress Prediction During Power Ascension Project stage: Request 2007-02-28
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Category:Letter
MONTHYEARML24295A3742024-10-23023 October 2024 Project Manager Assignment IR 05000354/20240032024-10-23023 October 2024 Integrated Inspection Report 05000354/2024003 ML24291A0572024-10-17017 October 2024 License Amendment Request (LAR) – Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 1 LR-N24-0063, Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF)2024-10-0707 October 2024 Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF) LR-N24-0059, 2024 Annual 10 CFR 50.46 Report2024-09-30030 September 2024 2024 Annual 10 CFR 50.46 Report LR-N24-0056, Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-09-26026 September 2024 Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle IR 05000272/20244022024-09-23023 September 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024402, 05000272/2024402, and 05000311/2024402 (Cover Letter Only) ML24255A8042024-09-11011 September 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N24-0057, In-Service Inspection Activities2024-09-10010 September 2024 In-Service Inspection Activities 05000354/LER-2024-001-01, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement2024-09-0505 September 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000354/20240052024-08-29029 August 2024 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2024005) LR-N24-0044, Relief Request VR-042024-08-0606 August 2024 Relief Request VR-04 IR 05000354/20240022024-07-30030 July 2024 Integrated Inspection Report 05000354/2024002 ML24200A0572024-07-18018 July 2024 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves NUREG-1433, – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 52024-07-16016 July 2024 – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 5 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 ML24197A0552024-07-15015 July 2024 Requalification Program Inspection 05000354/LER-2024-001, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)2024-07-0202 July 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves2024-06-28028 June 2024 License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves 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 ML24150A1002024-05-28028 May 2024 Core Operating Limits Report, Reload 25, Cycle 26, Revision 23 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 LR-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-05-20020 May 2024 License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle ML24142A4072024-05-20020 May 2024 License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5 IR 05000354/20240012024-05-0808 May 2024 Integrated Inspection Report 05000354/2024001 IR 05000354/20240102024-05-0707 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010 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 IR 05000354/20243012024-04-10010 April 2024 Initial Operator Licensing Examination Report 05000354/2024301 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 05000272/20240112024-04-0101 April 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Plant Modification and Annual Problem Identification and Resolution Inspection Report 05000354/2024011, 05000272/2024011, and 05000311/2024011 LR-N24-0028, And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024 And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal IR 05000272/20244032024-03-20020 March 2024 And Hope Creek Generating Station - Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000272/2024403, 05000311/2024403, and 05000354/2024403 LR-N24-0021, And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024 And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums 05000354/LER-2023-003-01, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram LR-N24-0027, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024 Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report IR 05000354/20230062024-02-28028 February 2024 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2023006) IR 05000272/20244012024-02-26026 February 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024401, 05000272/2024401 and 05000311/2024401 (Cover Letter Only) LR-N24-0010, Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges2024-02-22022 February 2024 Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges 05000354/LER-2023-003, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-02-12012 February 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram IR 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 2024-09-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24253A1942024-09-0909 September 2024 NRR E-mail Capture - Final Eeeb RAI - Hope Creek Amendment to Revise TS to Change Surveillance Interval to Accommodate 24-Month Fuel Cycle IR 05000354/20240102024-05-0707 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010 IR 05000272/20244032024-03-20020 March 2024 And Hope Creek Generating Station - Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000272/2024403, 05000311/2024403, and 05000354/2024403 ML24060A0492024-02-28028 February 2024 NRR E-mail Capture - Final Exhb RAI for Hope Creek, Salem 1 and 2 Amendment to Modify Exclusion Area Boundary 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 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) 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) ML17331A0072017-11-21021 November 2017 E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate 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 2024-09-09
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rdiI !10!At U01t WritL 1*tUR 'Kit: 0 ANICT INI WI~MA 11iur' G*p,$' REG&, "
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 13, 2007 Mr. William Levis President & Chief Nuclear Officer PSEG Nuclear LLC-N09 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST FOR EXTENDED POWER UPRATE (TAC NO. MD3002)
Dear Mr. Levis:
By letter dated September 18, 2006, as supplemented on October 10 and October 20, 2006, February 14, February 16, February 28, March 13 (2 letters), March 22, March 30 (2 letters),
April 13, April 18, April 30, May 10, May 18 (3 letters), June 22, August 3, August 17, August 31, September 11, October 10, and October 23, 2007, PSEG Nuclear, LLC (PSEG or licensee).
submitted an amendment request for an extended power uprate (EPU) for Hope Creek Generating Station (Hope Creek). The proposed amendment would increase the authorized maximum power level by approximately 15 percent, from 3339 megawatts thermal (MWt) to 3840 MWt.
The Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent by e-mail to you to ensure that the questions were understandable, the regulatory basis was clear and to determine if the information was previously docketed. The NRC staff has determined that the RAI contains proprietary information pursuant to Section 2.390 of Title 10 of the Code of FederalRegulations. As such, we have enclosed non-proprietary and proprietary versions of the RAI (Enclosures 1 and 2 respectively).
In the PSEG letter (LR-N07-0274) dated October 23, 2007, your staff agreed to respond by November 30, 2007, to the enclosed questions except for RAI 14.66 follow-up. Based on discussions with your staff, it is our understanding that PSEG is developing a plan to test a previously purchased, spare steam dryer to address the issues in RAI 14.66 follow-up. In a phone call on November 2, 2007, your staff stated that the test results for the spare dryer would be provided to the NRC staff by December 31, 2007.
Enclosure 2 transmitted herewith contains Official Use Only - Proprietary Information. When separated from Enclosure 2, this document is decontrolled.
OpCL
""-F""" "' USE O U "'""= .
- PROPRIETARY :;'FO M LRTION#
O.FFiCAL USE.NlY - PRO T NFE)RI'ATION W. Levis Please note that if you do not respond to this letter within the prescribed response times or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of FederalRegulations, Section 2.1,08. If you have any questions, I can be reached at (301) 415-3100.
Sincerely, ,_
John G. Lamb, Senior Project Manager Project Directorate 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosures:
As stated cc w/ Enclosure 1 only: See next page
. OFFielft USE E)HEY - FFIeNF RIETAY INFORMATION
. i
Hope Creek Generating Station cc:
Mr. Thomas Joyce Mr. Michael Gaffney Senior Vice President - Operations Manager - Hope Creek Regulatory PSEG Nuclear Assurance P.O. Box 236 PSEG Nuclear Hancocks Bridge, NJ 08038 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Dennis Winchester Vice President - Nuclear Assessment Township Clerk ,
PSEG Nuclear Lower Alloways Creek Township P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Carl Fricker Mr. Paul Bauldauf, PE., Asst. Director Vice President - Operations Support Radiation Protection Programs PSEG Nuclear NJ Department of Environmental P.O. Box 236 Protection and Energy Hancocks Bridge, NJ 08038 CN 415 Trenton, NJ 08625-0415 Mr. John Perry Plant Manager - Hope Creek Mr. Brian Beam PSEG Nuclear Board of Public Utilities P.O. Box 236 2 Gateway Center, Tenth Floor Hancocks Bridge, NJ 08038 Newark, NJ 07102 Mr. James Mallon Regional Administrator, Region I Manager -. Licensing U.S. Nuclear Regulatory Cormmissinn PSEG Nuclear 475 Allendale Road P.O. Box 236 King of Prussia, PA 19406 Hancocks Bridge, NJ 08038 Senior Resident Inspector Mr. Jeffrie J. Keenan, Esquire Hope Creek Generating Station PSEG Nuclear - N21 U.S. Nuclear Regulatory Commission P.O. Box 236 Drawer 0509 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. William Levis
.President & Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038,
REQUEST FOR ADDITIONAL INFORMATION (NON-PROPRIETARY VERSION)
REGARDING TECHNICAL SPECIFICATION CHANGES FOR EXTENDED POWER UPRATE HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated September 18, 2006, as supplemented on October 10 and October 20, 2006, February 14, February 16, February 28, March 13 (2 letters), March 22, March 30 (2 letters), April 13, April 18, April 30, May 10, May 18 (3 letters), June 22, August 3, August 17, August 31, September 11, and October 10, 2007, PSEG Nuclear, LLC (PSEG or licensee) submitted an amendment request for an extended power uprate (EPU) for Hope Creek Generating Station (Hope Creek). The proposed amendment would increase the authorized maximum power level by approximately 15 percent, from 3339 megawatts thermal (MWt) to 3840 MWt.
The Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review.
- 14. Mechanical & Civil Engineering Branch Request for Additional Information (RAI) 14.66 Follow-up In RAI 14.66, the staff noted that shifting the frequency of the Hope Creek steam dryer loading will account for uncertainty and bias in the finite element (FE) model resonance frequencies.
However, it does not account for errors in the mean and peak frequency response amplitudes due to uncertainty or bias in plate dimensions, boundary conditions (joints between plates and other members), pre-stresses within members, and friction between internal vanes and other components.
As a clarification of RAI 14.66, PSEG is requested to discuss its consideration of the uncertainty and bias in the dryer FE model frequency response function amplitudes (not in the modal frequencies, the uncertainties of which are already handled by frequency shifting the loads). For example, the assessment of the uncertainties should consider dryer component geometries (length and width, as well as thickness), boundary conditions, and pre-stresses that might occur during welding and assembly.
ENCLOSURE1 (NON-PROPRIETARY)
RAI 14.74 Follow-up In RAI 14.74, PSEG was requested to provide acceptance vibration limits for the safety relief valves (SRVs) on the Hope Creek main steam lines (MSLs). In its response to RAI 14.74, PSEG refers to the FE analysis of the SRVs conducted by MPR Associates. PSEG states that the results of this analysis will be incorporated into the power ascension plan. PSEG is requested to provide a summary of the MPR analysis including the results and conclusions.
NOTE: This RAI was answered in PSEG letter LR-N07-0266, dated October 10, 2007.
RAI 14.77 Follow-up In RAI 14.77, PSEG was requested to provide the following information for the seven weld locations, identified in Table 7b of CDI Report No. 06-27 (Rev. 2), having minimum alternate stress ratio (SR-a) at 115 percent current licensed thermal power (CLTP) conditions with frequency shifts: (1) thickness of the plates at a weld location, (2) if thicknesses are different, identify the nominal stresses in the weld leg attached to the thicker plate, (3) identify the type of loading (normal or bending) acting on the weld during EPU operation, (4) estimate the undersize weld factors, and (5) estimate the minimum alternate stress ratio at the seven weld locations taking into account the undersize weld factors. PSEG has provided part of the requested information in a table for six weld locations where components of different thicknesses are connected.
As a follow-up to RAI 14.77, the licensee is requested to provide the following missing information for each of the six weld locations: (1) identify the alternating stress intensity in both thick and thin components; (2) idenIify the type of loading (normal and/or bending) acting on the weld; (3) estimate the corresponding undersize weld factors; and (4) estimate the alternate stress ratio for both thick and thin plates.
RAI 14.79 Follow-up In response to RAI 14.79 and in Section 3.8, Mesh Details and Element Types, of CDI Report No.07-17P, PSEG describes numerical experiments carried out using the ANSYS code applied to simple analytically tractable structures with dimensions and mesh spacing similar to the ones used for the steam dryer, confirming that the natural frequencies are accurately recovered (less than 1 percent errors for the first modes). The staff noted that establishing convergence of resonance frequencies is not sufficient to establish convergence of strain and stress fields. Also, frequency shifting loarling functions does not account for lack of convergence in strain and stress fields. Therefore, as a follow-up to RAI 14.79, PSEG is requested to provide pertinent parametric evaluations related to mesh convergence in high strain and stress regions in the Hope Creek steam dryer to assess whether the dimensions and mesh spacing used for the model are adequate. In particular, plots of stresses near high stress regions for coarse and dense FE meshes could be used to confirm that the dryer model used to establish the Hope Creek limit curves are converged.
RAI 14.107 Follow-up The projected Hope Creek MSL pressure spectra provided in response to RAI 14.107 show that tones may appear near 120 Hz. Since PSEG currently filters 120 Hz signals from the MSL measurements, explain the monitoring and calculation of stress effects of any valve singing tone that occurs near 120 Hz.
RAI 14.110 Follow-up The stress analysis of the Hope Creek steam dryer represents the first application of the frequency based approach as presented in CDI Report 07-17P for ((
)). Therefore, a comprehensive verification of this approach is necessary for the reliable prediction of stresses in the Hope Creek steam dryer. The ((
)). To validate the approach, a rigorous calculation that includes (1) a complex structural dynamic, FE model, and (2) a complex spatial and temporal surface loading, is necessary. Item (1) has been met by the existing calculation, but item (2) has not. PSEG notes that ((
)) when analyzing a full steam dryer model. PSEG could consider an alternative analysis to verify the new approach. For example, a small section of a steam dryer could be analyzed, such as one of the outer hoods, using actual plant loads (such as those from CDI report 07-17P) over all frequencies. The outer hood boundaries could be constrained with pins or clamps. The model should retain the dynamic characteristics of the larger steam dryer model, such as having closely spaced natural frequencies. The analysis should include the following aspects:
(a) One percent Rayleigh damping would be used for the transient simulations. Estimate the actual damping value at each natural frequency of the simplified model (i.e., small section of dryer) and use them in performing new frequency based simulations.
Stress and displacement time histories at high stress locations from both approaches would be compared ((
)). Maximum stresses and displacements for both approaches would then be compared at several locations on the hood.
(b) Along with comparing time series computed using the transient and frequency based simulations for a model like the one described in part (a), PSEG should provide comparisons of Fast Fourier Transforms, as specified in the original RAI, and explain any differences between peak levels.
(c) Reevaluate the frequency simulations considered in Part (a) of this RAI with 1 percent of the critical damping for all the frequencies and the compare the results for high stresses, displacements and alternating stress ratios with those for the transient simulations presented in Part (a). Provide justification for the differences in the results.
Additional RAI 14.111
)). PSEG is requested to explain why such large differences exist in the source strengths.
Additional RAI 14.112
)). PSEG is requested to provide this report for evaluation of the new methodology.
Additional RAI 14.113 In CDI Report No.07-09P, a new ACM Rev. 4 is developed to improve prediction of the dryer load at low frequencies. f[
I]
Additional RAI 14.114 In the development of the hydrodynamic load contribution on page 8 of CDI Report No.07-09P, reference is made to pressure fluctuations p = 0.1 pU 2. It is not clear whether this estimate is used in equation 4.1 for the (( )). The other parameters used in equation 4.1 are also not clear.'PSEG is requested to:
(a) if the estimate p = 0.1 pU is used in equation 4.1, validate this estimate from f[
)) on the dryer, e.g. from Quad Cities 2 (QC2) dryer measurements; and (b) ((
Additional RAI 14.115 On page 4 of CDI Report No.07-09P, CDI develops a new ACM code to improve the prediction of dryer load at low frequency. The report states that the Helmholtz and Acoustic Circuit Model (ACM) analyses are driven by (( )). In the new ACM Rev. 4, it appears that ((
)). PSEG is requested to provide the ((
)).
Additional RAI 14.116 The pressure fluctuations measured by the strain gages on the MSLs contain noise signals that are not acoustic in nature. In CDI Report No.07-09P, the ((
)), In particular, PSEG should provide:
(a) (( ));
(b) ((
)); and (c) more detailed explanation of step 3.
Additional RAI 14.117 Referring to CDI Report No.07-09P, the predictions of ACM Rev. ((
)).
PSEG is requested to explain ((
I].
Additional RAI 14.118 Benchmarking of the new ACM Rev. 4 against the data of QC2 dryer is presented in CDI Report No. 07-09. PSEG has not demonstrated that this benchmarking is an adequate validation of the new methodology. For example, the low frequency loading on the dryer of QC2 is relatively small, and the (( )). The new version of ACM Rev. 4 needs to be validated against data from additional dryers exposed to strong low frequency loading. PSEG is requested to provide validation of this new methodology against additional dryer data.
Additional RAI 14.119 In CDI Report no. 07-18, ACM Rev. 4 is used to predict the dryer load of HC1 from strain gage measurements on.MSLs. No details however aregiven regarding the ((
)). PSEG is requested to provide the following:
(a) ((
I].
(b) ((
)).
(c) ((
(]
(d) ([
I]
Additional RAI 14.120 In CDI Report No.07-18P, the ((
)) In CDI Report No.07-17P, 90 percent of this signal is filtered out based on the determination that this component is n ot present in the pressure measurements taken from the steam dome (see page 79 of CDI Report No.07-17P). However, the absence of the ((
].
Although consideration of the full strength of the ((
)) (i.e. still results in a positive stress ratio), PSEG is requested to provide additional information to ((
Additional RAI 14.121 The following questions are intended for clarification of CDI Report 07-17P:
(a) In Equation (6), why is the right-hand side multiplied by (1 +X)?
(b) In Section 2.3, first paragraph, it is stated, "Off-surface loads are required by ANSYS to ensure proper interpolation of forces." What are off-surface loads? Please explain the statement.
(c) In Section 2.3, second paragraph, first sentence states, ((
)) Please explain this sentence. The last sentence of this paragraph states, "Linear interpolation is sufficient since the pressure load varies slowly over(( )) Please explain why the ((
)).
(d) Section 3.3, fourth bullet: Please explain the statement, ((
1]
(e) Please explain the connections of shell edges to solid faces and shell edges to solids as used in the steam-dryer model and discussed in Section 3.9.
(f) In Section 4.4, the factor fsw is used to reflect different weld types. Please explain the meaning of this factor and how it is used in the report.
Additional RAI 14.122 According to the stress analysis using frequency based approach as documented in CDI Report 07-17P (Section 6: Conclusions), the minimum alternating stress ratio at 115 percent CLTP is 2.71 when 10 percent of the 80 Hz signal is included in the analysis. In contrast, according to the stress analysis using direct time history method as documented in CDI Report 06-27, the minimum alternating stress ratio at 115 percent CLTP is 1.33 (Table 7b). Please explain why the
minimum alternating stress ratio as determined by the frequency based approach is more than twice the corresponding ratio determined using the direct time history analysis despite the inclusion of the 10 percent of the 80 Hz signal only with the frequency based approach.
Additional RAI 14.123 The weld locations having the lowest alternating stress ratios as reported in Tables 7b and 8b in CDI Report 07-17P (frequency based approach) appear to be different than those reported in Table 7b in CDI Report 06-27 (direct time history analysis). Please provide justification for these differences.