Letter Sequence Response to RAI |
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CAC:MF9930, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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MONTHYEARML17188A2652016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi Project stage: Request ML17188A2672017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) Project stage: Request ML17188A2602017-07-0707 July 2017 License Amendment Request for Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Request LR-N17-0044, Enclosure 15 to LR-N17-0044 and LAR H17-03 - LEFM Flow Meter Installation Location Drawings2017-07-0707 July 2017 Enclosure 15 to LR-N17-0044 and LAR H17-03 - LEFM Flow Meter Installation Location Drawings Project stage: Other ML17222A1182017-08-16016 August 2017 Acceptance of Requested Licensing Action License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Acceptance Review ML17235B1202017-08-28028 August 2017 Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance LR-N17-0141, Transmittal of 2017 Annual 10 CFR 50.46 Report2017-09-27027 September 2017 Transmittal of 2017 Annual 10 CFR 50.46 Report Project stage: Request ML17290B0132017-10-17017 October 2017 NRR E-mail Capture - Hope Creek Mur Request for Additional Information for Apla and Snpb Project stage: RAI LR-N17-0161, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-11-0101 November 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML17324A0522017-11-0909 November 2017 NRR E-mail Capture - Draft Request for Additional Information - Hope Creek Mur Chemical, Corrosion, and Steam Generator Project stage: Draft RAI ML17324A2602017-11-17017 November 2017 NRR E-mail Capture - Final Request for Additional Information - Hope Creek Mur Electrical Instrumentation and Controls Project stage: RAI ML17331A0072017-11-21021 November 2017 E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate Project stage: RAI LR-N17-0170, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-11-27027 November 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI LR-N17-0176, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Uprate2017-12-14014 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Uprate Project stage: Response to RAI LR-N17-0186, 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 Project stage: Response to RAI LR-N17-0175, 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 Project stage: Response to RAI LR-N17-0187, 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 Project stage: Response to RAI 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 Project stage: Response to RAI LR-N17-0189, Transmittal of Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-22022 December 2017 Transmittal of Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML18011A0352018-01-11011 January 2018 Request for Withholding Information from Public Disclosure for Hope Creek Generating Station (CAC No. MF9930; EPID L-2017-LLA-0426) Project stage: Withholding Request Acceptance LR-N18-0009, Supplemental Information for the Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2018-01-22022 January 2018 Supplemental Information for the Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Supplement ML18096A5422018-04-24024 April 2018 Hope Creek Generating Station - Issuance of Amendment Measurement Uncertainty Recapture Power Uprate (CAC MF9930; EPID L-2017-LLS-0002) Project stage: Approval 2017-12-19
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Category:Legal-Affidavit
MONTHYEARLR-N24-0042, Affidavit to Support Withholding the Core Operating Limits Report, Per 10 CFR 2.390(a)(4)2024-05-28028 May 2024 Affidavit to Support Withholding the Core Operating Limits Report, Per 10 CFR 2.390(a)(4) 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-N21-0018, 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 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-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 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-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 2024-05-28
[Table view] Category:Letter type:LR
MONTHYEARLR-N24-0044, Relief Request VR-042024-08-0606 August 2024 Relief Request VR-04 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 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 LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary LR-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 2024-08-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARLR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary LR-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-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-N21-0018, 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-N20-0069, Response to Final Request for Additional Information Regarding Revise Technical Specifications Requirements for High Pressure Coolant Injection System Inoperability2020-11-0404 November 2020 Response to Final Request for Additional Information Regarding Revise Technical Specifications Requirements for High Pressure Coolant Injection System Inoperability LR-N20-0043, PSEG Nuclear LLC - Response to Request for Additional Information, Adopt 10 CFR 50.69 LAR2020-06-25025 June 2020 PSEG Nuclear LLC - Response to Request for Additional Information, Adopt 10 CFR 50.69 LAR ML19308A5952019-11-0404 November 2019 Response to Request for Additional Information, License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements ML19280A0002019-10-0303 October 2019 NRR E-mail Capture - Hope Creek, Salem 1 and 2 - Final RAI Emergency Plan Staffing Requirements (L-2019-LLA-0145) LR-N18-0109, Response to Request for Additional Information, License Amendment Request: Inverter Allowed Outage Time (AOT) Extension2018-10-17017 October 2018 Response to Request for Additional Information, License Amendment Request: Inverter Allowed Outage Time (AOT) Extension LR-N18-0107, Response to Request for Additional Information, License Amendment Request Inverter Allowed Outage Time (AOT) Extension (Electrical Branch)2018-10-17017 October 2018 Response to Request for Additional Information, License Amendment Request Inverter Allowed Outage Time (AOT) Extension (Electrical Branch) LR-N18-0073, Supplement to License Amendment Request for Additional Information, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2018-07-19019 July 2018 Supplement to License Amendment Request for Additional Information, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. LR-N18-0061, Response to Request for Additional Information, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2018-06-27027 June 2018 Response to Request for Additional Information, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. LR-N17-0189, Transmittal of Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-22022 December 2017 Transmittal of Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate LR-N17-0175, 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-N17-0187, 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-N17-0181, 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-N17-0186, 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-N17-0176, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Uprate2017-12-14014 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Uprate LR-N17-0170, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-11-27027 November 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate LR-N17-0161, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-11-0101 November 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 LR-N17-0125, Response to Request for Additional Information Regarding Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2017-08-11011 August 2017 Response to Request for Additional Information Regarding Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors LR-N17-0109, Response to Final Request for Additional Information (Rai), Permanently Extend Type a and Type C Leak Rate Test Frequencies2017-07-13013 July 2017 Response to Final Request for Additional Information (Rai), Permanently Extend Type a and Type C Leak Rate Test Frequencies LR-N17-0063, Response to Request for Additional Information, Permanently Extend Type a and Type C Leak Rate Test Frequencies2017-03-27027 March 2017 Response to Request for Additional Information, Permanently Extend Type a and Type C Leak Rate Test Frequencies LR-N16-0231, Response to Request for Additional Information, License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling2016-12-27027 December 2016 Response to Request for Additional Information, License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling LR-N16-0226, Response to Request for Additional Information, Regarding Removing Certain Training Requirements2016-12-19019 December 2016 Response to Request for Additional Information, Regarding Removing Certain Training Requirements LR-N16-0232, Response to Prelim White Finding in Integrated Inspection Report 05000354/20160032016-12-14014 December 2016 Response to Prelim White Finding in Integrated Inspection Report 05000354/2016003 LR-N16-0192, Response to Request for Additional Information Stuck Open Safety/Relief Valves2016-12-13013 December 2016 Response to Request for Additional Information Stuck Open Safety/Relief Valves ML16305A2382016-10-31031 October 2016 Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spend Fuel Pools LR-N16-0165, Transmittal of Response to Request for Additional Information Regarding Digital Power Range Neutron Monitoring (Prnm) System Upgrade2016-09-23023 September 2016 Transmittal of Response to Request for Additional Information Regarding Digital Power Range Neutron Monitoring (Prnm) System Upgrade LR-N16-0174, Response to Second Request for Additional Information Regarding Relief Request VR-02 Associated with the Fourth 10-Year Inservice Test Interval2016-09-23023 September 2016 Response to Second Request for Additional Information Regarding Relief Request VR-02 Associated with the Fourth 10-Year Inservice Test Interval LR-N16-0148, Supplemental Information Regarding Request for Relaxation from the Hardened Containment Vent Release Point Height Requirement of NRC Order EA-13-1092016-09-0707 September 2016 Supplemental Information Regarding Request for Relaxation from the Hardened Containment Vent Release Point Height Requirement of NRC Order EA-13-109 LR-N16-0137, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External2016-08-24024 August 2016 Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External LR-N16-0119, Response to Request for Additional Information Regarding Review of Post-Extended Power Uprate Steam Dryer Stress Calculation Acoustic Circuit Model Software Error2016-06-29029 June 2016 Response to Request for Additional Information Regarding Review of Post-Extended Power Uprate Steam Dryer Stress Calculation Acoustic Circuit Model Software Error LR-N16-0109, and Hope Creek Generating Stations - Cover Letter for Response to Request for Additional Information Regarding Review of Security Plan, Revision 172016-06-15015 June 2016 and Hope Creek Generating Stations - Cover Letter for Response to Request for Additional Information Regarding Review of Security Plan, Revision 17 LR-N16-0105, Request for Additional Information Regarding Relief Requests Associated with the Fourth 10-Year Lnservice Test Interval2016-06-10010 June 2016 Request for Additional Information Regarding Relief Requests Associated with the Fourth 10-Year Lnservice Test Interval LR-N15-0256, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-12-23023 December 2015 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident LR-N15-0092, Compliance with NRC Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) and Responses to Requests for Additional Information2015-07-28028 July 2015 Compliance with NRC Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) and Responses to Requests for Additional Information 2024-04-26
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Attachment 3 Contains Proprietary Information to be Withheld from Public Disclosure Pursuant to 10 CFR 2.390 PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 PSlG Nuclear LLC 10 CFR 50.90 OEC 19 2017 LR-N17-0181 LAR H17-03 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE (CAC NO. MF9930)
References 1. PSEG letter to NRC, "License Amendment Request for Measurement Uncertainty Recapture (MUR) Power Uprate, " dated July 7, 2017 (ADAMS Accession No. ML17188A260)
- 2. NRC e-mail to PSEG, "EICB Request for Additional Information - Hope Creek Power Uprate," dated November 21, 2017 (ADAMS Accession No. ML17331A007)
In the Reference 1 letter, PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (HCGS). The proposed amendment will increase the rated thermal power (RTP) level from 3840 megawatts thermal (MWt) to 3902 MWt, and make Technical Specification (TS) changes as necessary to support operation at the uprated power level.
In the Reference 2 e-mail, the U.S. Nuclear Regulatory Commission staff provided PSEG a Request for Additional Information (RAI) to support the NRC staff's detailed technical review of Reference 1.
This letter provides the requested information in Attachment 1 (Non-Proprietary) and (Proprietary).
Attachment 3 Contains Proprietary Information to be Withheld from Public Disclosure Pursuant to 10 CFR 2.390 Page 2 10 CFR 50.90 LR-N17-0181 contains proprietary information as defined by 10 CFR 2.390. GE-Hitachi Nuclear Energy Americas LLC (GEH), as the owner of the proprietary information, has executed an affidavit (provided in Attachment 2) identifying that the proprietary information has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure. GEH requests that the proprietary information in Attachment 3 be withheld from public disclosure, in accordance with the requirements of 10 CFR 2.390(a)(4).
PSEG has determined that the information provided in this submittal does not alter the conclusions reached in the 10 CFR 50.92 no significant hazards determination previously submitted. In addition, the information provided in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
No new regulatory commitments are established by this submittal. If you have any questions or require additional information, please do not hesitate to contact Mr. Brian Thomas at (856) 339-2022.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on )?--/19/;*?-
(Date)
Eric Carr Site Vice President Hope Creek Generating Station
Attachment 3 Contains Proprietary Information to be Withheld from Public Disclosure Pursuant to 10 CFR 2.390 DtC 1 2017 Page '3 10 CFR 50.90 LR-N17-0181 Attachments
- 1. Response to EICB Request for Additional Information Regarding MUR Power Uprate Non-Proprietary (GEH Reference DOC-0006-01 06-087 Attachment 2)
- 2. GEH Affidavit supporting the withholding of information in Attachment 3 from public disclosure
- 3. Response to EICB Request for Additional Information Regarding MUR Power Uprate GEH Proprietary Information (GEH Reference DOC-0006-01 06-087 Attachment 1) cc: Mr. D. Dorman, Administrator, Region I, NRC Ms. L. Regner, Project Manager, NRC NRC Senior Resident Inspector, Hope Creek Mr. P. Mulligan, Chief, NJBNE Mr. L. Marabella, Corporate Commitment Tracking Coordinator Mr. T. MacEwen, Hope Creek Commitment Tracking Coordinator LAR H17-03 LR-N17-0xxx Response to EICB Request for Additional Information Regarding MUR Power Uprate Non-Proprietary This is the non-proprietary version of Attachment 3 of this letter which has the proprietary information removed. Portions of the document that have been removed are indicated by white space inside open and closed brackets as shown here (( )).
(GEH Reference DOC-0006-0106-087 Attachment 2) 1 of 6 LAR H17-03 LR-N17-0181 EICB-1 In the Section 5.1.1.3 of the LAR Enclosure 6, the licensee stated:
The rod block monitor (RBM) instrumentation is referenced to an APRM (Average Power Range Monitor) channel. Because the APRM has been rescaled, there is only a small effect on the RBM performance due to the LPRM (Local Power Range Monitor) performance at the higher average local flux. The RBM instrumentation is not significantly affected by the TPO (Thermal Power Optimization) uprate conditions, and no change is needed.
Please clarify what do "small effect" and "not sig nificantly affected" mean. The clarification should use the justification and conclusion made by the NRC approved technical reports such as the NEDC-32938P-A, "Thermal Power Optimization Licensing Topical Report" (TLTR),
NEDC-32424P-A, "Generic Guidelines for General Electric Boiling Water Reactor Extended Power Uprate" (ELTR1) or NEDC-32523P-A, "Generic Evaluations of General Electric Boiling Water Reactor Extended Power Uprate" (ELTR2); or use a qualitative and/or quantitative analysis. This information is needed to confirm that no change is needed to the RBM setpoint.
EICB -1 RESPONSE :
This statement is based on licensing topical report NEDC-33004P-A, "Constant Pressure Power Uprate, " Section 5.1.1.3. "LPRM performance" refers to accuracy, and per NEDC-33004P-A Section 5.1.1.2, LPRM accuracy remains within analyzed limits at uprate conditions. "Not significantly affected" means that the accuracy effect on the RBM due to the LPRMs is bounded by the analyzed performance of the RBM. As NEDC-33004P-A (Reference 1-1) is applicable to EPU uprated up to 120% of Original Licensed Thermal Power (OLTP) this statement is applicable to Hope Creek Generating Station (HCGS) at TPO conditions.
Additionally, Section 5.3.5 of NEDC-33004P-A states, "The severity of rod withdrawal error during power operation event is dependent upon the RBM rod block setpoint. This setpoint is only applicable to the control rod withdrawal error. ((
))
Because the RBM trip setpoints are analyzed on a cycle-specific basis as part of the core reload analysis, no changes to any RBM Technical Specification setpoints are required as part of the TPO uprate.
Reference 1-1. GE Nuclear Energy, "Constant Pressure Power Uprate," NEDC-33004P-A, Revision 4, July 2003.
2 of 6 LAR H17-03 LR-N17-0181 EICB-2 The licensee stated that the HCGS TPO RWM Lower Power Setpoint (LPSP) Analytical Limit (AL) has been scaled in terms of percent power to maintain the value in absolute power. The licensee summarized in the LAR Enclosure 1, Table 2.1, Item 11, LCO 3.1.4.1 Applicability is revised from 8.6% to 8.5% Rate Thermal Power (RTP) as minimum allowable LPSP. The licensee also listed in the LAR Enclosure 6, NEDC-33871P, "Safety Analysis Report for Hope Creek Generating Station Thermal Power Optimization," Revision 0 (TSAR), Table 5-1 that the RWM LPSP-AL (%RTP) is changed from 8.576 to 8.441.
- 1. Please confirm whether these two items (Item 11 in Table 2.1 in LAR Enclosure 1 and the RWM LPSP-AL in Table 5.1 in TSAR) refer to the same parameter.
- 2. Please provide additional details on the calculation for the change of the RWM LPSP-AL (%RTP), to allow the NRC staff to confirm the proposed change from 8.576 to 8.441 using the decrease factor of Current Licensed Thermal Power (CLTP) RTPITPO RTP (3840/3902).
EICB-2 RESPONSE:
- 1. LAR Enclosure 1, Table 2.1, Item 11 is the same parameter as the RWM LPSP-AL in Table 5.1 in the TSAR. In keeping with previous revisions of the Hope Creek Technical Specifications, this parameter has been conservatively rounded up from the value provided by GEH to the next 0.1% power.
- 2. For HCGS, the Rod Worth Minimizer (RWM) LPSP AL is ((
)), per Section F.4.2.9 of NEDC-32938P-A (Reference 2-1). Thus, the Therr:nal Power Optimization (TPO) AL decreases in terms of % RTP. ((
))
The change in the RWM LPSP AL can be calculated two ways:
(a) based on the published TPO increase of 1.6% RTP (NEDC-33871P (Reference 2-2)):
(8.576 I 1.016) = 8.4409 The calculation results are rounded up for conservatism to 8.441 % RTP.
and (b) based on the ratio of the change in RTP from 3,840 MW Th to 3, 902 MWTh:
(8.576) I (3, 902/3,840) = 8.4397 The calculation results are rounded up for conservatism to 8.440 % RTP.
3 of 6
Attachment 1 LAR H17-03 LR-N17-0181 The larger of these two calculated ALs (i.e., 8.441 % RTP) was chosen for the HCGS TPO, for conservatism.
Thus, the RWM rod withdrawal blocks enforcement will be based on a conservative change in the AL for TPO.
References 2-1. GE Nuclear Energy, "Generic Guidelines and Evaluations for General Electric Boiling Water Reactor Thermal Power Optimization," NEDC-32938P-A, Revision 2, May 2003.
2-2. GE Hitachi Nuclear Energy, "Safety Analysis Report for Hope Creek Generating Station Thermal Power Optimization," NEDC-33871 P, Revision 0, April 2017.
EICB- 3 The licensee summarized the change of the Single Loop Operation (SLO) Simulated Thermal Power (STP) Upscale Rod Block Nominal Trip Setpoint (NTSP) (%RTP) from 0.57 (Wd-1 0.6) +
54.0 to 0.56(Wd-1 0.8) +53.1 in LAR Enclosure 1, Table 2.1 Item 14. Please provide the calculation details for the change of the feedwater offset from 10.6 to 1 0.8.
EICB-3 RESPONSE:
Note that this question is actually discussing the recirculation offset as it pertains to the Average Power Range Monitor (APRM) STP flow-biased scram and rod block NTSPs, rather than the stated feedwater offset. These NTSPs are listed in items No. 8 and 14, respectively, in of the HCGS License Amendment Request (Reference 3-1).
Background:
For HCGS, the 11W equals 9% drive flow. The 11W is used in the APRM STP Allowable Value (AV) equations.
However, the APRM STP NTSP equations must account for increased flow errors in the idle loop while in SLO. Hence, a SLO to Two Loop Operation (TLO) setting adjustment (SLOsewngAdi) is used in the NTSP equations that is larger than the 11W. ((
)) If only 11W was used in the SLO equations, then a different intercept in the SLO NTSP equations would be needed, as shown in the example APRM STP scram and rod block equations below (in units of % Rated Thermal Power (RTP) and where Wd is the % recirculation drive flow, where 100% drive flow is required at 1 00% core power and flow):
4 of6 LAR H17-03 LR-N17-0181 TLO NTSP Equations Pa rameter Equation CLTP APRM STP-Upscale, Flow Biased-TLO (Scram) 0.57Wd +59 APRM STP-Upscale, Flow Biased - TLO (Rod Block) 0.57Wd +54 TPO APRM STP-Upscale, Flow Biased-TLO (Scram) 0.56Wd +58 APRM STP-Upscale, Flow Biased-TLO (Rod Block) 0.56Wd + 53.1 SLO NTSP Equations Parameter Eq uation with AW Equation with SLOsettingAd J CLTP APRM STP-Upscale, Flow 0.57(Wd-6.W) +58.1 0.57(Wd-SLOsettingAd J) +59 Biased-SLO (Scram) 0.57(Wd-9) +58.1 0.57(Wd-10.6) +59
= 0.57Wd +52.97 APRM STP-Upscale, Flow 0.57(Wd-6.W) +53.1 0.57(Wd-SLOsettlngAd J) +54 Biased-SLO (Rod Block) 0.57(Wd-9) +53.1 0.57(Wd-10.6) +54
= 0.57Wd + 47.97 TPO APRM STP-Upscale, Flow 0.56(Wd-6.W) +57 0.56(Wd -SLOsettingAdJ) +58 Biased-SLO (Scram) 0.56(Wd-9) +57 0.56(Wd -10.8) +58
= 0.56Wd +51.97 APRM STP-Upscale, Flow 0.56(Wd-6.W) +52.1 0.56(Wd-SLOsettingAdJ ) +53.1 Biased-SLO (Rod Block) 0.56(Wd-9) +52.1 0.56(Wd-1 0.8) +53.1
= 0.56Wd +47.07 Note that the ordinate (at zero recirculation flow) remains the same for TLO and SLO when the SLO to TLO setting adjustment (SLOsettlngAdJ) is used in the NTSP equations. For example, the APRM STP rod block uses 54 for both TLO and SLO for CLTP conditions. It uses 53.1 for both TLO and SLO for TPO conditions.
Calculation of SLO to TLO Setting Adjustment (SLOsettingAdi} :
CLTP Conditions:
The scram TLO NTSP is 0.57Wd +59%, with an intercept of 59. The scram SLO NTSP is 0.57Wd + 52.97%, with an intercept of 52.97. For the SLO flow biased STP scram NTSP of 0.57Wd + 52.97%, the SLO NTSP intercept ((
5 of 6 LAR H17-03 LR-N17-0181
)) The resulting TLO to SLO setting adjustment is 10.5789.
Because the setting adjustment is programmed into the NUMAC' equipment to one decimal place, the calculated number is rounded up to one decimal place for conservatism to 10.6.
Thus, the resulting APRM flow biased STP NTSPs set into the equipment will be slightly more conservative than the numbers reported.
TPO Conditions:
The scram TLO NTSP is 0.56Wd +58%, with an intercept of 58. The scram SLO NTSP is 0.56Wd +51.97%, with an intercept of 51.97. For the SLO flow biased STP scram NTSP of 0.56Wd + 51.97%, the SLO NTSP intercept ((
)) The resulting TLO to SLO setting adjustment is 10.7679. Again, this calculated number is rounded up to one decimal place for conservatism to 10.8 for programming into the NUMAC' equipment.
Calculations of the TLO to SLO setting adjustments for both the CLTP and TPO rod block NTSP equations provide the same results as for the associated scram NTSPs shown above.
The APRM STP scram and rod withdrawal block NTSPs are based on use of a conservative SLO to TLO setting adjustment (SLOsettingAdi)* This SLO to TLO setting adjustment changes slightly for TPO conditions because of the slight changes in the TLO and SLO NTSPs.
Reference 3-1. Letter, Eric Carr (PSEG) to NRC Document Control Desk, "License Amendment Request for Measurement Uncertainty Recapture (MUR) Power Uprate," LR-N17-0044, LAR H17-03, July 17, 2017.
6 of 6 LAR H17-03 LR-N17-0181 GEH Affidavit supporting the withholding of information in Attachment 3 from public disclosure
GE-Hitachi Nuclear Energy Americas LLC AFFIDAVIT I, Lisa K. Schicblein, state as follows:
(1) I am a Senior Project Manager, NPP/Services Licensing, Regulatory Affairs, GBHitachi Nuclear Energy Americas LLC ("GEH,), and have been delegated the function of reviewing the information described in par agra ph (2) which is sought to be withheld, and have b een authorized to apply for its withholding.
(2) The information so ught to be w ithheld is contai ned in Attachment 1 of GEH letter, DOC00060106-087, "GEH Respons e to NRC TPO EICB RAisin Support of the Hope Creek TPO LAR/; dated December 7, 2017. The GEH proprie tary information in A ttachm ent 1, which is entitled "Response to EICB RAis in Supp or t of the Hope Creek TPO LAR/' is identified by a dotted underline inside double square brackets. ((Iht.
S.111©.tl.Cf:l.i.S..1Jl.CJ5-.m:P.l..)) In each case, the superscript notation t3l refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or Hcen see, GEH relies upon the exemption from disclosure set forth in the Freedom Qfl11(ormatiofl Act ("FOIA), 5 U.S.C. Sec. 552(b)(4); and the Trade Secrets Act, 18 U.S.C.
Sec. 1905, and NRC r egu latio ns 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exempti on 4). The rnaterial for which exemption from disclosure is here sought also qualifies under the narrower definition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy i-PrQject v. Nuclear Rgulatory Commission, 975 F.Zd 871 (D.C. Cir. 1992), and Pu blic 1 Citizen Health Research Group v. FDA, 704 F.2d 1280 (D.C. Cir. 1983).
(4) The information sought to be withheld is considered to be proprietary for the reaso ns set forth in paragraphs (4)a. and (4)b. Some examples of categories of information that fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data an d analyses, where prevention of its use by GEHs c ompetit ors witl10ut license from GEH constitutes a competitive economic advantage over other companies;
- b. Infor ma ti on that, if used by a competitor, would reduce their expenditure of resources or improve their co mpetiti ve posit ion in the design, manufacture, shipm ent ,
installation, assurance of quality, or licensing of a similar product;
- c. Information that reveals aspects of past, present, or future GEH customerfunded development plans and programs, resulting in potential products to GEH;
- d. Information that discloses trade secret or potentially patentab le su bject matter for which it may be desirable to obta in patent protection.
(5) To address 10 CFR 2.390(b)(4), the infom1ation sought to be withheld is being submitted to NRC in confidence. The inform ation is of a sort customarily held in c on fi de nce by GEH, Affidavit for DOC-0006*0 l 06*087 Page 1 of3
GEHitachi Nuclear Energy Americas LLC and is in fact so held. The i nfonnation sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GEH, not been disclosed publicly, and not been made available in public sources. All disclosures to third parties, inc lud ing any required transmittals to the NRC, have been made, or must be mad e , pursuant to regulatory provisio ns or pr oprietary or conf dentiality agreements that provide for i
maintain i ng the information in confidence. The initial designation of this i n formation as proprietary information; and the subsequent steps taken to prevent its unauthorized di sclosure , are as set forth in the following paragraphs (6) and (7).
(6) Initial approval of proprietary treatment of a document is made by the manager of the origi nating component; who is the person most likely to be acquainted with the value and sensitivity of the in ormation in relation to industry knowledge, or who is the person most f
likely to be subject to the terms under which it was licensed to GEH.
(7) The pro cedure for approval of exte m al release of such a document typically requires r eview by the staff manager, project manager, principal scientist, or other equivalent author ity for technical content, competitive effect, a nd determination of the accuracy of the proprietary desi gnation . Disclosures out side GEH are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the i nfo rmation, and then only in accordance with appropriate regulatory provisions or proprietary or confidentiality agreements.
(8) The information ident ifi ed in paragtaph (2), above, is cl assi fied as proprietary because it contains de tai led GEH m e thodo l ogy for thennal power optimizati on for GEH Boiling Water Reactors (BWRs). Development of these methods, techn iques , and information and their application for the design, modification, and ana lyses methodologies and processes was achieved at a s i gnifi can t cost to GEH.
The de velopment of the evaluation processes along with the interpretation and application of the analytical resul ts is derived from the extensive experie nce and information databases that constitute a major GEH asset.
(9) Public disclosure of the information soug ht to be withheld is likely to cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit making opportunities . The information is part of GErJis comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.
The value of the technology base goes beyond the ext ensi ve physical database and analytical m ethodology and i ncludes development of the expertise to determine and apply the appropriate evaluation process. In add itionj the technology base includes the value derived from providing analyses done with NRC-approved methods .
The research development, engineerin g, analyti cal and NRC review costs comprise a s ubstantial investment of time and money by GEH. The precise value of the expertise to devise an evaluation process and apply the correct analyt ical methodology is difficult to quantify, but it cl early is substantial. GEH's compet itive advantage will be lost if its competit ors are able to use the res ults of the GEH experience to nonnalize or verifY their Affidavit for DOC0006-0l06*087 Page2 of3
GEHitacbi Nuclear Energy Americas LLC own process or if they are able to clai m an equivalent understanding by demonstrating th at they can arrive at the same or similar conclusions.
The value of this information to GEH would be lost if the information were disclose d to the public. Making such information available to competitors without th eir having been require d to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and dep rive GEH of the opportunity to exercise its com petitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
1 declare under penalty of perjury that the foregoing is true and correct.
Executed on this 6th day of De c embe r 2017.
Lisa K. Schichlein Senior Project Manager, NPP/Services Licensing Regula tory Aff airs GE-Hitachi Nuclear Energy Ame ricas LLC 3901 C astle Hayne Road Wilmington, NC 28401 Lisa. Schichlein@ge.com Affldavit for DOC00060 1 06*087 Page 3 of3