Letter Sequence Supplement |
---|
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] Category:Technical Specifications
MONTHYEARML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location ML21050A0022021-03-12012 March 2021 Issuance of Amendment No. 227 Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, RPV WIC Enhancements ML21047A3132021-03-10010 March 2021 Issuance of Amendment No. 226 Revise Emergency Core Cooling System Technical Specification for High Pressure Coolant Injection System Inoperability (Non-Proprietary) ML20281A6132020-11-0909 November 2020 Issuance of Amendment No. 225 Revise Technical Specification Actions for Suppression Pool Cooling ML20231A6322020-09-29029 September 2020 Issuance of Amendment No. 224 Regarding Adoption of 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components of Nuclear Power Reactors ML20034E6172020-02-27027 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 222, 333, and 314 Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer ML19186A2052019-08-0606 August 2019 Issuance of Amendment No. 217 Remote Shutdown System ML19065A1562019-03-27027 March 2019 Issuance of Amendment No. 215 Inverter Allowed Outage Time Extension ML17317A6052017-12-13013 December 2017 Issuance of Amendment, License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-535 ML17047A0202017-03-21021 March 2017 Issuance of Amendment to Delete Technical Specification Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves ML17053A1782017-03-15015 March 2017 Issuance of Amendment to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling ML16270A0382016-10-13013 October 2016 Issuance of Amendment No. 200 Safety Limit Minimum Critical Power Ratio Change ML15286A0912015-11-30030 November 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Traveler-522 ML15141A2712015-06-17017 June 2015 and Salem Nuclear Generating Station, Unit Nos.1 and 2, Issuance of Amendments Update of Appendix B to the Renewed Facility Operating Licenses ML14108A3992014-12-18018 December 2014 Issuance of Amendment Request to Relocate Flood Protection Technical Specification to the Technical Requirements Manual LR-N14-0189, License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process2014-11-25025 November 2014 License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process ML14108A3122014-07-29029 July 2014 Issuance of Amendment Request to Relocate Safety Relief Valve Position Instrumentation to Technical Requirements Manual LR-N13-0155, License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual2013-09-0505 September 2013 License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual LR-N13-0143, License Amendment Request to Relocate Safety/Relief Valve Position Instrumentation to the Technical Requirements Manual2013-07-30030 July 2013 License Amendment Request to Relocate Safety/Relief Valve Position Instrumentation to the Technical Requirements Manual LR-N12-0067, License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items2012-03-0101 March 2012 License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items LR-N12-0028, Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process2012-01-26026 January 2012 Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process ML0527202982011-07-20020 July 2011 Current Facility Operating License NPF-57, Tech Specs, Revised 12/18/2017 ML11116A1482011-07-20020 July 2011 Issuance of Renewed Facility Operating License No. NPF-57 for Hope Creek Generating Station LR-N11-0208, Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal2011-07-0606 July 2011 Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal ML1109801512011-04-19019 April 2011 Correction to Amendment No. 187 Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program Based on Technical Specification Task Force (TSTF) Change TSTF-425 LR-N11-0098, Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 1872011-04-0404 April 2011 Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 187 LR-N11-0068, Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process2011-02-28028 February 2011 Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process LR-N10-0310, Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times.2010-08-19019 August 2010 Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times. ML1015907132010-07-21021 July 2010 Issuance of Amendment Control Rod Notch Testing Frequency LR-N10-0097, License Amendment Request: Emergency Diesel Generators a and B Allowed Outage Time Extension2010-03-29029 March 2010 License Amendment Request: Emergency Diesel Generators a and B Allowed Outage Time Extension LR-N10-0015, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2010-03-19019 March 2010 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML0932700232009-12-0808 December 2009 Issuance of Amendment Mode Change Limitations ML0934302422009-12-0101 December 2009 License Amendment Request to Adopt TSTF-460, Revision 0, Control Rod Scram Times. ML0916006832009-07-15015 July 2009 Issuance of Amendment Technical Specification Requirements Related to Snubbers LR-N09-0001, License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications2009-01-0505 January 2009 License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications LR-N08-0150, Relief Request for Third Interval Inservice Inspection Program for Examinations and Tests of Snubbers and Associated License Amendment Request2008-07-30030 July 2008 Relief Request for Third Interval Inservice Inspection Program for Examinations and Tests of Snubbers and Associated License Amendment Request LR-N08-0071, License Amendment Request - Hydrogen Water Chemistry Low Power Restriction2008-04-25025 April 2008 License Amendment Request - Hydrogen Water Chemistry Low Power Restriction ML0734500402008-01-24024 January 2008 Tech Spec Pages for Amendment 173 Control Room Habitability LR-N08-0003, Supplement to License Amendment Request for Extended Power Uprate2008-01-16016 January 2008 Supplement to License Amendment Request for Extended Power Uprate ML0728500372007-10-16016 October 2007 Technical Specifications, Issuance of Amendment Removal of Turbine First Stage Pressure Values from Technical Specifications ML0724003042007-08-27027 August 2007 Tech Spec Pages for Amendment 171 Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications 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 ML0724805722007-06-15015 June 2007 Gnf S-0000-0068-2643, Gnf Additional Information Regarding the Requested Changes to the Technical Specification Slmcpr. Hope Creek (KT1) Cycle 15 LR-N07-0061, Application to Revise Technical Specifications (LCR H07-01) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-17017 April 2007 Application to Revise Technical Specifications (LCR H07-01) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0630704822006-10-31031 October 2006 Tech Spec Pages for Amendment 170 Regarding Clarification of Requirements During Handling of Irradiated Fuel Core Alterations, and Operations with the Potential for Draining the Reactor Vessel ML0624101882006-08-28028 August 2006 Technical Specifications - Fuel Storage and Handling ML0621403972006-08-0101 August 2006 Technical Specifications, Issuance of Amendment Ultimate Heat Sink, MC8054 LR-N06-0259, Supplement to Request for License Amendment Ultimate Heat Sink2006-07-18018 July 2006 Supplement to Request for License Amendment Ultimate Heat Sink ML0610105472006-04-10010 April 2006 Technical Specifications Pages Re Relocation of the Component Identification from the Overcurrent Protective Device Lists in TS 3/4.8.4.1, Primary Containment Penetration Conductor Overcurrent Protective Devices, and TS 3/4.8.4.5 2024-01-16
[Table view] |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 OPSEG NuVclear LLC 10 CFR 50.90 LR-N07-0215 LCR H05-01, Rev. 1 August 27, 2007 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:
Supplement to License Amendment Request for Extended Power Uprate
Reference:
- 1) Letter from George P. Barnes (PSEG Nuclear LLC) to USNRC, September 18, 2006
- 2) Letter from George P. Barnes (PSEG Nuclear LLC) to USNRC, May 10, 2007 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). Reference 1 stated that PSEG intends to implement the provisions of General Electric Company (GE) Licensing Topical Report NEDC-33173P, "Applicability of GE Methods to Expanded Operating Domains," as part of implementation of extended power uprate (EPU) at HCGS.
In Reference 2, PSEG addressed implementation of draft limitations and conditions for NEDC-33173P. Reference 2 stated that HCGS would comply with the condition requiring an adder to the cycle-specific safety limit minimum critical power ratio (SLMCPR) value for EPU operation. to this letter contains a marked up Technical Specification page incorporating the SLMCPR adder. The markup in Attachment 1 replaces the markup of the same page provided in the Reference 1 submittal. Attachment 2 provides additional information regarding the SLMCPR for EPU operation during HCGS Cycle 15. contains information proprietary to Global Nuclear Fuel (GNF). GNF 51ED7 7/99 REV.
95-2168
LR-N07-0215 LCR H05-01, Rev. 1 AUG 2 7 2007 Page 2 requests that the document be withheld from public disclosure in accordance with 10 CFR 2.390(a)(4). An affidavit supporting this request is also contained in Attachment 2. Attachment 3 contains a non-proprietary version of the GNF document.
There are no regulatory commitments contained in this letter.
PSEG has determined that the information contained in this letter and attachments does not alter the conclusions reached in the 10CFR50.92 no significant hazards analysis previously submitted.
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 /12717/O7 (date)
Sincerely, George P. Barnes Site Vice President Hope Creek Generating Station Attachments (3)
- 1. Replacement Markup of Proposed Technical Specification Page Changes
- 2. GNF Hope Creek C15 SLMCPR - Proprietary Letter
- 3. GNF Hope Creek C15 SLMCPR - Non-Proprietary Letter cc: S. Collins, Regional Administrator - NRC Region I J. Lamb, Project Manager - Hope Creek, USNRC NRC Senior Resident Inspector - Hope Creek P. Mulligan, Manager IV, NJBNE
ATTACHMENT I Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354 Extended Power Uprate Replacement Markup of Proposed Technical Specification Page Changes TS Page 2-1
2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS THERMAL POWER, Low Pressure or Low Flow 2- "i 2.1.1 THERMAL POWER shall not exceedý of RATED THERMAL POWER with the reactor vessel steam dome pressure less than 785 psig or core flow less than 10% of rated flow.
APPLICABILITY: OPERATIONAL CONDITIONS I and 2.
ACTION:
With THERMAL POWER exceeding RATED THERMAL POWER and the reactor vessel steam dome pressure less than785 psig or core flow less than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with the requirements of Specification 6.7.1.
THERMAL POWER, High Pressure and High Flow 2.1.2 With reactor steam dome pressure greater than 785 psig and core flow greater than 10% of rated flow: 0 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be ŽQ or two recirculation loop operation and shall be Ž:I for single recirculation loop operation.
APPLICABILITY: OPERATIONAL COIITIONS 1 and 2.
ACTION: . 1-0 With reactor steam dome pressure greater than 785 psig and core flow greater than 10% of rated flow and the MCPR below the values for the fuel stated in LCO 2.1.2, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> andcomply with the requirements of Specification 6.7.1.
REACTOR COOLANT SYSTEM PRESSURE 2.1.3 The reactor coolant system pressure, as measured in the reactor vessel steam dome, shall not exceed 1325 psig.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3 and 4.
ACTION:
With the reactor coolant system pressure, as measured in the reactor vessel steam dome, above 1325 psig, be in at least HOT SHUTDOWN with reactor coolant system pressure less than or equal to 1325 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with the requirements of Specification 6.7.1.
HOPE CREEK 2--1 Aiencdment No. 158
Affidavit Affidavit I, Jens G. M. Andersen, state as follows:
(1) I am Consulting Engineer, Thermal Hydraulic Methods, Global Nuclear Fuel -
Americas, L.L.C. ("GNF-A") and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in the attachment, "GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Hope Creek (KT1) Cycle 15," dated June 15, 2007.
GNF proprietary information is indicated by enclosing it in double brackets. In each case, the superscript notation (3) 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 licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4) and 2.390(a)(4) for "trade secrets and commercial or financial information obtained from a person and privileged or confidential" (Exemption 4). The material for which exemption from disclosure is here sought is all "confidential commercial information," and some portions also qualify 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 Project v. Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2dl280 (DC Cir. 1983).
(4) Some examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic 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 reveals cost or price information, production capacities, budget levels, or commercial strategies of GNF-A, its customers, or its suppliers;
- d. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, of potential commercial value to GNF-A;
- e. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
Affidavit The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b., above.
(5) To address the 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in (6) and (7) following. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A. Access to such documents within GNF-A is limited on a "need to know" basis.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology.
The development of the methods used in these analyses, along with the testing, development and approval of the supporting methodology was achieved at a significant cost, on the order of several million dollars, to GNF-A or its licensor.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The fuel design and licensing methodology is part of GNF-A's 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 extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A or its licensor.
Affidavit The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.
Executed at Wilmington, North Carolina, this 15th day of June, 2007.
S647 Jens G. M. Andersen Global Nuclear Fuel - Americas, LLC