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Category:Legal-Affidavit
MONTHYEARL-2021-129, Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses2021-07-0808 July 2021 Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses ML20329A2192020-11-16016 November 2020 Enclosure 2, Affidavits Supporting Withholding Proprietary Information from Public Disclosure Pursuant to 10 CFR 2.390 NRC 2019-0026, Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure2019-08-29029 August 2019 Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure NRC 2016-0040, Registration of NUHOMS-32PT Casks WNHOMS-32-041 and WNHOMS-32-0432016-08-30030 August 2016 Registration of NUHOMS-32PT Casks WNHOMS-32-041 and WNHOMS-32-043 NRC 2015-0068, Request for Additional Information for Relief Request 2-RR-11 - MF66152015-11-19019 November 2015 Request for Additional Information for Relief Request 2-RR-11 - MF6615 ML0600400192005-12-14014 December 2005 Westinghouse LTR-RCDA-873-NP Attachment Point Beach, Unit 1 - Reactor Vessel Upper Closure Head Volume Best-Estimate Mean Fluid Temperature (Non-Proprietary) NRC 2005-0094, Request for Review of Heavy Load Analysis2005-07-24024 July 2005 Request for Review of Heavy Load Analysis NRC 2005-0072, to Request for Exigent Review of Heavy Load Analysis and Response to Request for Additional Information2005-06-0909 June 2005 to Request for Exigent Review of Heavy Load Analysis and Response to Request for Additional Information NRC 2004-0059, Supplement 4 to Reactor Vessel Closure Head Penetration Repair and Flaw Characterization Relief Requests MR 02-018-1, Revision 1 and MR 02-018-2, Revision 12004-05-25025 May 2004 Supplement 4 to Reactor Vessel Closure Head Penetration Repair and Flaw Characterization Relief Requests MR 02-018-1, Revision 1 and MR 02-018-2, Revision 1 ML0413101222004-04-30030 April 2004 Request for Closed Meeting with USNRC to Discuss NMC Refueling Plans ML0627904482002-08-0505 August 2002 Letter from Stellpflug, Janssen, Hammer Kirschling and Bartels Regarding Meeting to Address the Inability to Work at the Nuclear Power Plant 2021-07-08
[Table view] Category:Report
MONTHYEARL-2023-089, Refueling Outage Owners Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owners Activity Report (OAR-1) Unit 2 for Inservice Inspections L-2023-028, And Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 And Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2022-168, And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2020-159, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2022-10-0404 October 2022 10 CFR 50.59 Evaluation and Commitment Change Summary Report L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-022022-07-29029 July 2022 Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 ML22140A1352022-05-20020 May 2022 RPS Instrumentation ML22140A1442022-05-20020 May 2022 Enclosure 8 - Attributes of the Configuration Risk Management Model NRC 2022-0007, Enclosure 11 - Monitoring Program2022-05-20020 May 2022 Enclosure 11 - Monitoring Program ML22140A1332022-05-20020 May 2022 Attachment 1 - Evaluation of the Proposed Changes ML22140A1432022-05-20020 May 2022 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by PRA Models ML22140A1422022-05-20020 May 2022 Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions and Additional Supporting Information ML22140A1362022-05-20020 May 2022 Containment Isolation Valves ML22140A1382022-05-20020 May 2022 Containment Isolation Valves ML22140A1412022-05-20020 May 2022 Attachment 6 - Point Beach RICT Program Pre-Implementation Items ML22140A1402022-05-20020 May 2022 Attachment 5 - Evaluation of Plant-Specific Variations ML22140A1392022-05-20020 May 2022 Attachment 4 - Cross-Reference of TSTF-505, Revision 2, and Point Beach Proposed Changes ML21214A0432021-08-0202 August 2021 SLRA June 30, 2021, Public Meeting Discussion Questions ML21126A2392021-05-0606 May 2021 Subsequent License Renewal Application, Aging Management Supplement 2 ML21040A4842021-02-0909 February 2021 Fws to NRC, Point Beach Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location And/Or May Be Affected by Your Project ML21040A4852021-02-0909 February 2021 Fws to NRC, Verification Letter for Point Beach SLR Under Programmatic Biological Opinion for Northern Long-eared Bat NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report ML21008A0172020-10-25025 October 2020 Revised ANS Design Report NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0026, Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure2019-08-29029 August 2019 Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-08-0606 August 2019 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds NRC 2019-0002, Refueling Outage U2R36 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2019-01-24024 January 2019 Refueling Outage U2R36 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2018-0017, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2018-05-0202 May 2018 10 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2017-0045, Updated Final Response to NRC Generic Letter 2004-022017-12-29029 December 2017 Updated Final Response to NRC Generic Letter 2004-02 NRC 2017-0037, High Frequency Seismic Evaluation Confirmation Report2017-08-0202 August 2017 High Frequency Seismic Evaluation Confirmation Report NRC 2017-0032, Focused Evaluation for Local Intense Precipitation2017-06-22022 June 2017 Focused Evaluation for Local Intense Precipitation ML17136A3222017-05-19019 May 2017 Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood-Causing Mechanism Reevaluation L-2017-014, Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 20162017-04-17017 April 2017 Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 2016 ML17018A2712017-02-0909 February 2017 Flood Hazard Mitigation Strategies Assessment NRC 2016-0041, Submittal of 10 CFR 50.59 Summary Report for 20152016-08-31031 August 2016 Submittal of 10 CFR 50.59 Summary Report for 2015 NRC 2015-0072, Notification of Full Compliance with Order EA-12-049, Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events and Submittal of Final Integrated Plan2015-12-16016 December 2015 Notification of Full Compliance with Order EA-12-049, Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events and Submittal of Final Integrated Plan ML15300A1402015-11-0303 November 2015 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15211A5932015-08-0303 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force NRC 2015-0043, Spent Fuel Storage Five-Year Inspection Report Ventilated Spent Fuel Storage Cask WVSC-24-01 Certificate of Compliance 10072015-07-20020 July 2015 Spent Fuel Storage Five-Year Inspection Report Ventilated Spent Fuel Storage Cask WVSC-24-01 Certificate of Compliance 1007 NRC 2014-0041, 10 CFR 50.59 Summary Report for 20132014-08-27027 August 2014 10 CFR 50.59 Summary Report for 2013 ML14147A0342014-06-0606 June 2014 Review of the 2013 Steam Generator Tube Inspections NRC 2014-0024, NextEra Energy Point Beach, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the F2014-03-31031 March 2014 NextEra Energy Point Beach, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukush ML13338A5102014-01-27027 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML14006A1872014-01-10010 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Point Beach Station, Units 1 and 2, TAC Nos.: MF0725 and MF0726 NRC 2013-0069, Supporting Documentation for July 22, 2013, Regulatory Conference to Discuss Inspection Report 05000266/2013011 and 05000301/2013011, Preliminary Yellow Finding2013-07-15015 July 2013 Supporting Documentation for July 22, 2013, Regulatory Conference to Discuss Inspection Report 05000266/2013011 and 05000301/2013011, Preliminary Yellow Finding ML13193A0322013-07-11011 July 2013 Additional Equipment Height Information with Vulnerability to Flood Waters NRC 2013-0057, Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R342013-07-0303 July 2013 Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R34 NRC 2013-0061, CFR 50.59 Summary Report for 20122013-06-28028 June 2013 CFR 50.59 Summary Report for 2012 NRC 2012-0101, NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic2012-11-26026 November 2012 NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic NRC 2011-0059, 10 CFR 50.59 Summary Report for 20102011-07-0101 July 2011 10 CFR 50.59 Summary Report for 2010 2023-07-24
[Table view] Category:Technical
MONTHYEARL-2022-168, And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2020-159, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2022-10-0404 October 2022 10 CFR 50.59 Evaluation and Commitment Change Summary Report L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-022022-07-29029 July 2022 Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 ML22140A1432022-05-20020 May 2022 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by PRA Models ML22140A1422022-05-20020 May 2022 Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions and Additional Supporting Information ML22140A1412022-05-20020 May 2022 Attachment 6 - Point Beach RICT Program Pre-Implementation Items ML22140A1352022-05-20020 May 2022 RPS Instrumentation ML22140A1382022-05-20020 May 2022 Containment Isolation Valves ML22140A1332022-05-20020 May 2022 Attachment 1 - Evaluation of the Proposed Changes NRC 2022-0007, Enclosure 11 - Monitoring Program2022-05-20020 May 2022 Enclosure 11 - Monitoring Program ML22140A1442022-05-20020 May 2022 Enclosure 8 - Attributes of the Configuration Risk Management Model ML22140A1362022-05-20020 May 2022 Containment Isolation Valves ML22140A1392022-05-20020 May 2022 Attachment 4 - Cross-Reference of TSTF-505, Revision 2, and Point Beach Proposed Changes ML22140A1402022-05-20020 May 2022 Attachment 5 - Evaluation of Plant-Specific Variations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report ML21008A0172020-10-25025 October 2020 Revised ANS Design Report NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0026, Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure2019-08-29029 August 2019 Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds NRC 2018-0017, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2018-05-0202 May 2018 10 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2017-0037, High Frequency Seismic Evaluation Confirmation Report2017-08-0202 August 2017 High Frequency Seismic Evaluation Confirmation Report NRC 2017-0032, Focused Evaluation for Local Intense Precipitation2017-06-22022 June 2017 Focused Evaluation for Local Intense Precipitation ML13338A5102014-01-27027 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML14006A1872014-01-10010 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Point Beach Station, Units 1 and 2, TAC Nos.: MF0725 and MF0726 ML13193A0322013-07-11011 July 2013 Additional Equipment Height Information with Vulnerability to Flood Waters NRC 2013-0057, Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R342013-07-0303 July 2013 Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R34 NRC 2012-0101, NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic2012-11-26026 November 2012 NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic ML14006A3192010-03-31031 March 2010 LTR-PAFM-10-50-NP, Rev. 0, Section XI Flaw Evaluation of Indication Recorded on RC-32-MRCL-ALL-03 of the Point Beach Unit 1 Inlet Nozzle to Pipe Weld. NRC 2010-0012, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation2010-03-0303 March 2010 License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation ML0935704152009-12-31031 December 2009 WEP-09-133 Np, Point Beach Unit 1 & Unit 2 (Wep/Wis) Extended Power Uprate License Amendment Request Responses to Request for Additional Information. ML0912505662009-04-0707 April 2009 Attachment 5 - Point Beach, Units 1 and 2, License Amendment Request 261, Extended Power Uprate, Licensing Report, Introduction Through Chapter 2, Section 2.5.7 ML0912505692009-04-0707 April 2009 Attachment 5 - Point Beach, Units 1 and 2, License Amendment Request 261, Extended Power Uprate, Licensing Report, Chapter 2, Section 2.5.8 Through Appendices ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0822406862008-06-30030 June 2008 WCAP-16541-NP, Revision 2, Spent Fuel Pool Criticality Safety Analysis. NRC 2008-0029, Pressure and Temperature Limits Report2008-05-30030 May 2008 Pressure and Temperature Limits Report NRC 2008-0034, License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair2008-05-28028 May 2008 License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair NRC 2007-0049, Supplement to License Amendment Request 251; Technical Specification 5.6.5., Reactor Coolant System Pressure and Temperature Limits Report2007-06-13013 June 2007 Supplement to License Amendment Request 251; Technical Specification 5.6.5., Reactor Coolant System Pressure and Temperature Limits Report NRC 2006-0061, LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program2006-07-11011 July 2006 LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program NRC 2006-0054, Public Version, Request for Review of Reactor Vessel Toughness Fracture Mechanics Analysis2006-06-0606 June 2006 Public Version, Request for Review of Reactor Vessel Toughness Fracture Mechanics Analysis ML0600400192005-12-14014 December 2005 Westinghouse LTR-RCDA-873-NP Attachment Point Beach, Unit 1 - Reactor Vessel Upper Closure Head Volume Best-Estimate Mean Fluid Temperature (Non-Proprietary) ML0533203122005-11-18018 November 2005 Reactor Vessel CMTRs (Non-Proprietary) NRC 2005-0117, Request for Withholding of Proprietary Information from Public Disclosure2005-09-0707 September 2005 Request for Withholding of Proprietary Information from Public Disclosure NRC 2005-0068, Submittal of Supporting Analyses Regarding Control of Heavy Loads2005-06-0303 June 2005 Submittal of Supporting Analyses Regarding Control of Heavy Loads ML0435700172004-12-14014 December 2004 from NMC Re Technical Evaluation of Proposed Method of Class 3 Pipe Leak Operability Determinations ML0514002682004-10-0808 October 2004 Enclosures V & VI Point Beach Revised EAL Submittal, Justification Matrix Reference Material NRC 2004-0004, Fitness-For-Duty (FFD) Program for Six Month Period Ending June 30, 20042004-08-30030 August 2004 Fitness-For-Duty (FFD) Program for Six Month Period Ending June 30, 2004 NRC 2004-0081, Transmittal of Point Beach Nuclear Plant, Units 1 and 2, Excellence Plan - Revision 42004-08-13013 August 2004 Transmittal of Point Beach Nuclear Plant, Units 1 and 2, Excellence Plan - Revision 4 ML0426603132004-07-31031 July 2004 BAW-2467NP, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessel of Point Beach Units I and 2 for Extended Life Through 53 Effective Full Power Years. ML0508800622004-05-0707 May 2004 Licensee Procedure, HPIP 4.58, Issuance of Respiratory Equipment Revision 14 ML0508800432004-04-30030 April 2004 NMC Incident Response Team for Issues Encountered During Unit 1 Reduced Inventory and Nozzle Dam Installation at Pbnp 2022-07-29
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ENCLOSURE I WESTINGHOUSE LTR-RCDA-873-NP ATTACHMENT POINT BEACH UNIT I REACTOR VESSEL UPPER CLOSURE HEAD VOLUME BEST-ESTIMATE MEAN FLUID TEMPERATURE (NON-PROPRIETARY)
WESTINGHOUSE AFFIDAVIT (8 pages follow)
WESTINGHOUSE NON-PROPRIETARY CLASS 3 LTR-RCDA-873-NP Attachment Point Beach Unit 1 - Reactor Vessel Upper Closure Head Volume Best-Estimate Mean Fluid Temperature December 14, 2005 Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355 C)2005 Westinghouse Electric Company LLC All Rights Reserved LTR-RCDA-873-NP Attachment
WESTINGHOUSE NON-PROPRIETARY CLASS 3
Reference:
- 1. Westinghouse Letter WEP-60-168, Rev. 1-NP, "Point Beach Unit 1, Cycle 29- Reactor Vessel Upper Closure Head Volume Best-Estimate Mean Fluid Temperature," June 20, 2005 Reference 1 provided the Point Beach Unit 1 best-estimate mean fluid temperature of the reactor vessel upper closure head volume based on the actual operating conditions and the cycle 29 core assemblywise power distributions. The averaged temperature over the cycle was calculated to be 593.90 F . This temperature is not an estimated temperature like the 5980 F temperature in reference 1. The 5980 F temperature was an estimated value and took into account the effects of a low-leakage core loading pattern with hafnium absorbers, the 1.7% mini power uprate, and the effect of utilizing the best-estimate flow. These effects were added to an initial mean fluid temperature of the reactor vessel upper closure head volume to obtain the 598 0 F temperature.
The estimated effects to the reactor vessel upper closure head volume, due to the low-leakage core loading pattern with hafnium absorbers, the 1.7% mini power uprate, and the effect of utilizing the best-estimate flow are classified as Westinghouse proprietary data. These effects on the mean fluid temperature of the reactor vessel upper closure head volume have been calculated using the methodology developed by Westinghouse. A third party could easily determine the total effect of the low-leakage core loading pattern with hafnium absorbers, the 1.7% mini power uprate, and the effect of utilizing the best-estimate flow given the initial mean fluid temperature of the reactor vessel upper closure head volume.
Therefore, the initial mean fluid temperature of the reactor vessel upper closure head volume before the effects were added was also classified as Westinghouse proprietary data.
The initial mean fluid temperature of the reactor vessel upper closure head volume used in the estimation of the 5980F temperature and the cycle 29 specific mean fluid temperature of the reactor vessel upper closure head volume are based on different plant operating conditions and any similarities between the two temperatures is purely a coincidence.
LTR-RCDA-873-NP Attachment
Westinghouse Westinghouse Electric Company Nuclear Services P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA U.S. Nuclear Regulatory Commission Direct tel: (412) 374-4643 Document Control Desk Directfax: (412) 374-4011 Washington, DC 20555-0001 e-mail: greshajaewestinghouse.com Our ref. CAW-05-2087 December 16, 2005 AFFIDAVIT FOR NON-PROPRIETARY INFORMATION
Subject:
LTR-RCDA-873-NP Attachment, "Point Beach Unit I - Reactor Vessel Upper Closure Head Volume Best-Estimate Mean Fluid Temperature," dated December 14, 2005 (Non-Proprietary)
The non-proprietary information in the above-referenced report is identified in Affidavit CAW-05-2087 signed by the owner of the non-proprietary information, Westinghouse Electric Company LLC.
Accordingly, this letter authorizes the utilization of the accompanying affidavit by Nuclear Management Company.
Correspondence with respect to the non-proprietary aspects of the Westinghouse affidavit should reference this letter, CAW-05-2087, and should be addressed to J. A. Gresham, Manager, Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.
Very truly yours, J'. A. Gresham, Manager Regulatory Compliance and Plant Licensing Enclosures cc: B. Benney L. Feizollahi A BNFL Group company
CAW-05-2087 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
Ss COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared J. A. Gresham, 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:
A. Gresham, Manager Regulatory Compliance and Plant Licensing Sworn to and subscribed before me this Zg At day of Z 2005 Notary Public Notaft Seal Shamvn L. Fodx, NOaMy P&Lc-M=Mvoeile Boo, AiOeghw County My Comxnssisn Expies Janualy 29,2007 Member, Pemrsymania Assocaton O( Nanes
2 CAW-05-2087 (1) I am Manager, Regulatory Compliance and Plant Licensing, in Nuclear Services, Westinghouse Electric Company LLC (Westinghouse), and as such, I have been specifically delegated the function of reviewing the non-proprietary information in connection with nuclear power plant licensing and rule making proceedings.
(2) 1am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 of the Commission's regulations.
(3) 1have personal knowledge of the criteria and procedures utilized by Westinghouse 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 2.390 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 Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
3 CAW-05-2087 (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.
(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.
4 CAW-05-2087 (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 2.390, 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 non-proprietary information in this submittal is that which is appropriately marked in LTR-RCDA-873-NP Attachment, "Point Beach Unit I - Reactor Vessel Upper Closure Head Volume Best-Estimate Mean Fluid Temperature" (Non-proprietary), dated December 14, 2005. The information is provided in support of a submittal to the Commission, being transmitted by Nuclear Management Company letter and Affidavit CAW-05-2087, to the Document Control Desk.
This information is part of that which will enable Westinghouse to:
(a) Show that a postulated drop of the replacement reactor vessel closure head would produce impact forces at the vessel supports that are no greater than those calculated for the original vessel head, accounting for the different weights of new replacement reactor vessel head and head assembly upgrade packages.
(b) Assist the customer to obtain NRC approval.
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 meeting NRC requirements for licensing documentation.
5 CAW-05-2087 (b) Westinghouse can sell support and defense of this information to its customers in the licensing process.
Public disclosure of 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 licensing support documentation 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.