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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:Letter type:NRC
MONTHYEARNRC 2024-0007, Ile Post-Exam Submittal Letter2024-03-18018 March 2024 Ile Post-Exam Submittal Letter NRC-2024-0026, Ile Proposed Exam Submittal Letter2023-12-20020 December 2023 Ile Proposed Exam Submittal Letter NRC 2023-0013, Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-07-0707 July 2023 Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations NRC 2023-0006, Post-Exam Submittal Cover Letter2023-03-0101 March 2023 Post-Exam Submittal Cover Letter NRC 2023-0005, Report of Changes to Emergency Plan2023-02-21021 February 2023 Report of Changes to Emergency Plan NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan2022-09-30030 September 2022 Sixth 10-Year Interval Inservice Testing (1ST) Program Plan NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022 License Amendment Request 295, Beacon Power Distribution Monitoring System NRC 2022-0019, Report of Changes to Emergency Plan2022-07-13013 July 2022 Report of Changes to Emergency Plan NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, NRC 2022-0015, Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report2022-04-27027 April 2022 Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report NRC 2022-0014, 2021 Annual Monitoring Report2022-04-14014 April 2022 2021 Annual Monitoring Report NRC 2021-0012, Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41)2022-04-0707 April 2022 Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41) NRC 2022-0003, License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process2022-03-25025 March 2022 License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process NRC 2022-0006, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2022-02-22022 February 2022 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections NRC 2022-0004, Report of Changes to Emergency Plan2022-02-0909 February 2022 Report of Changes to Emergency Plan NRC 2022-0005, Refueling Outage U2R38 Owners Activity Report for Class 1, 2, 3 and Mc ISI Examinations2022-02-0101 February 2022 Refueling Outage U2R38 Owners Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2022-0001, Report of Changes to Emergency Plan2022-01-11011 January 2022 Report of Changes to Emergency Plan NRC 2021-0046, Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40)2021-10-28028 October 2021 Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40) NRC 2021-0031, Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-0562021-07-15015 July 2021 Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-056 NRC 2021-0027, Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-0532021-06-30030 June 2021 Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-053 NRC 2021-0028, Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism2021-06-23023 June 2021 Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism NRC 2021-0021, 2020 Annual Monitoring Report2021-04-29029 April 2021 2020 Annual Monitoring Report NRC 2021-0019, Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations NRC-2021-0010, CFR 50.59 Evaluation and Commitment Change Summary Report2021-04-0202 April 2021 CFR 50.59 Evaluation and Commitment Change Summary Report NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021 Technical Specification Bases and Technical Requirement Manual Change Summary NRC 2021-0006, Report of Changes to Emergency Plan2021-03-18018 March 2021 Report of Changes to Emergency Plan NRC 2021-0005, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-022021-02-11011 February 2021 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-02 NRC 2021-0002, Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2021-01-21021 January 2021 Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations 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 NRC 2021-0001, Report of Changes to Emergency Plan2021-01-13013 January 2021 Report of Changes to Emergency Plan NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)2020-11-0202 November 2020 Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40) NRC 2020-0031, NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-0812020-10-0505 October 2020 NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-081 NRC 2020-0029, Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-09-15015 September 2020 Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020 License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0023, NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-08-12012 August 2020 NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations NRC 2020-0021, Response to NRC Inspection Report and Preliminary White Finding2020-08-12012 August 2020 Response to NRC Inspection Report and Preliminary White Finding NRC 2020-0018, Report of Changes to Emergency Plan2020-07-15015 July 2020 Report of Changes to Emergency Plan NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic NRC 2020-0012, Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2020-05-20020 May 2020 Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2020-0008, Report of Changes to Emergency Plan2020-04-0606 April 2020 Report of Changes to Emergency Plan NRC 2020-0007, Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38)2020-03-27027 March 2020 Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38) NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0044, Report of Changes to Emergency Plan2019-11-0101 November 2019 Report of Changes to Emergency Plan NRC 2019-0036, Submittal of 2018 Update to Final Safety Analysis Report2019-10-18018 October 2019 Submittal of 2018 Update to Final Safety Analysis Report NRC 2019-0037, Technical Specification Bases Change Summary2019-10-18018 October 2019 Technical Specification Bases Change Summary NRC 2019-0034, Technical Requirements Manual Change Summary2019-10-18018 October 2019 Technical Requirements Manual Change Summary 2024-03-18
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-098, And Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 And Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response L-2023-011, Response to Requests for Additional Information (Rais) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed2023-02-21021 February 2023 Response to Requests for Additional Information (Rais) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed ML23011A2802023-01-11011 January 2023 Units 1 and 2 - Response to Requests for Additional Information (Rals) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed . ML22229A1052022-08-17017 August 2022 Response to Questions Regarding Point Beach Nuclear Power Plant with Attachment NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, L-2022-013, Subsequent License Renewal Application - Environmental Report Review Review Request for Additional Information (RAI) No. HCR-1 Supplemental Response2022-01-25025 January 2022 Subsequent License Renewal Application - Environmental Report Review Review Request for Additional Information (RAI) No. HCR-1 Supplemental Response L-2021-248, Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response2022-01-0606 January 2022 Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response L-2021-240, Subsequent License Renewal Application - Aging Management Request for Additional Information Set 13 Response2022-01-0606 January 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information Set 13 Response L-2021-223, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response2021-12-0909 December 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response L-2021-222, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response Revision 12021-11-23023 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response Revision 1 L-2021-199, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses2021-11-0404 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses L-2021-208, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 9 Response Supplement 12021-11-0404 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 9 Response Supplement 1 L-2021-190, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 12021-11-0303 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 1 L-2021-200, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response2021-10-25025 October 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response L-2021-174, NextEra Energy Point Beach, LLC - Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) Set 9 Response2021-10-0101 October 2021 NextEra Energy Point Beach, LLC - Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) Set 9 Response L-2021-172, Subsequent License Renewal Application - Aging Management Requirement for Additional Information Set 7, Response2021-09-20020 September 2021 Subsequent License Renewal Application - Aging Management Requirement for Additional Information Set 7, Response L-2021-173, Subsequent License Renewal Application-Aging Management Request for Additional Information (RAI) Set 8 Response2021-09-16016 September 2021 Subsequent License Renewal Application-Aging Management Request for Additional Information (RAI) Set 8 Response L-2021-165, Submittal of Subsequent License Renewal Application - Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses Supplement 12021-09-10010 September 2021 Submittal of Subsequent License Renewal Application - Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses Supplement 1 L-2021-157, L-2021-157 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses2021-09-10010 September 2021 L-2021-157 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses L-2021-155, Subsequent License Renewal Application on Aging Management - Request for Additional Information (Rai), Set 4 Response2021-08-30030 August 2021 Subsequent License Renewal Application on Aging Management - Request for Additional Information (Rai), Set 4 Response L-2021-154, Subsequent License Renewal Application -Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 3 Responses2021-08-25025 August 2021 Subsequent License Renewal Application -Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 3 Responses L-2021-144, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses2021-08-11011 August 2021 Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses L-2021-116, Subsequent License Renewal Application Environmental Report Review Requests for Confirmation Of/Additional Information (Rci/Ral) Set Response2021-06-10010 June 2021 Subsequent License Renewal Application Environmental Report Review Requests for Confirmation Of/Additional Information (Rci/Ral) Set Response NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2019-0042, NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information2019-10-17017 October 2019 NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information NRC-2018-0050, Response to Request for Additional Information Regarding License Amendment Request 288, Request to Extend Containment Leakages Rate Test Frequency2018-11-16016 November 2018 Response to Request for Additional Information Regarding License Amendment Request 288, Request to Extend Containment Leakages Rate Test Frequency NRC 2018-0044, Supplement to Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, ...2018-09-28028 September 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, ... NRC 2018-0038, Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear2018-08-10010 August 2018 Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear NRC 2018-0014, NextEra Energy Point Beach, LLC, Construction Truss License Amendment Request 278, Response to Request for Additional Information2018-04-12012 April 2018 NextEra Energy Point Beach, LLC, Construction Truss License Amendment Request 278, Response to Request for Additional Information L-2018-068, Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations2018-04-0303 April 2018 Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations ML17363A1452017-12-21021 December 2017 Response to Request for Additional Information Regarding License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor NRC 2017-0052, Supplement to LAR 287, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants2017-10-26026 October 2017 Supplement to LAR 287, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants NRC 2017-0041, to License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2017-08-21021 August 2017 to License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors NRC 2017-0010, Response to Final Request for Additional Information Steam Generator License Amendment Request for H* Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region2017-04-20020 April 2017 Response to Final Request for Additional Information Steam Generator License Amendment Request for H* Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region NRC 2017-0008, Response to Final Request for Additional Information on Steam Generator Tube Inspection Report2017-02-23023 February 2017 Response to Final Request for Additional Information on Steam Generator Tube Inspection Report L-2016-137, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage...2016-12-15015 December 2016 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage... NRC 2016-0048, Response to Request for Additional Information Regarding LAR 280 - Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program2016-11-0404 November 2016 Response to Request for Additional Information Regarding LAR 280 - Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program L-2016-188, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)2016-11-0303 November 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) NRC-2016-0033, Response to Request for Additional Information, License Amendment Request 279, Elimination of Technical Specification Section 3.7.14, Primary Auxiliary Building Ventilation2016-07-27027 July 2016 Response to Request for Additional Information, License Amendment Request 279, Elimination of Technical Specification Section 3.7.14, Primary Auxiliary Building Ventilation NRC 2016-0029, Response to Request for Additional Information Regarding License Amendment Request 280 - Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program2016-07-11011 July 2016 Response to Request for Additional Information Regarding License Amendment Request 280 - Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program NRC 2016-0012, Response to Request for Additional Information, License Amendment Request 271 Associated with NFPA 8052016-04-0707 April 2016 Response to Request for Additional Information, License Amendment Request 271 Associated with NFPA 805 NRC 2016-0008, Response to Request for Additional Information on NFPA 805 License Amendment Request 2712016-02-22022 February 2016 Response to Request for Additional Information on NFPA 805 License Amendment Request 271 NRC 2016-0006, License Amendment Request 277. Revision to Staff Augmentation Times in the Emergency Plan, Supplemental Response to Request for Additional Information No. 5 -Correction to Table 5.12016-02-0909 February 2016 License Amendment Request 277. Revision to Staff Augmentation Times in the Emergency Plan, Supplemental Response to Request for Additional Information No. 5 -Correction to Table 5.1 2024-09-16
[Table view] |
Text
Proprietary Information- Withhold from Public Disclosure Under 10 CFR 2.390 NEXTera ENERGY ~
~-
BEACH November 19, 2015 NRC 2015-0068 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant Unit 2 Docket 50-301 Renewed License No. DPR-27 Point Beach Nuclear Plant Unit 2- Request For Additional Information for Relief Request 2-RR MF6615
References:
(1) NextEra Energy Point Beach, LLC (NextEra) letter to NRC, dated August 13, 2015, 10 CFR 50.55a Request, Relief Request 2-RR-11 Unit 2 Steam Generator Nozzle to Safe-End Dissimilar Metal (OM) Weld Inspection (ML15225A104)
(2) NRC electronic mail to NextEra Energy Point Beach, LLC dated October 28, 2015, Point Beach Nuclear Plant Unit 2- Request For Additional Information for Relief Request 2-RR MF6615 By letter dated August 13, 2015 (Reference 1), NextEra Energy Point Beach, LLC (NextEra) submitted Relief Request 2-RR-11 . By Reference 2, NRC requests additional information to complete the Relief Request review. NextEra responses to the additional information request are provided in the Enclosure.
Attachment A contains one copy of the responses to the Request for Additional Information number 1 and 3 (Proprietary) to be withheld from public disclosure under 10 CFR 2. 390. Upon removal of Attachment A, this letter is uncontrolled. contains one copy of the responses to the Request for Additional Information number 1 and 3 (Non-Proprietary).
Attachment C contains the Westinghouse Application for Withholding Proprietary Information from Public Disclosure CAW-15-4336, accompanying Affidavit, Proprietary Information Notice, and Copyright Notice.
Proprietary Information- Withhold Under 10 CFR 2.390.
Attachment A Contains Proprietary Information, Upon Separation of Attachment A this letter is Non-Proprietary.
NextEra Energy Point Beach , LLC, 6610 Nuclear Road , Two Rivers, WI 54241
Proprietary Information- Withhold from Public Disclosure Under 10 CFR 2.390 Attachment A contains information proprietary to Westinghouse Electric Company LLC. It is supported by an Affidavit signed by Westinghouse, the owner of the information. The Affidavit 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 2.390. Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure.
This letter contains no new Regulatory Commitments or revisions to existing Regulatory Commitments.
If you have questions or require additional information, please contact Mr. Bryan Woyak, Licensing Manager, at 920/755-7599.
In accordance with the provisions of 10 CFR 50.91, a copy of this submittal has been provided to the designated Wisconsin Official.
Very truly yours, NextEra Energy Point Beach, LLC Y-~~
Eric McCartney Site Vice President Enclosure cc: Regional Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW Mr. Mike Verhagan, Department of Commerce, State of Wisconsin Proprietary Information -Withhold Under 10 CFR 2.390.
Attachment A Contains Proprietary Information, Upon Separation of Attachment A this letter is Non-Proprietary.
ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 10 CFR 50.55a REQUEST, RELIEF REQUEST 2-RR-11 UNIT 2 STEAM GENERATOR NOZZLE TO SAFE-END DISSIMILAR METAL (OM} WELD INSPECTION Provide axial and hoop weld residual stresses without modification to include operating conditions (i.e. temperature and pressure).
Response to RAJ 1 Refer to Attachment A (Proprietary) or Attachment 8 (Non-Proprietary) for this response.
On page 2 of your request, you state that relief is being requested to extend the hot leg inspection schedule to be in line with the cold leg schedule, which is approximately 7.5 years from the previous examination. However, the cold leg inspection requirements per Code Case N-770-1 require inspections at least every 7 years. Please clarify if you are also requesting for an extension of the cold leg inspection frequency.
Response to RAJ 2 Yes, we are requesting that the cold leg inspections be performed at the same time as the hot leg inspections. Therefore, we are requesting the Code Case N-770-1 cold leg inspection interval be extended from 7 years to 7.5 years.
RAI3 In order to review NRC analysis results with the licensee's, please provide K calculations for axial and circumferential through-weld flaw growth.
Response to RAJ 3 Refer to Attachment A (Proprietary) or Attachment 8 (Non-Proprietary) for this response.
Attachment B (Non-Proprietary)
Responses to NRC RAis 1 and 3 Regarding Point Beach Unit 2 Steam Generator Primary Nozzle to Safe-end Weld Flaw Evaluation (7 pages follow)
Westinghouse Non-Proprietary Class 3 Page 1 of7 Attachment B Ourref: LTR-PAFM-15-108 November 16, 2015 Attachment B (Non-Proprietary)
Responses to NRC RAis Regarding Point Beach Unit 2 Steam Generator Primary Nozzle to Safe-end Weld Flaw Evaluation Portions of this report contain proprietary information. Proprietary information is identified and bracketed. For each of the bracketed sections, the reasons for the proprietary classification are provided using superscripted letters "a", "c", and "e". These letter designations are:
- b. The information reveals the distinguishing aspects of a process or component, structure, tool, method, etc. The prevention of its use by Westinghouse's competitors, without license from Westinghouse, gives Westinghouse a competitive economic advantage.
- d. The information, if used by a competitor, would reduce the competitor's expenditure of resources or improve the competitor's advantage in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.
f The information reveals aspects of past, present, or future Westinghouse- or customer-funded development plans and programs of potential commercial value to Westinghouse.
Westinghouse Non-Proprietary Class 3 Page2 of7 Attachment B Our ref: LTR-PAFM-15-108 November 16, 2015 Responses to NRC RAis Regarding Point Beach Unit 2 Steam Generator Primary Nozzle to Safe-end Weld Flaw Evaluation The NRC submitted three RAis (Reference 1) for the crack growth analysis performed in LTR-PAFM 11-NP (Reference 2) for Point Beach Unit 2 Steam Generator primary nozzle to safe-end welds. Given below are the RAis based on the NRC email correspondence (Reference 1). NextEra Energy requested Westinghouse to provide responses to RAI Nos. 1 and 3, which are provided in this letter report.
Response to RAI No.2 will be generated by NextEra.
By letter dated August I3, 20I5, (Agencywide Documents Access and Management System (ADAMS)
Accession Number ML15225AI04), NextEra Energy submitted for US. Nuclear Regulatory Commission (NRC) staff review and approval Relief Request 2-RR-11, which requests an extension of inspection frequency of the primary Steam Generator (SG) nozzle to safe-end welds under American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-770-I with conditions specified in I 0 CFR50. 55a(g)(6)(ii)(F) for duration of the extended license at Point Beach Nuclear Plant, Unit 2. To complete its review, the NRC staff requests the following additional iriformation:
I. Provide axial and hoop weld residual stresses without modification to include operating conditions (i.e. temperature and pressure).
- 2. On page 2 of your request, you state that relief is being requested to extend the hot leg inspection schedule to be in line with the cold leg schedule, which is approximately 7.5 years from the previous examination. However, the cold leg inspection requirements per Code Case N-770-I require inspections at least every 7 years. Please clarify if you are also requesting for an extension of the cold leg inspection frequency.
- 3. In order to review NRC analysis results with the licensee's, please provide K calculations for axial and circumferential through-weld flaw growth.
NRC RAJ I: Provide axial and hoop weld residual stresses without modification to include operating conditions (i.e. temperature and pressure).
Westinghouse Response:
The Point Beach Unit 2 steam generator primary nozzle to safe-end weld residual stresses shown in Figures 4-2 and 4-3 of LTR-PAFM-15-11-NP (Reference 2) contain the effects of normal operating pressure and temperature. The Point Beach Unit 2 steam generator primary nozzle to safe-end weld residual stresses in the as-welded condition are shown in Figures 1 and 2 in the hoop and axial direction, respectively. The welding residual stresses provided in Figures 1 and 2 do not account for normal operating pressure and temperature condition. The welding residual stresses were determined in Reference 3, and are plant specific to the Point Beach Unit 2 geometry and weld configuration as described in Section 4.0 ofLTR-PAFM-15-11-NP (Reference 2).
Westinghouse Non-Proprietary Class 3 Page 3 of7 Attachment B Ourref: LTR-PAFM-15-108 November 16, 2015 a,c,e Figure 1: Through-Wall Hoop Residual Stress at the SG Inlet and Outlet Nozzle DM Welds at the As-Welded Condition
Westinghouse Non-Proprietary Class 3 Page 4 of7 Attachment B Ourref: LTR-PAFM-15-108 November 16, 2015 a,c,e Figure 2: Through-Wall Axial Residual Stress at the SG Inlet and Outlet Nozzle DM Welds at the As-Welded Condition
Westinghouse Non-Proprietary Class 3 Page 5 of7 Attachment B Ourref: LTR-PAFM-15-108 November 16,2015 NRC RAJ 3: In order to review NRC analysis results with the licensee's, please provide K calculations for axial and circumferential through-weld flaw growth.
Westinghouse Response:
The stress intensity factors used in the Point Beach Unit 2 steam generator primary nozzle to safe-end crack growth analysis in LTR-PAFM-15-11-NP (Reference 2) were determined based on the stress intensity factor expressions from References 4 and 5 for axial and circumferential flaws, respectively, as discussed in Section 6 of Reference 2. The through-wall stress intensity factors for axial and circumferential flaws are shown in Figure 3.
The stress intensity factors were determined using a combination of stresses including the normal operating welding residual stresses from Reference 3. More specifically, the through-wall stress intensity factors shown in Figure 3 are based on the modified normal operating welding residual stresses as discussed in Section 4 ofLTR-PAFM-15-11-NP, which are provided in Figures 4-2 and 4-3 of Reference 2.
In addition to the normal operating welding residual stresses, the stress intensity factors also include normal operating steady state piping loads (deadweight and normal thermal), and effect of crack-face pressure on the crack front.
It should be noted that the stress intensity factors given in Figure 3 are based on the deepest point along the crack front. The difference between the stress intensity factor at the surface tip and the deepest tip of the crack front is small; the final crack growth results shown in Section 7.0 of LTR-PAFM-15-11-NP (Reference 2) conservatively consider the surface and deepest tip of the flaw.
Westinghouse Non-Proprietary Class 3 Page 6 of7 Attachment B Ourref: LTR-PAFM-15-108 November 16, 2015 a,c,e Figure 3: Through-Wall Axial and Circumferential Stress Intensity Factors at the SG Inlet and Outlet Nozzle DM Welds
Westinghouse Non-Proprietary Class 3 Page 7 of7 Attachment B Ourref: LTR-PAFM-15-108 November 16, 2015 References
- 1) NRC Email from Mahesh Chawla (NRC) to Thomas Schneider (NextEra),
Subject:
"Point Beach Nuclear Plant Unit 2 - Request For Additional Information for Relief Request 2-RR MF6615," dated October 28,2015.
- 2) Westinghouse Letter No. LTR-PAFM-15-11-NP, Rev. 0, "Point Beach Unit 2 Steam Generator Primary Nozzle to Safe-end Weld Crack Growth Analysis," June 2015.
- 3) Dominion Engineering, Inc, Document C-8850-00-01, Rev. 0, "Welding Residual Stress Calculation for Steam Generator Nozzle DMW."
- 4) S. R. Mettu, I. S. Raju, "Stress Intensity Factors for Part-through Surface Cracks in Hollow Cylinders," Jointly developed under Grants NASA-JSC 25685 and Lockheed ESC 30124, Job Order number 85-130, Call number 96N72214 (NASA-TM-111707), July 1992.
- 5) American Petroleum Institute, API 579-1/ASME FFS-1 (API 579 Second Edition), "Fitness-For-Service," June 2007.
Attachment C Westinghouse Application for Withholding Proprietary Information from Public Disclosure CAW-15-4336, accompanying Affidavit, Proprietary Information Notice, and Copyright Notice (7 pages follow)
@ Westinghouse Wes1inghouse Electric Company 1000 Westinghouse Drive Cranberry Township, Pennsylvania 16066 USA U.S. Nuclear Regulatory Commission Direct tel: (412) 374-4643 Document Control Desk Direct fax: (724) 940-8560 11555 Rockville Pike e-mail: greshaja@westinghouse.com.
Rockville, MD 20852 CAW-15-4336 November 12,2015 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
LTR-PAFM-15-108, Attachment A, "Responses to NRC RATs Regarding Point Beach Unit 2 Steam Generator Primary Nozzle to Safe-end Weld Flaw Evaluation" (Proprietary)
The Application for Withholding Proprietary Information from Public Disclosure is submitted by Westinghouse Electric Company LLC (Westinghouse), pursuant to the provisions of paragraph (b)(l) of Section 2.390 of the Commission's regulations. It contains commercial strategic information proprietary to Westinghouse and customarily held in confidence.
The proprietary information for which withholding is being requested in the above-referenced report is further identified in Affidavit CAW-15-4336 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 2.390 of the Commission's regulations.
Accordingly, this letter authorizes the utilization of the accompanying Affidavit by NextEra Energy.
Correspondence with respect to the proprietary aspects of the Application for Withholding or the Westinghouse Affidavit should reference CAW-15-4336, and should be addressed to James A. Gresham, Manager, Regulatory Compliance, Westinghouse Electric Company, 1000 Westinghouse Drive, Building 3 Suite 310, Cranberry Township, Pennsylvania 16066.
Very truly yours,
!1~
ffames A. Gresham, Manager Regulatory Compliance
CAW-15-4336 November 12,2015 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
ss COUNTY OF BUTLER:
I, James A. Gresham, am 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 my knowledge, infonnation, and belief.
fames A. Gresham, Manager Regulatory Compliance
2 CAW-15-4336 (1) I am Manager, Regulatory Compliance, 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 Westinghouse.
(2) I am making this Affidavit in conformance with the provisions of 10 CPR Section 2.390 of the Commission's regulations and in conjunction with the Westinghouse Application for Withholding Proprietary Information from Public Disclosure accompanying this Affidavit.
(3) I have 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 Co'mmission in detennining 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 detennining the types of information customarily held in confidence by it and, in that collllection, 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 constitute Westinghouse policy and provide 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-15-4336 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, orfuture Westinghouse or customerfunded development plans and programs of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable.
(iii) 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 infonnation 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 infonnation.
(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
4 CAW-15-4336 (d) Each component of proprietary information pertin,ent 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.
(iv) 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.
(v) 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.
(vi) The proprietary infonnation sought to be withheld in this submittal is that which is appropriately marked in LTR-PAFM-15-108, Attachment A, "Responses to NRC RAis Regarding Point Beach Unit 2 Steam Generator Primary Nozzle to Safe-end Weld Flaw Evaluation" (Proprietary), for submittal to the Commission, being transmitted by NextEra Energy letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted by Westinghouse is that associated with technical justification to support extended volumetric examination interval for Point Beach Unit 2 steam generator primary nozzle to safe-end dissimilar metal welds, and may be used only for that purpose.
(a) This information is part of that which will enable Westinghouse to provide technical justification to support extended volumetric examination interval for
5 CAW~15-4336 Point Beach Unit 2 steam generator primary nozzle to safe-end dissimilar metal welds.
(b) Further this information has substantial commercial value as follows:
(i) Westinghouse plans to sell the use of similar information to its customers for the purpose of providing technical justification to support extended volumetric examination interval for steam generator primary nozzle to safe end dissimilar metal welds.
(ii) Westinghouse can sell support and defense of industry guidelines and acceptance criteria for plant-specific applications.
(iii) 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 technical evaluation justifications 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 infom1ation.
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 perfom1ed and a significant manpower effott, having the requisite talent and experience, would have to be expended.
Further the deponent sayeth not.
PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary and non-proprietary versions of documents furnished to the NRC associated with fracture mechanics technical justification to support extended volumetric examination interval for Point Beach Unit 2 steam generator primary nozzle to safe-end dissimilar metal welds.
In order to conform to the requirements of 10 CFR 2. 390 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 infonnation 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)(t) of the Affidavit accompanying this transmittal pursuant to 10 CPR 2.390(b)(l).
COPYRIGHT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the infonnation 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 2.390 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 pennitted 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 proprietmy notice ifthe original was identified as proprietary.