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MONTHYEARML0730400032007-11-0202 November 2007 Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses (TAC Nos. MD6212 & MD6213) Project stage: RAI CP-200700024, Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses2007-11-15015 November 2007 Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses Project stage: Supplement CP-200700132, Supplement to License Amendment Request (LAR) 07-003 - Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses2007-11-19019 November 2007 Supplement to License Amendment Request (LAR) 07-003 - Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses Project stage: Supplement CP-200800212, Response to Request for Additional Information Related to License Amendment Request 07-003 Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentations, and 5.6.5b.2008-02-11011 February 2008 Response to Request for Additional Information Related to License Amendment Request 07-003 Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentations, and 5.6.5b. Project stage: Response to RAI CP-200800264, Supplement to License Amendment Request (LAR) 07-003: Response to Request for Additional Information Related to License Amendment Request Associated with Methodology Used to Establish Core Operating Limits2008-03-0606 March 2008 Supplement to License Amendment Request (LAR) 07-003: Response to Request for Additional Information Related to License Amendment Request Associated with Methodology Used to Establish Core Operating Limits Project stage: Supplement CP-200800411, Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses2008-03-13013 March 2008 Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses Project stage: Supplement ML0805006272008-04-0202 April 2008 Issuance of Amendment Nos. 144 & 144, Changes to Technical Specifications to Allow Use of Westinghouse-developed/NRC-approved Analytical Methods Used to Establish Core Operating Limits Project stage: Approval ML0805100832008-04-0202 April 2008 License and Technical Specifications, Amendment 144 and 144, Changes to TS to Allow Use of Westinghouse-developed/NRC-approved Analytical Methods Used to Establish COLs Project stage: Other 2008-02-11
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Category:Letter type:CP
MONTHYEARCP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel2024-09-12012 September 2024 License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel CP-202400294, (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule CP-202400319, (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-13013 August 2024 (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-0505 August 2024 (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality CP-202400253, (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 52024-06-26026 June 2024 (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 5 CP-202400235, (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 02024-06-18018 June 2024 (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 0 CP-202400205, (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval2024-05-30030 May 2024 (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval CP-202400175, (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-05-16016 May 2024 (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters CP-202400107, (CPNPP) - 2023 Annual Radiological Environmental Operating Report2024-04-18018 April 2024 (CPNPP) - 2023 Annual Radiological Environmental Operating Report CP-202400099, (CPNPP) - Registration of Dry Spent Fuel Storage Canisters2024-04-0909 April 2024 (CPNPP) - Registration of Dry Spent Fuel Storage Canisters CP-202400092, (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-04-0101 April 2024 (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400089, Property Damage Insurance2024-03-25025 March 2024 Property Damage Insurance CP-202400087, (CPNPP) - Notification of Deviation from Electric Power Research Institute (EPRI) MRP 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-Isolatable2024-03-21021 March 2024 (CPNPP) - Notification of Deviation from Electric Power Research Institute (EPRI) MRP 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-Isolatable CP-202400085, (CPNPP) - Revised Requested Compliance Date - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-0707 March 2024 (CPNPP) - Revised Requested Compliance Date - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CP-202400073, (CPNPP) - Response to RAI for License Amendment Request to Extend Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-03-0404 March 2024 (CPNPP) - Response to RAI for License Amendment Request to Extend Allowed Outage Time for an Inoperable Emergency Diesel Generator CP-202400072, (Cpnpp), Unit 1, Special Report 1-SR-24-001-00, Inoperable Post Accident Monitoring Instrumentation2024-02-29029 February 2024 (Cpnpp), Unit 1, Special Report 1-SR-24-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300470, (Cpnpp), Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-02-28028 February 2024 (Cpnpp), Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown CP-202300474, (Cpnpp), Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-02-28028 February 2024 (Cpnpp), Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions CP-202400063, (CPNPP) - Inservice Inspection (ISI) Owners Activity Reports (OAR-1 Forms) for Unit 1 Refueling Outage 23 (1RF23)2024-02-12012 February 2024 (CPNPP) - Inservice Inspection (ISI) Owners Activity Reports (OAR-1 Forms) for Unit 1 Refueling Outage 23 (1RF23) CP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 CP-202400034, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1)2024-01-29029 January 2024 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1) CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 22023-12-13013 December 2023 (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2 CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300494, License Renewal Application Revision 0, Supplement 32023-12-0606 December 2023 License Renewal Application Revision 0, Supplement 3 CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation2023-11-20020 November 2023 License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation CP-202300533, (CPNPP) - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-14014 November 2023 (CPNPP) - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CP-202300416, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-10-12012 October 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300432, Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 42023-10-0404 October 2023 Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4 CP-202300442, (CPNPP) - Request to Use Later Code Edition for Inservice Inspection (ISI) Program2023-09-15015 September 2023 (CPNPP) - Request to Use Later Code Edition for Inservice Inspection (ISI) Program CP-202300391, (CPNPP) - Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2023-08-24024 August 2023 (CPNPP) - Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule CP-202300361, (CPNPP) - Unit 2 Refueling Outage 20 (2RF20) Steam Generator 180 Day Report2023-08-17017 August 2023 (CPNPP) - Unit 2 Refueling Outage 20 (2RF20) Steam Generator 180 Day Report CP-202300411, (Cpnpp), Inservice Inspection (ISI) Owners Activity Reports (OAR-1 Forms) for Unit 2 Refueling Outage 20 (2RF20)2023-08-17017 August 2023 (Cpnpp), Inservice Inspection (ISI) Owners Activity Reports (OAR-1 Forms) for Unit 2 Refueling Outage 20 (2RF20) CP-202300401, 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 0182023-08-15015 August 2023 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 018 CP-202300358, (Cpnpp), Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendment 1122023-08-0101 August 2023 (Cpnpp), Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendment 112 CP-202300322, Response to Requests for Additional Information Regarding Review of the License Renewal Application – Sets 2 and 32023-07-27027 July 2023 Response to Requests for Additional Information Regarding Review of the License Renewal Application – Sets 2 and 3 CP-202300348, (Cpnpp), Transmittal of Revised Emergency Plan (Revision 48)2023-07-18018 July 2023 (Cpnpp), Transmittal of Revised Emergency Plan (Revision 48) CP-202300285, Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 12023-07-12012 July 2023 Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 1 CP-202300262, Response to Request for Confirmation of Information Regarding Review of the License Renewal Application - Set 22023-06-20020 June 2023 Response to Request for Confirmation of Information Regarding Review of the License Renewal Application - Set 2 CP-202300263, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-06-15015 June 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300248, Response to Request for Additional Information Regarding License Renewal Application - Set 12023-06-13013 June 2023 Response to Request for Additional Information Regarding License Renewal Application - Set 1 CP-202300209, Response to Request for Additional Information - License Renewal Application Environmental Review2023-06-0606 June 2023 Response to Request for Additional Information - License Renewal Application Environmental Review CP-202300207, Revision to Comanche Peak Nuclear Power Plants Response to Notice of Violation (NOV) 05000445/2021011-052023-05-25025 May 2023 Revision to Comanche Peak Nuclear Power Plants Response to Notice of Violation (NOV) 05000445/2021011-05 CP-202300182, Response to Requests for Confirmation of Information Regarding the Environmental Review of the License Renewal Application2023-05-0808 May 2023 Response to Requests for Confirmation of Information Regarding the Environmental Review of the License Renewal Application CP-202300201, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0)2023-05-0404 May 2023 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0) CP-202300160, (Cpnpp), 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 (Cpnpp), 2022 Annual Radiological Environmental Operating Report CP-202300159, (Cpnpp), 2022 Annual Radiological Effluent Release Report2023-04-27027 April 2023 (Cpnpp), 2022 Annual Radiological Effluent Release Report CP-202300165, License Renewal Application Revision 0 - Supplement 22023-04-24024 April 2023 License Renewal Application Revision 0 - Supplement 2 CP-202300175, Submittal of 2022 Annual Environmental Operating Report (Non-Radiological)2023-04-20020 April 2023 Submittal of 2022 Annual Environmental Operating Report (Non-Radiological) 2024-09-12
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARCP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel2024-09-12012 September 2024 License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel ML24194A1332024-08-28028 August 2024 Issuance of Amendment Nos. 190 and 190, Respectively, Revision to Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown CP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 ML24023A0242024-01-24024 January 2024 Correction to Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident Methodology CP-202300494, License Renewal Application Revision 0, Supplement 32023-12-0606 December 2023 License Renewal Application Revision 0, Supplement 3 CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation2023-11-20020 November 2023 License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation CP-202300293, (CPNPP) - License Amendment Request Proposing Changes to Technical Specifications to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days2023-09-14014 September 2023 (CPNPP) - License Amendment Request Proposing Changes to Technical Specifications to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300165, License Renewal Application Revision 0 - Supplement 22023-04-24024 April 2023 License Renewal Application Revision 0 - Supplement 2 CP-202300096, License Amendment Request (LAR) 23-002 Application Regarding GDC-5 Shared Systems Requirements2023-04-20020 April 2023 License Amendment Request (LAR) 23-002 Application Regarding GDC-5 Shared Systems Requirements CP-202300140, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. LAR 23-0012023-04-19019 April 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. LAR 23-001 CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300135, License Renewal Application Revision 0 - Supplement 12023-04-0606 April 2023 License Renewal Application Revision 0 - Supplement 1 CP-202200380, (CPNPP) - Non-Voluntary License Amendment Request to Revise Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications2022-11-21021 November 2022 (CPNPP) - Non-Voluntary License Amendment Request to Revise Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications CP-202200355, Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-0022022-11-21021 November 2022 Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002 CP-202200350, Facility Operating License Numbers NPF-87 and NPF-89 - License Renewal Application - Appendix E, Environmental Report2022-10-0303 October 2022 Facility Operating License Numbers NPF-87 and NPF-89 - License Renewal Application - Appendix E, Environmental Report ML22192A0072022-08-22022 August 2022 Issuance of Amendment Nos. 183 and 183 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 CP-202200273, Third Supplement to License Amendment Request (LAR) 20-006 Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative2022-07-20020 July 2022 Third Supplement to License Amendment Request (LAR) 20-006 Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative CP-202200006, (CPNPP) - Second Supplement to License Amendment Request (LAR) 20-006 Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended.2022-02-17017 February 2022 (CPNPP) - Second Supplement to License Amendment Request (LAR) 20-006 Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended. CP-202200075, Third Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections2022-02-15015 February 2022 Third Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections CP-202100575, (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections2021-08-31031 August 2021 (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections CP-202100251, (CPNPP) - Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections2021-07-27027 July 2021 (CPNPP) - Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections CP-202100394, Supplement to License Amendment Request (LAR) 20-0062021-07-13013 July 2021 Supplement to License Amendment Request (LAR) 20-006 CP-202100065, Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-05-11011 May 2021 Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b CP-202000585, (CPNPP) - Supplement to License Amendment Request (LAR) 20-005, Revision to Technical Specification (TS) 3.6.8, Containment Sump2021-01-27027 January 2021 (CPNPP) - Supplement to License Amendment Request (LAR) 20-005, Revision to Technical Specification (TS) 3.6.8, Containment Sump CP-202000584, (CPNPP) - Supplement to License Amendment Request (LAR) 15-001, Revision to Technical Specification (TS) 3.8.l, AC SOURCES-OPERATING2020-12-0909 December 2020 (CPNPP) - Supplement to License Amendment Request (LAR) 15-001, Revision to Technical Specification (TS) 3.8.l, AC SOURCES-OPERATING CP-202000575, (CPNPP) - Exigent License Amendment Request (LAR) 20-007 Revision to Technical Specification (TS) 3.7.8, Station Service Water System and TS 3.8.1, AC Sources - Operating2020-11-19019 November 2020 (CPNPP) - Exigent License Amendment Request (LAR) 20-007 Revision to Technical Specification (TS) 3.7.8, Station Service Water System and TS 3.8.1, AC Sources - Operating CP-202000365, Luminant, Comamche Leak Nuclear Power Plant, License Amendment Request 20-005, New Technical Specification 3.6.8, Containment Sump2020-08-31031 August 2020 Luminant, Comamche Leak Nuclear Power Plant, License Amendment Request 20-005, New Technical Specification 3.6.8, Containment Sump CP-202000401, (CPNPP) - Supplement to Exigent License Amendment Request (LAR) 20-002, Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water2020-07-28028 July 2020 (CPNPP) - Supplement to Exigent License Amendment Request (LAR) 20-002, Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water CP-202000388, (CPNPP) - Supplement to Exigent License Amendment Request (LAR) 20-002, Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water2020-07-16016 July 2020 (CPNPP) - Supplement to Exigent License Amendment Request (LAR) 20-002, Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water CP-202000321, (CPNPP) - License Amendment Request (LAR) 20-001 Technical Specification (TS) 1.1, Definitions - ESP & RTS Response Time2020-07-0202 July 2020 (CPNPP) - License Amendment Request (LAR) 20-001 Technical Specification (TS) 1.1, Definitions - ESP & RTS Response Time CP-202000305, (CPNPP) - Exigent License Amendment Request (LAR) 20-002 Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water2020-06-24024 June 2020 (CPNPP) - Exigent License Amendment Request (LAR) 20-002 Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water TXX-2002, Exigent License Amendment Request (LAR) 20-003 Revision to Technical Specification (TS) 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator Program2020-04-10010 April 2020 Exigent License Amendment Request (LAR) 20-003 Revision to Technical Specification (TS) 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator Program CP-201900368, Revision to Technical Specifications 3.8.1, AC Sources - Operating2020-03-31031 March 2020 Revision to Technical Specifications 3.8.1, AC Sources - Operating CP-202000016, Editorial Correction to License Amendment Request (LAR) 19-002 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program.2020-01-16016 January 2020 Editorial Correction to License Amendment Request (LAR) 19-002 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program. CP-201900415, License Amendment Request (LAR) 19-002, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-11-0707 November 2019 License Amendment Request (LAR) 19-002, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program CP-201900393, License Amendment Request (LAR) 19-001, Application to Adopt TSTF-513-A, Revision 3, PWR Operability Requirements and Actions for RCS Leakage Instrumentation2019-11-0707 November 2019 License Amendment Request (LAR) 19-001, Application to Adopt TSTF-513-A, Revision 3, PWR Operability Requirements and Actions for RCS Leakage Instrumentation CP-201800115, License Amendment Request 17-001 Revision to Technical Specification 3.3.2. ESFAS Instrumentation2018-03-29029 March 2018 License Amendment Request 17-001 Revision to Technical Specification 3.3.2. ESFAS Instrumentation ML17074A4942017-04-13013 April 2017 Issuance of Amendment Nos. 168 and 168 Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML16351A2002016-12-14014 December 2016 Submittal of License Amendment Request 16-003, Administrative Change to License Name CP-201600216, License Amendment Request 16-001, Application to Revise Technical Specifications to Adopt TSF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing.2016-04-27027 April 2016 License Amendment Request 16-001, Application to Revise Technical Specifications to Adopt TSF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing. CP-201501062, ISFSI - Application for Order Approving Transfer of Licenses and Conforming License Amendments2015-11-12012 November 2015 ISFSI - Application for Order Approving Transfer of Licenses and Conforming License Amendments CP-201400165, (CPNPP) - Redacted Version of License Amendment Request (LAR) 13-003, for Approval of the Revised CPNPP Cyber Security Plan Implementation Schedule2014-02-0404 February 2014 (CPNPP) - Redacted Version of License Amendment Request (LAR) 13-003, for Approval of the Revised CPNPP Cyber Security Plan Implementation Schedule CP-201301322, License Amendment Request (LAR) 13-003, for Approval of the Revised CPNPP Cyber Security Plan Implementation Schedule2013-11-21021 November 2013 License Amendment Request (LAR) 13-003, for Approval of the Revised CPNPP Cyber Security Plan Implementation Schedule CP-201301065, Revision to Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2013-08-29029 August 2013 Revision to Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process CP-201300738, License Amendment Request 13-002, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item..2013-07-10010 July 2013 License Amendment Request 13-002, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item.. CP-201300257, License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals.2013-03-28028 March 2013 License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals. CP-201300083, License Amendment Request 12-06, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage and 5.5 Programs and Manuals.2013-01-15015 January 2013 License Amendment Request 12-06, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage and 5.5 Programs and Manuals. 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um Luminant Mike Blevins Executive Vice President
& Chief Nuclear Officer Mike.Blevins @Luminantcom Luminant Power P 0 Box 1002 6322 North FM 56 Glen Rose, TX 76043 T 254 897 5209 C 817 559 9085 F 254 897 6652 CP-200700132 Ref. # 10CFR50.90 Log # TXX-07168 10CFR50.46 November 19, 2007 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 SUPPLEMENT TO LICENSE AMENDMENT REQUEST (LAR)07-003 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO REVIEW ASSOCIATED WITH LARGE AND SMALL BREAK LOCA ANALYSES (TAC Nos. MD6212 and MD6213)
REFERENCE:
- 1. Letter logged TXX-07063 dated April 10, 2007 submitting License Amendment Request (LAR)07-003 revision to Technical Specification 3.1, "REACTIVITY CONTROL SYSTEMS," 3.2, "POWER DISTRIBUTION LIMITS," 3.3, "INSTRUMENTATION," and 5.6.5b, "CORE OPERATING LIMITS REPORT (COLR)," from Mike Blevins to the NRC.
- 2. Letter logged TXX-07107 dated July 31, 2007 submitting the Comanche Peak Units 1 and 2 Large and Small Break LOCA Analyses from Mike Blevins to the NRC.
- 3. Letter logged TXX-07151 dated November 15, 2007 submitting additional information regarding the Comanche Peak Units 1 and 2 Large and Small Break LOCA Analyses from Mike Blevins to the NRC.
Dear Sir or Madam:
Per Reference 1, Luminant Generation Company, LLC (Luminant Power) submitted proposed changes to the Comanche Peak Steam Electric Station, herein referred to as Comanche Peak Nuclear Power Plant (CPNPP), Unit 1 and Unit 2 Technical Specifications to allow the use of several Nuclear Regulatory Commission (NRC) approved accident analysis methodologies to be used to establish core operating limits. Included in that'submittal were different methods for analyzing the small break loss of coolant accident (LOCA) and the large break LOCA. As prescribed in the NRC's Safety Evaluations approving the generic use of these methods, and in compliance with 10CFR50.46, Luminant Power transmitted, per Reference 2, the evaluation models and results developed in accordance with those methodologies for NRC review.
On November 2, 2007, the NRC provided Luminant Power with a request for additional information regarding the large and small break loss-of-coolant accidents for Comanche Peak. The response to these questions was provided in Reference 3 except for the response to question 26, which contained information proprietary to Westinghouse Electric Company LLC. The response to question 26 is provided in Attachment 1 to this letter.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway - Comanche Peak
U. S. Nuclear Regulatory Commission TXX-07168 Page 2 11/19/2007 contains information proprietary to Westinghouse Electric Company LLC, and is supported by an affidavit signed by Westinghouse, the owner of the information. Attachment 2 is the non-proprietary response to question 26. The affidavit set 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 Section 2.390 of the Commissions' regulations. Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.390 of the Commission's regulations.
Correspondence with respect to the copyright or proprietary aspects of Attachment 1 or the supporting Westinghouse affidavit should reference CAW-07-2359 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.
In accordance with 10CFR50.91(b), Luminant Power is providing the State of Texas with a copy of this proposed amendment.
This communication contains no new licensing basis commitments regarding Comanche Peak Units 1 and 2.
Should you have any questions, please contact Mr. J. D. Seawright at (254) 897-0140.
I state under penalty of perjury that the foregoing is true and correct.
Executed on November 19, 2007.
Sincerely, Luminant Generation Company LLC Mike Blevins By: 4 j1u, 2
,1_,, )/'b
/Fred W. Madden Director, Oversight & Regulatory Affairs . Response to NRC Request for Additional Information on Post LOCA Long Term Cooling for CPNPP (Proprietary)
- 2. Response to NRC Request for Additional Information on Post LOCA Long Term Cooling for CPNPP (Non-Proprietary)
Enclosure - Westinghouse authorization letter CAW-07-2359 with accompanying affidavit, Proprietary Information Notice and Copyright Notice.
c- E. E. Collins, Region IV Alice Rogers B. K. Singal, NRR Environmental & Consumer Safety Section Resident Inspectors, Comanche Peak Texas Department of State Health Services 1100 West 49th Street Austin, Texas 78756-3189
Attachment 2 to TXX-07168 Response to NRC Request for Additional Information on Post-LOCA Long Term Cooling for CPNPP (Non-Proprietary) to TXX-07168 Page 1 of 2 Westinghouse Non-Proprietary Class 3 WPT-17073 ATTACHMENT2 Response to NRC Request for Additional Information on Post LOCA Long-Term Cooling for CPNPP (NRC Question #26)
POST-LOCA LONG-TERM COOLING CALCULATIONS
- 26. Placing the break on the top of the discharge leg will delay the growth of the mixing volume through the core and upper plenum and increase the concentrations early in the event. Please discuss the effect of breaks located on the top of the discharge leg in determining precipitation timing.
Please discuss the growth of the mixing volume vs. time for this scenario (i.e. the two-phase mixture volume in half of the lower plenum and core).
At what time in the event does the mixture volume grow sufficiently to reach the upper plenum region?
Response
The primary impact of placing the break on the top of the discharge leg is the potential to refill the loop seal piping thereby increasing the loop pressure drop resulting in a depression of the two-phase mixture level in the inner vessel region. Loop seal refilling for the large break LOCA is unlikely because of the high loop vapor flow'rates and the large steam vent area provided by the break.
One of the possible mechanisms for loop seal refilling is the backflow of ECCS water injected into the cold legs. In order for this backflow to occur it is necessary to already have injected enough ECCS water to have refilled the reactor vessel, including the core. A vessel,refilled to this extent would have a mitigating effect on the inner vessel region boric acid concentration transient.
Further, the loop steam flow would need to be low enough that counter current flow limit does not occur. The higher core power associated with the uprate is beneficial in this regard, in that, the vapor flow through the loops will be higher due to higher decay heat. The consequences of post-LOCA loop seal refilling' were evaluated as reported -in Reference 1. The expected system response would be a cyclic plugging and clearing but not a sustained core uncovery that could adversely impact core cooling.
Another possible mechanism for loop seal refilling is condensation in the steam generators during a small break LOCA event. In the unlikely event of a'sustained core uncovery, the operators would follow prescribed emergency operating procedures to take actions that would disrupt the conditions necessary to sustain the inner vessel region mixture level depression. While variations in break size and orientation
]axc Page 1 of 2 to TXX-07168 Page 2 of 2 Westinghouse Non-Proprietary Class 3 WPT-17073 ATTACHMENT 2 One beneficial aspect of this scenario is that cyclic loop seal plugging and clearing would
]axc The core region boric acid concentration versus time for the scenario described (regardless of break size or orientation) is conservatively represented by the boric acid concentration calculated for the quasi-stagnant case that accounts for voiding in the core and upper plenum regions that credits mixing in only 50% of the lower plenum.
References:
- 1. Letter from Westinghouse to NRC, NSD-NRC-97-5092, "Core Uncovery Due to Loop Seal Re-Plugging During Post-LOCA Recovery," March 1997.
- 2. J. Tuunanen, et al., Experimental and analytical studies of boric acid concentrations in a WER-440 reactor during the long-term cooling period of loss-of-coolant accidents, Nuclear Engineering and Design, Vol. 148, 1994, pp. 217-231.
Page 2 of 2
Enclosure to TXX-07168 Westinghouse authorization letter CAW-07-2359 with accompanying affidavit, Proprietary Information Notice and Copyright Notice
S)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 Direct fax: (412) 374-4011 Washington, DC 20555-0001 e-mail: greshaja@westinghouse.com Our ref CAW-07-2359 November 16, 2007 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
WPT-17073, Attachment 1, "Response to NRC Request for Additional Information on Post LOCA Long-Term Cooling for CPNPP (NRC Question #26)" (Proprietary)
The proprietary information for which withholding is being requested in the above-referenced letter is further identified in Affidavit CAW-07-2359 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 Luminant Generation Company LLC.
Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-07-2359, 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 yo A. Gresham Mlan ager Regulatory Compliance and Plant Licensing Enclosures cc: J. Thompson, NRC
CAW-07-2359 bcc: J. A. Gresham (ECE 4-7A) IL R. Bastien, IL (Nivelles, Belgium)
C. Brinkman, IL (Westinghouse Electric Co., 12300 Twinbrook Parkway, Suite 330, Rockville, MD 20852)
RCPL Administrative Aide (ECE 4-7A) 1L, 1A (letter and affidavit only)
R. Morrison (ECE 4-7A) IL, IA
CAW-07-2359 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:
J. A. Gresham, Manager Regulatory Compliance & Plant Licensing Sworn to and subscribed before me this 16'h day of November, 2007 Notary Public COMMONWEALTH OF PENNSYLVANIA Notarial Seal Sharon L. Marlde, Notary Public Monroeville Boro, Allegheny County My Commission Expires Jan. 29, 2011 Member, Pennsylvania Association of Notaries
2 2CAW-07-2359 (1) 1 am Manager, Regulatory Compliance & Plant Licensing, 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 Westinghouse.
(2) 1 am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 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 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
3 3CAW-07-2359 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 infornation, production capacities, budget levels, or conmmercial 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-07-2359 (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 2.390, 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 proprietary information sought to be withheld in this submittal is that which is appropriately marked in WPT-17073, Attachment 1, "Response to NRC Request for Additional Information on Post LOCA Long-Term Cooling for CPNPP (NRC Question
- 26)" (Proprietary), for Comanche Peak Nuclear Power Plant Units 1 and 2, being transmitted by Luminant Generation Company 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 for Comanche Peak Nuclear Power Plant Units 1 and 2 is expected to be applicable for other licensee submittals in response to certain NRC requirements for justification of stretch power uprating.
This information is part of that which will enable Westinghouse to:
5 CAW-07-2359 (a) Provide information in support of plant power uprate licensing submittals.
(b) Provide customer specific response to NRC requests for information.
(c) Provide licensing support for customer submittals.
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 associated with power uprate licensing submittals.
(b) Westinghouse can sell support and defense of the technology to its customer in the licensing process.
(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 information 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.
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 2.390 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 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 2.390(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 2.390 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 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.