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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
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 SEP 0 8 2003 O PSEG Nuclear LLC LR-N03-0386 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 SVEA-96+ MODELING DIMENSIONS HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354
Reference:
GNF-A Proprietary Report, NEDC-33107P, "GEXL80 Correlation for SVEA96+ Fuel," dated September 2003 PSEG Nuclear LLC (PSEG) is providing the attached information in support of the NRC's review of the Reference submittal. The information relates to SVEA-96+
modeling dimensions and was used by Global Nuclear Fuel - Americas (GNF-A) in developing the GEXL80 correlation for the Westinghouse SVEA96+ fuel design. contains information which Westinghouse Electric Company LLC (Westinghouse) considers to be proprietary. Westinghouse requests that the proprietary information in Attachment 1 be withheld from public disclosure in accordance with 10 CFR 2.790. An affidavit in support of this request is provided in . A non-proprietary version of Attachment 1 is provided in Attachment 3.
Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse Affidavit should reference CAW-03-1698 and should be addressed to H. A. Sepp, Manager of Regulatory Compliance and Plant Licensing, Westinghouse Electric Company, P.O. Box 355, Pittsburgh, PA 15230-0355.
Should you have any questions regarding this matter, please contact Mr. Paul Duke at 856-339-1466.
Sincerely, S Con M anamon a c Manager - Nuclea Cafety and Licensing Attachments (3)
- -ro 2 This letter forwards proprietary information in accordance with 10CFR 2.790. The balance of this letter may be considered non-proprietary upon removal of Attachment 1.
95-2168 REV. 7/99
Document Control Desk SEP 0 8 2003 LR-N03-0386 C Mr. H. J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission ATTN: Mr. R. Ennis, Licensing Project Manager - Hope Creek Mail Stop 08B3 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Hope Creek (X24)
Mr. K. Tosch, Manager IV (without Attachment 1)
Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625 H. A. Sepp, Manager of Regulatory Compliance and Plant Licensing Westinghouse Electric Company P.O. Box 355 Pittsburgh, PA 15230-0355.
This letter forwards proprietaryinformation In accordancewith 10CFR 2.790. The balance of this letter may be considered non-proprietaryupon removal of Attachment 1.
Document Control Desk LR-N03-0386 Attachment I Table 2-3 of GEXL80 Correlation for SVEA96+ Fuel (proprietary version)
PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in connection with requests for generic and/or plant-specific review and approval.
In order to conform to the requirements of 10 CFR 2.790 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying this transmittal pursuant to 10 CFR 2.790(b)(1).
COPYRIGHT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.
Document Control Desk LR-N03-0386 Request for Withholding Attachment I from Public Disclosure
Westinghouse Westinghouse Electric Company Nuclear Services P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA U.S. Nuclear Regulatory Commission Direct tel: (412) 374-5282 Document Control Desk Direct fax: (412) 374-4011 Washington, DC 20555-0001 e-mail: fasnacjw@westinghouse.com Our ref: CAW-03-1698 September 8, 2003 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
Letter LR-N03-0386, G. Salamon to NRC Document Control Desk, "SVEA-96+ MODELING DIMENSIONS, HOPE CREEK GENERATING STATION, FACILITY OPERATING LICENSE NPF-57, DOCKET NO. 50-354," dated September 8, 2003 (Proprietary) and Letter LR-N03-0388, G. Salamon to NRC Document Control Desk, "GE 14 and SVEA-96+ THERMAL-HYDRAULIC COMPATIBILITY REPORT, HOPE CREEK GENERATING STATION, FACILITY OPERATING LICENSE NPF-57, DOCKET NO. 50-354," dated September 8, 2003 (Proprietary)
The proprietary information for which withholding is being requested in the above-referenced report is further identified in Affidavit CAW-03-1698 signed by the owner of the proprietary information, Westinghouse Electric Company LLC. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.790 of the Commission's regulations.
Accordingly, this letter authorizes the utilization of the accompanying affidavit by PSEG Nuclear, LLC Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-03-1698 and should be addressed to the undersigned.
Very truly yours, lJWt Fasnacht, Manager Programs Group Enclosures cc: J. Dyer D. Holland B. Benney E. Peyton A BNFL Group company
CAW 1698 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
ss COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared J. W. Fasnacht, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Company LLC ("Westinghouse"), and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:
r6wctl r Fasnacht, Manager Major Programs Group Sworn to and subscribed before me this day of, 2003 Notary Public
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2 CAW 1698 (1) I am Manager, Major Programs Group, in Nuclear Services, Westinghouse Electric Company LLC ("Westinghouse"), and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rule making proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Electric Company LLC.
(2) 1 am making this Affidavit in conformance with the provisions of 10 CFR Section 2.790 of the Commission's regulations and in conjunction with the Westinghouse application for withholding accompanying this Affidavit.
(3) 1 have personal knowledge of the criteria and procedures utilized by the Westinghouse Electric Company LLC in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.
(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of
3 CAW 1698 Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
(c) Its use 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 a similar product.
(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable.
There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
(b) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.
(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
4 CAW 1698 (d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.
(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.
(iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.790, it is to be received in confidence by the Commission.
(iv) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.
(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in "Table 2.3 of GEXL80 Correlation for SVEA-96+ Fuel" and input to the "Thermal Hydraulic Compatibility Report" (Proprietary), for PSEG Nuclear LLC, being transmitted by the PSEG Nuclear LLC letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted for use by Westinghouse Electric Company LLC for Hope Creek is expected to be applicable for other licensee submittals in response to certain NRC requirements for justification of GE 14 fuel transition This information is part of that which will enable Westinghouse to:
(a) Determine the correlation for SVEA-96+ fuel.
5 CAW 1698 (b) Determine Thermal Hydraulic Compatibility.
Further this information has substantial commercial value as follows:
(a) Westinghouse plans to sell the use of similar information to its customers for purposes of using SVEA-96+ fuel.
(b) Westinghouse can sell support and defense of licensing support.
(c) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar calculations and data and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.
In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.
Further the deponent sayeth not.
Document Control Desk LR-N03-0386 Table 2-3 of GEXL80 Correlation for SVEA96+ Fuel (non-proprietary version)
PROPRIETARY INFORMATION NOTICE Transmritted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in connection with requests for generic and/or plant-specific review and approval.
In order to conform to the requirements of 10 CFR 2.790 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying this transmittal pursuant to 10 CFR 2.790(b)(1).
COPYRIGHT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.
Document Control Desk LR-N03-0386 Westinghouse Non-Proprietary Class 3 Table 2-3. SVEA96+ Modeling Dimensions Characteristic Assembly Nominal Inside Width of Channel 1 11JSC Inside Corner Radius of Channel 11ast Rod Pitch1 ac Diameter of Heated Rods 1[ fla,c