Letter Sequence Response to RAI |
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MONTHYEARML14064A3292014-02-26026 February 2014 NP-Attachment to LTR-LIS-13-557, Rev 0, Application of Westinghouse Best-Estimate Large Break LOCA Methodology to the Wolf Creek Generating Station Project stage: Request ET 14-0008, Application for Amendment to Revise Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology2014-02-26026 February 2014 Application for Amendment to Revise Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology Project stage: Request ML14120A0202014-04-30030 April 2014 NRR E-mail Capture - Acceptance Review Project stage: Acceptance Review ML14182A3762014-07-14014 July 2014 Request for Withholding from Public Disclosure - 1/21/14 Affidavit Executed by J. Gresham, Westinghouse LTR-LIS-13-557P-Attachment, Revision 0 Provided as Enclosure 1 to 2/26/14 License Amendment Request Project stage: Other ML14324A0132014-11-19019 November 2014 NRR E-mail Capture - Question on LAR to Add Astrum to COLR Project stage: Other ML14324A8582014-11-20020 November 2014 NRR E-mail Capture - Question on LAR to Add Astrum to COLR (Wolf Creek TAC No. MF3518) Project stage: Other ET 14-0038, Supplemental Information Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology2014-12-0808 December 2014 Supplemental Information Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology Project stage: Supplement ET 15-0002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology2015-01-21021 January 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology Project stage: Response to RAI ML15076A3132015-03-18018 March 2015 Request for Withholding Information from Public Disclosure - 1/15/2015 Affidavit Executed by J. Gresham, Westinghouse, Two Attachments to LTR-LIST-15-11, Revision 1 Project stage: Withholding Request Acceptance ML15091A3822015-03-20020 March 2015 Submission of 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes Project stage: Request WO 15-0044, Proposed License Condition Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology2015-07-15015 July 2015 Proposed License Condition Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology Project stage: Request ML15203A0052015-08-28028 August 2015 Redacted, Issuance of Amendment No. 213, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large-Break Loss-of-Coolant Accident Analysis Methodology (Astrum) Project stage: Approval 2014-07-14
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Category:Legal-Affidavit
MONTHYEARWO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 WO 22-0056, Operating Corporations Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082022-12-19019 December 2022 Operating Corporations Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML22353A5552022-12-15015 December 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-12-22022 December 2021 Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-11011 October 2021 Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption.2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. ML18313A2252018-10-25025 October 2018 Westinghouse Affidavit CAW-18-4828 - Application for Withholding Proprietary Information from Public Disclosure ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 15-0002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology2015-01-21021 January 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology ET 14-0009, Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-02-25025 February 2014 Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis ML12298A0302012-10-22022 October 2012 Transmittal of Pci Proprietary Document No. PCI-2012.10.22-1 Rev 0; Responses to Staff Comments Dated July 11, 2012 ET 08-0017, Additional-Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification2008-03-14014 March 2008 Additional-Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification ET 07-0050, Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation Valves and Controls2007-10-16016 October 2007 Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation Valves and Controls ET 07-0022, Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification2007-06-15015 June 2007 Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification ML0715502252007-05-25025 May 2007 PWR Owners Group - Draft Revisions to Topical Report WCAP-15791 Revision 1, Risk-Informed Evaluation of Extensions to Containment Isolation Valve Completion Times, and the Final Safety Evaluation, MUHP-3010/LSC-0029/LSC-0135 ML0701702062006-11-0202 November 2006 Request for Withholding Proprietary Documentation of Material: White Paper: MRP Review of Implications of Wolf Creek Pressurizer Indications 2023-12-26
[Table view] Category:Letter type:ET
MONTHYEARET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen2023-03-16016 March 2023 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications2023-03-0101 March 2023 License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 23-0004, Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2023-01-26026 January 2023 Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0010, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2022-08-0202 August 2022 License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0011, Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface2022-05-31031 May 2022 Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface ET 22-0005, Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-04-13013 April 2022 Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0003, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads2022-04-0606 April 2022 CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads ET 22-0002, Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head .2022-04-0404 April 2022 Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head . ET 22-0004, Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report2022-03-15015 March 2022 Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report ET 22-0001, Removal of the Table of Contents from the Technical Specifications2022-01-12012 January 2022 Removal of the Table of Contents from the Technical Specifications ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-12-22022 December 2021 Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0009, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage2021-11-0101 November 2021 Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage ET 21-0015, Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-20020 October 2021 Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-11011 October 2021 Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0004, License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2021-09-29029 September 2021 License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0005, Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-1912021-08-12012 August 2021 Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 20-0013, Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415)2020-10-26026 October 2020 Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415) ET 20-0011, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-10-0101 October 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ET 20-0007, License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers2020-06-0808 June 2020 License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ET 20-0008, Operating Corporation Update for Full Implementation of Open Phase Detection System2020-05-20020 May 2020 Operating Corporation Update for Full Implementation of Open Phase Detection System ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ET 20-0002, Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12020-01-29029 January 2020 Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 ET 19-0021, Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-12-0909 December 2019 Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0020, Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-11-13013 November 2019 Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0019, Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-09-10010 September 2019 Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0018, Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-08-22022 August 2019 Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0014, lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 12019-08-15015 August 2019 lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 1 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption.2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. ET 19-0003, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange2019-02-25025 February 2019 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ET 19-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-01-23023 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 ET 18-0032, Operating Corporation Change of Date for Full Implementation of Open Phase Detection System2018-12-0707 December 2018 Operating Corporation Change of Date for Full Implementation of Open Phase Detection System ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0029, (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection2018-10-31031 October 2018 (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information ET 18-0014, Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-05-29029 May 2018 Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0013, Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld2018-05-0202 May 2018 Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld ET 18-0011, (WCGS) - Guarantee of Payment of Deferred Premiums2018-04-30030 April 2018 (WCGS) - Guarantee of Payment of Deferred Premiums ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0010, Financial Protection Levels2018-03-29029 March 2018 Financial Protection Levels ET 18-0007, Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-02-15015 February 2018 Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0005, Withdrawal of License Amendment Request for Revision to the Emergency Plan2018-02-0505 February 2018 Withdrawal of License Amendment Request for Revision to the Emergency Plan ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term 2023-05-17
[Table view] Category:Report
MONTHYEARML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23244A2142023-09-0101 September 2023 IAEA Osart Report ML23068A1962023-03-0909 March 2023 Biennial 50.59 Evaluation Report ML23135A2012022-12-0606 December 2022 EQSD-I, Rev 18, Equipment Qualification Design Basis Document ML23135A1932022-09-0101 September 2022 EQSD-II, Rev 34, Equipment Qualification Summary Document WO 22-0021, Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2022-08-29029 August 2022 Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ML22152A2042022-05-18018 May 2022 EQSD-I, Revision 16, Equipment Qualification Design Basis Document ML22152A1992022-05-18018 May 2022 EQSD-II, Revision 33, EQ Program Master List (Table 1) Plus Mild Environment SR Electrical Equipment List (Table 2) ML22152A1942022-05-18018 May 2022 EQSD-I, Revision 15, Equipment Qualification Design Basis Document ML23135A2072022-04-0606 April 2022 EQSD-I, Rev 17, Equipment Qualification Design Basis Document ML20290A6192020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, EQSD-I, Rev. 14, Equipment Qualification Design Basis Document ML20182A4292020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating WO 20-0048, Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating2020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating WO 20-0041, Rev. 32 to Equipment Qualification Summary Document-II (EQSD-II)2020-01-15015 January 2020 Rev. 32 to Equipment Qualification Summary Document-II (EQSD-II) ML19330F8632019-12-0606 December 2019 Regulatory Audit Summary Regarding License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, ML19178A3392019-07-0909 July 2019 Staff Assessment of Aging Management Program and Inspection Plan of Reactor Vessel Internals ML19092A1562018-09-18018 September 2018 EQSD-I, Rev 14 ML18093B0112018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Equipment Classification Design Basis Document, EQSD-I Rev 13 ML18093B0132018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Equipment Qualification Summary Document, EQSD-II, Rev 30, Redacted WO 19-0010, EQSD-II, Rev 312018-02-19019 February 2018 EQSD-II, Rev 31 ML18023A1572018-01-18018 January 2018 Submittal of Blind Sample Error Investigation Report ML17241A2512017-11-0808 November 2017 Staff Assessment of Flooding Focused Evaluation ML17234A4002017-08-17017 August 2017 Summary of Changes to Three Forms That Implement Radiological Emergency Response Plan (RERP) ML17093A6652017-03-27027 March 2017 Report on Financial Protection Levels ML17151B0452017-03-0909 March 2017 Equipment Qualification Summary Document, Master List Section II, EQSD-II, Rev 28, Part 2 - Redacted ML17151B0442017-03-0202 March 2017 Equipment Qualification Summary Document, Master List Section II, EQSD-II, Rev 28, Part 1 ML17072A0512017-03-0202 March 2017 Biennial 50.59 Evaluation Report for 01/01/2015 - 12/31/2016 ML17151B0432017-01-26026 January 2017 Equipment Qualification Design Basis Document, EQSD-I, Rev 11 ML17054C2302017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - A-3788, Technical Report, Appendix a, Fission Product Removal Effectiveness of Chemical Additives in PWR Containment Sprays ET 17-0005, 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS2016-12-15015 December 2016 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document.2016-05-31031 May 2016 Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document. ML16204A1802016-05-31031 May 2016 Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document. WM 16-0008, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-II, Revision 27 Redacted2016-05-31031 May 2016 Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-II, Revision 27 Redacted ML15314A6572015-11-0404 November 2015 Submittal of 10 CFR 50.46 Thirty Day Report of Emergency Core Cooling System (ECCS) Model Changes ML17151B0392015-10-26026 October 2015 E-1F9915, Rev 8, Design Basis Document for Ofn RP-017, Control Room Evaluation ET 16-0003, Flood Hazard Reevaluation Report, Revision 12015-10-21021 October 2015 Flood Hazard Reevaluation Report, Revision 1 ML15216A3202015-08-12012 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights ML15075A0282015-03-0404 March 2015 Biennial 50.59 Evaluation Report ML15062A2752015-02-24024 February 2015 Pressure and Temperature Limits Report, Revision 2 ET 15-0002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology2015-01-21021 January 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology WO 14-0095, Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-12-23023 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request 2024-09-04
[Table view] Category:Miscellaneous
MONTHYEARML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23068A1962023-03-0909 March 2023 Biennial 50.59 Evaluation Report WO 20-0048, Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating2020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating ML20182A4292020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating WO 20-0041, Rev. 32 to Equipment Qualification Summary Document-II (EQSD-II)2020-01-15015 January 2020 Rev. 32 to Equipment Qualification Summary Document-II (EQSD-II) ML19330F8632019-12-0606 December 2019 Regulatory Audit Summary Regarding License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, ML18023A1572018-01-18018 January 2018 Submittal of Blind Sample Error Investigation Report ML17234A4002017-08-17017 August 2017 Summary of Changes to Three Forms That Implement Radiological Emergency Response Plan (RERP) ML17093A6652017-03-27027 March 2017 Report on Financial Protection Levels ET 17-0005, 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS2016-12-15015 December 2016 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS ML15314A6572015-11-0404 November 2015 Submittal of 10 CFR 50.46 Thirty Day Report of Emergency Core Cooling System (ECCS) Model Changes ET 16-0003, Flood Hazard Reevaluation Report, Revision 12015-10-21021 October 2015 Flood Hazard Reevaluation Report, Revision 1 ML15216A3202015-08-12012 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights ML15075A0282015-03-0404 March 2015 Biennial 50.59 Evaluation Report ET 15-0002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology2015-01-21021 January 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology WO 14-0095, Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-12-23023 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14136A1712014-05-30030 May 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14077A2812014-02-10010 February 2014 Operating Corporation Flood Hazard Reevaluation Report,Revision 0 ML1307206802013-03-0404 March 2013 Cycle 20 Core Operating Limits Report ET 12-0032, WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-1 Through Page B-502012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-1 Through Page B-50 ML12342A2502012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-51 Through Page B-100 ML12342A2512012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-101 Through Page B-150 ML12342A2532012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Cover Through Appendix a, Seismic Walkdown Checklists (Swcs) Page A-112 ML12342A2542012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-151 Through Page B-184 ML12342A2552012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-185 Through Page B-228 ML12342A2572012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix C, Licensing Basis Evaluations Summary, Page C-1 Through End ML12342A2592012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix a, Seismic Walkdown Checklists (Swcs) Page A-113 Through Page A-222 ML12342A2602012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix a, Seismic Walkdown Checklists (Swcs) Page A-223 Through Page A-320 ML12342A2612012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix a, Seismic Walkdown Checklists (Swcs) Page A-321 Through Page A-350 ML12342A2622012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix a, Seismic Walkdown Checklists (Swcs) Page A-348 Through Page A-440 ML12100A0762012-03-26026 March 2012 Foreign Ownership, Control or Influence Information - Updated Lists of Owners, Officers, Directors and Executive Personnel ML11133A3482011-05-0808 May 2011 Great Plains Energy, Inc. and Kansas Electric Power Cooperative, Inc. - Item 8. Financial Statemnts and Supplemental Data ML11279A0052011-03-31031 March 2011 John Redmond Reservoir Diversion and Impacts to Downstream Conditions: System Simulation Modeling ML1107500302011-03-10010 March 2011 Biennial 50.59 Evaluation Report ML1023501702010-09-15015 September 2010 Review of the Results of 16th Steam Generator Tube Inservice Inspections Performed During Refueling Outage 17 ML0917607642009-06-24024 June 2009 Phase 3 Potential Loss of RHR Due to Inadequate Cooling of Suction Line During Mode 4 to Mode 3 Transition at Wolf Creek ET 09-0010, Pressure and Temperature Limits Report, Revision 12009-03-0606 March 2009 Pressure and Temperature Limits Report, Revision 1 ET 09-0005, Submittal of Requested Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification2009-01-29029 January 2009 Submittal of Requested Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification 2024-09-04
[Table view] |
Text
WNLF CREEK NUCLEAR OPERATING CORPORATION Jaime H. McCoy January 21, 2015 Vice President Engineering ET 15-0002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
- 1) Letter ET 14-0008, dated February 26, 2014, from J. P. Broschak, WCNOC to USNRC
- 2) Electronic Mail dated November 20, 2014, from C. F. Lyon, USNRC, to S. G. Wideman, WCNOC
Subject:
Docket No. 50-482: Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology Gentlemen:
Reference 1 provided the Wolf Creek Nuclear Operating Corporation (WCNOC) application to revise the Wolf Creek Generating Station (WCGS) Technical Specifications (TS). Specification 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)," is revised to incorporate WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," to the list of analytical methods used to determine the core operating limits. The Reference 1 application was a plant specific best-estimate large break LOCA analysis that accounted for the effects of fuel thermal conductivity degradation (TCD). Reference 2 provided a request for additional information related to the application. The Attachment provides WCNOC's response to the request for additional information.
The additional information does not expand the scope of the application and does not impact the no significant hazards consideration determination presented in Reference 1.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," a copy of this submittal is being provided to the designated Kansas State official.
/+001 364-8831 P.O. Box 411 / Burlington, KS 66839 / Phone: (620)
An Equal Opportunity Employer M/F/HCNET
ET 15-0002 Page 2 of 3 Enclosure I provides the proprietary Westinghouse Electric Company LLC Attachment 1 to LTR-LIS-1 5-11, Revision 1, "Westinghouse Suggested Response to NRC Request for Additional Information (RAI) Regarding the Wolf Creek (SAP) ASTRUM Analysis - Proprietary." Enclosure II provides the non-proprietary version of Westinghouse Electric Company LLC Attachment 1 to LTR-LIS-15-1 1, Revision 1. Enclosure IV is a CD-ROM containing a spreadsheet version of the data documented in Tables 1 and 2 of Attachment 1 to LTR-LIS-15-11, Revision 1. As Enclosure I and IV contains information proprietary to Westinghouse Electric Company LLC, it is supported by an affidavit signed by Westinghouse Electric Company LLC, 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 of the Commission's regulations. Accordingly, it is respectfully requested that the information, which is proprietary to Westinghouse, be withheld from public disclosure in accordance with 2.390 of the Commission's regulations. This affidavit, along with Westinghouse authorization letter, CAW-15-4077, "Application for Withholding Proprietary Information from Public Disclosure," is contained in Enclosure Ill.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4156, or Mr. Steven R. Koenig at (620) 364-4041.
Sincerely, Jaime H. McCoyv JHM/rlt Attachment Enclosure I Attachment 1 to LTR-LIS-15-11, Revision 1, "Westinghouse Suggested Response to NRC Request for Additional Information (RAI) Regarding the Wolf Creek (SAP) ASTRUM Analysis - Proprietary" II Attachment 2 to LTR-LIS-15-11, Revision 1, "Westinghouse Suggested Response to NRC Request for Additional Information (RAI) Regarding the Wolf Creek (SAP) ASTRUM Analysis - Non- Proprietary" III CAW-15-4077, "Application for Withholding Proprietary Information from Public Disclosure" IV CD-ROM - Spreadsheet Version of Data Documented in Tables 1 and 2 of Attachment 1 to LTR-LIS-1 5-11, Revision 1 (Proprietary) cc: T. A. Conley (KDHE), w/a, w/e (Enclosure II only)
M. L. Dapas (NRC), w/a, w/e C. F. Lyon (NRC), w/a, w/e N. F. O'Keefe (NRC), w/a, w/e Senior Resident Inspector (NRC), w/a, w/e
ET 15-0002 Page 3 of 3 STATE OF KANSAS )
COUNTY OF COFFEY )
Jaime H. McCoy, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
Jaime H cCoy Vice Psident Engineering SUBSCRIBED and sworn to before me this 2/1 4day of iTOilCr./ f 2015.
I**GAYLE3OHEP.-- T-AP Notarygublic r Nc'iOarfj PullCr - ctf ziz-s cf Expiration Date __ /f5
Attachment to ET 15-0002 Page 1 of 3 Response to Request for Additional Information Reference 1 provided the Wolf Creek Nuclear Operating Corporation (WCNOC) application to revise the Wolf Creek Generating Station (WCGS) Technical Specifications (TS). Specification 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)," is revised to incorporate WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," to the list of analytical methods used to determine the core operating limits. The Reference 1 application was a plant specific best-estimate large break loss-of-coolant accident (LOCA) analysis that accounted for the effects of fuel thermal conductivity degradation (TCD). Reference 2 provided a request for additional information related to the application. The specific NRC question is provided in italics.
- 1. Please provide a table of the ASTRUM initial conditions, operating parameters, and results. Please also include PCT, Time of PCT, Fq, FdH, Cycle Bumup, RCS Tavg, Accumulator Temperature, Safety Injection Temperature, and Safety Injection Time. A data file is an acceptable and preferredformat.
Response: Enclosure I provides a table of the ASTRUM initial conditions, operating parameters and results. The table includes peak cladding temperature (PCT), Time of PCT, Fq, FdH, Cycle Burnup, Reactor Coolant System (RCS) Tavg, Accumulator Temperature, Safety Injection Temperature, and Safety Injection Time. Enclosure IV is a CD-ROM of the data.
SUPPLEMENTAL INFORMATION Provided below is supplemental information related to the plant specific best-estimate large break LOCA analysis that has been identified subsequent to the submittal of Reference 1.
Treatment of Burnup Effects
Background
While updating the FULL SPECTRUMTM LOCA (FSLOCATM ) Evaluation Model (Reference 3) analysis methodology to explicitly consider pellet TCD and fuel beyond the first cycle of irradiation, it was discovered that some approximations made in the WCGS plant specific adaptation of the ASTRUM methodology (References 1 and 4) to address TCD could introduce nonconservatisms. As described in Section 3.3 of Enclosure I of Reference 1, the statistically sampled time-in-cycle was translated into rod average burnups consistent with the NRC-approved ASTRUM methodology. For second-cycle fuel, the approach tends to over-estimate the actual rod burnups in the core. Because the peaking factors assumed in the analysis reduce as rod burnup increases (see Table 2 in Enclosure I of Reference 1), the analyzed rod power and local peaking could under-estimate the peaking factors of the rods at the sampled time-in-cycle.
Also, the treatment of gamma energy deposition assumes that the modeled hot assembly is surrounded by assemblies with power consistent with the core-average. However, second-cycle assemblies are often face-adjacent with feed assemblies, which can have power higher than the core-average. This can result in an over-estimation of the energy deposited away from the hot rod and hot assembly.
Attachment to ET 15-0002 Page 2 of 3 Affected Evaluation Model 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using ASTRUM (plant-specific adaptation for WCGS)
Estimated Effect The as-analyzed peaking factors for the cases in the WCGS analysis were compared to the peaking factors that would realistically bound the rods in the core at the statistically sampled time-in-cycle. It was confirmed that the analysis results remain applicable. Any non-conservatisms associated with the rod burnup and peaking factor approximations and the application of the gamma deposition model are offset by conservatisms in the assumed peaking factors such that the most limiting PCT results are unaffected.
Because the as-analyzed conditions (rod burnup and peaking factors) for the most limiting results in the analysis remain applicable, the estimated peak cladding temperature effect of these closely related issues is 0°F.
Errors in Decay Group Uncertainty Factors Back-ground Errors in the calculation of decay heat were discovered in the WCOBRA/TRAC code. The decay group uncertainty factors for each fissile isotope are provided in Table 8-14 of WCAP-16009-P-A. The uncertainty factors for 239pu were applied to 2 38U, and those for 238U were applied 239 to 239pu. This error causes an over-prediction of the uncertainty in decay power from pu and an under-prediction of the uncertainty in decay power from 23SU. Further, the decay group uncertainty factor for Decay Group 6 of 235U was erroneously coded as 2.5% instead of 2.25%. Correction of these errors impacts the application of the sampled decay heat uncertainty, which may result in small changes to the decay heat power. These issues have been evaluated to estimate the impact on Automated Statistical Treatment of Uncertainty Method (ASTRUM) Best-Estimate (BE) Large-Break Loss-of-Coolant Accident (LBLOCA) analysis results.
Affected Evaluation Model 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using ASTRUM Estimated Effect The issues described above were evaluated to account for the correction of these errors. The plant-specific sensitivity study resulted in an estimated PCT impact of -10°F for WCGS.
This change results in the following to the Table 1 results on page 3 of Attachment I of Reference 1.
Attachment to ET 15-0002 Page 3 of 3 Table I WCGS Best-Estimate Large Break LOCA Results 10 CFR 50.46 Requirement Value Criteria 95/95 Peak Cladding Temperature (OF) 1890 < 2200 95/95 Maximum Local Oxidation (%) 4.21 < 17 95/95 Core-Wide Oxidation (%) 0.1352 < 1
References:
- 1. WCNOC letter ET 14-0008, "Application for Amendment to Revise Specification 5.6.6, "CORE OPERATING LIMITS REPORT (COLR)," for Large Break Loss-of-Coolant Accident Analysis Methodology," February 26, 2014. ADAMS Accession No. ML14064A328
- 2. Electronic mail from C. F. Lyon, USNRC, to S. G. Wideman, WCNOC, "RE: Question on LAR to add ASTRUM to COLR (Wolf Creek TAC No. MF3518)," November 20, 2014.
ADAMS Accession No. ML14324A858
- 3. WCAP-16996-P, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA Methodology)," November 2010.
- 4. WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment Of Uncertainty Method (ASTRUM)," January 2005.
Enclosure II to ET 15-0002 to LTR-LIS-15-11, Revision 1, "Westinghouse Suggested Response to NRC Request for Additional Information (RAI) Regarding the Wolf Creek (SAP) ASTRUM Analysis - Non-Proprietary"
Westinghouse Non-Proprietary Class 3 Attachment 2 to LTR-LIS-15-11, Revision 1 Westinghouse Suggested Response to NRC Request for Additional Information (RAI) Regarding the Wolf Creek (SAP) ASTRUM Analysis - Non-Proprietary (11 Pages including Cover Page)
© 2015 Westinghouse Electric Company LLC All Rights Reserved
Westinghouse Non-Proprietary Class 3 to LTR-LIS-15-11, Revision 1 Page 2 of 11
- 1) Please provide a table of the ASTRUM initial conditions, operating parameters, and results. Please also include PCT, Time of PCT, Fq, FdH, Cycle Burnup, RCS Tavg, Accumulator Temperature, Safety Injection Temperature, and Safety Injection Time. A data file is an acceptable and preferred format [from Reference 1].
Table 1: Wolf Creek (SAP) Cycle 1 ASTRUM Runset Data Run Max HS HS Sl TAVG PRCS PACC VACC TACC TSI FQ FDH PBOT PMID Sampled Hot Rod PCT PCT Time Cycle Burnup Time Burnup
[°F] [s] [s] [*F] [psia] [psia] [ft3] [(F] [°F] [-] [-] [-] [-] [MWD/ [MWD/
MTU] MTU]
a,c
Westinghouse Non-Proprietary Class 3 to LTR-LIS-1 5-11, Revision 1 Page 3 of 11 Run Max HS HS SI TAVG PRCS PACC VACC TACC TSI FQ FDH PBOT PMID Sampled Hot Rod PCT PCT Time Cycle Burnup Time Burnup
[fFl Is] [s] [°F] [psia] [psia] [ft3] [°F] [*F] [-] [-] [-] -] [MWD/ (MWD/
MTU] MTU]
a,c
_ i I _ _ _ J_ _I _ I _ _ I _ I _ _
I- 4 4 F + 4 4 4 4 + 4 F 4 4 I- + 4 4 I 4 4 4 1 4- 4 I 4 1 F 4-- 4 4 4 + 4 4 4 4 + 4 F 4 4
+ 4 4 F + 4 4 4 1 + 4 4 4 F -I- 4 4 F 4 4 4 4 + 4 4 4 4
Westinghouse Non-Proprietary Class 3 to LTR-LIS-15-11, Revision 1 Page 4 of 11 Run Max HS HS SI TAVG PRCS PACC VACC TACC TSI FQ FDH PBOT PMID Sampled Hot Rod PCT PCT Time Cycle Burnup Time Burnup
[°F] [s] Es] ['F] [psia] [psia] [ft3] ['F] ['F] [-] [-] [-] [-] [MWD/ [MWD/
MTU] MTU]
a,c
Westinghouse Non-Proprietary Class 3 to LTR-LIS-15-11, Revision 1 Page 5 of 11 Run Max HS HS Sl TAVG PRCS PACC VACC TACC TSI FQ FDH PBOT PMID Sampled Hot Rod PCT PCT Time Cycle Burnup Time Burnup
[°F] [s] [s] [*F] (psia] [psia] [ft3] ['F] [0F] [-] [-] [-] [-] (MVVD/ [MWD/
MTU] MTU]
a,c
Westinghouse Non-Proprietary Class 3 to LTR-LIS-15-11, Revision 1 Page 6 of 11 Run Max HS HS Sl TAVG PRCS PACC VACC TACC TSI FQ FDH PBOT PMID Sampled Hot Rod PCT PCT Time Cycle Burnup Time Burnup
[*F] [s] [s] [(F] [psia] [psia] [ft3] [°F] [°F] [-] [-] H-] -] [MWD/ [MWD/
MTU] MTU]
a,c Notes:
- 1. Evaluations that were performed subsequent to the submittal in Reference 2 are not reflected in the tabulated data presented in this table (i.e., the evaluation of the treatment of burnup effects and the errors in decay group uncertainty factors.)
Westinghouse Non-Proprietary Class 3 Attachment 2 to LTR-LIS-1 5-11, Revision 1 Page 7 of 11 Table 2: Wolf Creek (SAP) Cycle 2 ASTRUM Runset Data HS Max HS PCT SI Cycle Hot Rod Run PCT Time Time TAVG PRCS PACC VACC TACC TSI FQ FDH PBOT PMID Burnup Burnup
[°F] Is] Is] [oF] [psia] [psia] fl [°F] ['F] [ - -] [MWD/
MTU] [MWD/
MTU]
[fL3]
a,c
__ __ __ J__ I___ I__ J
__ J
__ I __ It __ I__ I__ I__ I__
Westinghouse Non-Proprietary Class 3 to LTR-LIS-15-11, Revision 1 Page 8 of 11 HS Max HS POT SI Cycle Hot Rod Run PCT Time Time TAVG PRCS PACC VACC TACC TSI FQ FDH PBOT PMID Burnup Burnup
[MWD/ [MWD/
[°]s [] [*F] [psia] [psia] fl °][F - - - - MTU] MTU]
a,c
Westinghouse Non-Proprietary Class 3 to LTR-LIS-15-11, Revision 1 Page 9 of 11 HS Max HS PCT SI Cycle Hot Rod Run PCT Time Time TAVG PRCS PACC VACC TACC TSI FQ FDH PBOT PMID Burnup Burnup
[MWD/ [MWD/
(F] Is] Is] [*FL [psia3 [psia] f [F] [FL [-] MTU] MTU]
a,c
Westinghouse Non-Proprietary Class 3 to LTR-LIS-1 5-11, Revision 1 Page 10 of 11 HS Max HS PCT SI Cycle Hot Rod Run PCT Time Time TAVG PRCS PACC VACC TACC TSI FQ FDH PBOT PMID Burnup Burnup
[MWD/ [MWD/
[*F] Is] Is] [°F] [psia] [psia] [ *t][F] [°F] [-] [-] [-] [-] MTU] MTU]
a,c
Westinghouse Non-Proprietary Class 3 to LTR-LIS-15-11, Revision 1 Page 11 of 11 HS Max HS PCT SI Cycle Hot Rod Run PCT Time Time TAVG PRCS PACC VACC TACC TSl FQ FDH PBOT PMID Burnup Burnup WD/ [M W D /
[*F] Is) Is] ['Fl [psia] [psial _ 3_ _~ i[M[*F]
W- [*F] [-] [-] HL MTU] MTU a,c 4 4 4 4 4 4 + 4 4 4 + 4 4 4 +
1 4 4 4 4 4 4 4 1 4 +/- 4 4 4 4 4 4 4 I. 4 4 4 4 -I- I' 4 -
4 4 4 4 4 4 4 4 4 4 + 4 4 4 +
1 4 4 4 4 4 4 1 1 1 4. 4 4 4 4.
4 4 4 4 I. 4 4 4 4 -I- I- 4 4 4 4 4 4 4 4
Notes:
- 1. Evaluations that were performed subsequent to the submittal in Reference 2 are not reflected in the tabulated data presented in this table (i.e., the evaluation of the treatment of burnup effects and the errors in decay qroup uncertainty factors.)
References
- 1. Electronic mail from F. Lyon, USNRC, to S. G. Wideman, WCNOC, "RE: Question on LAR to add ASTRUM to COLR (Wolf Creek TAC No. MF3518),"
November 20, 2014. ADAMS Accession No. ML14324A858.
- 2. WCNOC letter ET 14-0008, "Application for Amendment to Revise Specification 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)," for Large Break Loss-of-Coolant Accident Analysis Methodology," February 26, 2014. ADAMS Accession No. ML14064A328.
Enclosure III to ET 15-0002 CAW-15-4077, "Application for Withholding Proprietary Information from Public Disclosure" (8 pages)
Westinghouse Westinghouse Electric Company Engineering, Equipment and Major Projects 1000 Westinghouse Drive, Building 3 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 Proj letter: SAP-15-4 Rev. I CAW-1 5-4077 January 15, 2015 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE Suibject: LTR-LIS- 15-11, Revision 1, Attachment 1, "Westinghouse Suggested Response to NRC Request for Additional Information (RAI) Regarding the Wolf Creek (SAP) ASTRUM Analysis" (Proprietary) and LTR-LIS-15-11, Revision 1, Attachment 3, "Electronic Data Tables Supporting the Westinghouse Suggested Response to NRC Request for Additional Information (RAI)
Regarding the Wolf Creek (SAP) ASTRUM Analysis" (Proprietary)
The proprietary information for which withholding is being requested in the above-referenced reports is further identified in Affidavit CAW-15-4077 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 Wolf Creek Nuclear Operation Corp (WCNOC).
Correspondence with respect to the proprietary aspects of the Application for Withholding or the Westinghouse Affidavit should reference CAW-1 5-4077, 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, james A. Gresham, Manager Regulatory Compliance
CAW-15-4077 January 15, 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, information, and belief.
J/ames A. Gresham, Manager Regulatory Compliance
2 CAW-15-4077 (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) 1am 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 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 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 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-15-4077 Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price information, production capacities, budget levels,, or commercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable.
(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 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-1 5-4077 (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.
(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 information sought to be withheld in this submittal is that which is appropriately marked in LTR-LIS-15-11, Revision 1, Attachment 1, "Westinghouse Suggested Response to NRC Request for Additional Information (RAI) Regarding the Wolf Creek (SAP) ASTRUM Analysis" and LTR-LIS-15-11, Revision 1, Attachment 3, "Electronic Data Tables Supporting the Westinghouse Suggested Response to NRC Request for Additional Information (RAI) Regarding the Wolf Creek (SAP) ASTRUM Analysis" (Proprietary) for submittal to the Commission, being transmitted by Wolf Creek Nuclear Operation Corp. (WCNOC) 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 the results of the Wolf Creek ASTRUM analysis, and may be used only for that purpose.
6 CAW-15-4077 (a) This information is part of that which will enable Westinghouse to:
(i) Provide input to Wolf Creek Nuclear Operation Corp. (WCNOC) to provide to the U.S. Nuclear Regulatory Commission in response to NRC Request for Additional Information related to the Wolf Creek ASTRUM submittal.
(ii) Provide licensing support for customer submittal.
(b) Further this information has substantial commercial value as follows:
(i) Westinghouse plans to sell the use of the information to its customers for the purpose of responding to NRC RAIs.
(ii) Westinghouse can sell support and defense of the technology to its customer in the licensing process.
(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 calculation results 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.
PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary versions of documents furnished to the NRC associated with the results of the Wolf Creek ASTRUM analysis, and may be used only for that purpose.
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.
Enclosure IV to ET 15-0002 CD-ROM - Spreadsheet Version of Data Documented in Tables 1 and 2 of Attachment I to LTR-LIS-15-11 (Proprietary)