Letter Sequence Response to RAI |
---|
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
[Table View] |
|
---|
Category:Legal-Affidavit
MONTHYEARLR-N21-0040, Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-05-27027 May 2021 Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication LR-N21-0042, Core Operating Limits Report, Reload 23, Cycle 24, Revision 212021-05-24024 May 2021 Core Operating Limits Report, Reload 23, Cycle 24, Revision 21 LR-N21-0018, Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-04-29029 April 2021 Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication LR-N20-0023, License Amendment Request: Revise Hope Creek Generating Station Low Pressure Safety Limit to Address General Electric Nuclear Energy Part-21 Safety Communication SC05-032020-09-24024 September 2020 License Amendment Request: Revise Hope Creek Generating Station Low Pressure Safety Limit to Address General Electric Nuclear Energy Part-21 Safety Communication SC05-03 LR-N19-0101, Submittal of Core Operating Limits Report, Reload 22, Cycle 23, Revision 172019-11-12012 November 2019 Submittal of Core Operating Limits Report, Reload 22, Cycle 23, Revision 17 LR-N19-0074, Core Operating Limits Report, Reload 21, Cycle 22, Revision 162019-09-0303 September 2019 Core Operating Limits Report, Reload 21, Cycle 22, Revision 16 LR-N19-0015, Core Operating Limits Report, Reload 21, Cycle 22, Revision 152019-03-0606 March 2019 Core Operating Limits Report, Reload 21, Cycle 22, Revision 15 LR-N18-0055, Attachment 3 to LR-N18-0055, Affidavit for Core Operating Limits Report for Unit 12018-05-0909 May 2018 Attachment 3 to LR-N18-0055, Affidavit for Core Operating Limits Report for Unit 1 LR-N17-0181, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate LR-N17-0126, Response to Request for Additional Information (Rai), P-T Limit Report License Amendment Application2017-09-0505 September 2017 Response to Request for Additional Information (Rai), P-T Limit Report License Amendment Application ML17188A2622017-03-29029 March 2017 Enclosure 7 to LR-N17-0044 and LAR H17-03 - Affidavits from GEH and the Electric Power Research Institute (EPRI) Supporting the Withholding of Information in Enclosure 6 from Public Disclosure ML17188A2682017-03-29029 March 2017 Enclosure 13 of LR-N17-0044 and LAR H17-03 - Affidavits from Cameron International Corporation Supporting the Withholding of Information in Enclosures 9 and 11 from Public Disclosure LR-N17-0044, Enclosure 13 of LR-N17-0044 and LAR H17-03 - Affidavits from Cameron International Corporation Supporting the Withholding of Information in Enclosures 9 and 11 from Public Disclosure2017-03-29029 March 2017 Enclosure 13 of LR-N17-0044 and LAR H17-03 - Affidavits from Cameron International Corporation Supporting the Withholding of Information in Enclosures 9 and 11 from Public Disclosure LR-N17-0044, Enclosure 7 to LR-N17-0044 and LAR H17-03 - Affidavits from GEH and the Electric Power Research Institute (EPRI) Supporting the Withholding of Information in Enclosure 6 from Public Disclosure2017-03-29029 March 2017 Enclosure 7 to LR-N17-0044 and LAR H17-03 - Affidavits from GEH and the Electric Power Research Institute (EPRI) Supporting the Withholding of Information in Enclosure 6 from Public Disclosure LR-N16-0202, PSEG Nuclear LLC (PSEG) - Board Resolutions - Foreign Ownership, Control, or Influence2016-11-0303 November 2016 PSEG Nuclear LLC (PSEG) - Board Resolutions - Foreign Ownership, Control, or Influence LR-N22-0083, Enclosure 3 - Global Nuclear Fuel - Americas Affidavit of Lukas Trosman2016-10-28028 October 2016 Enclosure 3 - Global Nuclear Fuel - Americas Affidavit of Lukas Trosman LR-N16-0204, Affidavit for Core Operating Limits Report, Reload 20, Cycle 21, Revision 132016-10-28028 October 2016 Affidavit for Core Operating Limits Report, Reload 20, Cycle 21, Revision 13 LR-N16-0113, GEH Affidavits Supporting the Withholding of Information in Enclosure 6 from Public Disclosure2016-08-16016 August 2016 GEH Affidavits Supporting the Withholding of Information in Enclosure 6 from Public Disclosure LR-N15-0071, Core Operating Limits Report, Reload 18, Cycle 19, Revision 102015-03-20020 March 2015 Core Operating Limits Report, Reload 18, Cycle 19, Revision 10 ML14204A7092014-07-23023 July 2014 Enclosure 3, Affidavit of Peter M. Yandow LR-N14-0157, PSEG Nuclear (PSEG) Response to NRC Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request, Dated May 5, 20142014-06-19019 June 2014 PSEG Nuclear (PSEG) Response to NRC Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request, Dated May 5, 2014 LR-N12-0075, Core Operating Limits Report, Reload 16, Cycle 17, Revision 62012-02-28028 February 2012 Core Operating Limits Report, Reload 16, Cycle 17, Revision 6 ML1127000682011-09-26026 September 2011 Enclosure 3, Mfn 10-245 R4, Affidavit LR-N11-0087, 2011 Annual Report - Guarantees of Payment of Deferred Premiums2011-03-31031 March 2011 2011 Annual Report - Guarantees of Payment of Deferred Premiums ML0831008272008-10-31031 October 2008 Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit LR-N08-0224, Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit2008-10-31031 October 2008 Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit LR-N08-0029, Transmittal of Proprietary Report 07-17P, Revision 3, Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Revision 4 Loads Model.2008-01-30030 January 2008 Transmittal of Proprietary Report 07-17P, Revision 3, Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Revision 4 Loads Model. LR-N08-0028, Responses to Requests for Additional Information Request for License Amendment - Extended Power Uprate2008-01-25025 January 2008 Responses to Requests for Additional Information Request for License Amendment - Extended Power Uprate LR-N08-0014, Responses to Requests for Additional Information Request for License Amendment - Extended Power Uprate2008-01-18018 January 2008 Responses to Requests for Additional Information Request for License Amendment - Extended Power Uprate LR-N07-0215, Supplement to License Amendment Request for Extended Power Uprate2007-08-27027 August 2007 Supplement to License Amendment Request for Extended Power Uprate 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 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 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 LR-N06-0192, Guaranteed Retrospective Premiums Following Nuclear Accident, Salem and Hope Creek2006-05-0101 May 2006 Guaranteed Retrospective Premiums Following Nuclear Accident, Salem and Hope Creek LR-N05-0448, Response to Request for Additional Information Re Request for Change to Technical Specifications Arts/Mellla Implementation2005-09-23023 September 2005 Response to Request for Additional Information Re Request for Change to Technical Specifications Arts/Mellla Implementation ML0520003282005-07-14014 July 2005 Surveillance Program for Channel-Control Blade Interference LR-N05-0247, Stations - Guaranteed Retrospective Premiums Following a Nuclear Accident2005-04-29029 April 2005 Stations - Guaranteed Retrospective Premiums Following a Nuclear Accident ML0419004262004-07-0101 July 2004 GE Nuclear Energy Request for Withholding - Hope Creek Fuel Vendor Change Response to NRC Request for Additional Information (Docket No. 50-354) LR-N03-0386, Transmittal of Information Relating to SVEA-96+ Modeling Dimensions in Support of the Nrc'S Review of GNF-A Proprietary Report, NEDC-33107P, GEXL80 Correlation for SVEA96+ Fuel, Dated September 20032003-09-0808 September 2003 Transmittal of Information Relating to SVEA-96+ Modeling Dimensions in Support of the Nrc'S Review of GNF-A Proprietary Report, NEDC-33107P, GEXL80 Correlation for SVEA96+ Fuel, Dated September 2003 2021-05-27
[Table view] Category:Letter type:LR
MONTHYEARLR-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 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 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) 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 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 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 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 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 LR-N22-0075, 2022 Annual 10 CFR 50.46 Report2022-09-30030 September 2022 2022 Annual 10 CFR 50.46 Report LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022 Emergency Plan Evacuation Time Estimate LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022 Emergency Plan Document Revisions Implemented November, 2021 LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) LR-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022 Emergency Plan Document Revisions Implemented March 24, 2022 LR-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022 Guarantees of Payment of Deferred Premiums LR-N22-0017, Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data2022-02-25025 February 2022 Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility2022-02-24024 February 2022 Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility LR-N22-0019, Technical Specification 6.9.1.5.b 2021 Annual Report of SRV Challenges2022-02-24024 February 2022 Technical Specification 6.9.1.5.b 2021 Annual Report of SRV Challenges LR-N22-0011, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2022-02-0101 February 2022 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N22-0005, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-01-0707 January 2022 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs LR-N22-0007, Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2022-01-0505 January 2022 Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs LR-N21-0087, Corrected Hope Creek 10 CFR 50.46 Reports2021-12-0202 December 2021 Corrected Hope Creek 10 CFR 50.46 Reports LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0081, Submittal of Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments2021-11-15015 November 2021 Submittal of Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments LR-N21-0056, License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System2021-11-0303 November 2021 License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2021-11-0303 November 2021 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N21-0071, 2021 Annual 10 CFR 50.46 Report2021-09-30030 September 2021 2021 Annual 10 CFR 50.46 Report LR-N21-0065, License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-09-29029 September 2021 License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0069, Emergency Plan Document Revisions Implemented August 10, 20212021-09-0909 September 2021 Emergency Plan Document Revisions Implemented August 10, 2021 LR-N21-0059, In-Service Inspection Activities - 90 Day Twenty-Third Refueling Outage2021-08-13013 August 2021 In-Service Inspection Activities - 90 Day Twenty-Third Refueling Outage LR-N21-0054, Correction to Prior Spent Fuel Cask Registration Letter2021-07-15015 July 2021 Correction to Prior Spent Fuel Cask Registration Letter LR-N21-0046, Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2021-06-17017 June 2021 Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem LR-N21-0040, Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-05-27027 May 2021 Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication LR-N21-0042, Core Operating Limits Report, Reload 23, Cycle 24, Revision 212021-05-24024 May 2021 Core Operating Limits Report, Reload 23, Cycle 24, Revision 21 LR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021 License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N21-0039, Deviation from EPRI Document 33002012244 Inspection Requirements2021-04-30030 April 2021 Deviation from EPRI Document 33002012244 Inspection Requirements LR-N21-0018, Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-04-29029 April 2021 Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication 2023-09-08
[Table view] |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0PSEG Nuclear LLC 10 CFR 50.90 LR-N08-0028 LCR H05-01, Rev'. 1 January 25, 2008 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington-, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Responses to Requests for Additional Information Request for License Amendment - Extended Power Uprate
Reference:
- 1) Letter from George P. Barnes (PSEG Nuclear LLC) to USNRC, September 18, 2006
- 2) Letterfrom USNRC to William Levis (PSEG Nuclear LLC),
January 23, 2008
- 3) Letter from USNRC to William Levis (PSEG Nuclear LLC),
January 25, .2008 In Reference 1, PSEG Nuclear LLC (PSEG) requested an amendment to Facility Operating License NPF-57 and the Technical Specifications (TS) for the ýHope Creek Generating Station (HCGS) to increase the maximum authorized power level to 3840 megawatts thermal (MWt).
In Reference 2, the NRC requested additional information concerning PSEG's request. to this letter provides. PSEG's responses. Attachment 1 also provides responses to two additional questions, in Reference 3.
As discussed in the response to RAI 14.66 2nd Follow-Up - 1,PSEG will provide an evaluation of the differences and resulting changes (if any) to the finite element model bias and uncertainty by February 08, 2008. contains information proprietar~y to Continuum Dynamics, Inc. (C.D.l.).
C.DI. requests that the proprietary informhation in Attachment 1 be withheld from public 95-2168 REV. 7/99
LR-N08-0028 LCR H05-01, Rev. 1 January 18, 2008 Page 2 disclosure in accordance with 10 CFR 2.390(a)(4). An affidavit supporting this request is included with Attachment 1. A non-proprietary version of PSEG's Attachment 1
.responses is provided in Attachment 2.
There are no regulatory commitments contained within this letter.
Should you have any questions regarding this submittal, please contact Mr. Paul Duke at 856-339-1466.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on /129 (date)c~
Sincerely, George P. Barnes Site Vice President Hope Creek Generating Station
LR-N08-0028 LCR H05-01, Rev. 1 January 25, 2008 Page 3 Attachments (2)
- 1. Response to Request for Additional Information (proprietary)
- 2. Response to Request for Additional Information (non-proprietary) cc: S. Collins, Regional Administrator - NRC Region I J. Lamb, Project Manager - USNRC NRC Senior Resident Inspector - Hope Creek P. Mulligan, Manager IV, NJBNE
4rA:W Continuum Dynamics, Inc.
(609) 538&0444 (609) 53&-0464 fax 34 Lexington Avenue Ewing, NJ 086 18-2302 AFFIAVIT Re: Responses to Hope Creek Generating Station - Request for Additional Information Regarding Extended Power Uprate (TAO No. MD3 002),
January 23, 2008 1, Barbara A. Agans, being duly sworn, depose and state as follows:
I I hold the position of Director, Business Administration of Continuum Dynamics, Inc. (hereinafter referred to as C.D.I.), and I am authorized to make the request for withholding from Public Record the Information contained in the documents described in Paragraph 2. This Affidavit is submiited to the Nuclear Regulatory Commission (NRC) pursuant to 10 CER 2.390(a)(4) based on the fact that the attached information consists of trade secret(s) of C.D.I. and that the NRC will receive the information from C.D.1. under privilege and in confidence.
2.- The Information sought to be withheld, as transmitted to PSEG Nuclear LLC as attachment to C.D.I. Letter No. 080 17 dated 25 January.2008 Responses -to Hope Creek Generating Station - Request for Additional Information Regarding Extended Power Uprate (ITAC No. MDii 3002), January 23, 2008.
- 3. The Inormation summarizes:
(a) a process or method, including supporting data and analysis, where prevention of its use by C.D.L.'s competitors without license from C.D.I. constitutes a competitive advantage over other companies; (b) Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product; (c) Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs 3(a), 3(b) and 3(c) above.
- 4. The Information has been held in confidence by C.D.L., its owner. The Information has consistently been held in confidence by C.D.I. and no public disclosure has been made and it is not available to the public. All disclosures to
third parties, which have been limited, have been made pursuant to the terms and conditions contained in C.D.T. 's Nondisclosure Secrecy Agreement which must be fulfly executed prior to disclosure.
.5. The Information is a type customarily held in confidence by C.D.T. and there is a rational basis therefore. The Information is a type, which C.D.T. considers trade secret and is held in confidence by C.D.T. because it constitutes a source of competitive advantage in the competition and performance of such work in the industry. Public disclosure of the Information is likely to cause substantial harm to C.D.T.'s competitive position and foreclose or reduce the availability of profit-making opportunities.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to be the best of my knowledge, information and belief.
Executed on this ____ day of .. ) L 2008.
brara A. Agans Continuum Dynamics, Inc.
Subscribed and sworn before me this day: 9c?
C4fýurese4 ýbc EILEEN P. BURMEISTER NOTARY PUBLIC OF NEW JERSEY MY COMM. EXPIRES MAY 6,2012
LR-N08-0028 ATTACHMENT 2 Hope Creek Generating Station Facility Operating License NPF-57 Docket No. 50-354 Extended Power Uprate Response to Request for Additional Information In Reference 1, PSEG Nuclear LLC (PSEG) requested an amendment to Facility Operating License NPF-57 and the Technical Specifications (TS) -for the Hope Creek Generating Station (HCGS) to increase the maximum authorized power level to 3840 megawatts thermal (MWt).
In References 2 and 3, the NRC requested additional information concerning PSEG's request. PSEG's responses are provided below.
RAI 14.66 2nd Follow-Up -I Page .22 of Continuum Dynamics, Inc. (CDI) Report 07-27P, "Finite Element Modeling Bias and Uncertainty Estimates Derived from the Hope Creek Unit 2 Dryer Shaker Test, Rev. 0," presents damping values computed for the finite element (FE) model to best match FE and measured acceleration response function peaks. CDI states that the inferred FE damping values are consistent with measured damping values in STI Technologies Report PA2168, "Hope Creek Steam Dryer Vibration Test." However, no damping values (other than those for low frequency rigid body modes) are presented in the STI report.
(a) Provide and plot the damping values from the measurements as a function of shaker location and frequency. Also include minimum, maximum, mean,-and root mean square values (computed over frequency) for each shaker location consistent with those in Table 3 in CDI Report 07-27P.
Response
Data Description A 24 channel dynamic signal analyzer was used to acquire and process the signals from the sensors. ICP signal conditioning in the analyzer allows direct connection of the sensors. The signals were digitized using 24 bit resolution and a sampling rate of 625Hz. During the steam dryer test, the sine sweep method was used to identify the most prominent natural frequencies excited from each driving point. The sweep tests were not designed to extract structural damping, values. Frequency functions were calculated for each signal using 16384 lines to achieve a frequency resolution 0.019 Hz in the frequency band up to 250 Hz. A Hanning window was used to
LR-NO8-0028 Attachment 2 Page 2 mitigate leakage in the Fourier transform. The use of an exponential weighting window is known to bias damping estimates high (Formenti & McMillan, S&V Questions & Answers, Sound and Vibration Magazine, p.2, 1999)'. The affect of a Hanning window is likely to bias damping estimates high as well, but the exact magnitude is not known. Modal damping ratios wer6eextracted using-the LMS PolyMax modal parameter estimator.
Damping Estimates Table 1 below summarizes the experimental damping estimates. The graphs on the following pages show the analytic and experimental damping estimates as functions of frequency by driving point (shaker location).
(b)Plot and compare the measured damping values andý FIE damping, values inferred in CDI Report No.07-27P as a function of frequency and shaker location.
Response
The requested information is contained in Figures 1through 8 below.
LR-N08-0028 Attachment 2 Page 3 Figure 1 Driving point 1 experimental damping ratios 11 11
LR-N08-0028 Attachment 2 Page 4 Figure 2 Driving point 2 experimental damping ratios 11
LR-N08-0028 Attachment 2 Page 5 Figure 3 Driving point 3 experimental damping ratios 11
LR-N08-0028 Attachment 2 Page 6 Figure 4 Driving point 4 experimental damping ratios 11
LR-N08-0028 Attachment 2 Page 7 Figure 5 Driving point 5 experimental damping ratios III 11
LR-N08-0028 Attachment 2 Page 8 Figure 6 Driving point 6 experimental damping ratios 11
LR-N08-0028 Attachment 2 Page 9 Figure 7 Driving point 7 experimental damping ratios 11
LR-N08-0028 Attachment 2 Page 10 Figure 8 Driving point 8 experimental damping ratios 11l 11
LR-N08-0028 Attachment 2 Page 11 (c) Reconcile the differences between the measured and inferred FE damping values, and provide, the resulting FE bias and uncertainty.
Response
The tables of measured and inferred FE damping values show that the ranges of values are consistent with each other. PSEG will provide an evaluation of the differences and resulting changes (if any) to the FE bias and uncertainty by
'February 08, 2008.
RAI 14.66 2nd Follow-Up - 11 STI Technologies Report PA2168, "Hope Creek Steam Dryer Vibration Test" states on page 7 that a Hanning window was applied to the measured vibration response.
Hanning windows reduce peak amplitudes in Fourier Transforms. Was the Hanning window used during the peak response measurements conducted by driving -the shaker at a single frequency? If so, how has the peak amplitude reduction been accounted for?
Response
The Hanning window was applied to both the excitation and response during the sine dwell test. Therefore the same amplitude reduction is applied to both the applied force and to the measured acceleration. For a linear model such as the one developed by CDI, reducing the excitation and response by the same factor does not change the predicted -frequency response function.
RAI 14.79 - 3 rd Follow-up In RAI 14.79 - 2 nd Follow-up, PSEG was asked to evaluate the effects of the 10% non-conservative bias error in its FE stress calculations on the stress margins. In LR-N08-0006 dated 15 January-2008, PSEG argues that the stress underprediction bias factor associated with the dryer FE models may be neglected since it is embedded within the uncertainty associated with the FE models based on dryer shaker tests of accelerations.
However, the stresses converge with mesh resolution more slowly than displacements and accelerations do (accelerations were measured and compared in the dryer shaker test study), and that stress bias errors cannot be replaced with displacement-based uncertainties. When.PSEG submits its final dryer stress analyses, it should include the 10% non-conservative bias error associated with stress convergence in the margin calculations for maximum and alternating stress intensities.
Response
,LR-N08-0028 Attachment 2 Page 12 Note that both e,, and efe were calculated on grids with mesh resolution comparable to that used in operational steam dryer analysis.
The NRC staff subsequently pointed out that peak finite element stresses do not converge at the same rate as displacements. In a finite element calculation, the displacement generally converges at a different rate than stress since the latter is essentially a spatial derivative of the former. [
LR-NOB-0028 Attachment 2 Page 13
'I]
Figure 1. Displacement amplitude vs. frequency for location 2 in the 100-102 Hz frequency range.
-LR-N08-0028 Attachment 2 Page 14 As was also observed in the corresponding stress amplitude the displacement exhibits a peak about frequency 100.75 Hz. The associated peak values are plotted versus normalized mesh size squared in Figure 2. [
With this result in hand, one can conclude that the total error in the stress prediction due to both finite element modeling approximations and finite mesh size is:
LR-N08-0028 Attachment 2
.Page 15 Figure 2. Extrapolation of the peak displacement amplitudes as a function of mesh size. The peak displacement amplitudes occur about 100.75 Hz in Figure 1.. 'The mesh size is normalized by the mesh spacing on Mesh xl.
PSEG's final dryer stress analyses will include the additional (( ,)) error in the margin calculations for maximum and alternating stress intensities.
LR-N08-0028 Attachment 2 Page 16 RAI 14.120(f) - 2 nd Follow-up PSEG clearly explains [
))So that the staff may quantitatively determine the degree to which the Main Steam Line inputs have been filtered (using equation 8 on page 83 of the report),
provide plots of the frequency-dependent MSL input loads before and after filtering using the low-flow data.
Response
Figures 14.120.1 to 14.120.4 plot the PSID of the MSL ýinlet pressures as a function of frequency. [
11
LR-N08-0028 Attachment 2 Page 17 1]
LR-N08-0028 Attachment 2 Page 18 03
LR-N08-0028 Attachment 2 Page 19 I]
LR-N08-0028 Attachment 2
.Page 20 11
LR-N08-0028 Attachment 2 Page 21 References
- 1) Letter from George P. Barnes (PSEG Nuclear LLC) to USNRC, September 18,
.2006
- 2) Letter from USNRC to William Levis .(PSEG Nuclear LLC), January 23, 2008
- 3) Letter from USNRC to William Levis (PSEG Nuclear LLC), January 25, 2008