|
---|
Category:Letter
MONTHYEARIR 05000483/20240032024-10-23023 October 2024 Integrated Inspection Report 05000483/2024003 IR 05000483/20240132024-10-21021 October 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000483/2024013 IR 05000483/20244012024-10-0909 October 2024 Material Control and Accounting Program Inspection Report 05000483/2024401 Public ULNRC-06901, Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (Letter)2024-10-0101 October 2024 Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (Letter) ML24247A3042024-09-11011 September 2024 Regulatory Audit Questions for License Renewal Commitments 34 and 35 (EPID L-2024-LRO-0009) - Non-Proprietary IR 05000483/20244032024-08-28028 August 2024 Security Baseline Inspection 05000483-2024-403 IR 05000483/20240052024-08-14014 August 2024 Updated Inspection Plan for Callaway Plant (Report 05000483/2024005) IR 05000483/20253012024-08-0505 August 2024 Notification of NRC Initial Operator Licensing Examination 05000483/2025301 ML24212A2822024-08-0202 August 2024 Regulatory Audit Summary Concerning Review of Request No. C3R-01 for Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections IR 05000483/20240022024-07-18018 July 2024 And Independent Spent Fuel Storage Installation Integrated Inspection Report 05000483/2024002 and 07201045/2024001 ML24185A1032024-07-16016 July 2024 2024 Biennial Problem Identification and Resolution Inspection Report ULNRC-06892, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00062024-06-26026 June 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0006 ULNRC-06891, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00052024-06-26026 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0005 ULNRC-06884, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00022024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0002 ULNRC-06886, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00042024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0004 ULNRC-06885, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00032024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0003 ML24144A0492024-06-11011 June 2024 Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval ML24158A5222024-06-0606 June 2024 Application to Revise Technical Specifications to Adopt Tstf-569, Rev. 2, Revise Response Time Testing Definition (LDCN 24-0008) ML24178A1132024-06-0606 June 2024 Ameren Missouris Intent to Adopt Revision 1 to Amendment 0 of Certificate of Compliance No. 1040 as Applicable to the ISFSI at the Callaway Plant Site ML24143A1632024-05-23023 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Storage Canister HGMPC0001 ULNRC-06882, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00122024-05-16016 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0012 ML24137A2342024-05-16016 May 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Canister HGMPC0011 ML24122A1502024-05-0707 May 2024 Audit Plan to Support Review of Steam Generator License Renewal Response to Commitment Nos 34 and 35 ULNRC-06877, Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 252024-05-0606 May 2024 Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 25 IR 05000483/20244022024-05-0606 May 2024 Security Baseline Inspection Report 05000483/2024402 (Full Report) IR 05000483/20240112024-05-0101 May 2024 NRC Post-Approval Site Inspection for License Renewal (Phase 2) Report 05000483/2024011 ULNRC-06856, CFR 50.59 and 10 CFR 72.48 Summary Report2024-05-0101 May 2024 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06869, Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report ML24122A1132024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radioactive Effluent Release Report ULNRC-06876, Registration of Dry Spent Fuel Storage Canister HGMPC00102024-04-25025 April 2024 Registration of Dry Spent Fuel Storage Canister HGMPC0010 ML24108A1082024-04-17017 April 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0009 ULNRC-06871, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00072024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0007 ULNRC-06872, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00082024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0008 ULNRC-06866, Submittal of Cycle 26 Commitment Change Summary Report2024-04-17017 April 2024 Submittal of Cycle 26 Commitment Change Summary Report IR 05000483/20240012024-04-16016 April 2024 Integrated Inspection Report 05000483/2024001 IR 05000483/20244042024-04-0909 April 2024 Cyber Security Inspection Report 05000483/2024404 ML24088A3212024-04-0101 April 2024 Notification of Commercial Grade Dedication Inspection (05000483/2024013) and Request for Information ML24086A5132024-03-26026 March 2024 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06863, Submittal of Annual Exposure Report for 20232024-03-20020 March 2024 Submittal of Annual Exposure Report for 2023 ML24079A1622024-03-19019 March 2024 Re Nuclear Property Insurance Reporting ML24066A1932024-03-0707 March 2024 2024 Callaway Plant Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ULNRC-06852, Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 262024-03-0505 March 2024 Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 26 IR 05000483/20230062024-02-28028 February 2024 Annual Assessment Letter for Callaway Plant Report 05000483/2023006 ML24052A3662024-02-26026 February 2024 Regulatory Audit Plan in Support of Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ULNRC-06858, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-02-21021 February 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation ML24036A1712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0079 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) IR 05000483/20230042024-01-19019 January 2024 – Integrated Inspection Report 05000483/2023004 ML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 2024-09-11
[Table view] Category:Report
MONTHYEARML24122C6372024-05-0101 May 2024 CFR 50.59 and 10 CFR 72.48 Summary Report November 24, 2022 to May 1 2024 ML24115A0992024-04-0101 April 2024 EIP-ZZ-A0066, Rev 30, RERP Training Program ML24086A5142024-03-26026 March 2024 Changes to the Westinghouse and Framatome ECCS Evaluation Models and PCT Penalty Assessments ULNRC-06861, Westinghouse and Framatome, ECCS Evaluation Model Margin Assessments2024-03-26026 March 2024 Westinghouse and Framatome, ECCS Evaluation Model Margin Assessments ML24065A2992024-03-0505 March 2024 Enclosure - Callaway Nuclear Plant: Form Oar-1 Owners Activity Report ULNRC-06849, Cracking Assessment for Framatome RSG Channel Head Assembly2023-12-20020 December 2023 Cracking Assessment for Framatome RSG Channel Head Assembly ML23215A1992023-08-31031 August 2023 ANP-4012NP, Callaway, Unit 1, Rod Ejection Accident Analysis Revision 2, August 2023 ML23299A1982023-06-16016 June 2023 Enclosure 2: Callaway RR Tech Report Containment Post-Tensioning System Inservice Inspection Technical Report Basis for Proposed Extension of Examination Interval, Revision 0 ML23156A6712023-06-0505 June 2023 Description and Justification for Changes ML23150A1832023-05-30030 May 2023 EIP-ZZ-00240 Addendum E, Revision 027, Health Physics Coordinator (Hpc) Checklist Administrative Correction ML23150A1842023-05-18018 May 2023 EIP-ZZ-00240 Addendum E, Revision 027, Health Physics Coordinator (Hpc) Checklist ML23150A1892023-05-18018 May 2023 EIP-ZZ-00245 Addendum H, Revision 004, Security Coordinator Checklist for the Alternate Tsc/Osa Assembly Area ML23131A3882023-04-26026 April 2023 EIP-ZZ-PRO2O Minor Revision 54, Activation and Operation of the Joint Information Center - Procedure Review Form and 50.54(q) Screening Form ML23110A0712023-04-0606 April 2023 Procedure Review Form (PRF) for EIP-ZZ-A0066, Revision 28, RERP Training Program ML24115A1002023-03-26026 March 2023 EIP-ZZ-PRO2O, Rev. 55, Activation and Operation of the Joint Information Center ML23068A0992023-03-0909 March 2023 Special Report 2023-01 PAM Report ULNRC-06796, Enclosure 7 - Holtec International Report HI-2230125, Revision 0, Supplemental Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station, Revision 0, Dated February 14, 20232023-02-14014 February 2023 Enclosure 7 - Holtec International Report HI-2230125, Revision 0, Supplemental Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station, Revision 0, Dated February 14, 2023 ML22349A6272022-12-15015 December 2022 Enclosure 3 - 2022 Proxy Statement of Ameren Corporation ML22349A6322022-12-15015 December 2022 Enclosure 8 - 10-K Filed 02/23/2022 ML22349A6342022-12-15015 December 2022 Enclosure 9 - 10-Q Filed 03/31/2022 ML22349A6352022-12-15015 December 2022 Enclosure 10 - 10-Q Filed 06/30/2022 ML22349A6362022-12-15015 December 2022 Enclosure 11 - 10-Q Filed 09/30/2022 ML22349A6402022-12-15015 December 2022 Enclosure 14 - Schedule 14C Information for Union Electric Company March 2022 ML22327A2242022-11-23023 November 2022 Enclosure 1: Callaway Plant - Report Period: 10 CFR 50.59 and 10 CFR 72.48 Summary Report June 16, 2021 to November 23, 2022 ML22335A5012022-11-16016 November 2022 Enclosure 3: ANP-4012NP, Revision 1, Callaway Rod Ejection Accident Analysis ML22318A1902022-11-14014 November 2022 Enclosure 2 - Pressurized Water Reactor Owners Group Letter, OG-22-187, Subject: PWR Owners Group Mode 4 LOCA Analysis for Westinghouse NSSS Plants ULNRC-06774, HI-2220020, Revision 2, Non Proprietary Version of Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station2022-10-21021 October 2022 HI-2220020, Revision 2, Non Proprietary Version of Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station ULNRC-06768, Attachment 8 to Enclosure 1: ANP-3969NP, Callaway Non-LOCA Summary Report, Revision 2, Dated October 20222022-10-12012 October 2022 Attachment 8 to Enclosure 1: ANP-3969NP, Callaway Non-LOCA Summary Report, Revision 2, Dated October 2022 ML22285A1222022-10-12012 October 2022 Attachment 5 to Enclosure 1: ANP-3947NP, Callaway Unit 1 License Amendment Request Inputs for Use of Framatome Fuel, Revision 3, Dated October 2022 ML22285A1232022-10-12012 October 2022 Attachment 6 to Enclosure 1: ANP-3944NP, Callaway Realistic Large Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22285A1242022-10-12012 October 2022 Attachment 7 to Enclosure 1: ANP-3943NP, Callaway Small Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22181B1362022-06-30030 June 2022 Attachment 6 - Replacement for Attachment 6, Description and Assessment Specific to TSTF-439, of ULNRC-06688 ML22181B1402022-06-30030 June 2022 Enclosure 1 - Replacement for Enclosure 1, List of Revised Required Actions to Corresponding PRA Functions, of ULNRC-06688 ML22181B1412022-06-30030 June 2022 Enclosure 4 - Replacement for Enclosure 4, Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models, of ULNRC-06688 ULNRC-06729, Attachment 8 - Non-Proprietary Version of Non-LOCA Summary Report2022-06-0202 June 2022 Attachment 8 - Non-Proprietary Version of Non-LOCA Summary Report ML22153A1822022-06-0202 June 2022 Attachment 6 - Non-Proprietary Version of Rlbloca Summary Report ML22153A1832022-06-0202 June 2022 Attachment 7 - Non-Proprietary Version of SBLOCA Summary Report ML22027A8082022-01-27027 January 2022 Enclosure 3: Callaway, Unit 1, Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ML22027A8092022-01-27027 January 2022 Enclosure 4: Callaway, Unit 1, Acronyms and Definitions ML22027A8062022-01-27027 January 2022 Enclosure 1: Request for Exemptions for Risk-Informed Approach to Resolution for Generic Letter 2004-02 ML21356B5072021-12-22022 December 2021 Enclosure 1: Mark-up of Operating License (OL) ML21356B5082021-12-22022 December 2021 Enclosure 2: Clean Copy of Affected OL Pages (Reflecting Proposed Change) ML21343A0952021-12-0909 December 2021 Attachment 1: Description and Assessment ML21335A1602021-12-0101 December 2021 Special Report 2021-02: Accident Monitoring Instrumentation Non-Functional for Greater than 7 Days ML21280A3802021-10-0707 October 2021 Cumulative Summary of Changes to Enclosure 2, License Amendment Request, and Enclosure 3, Callaway Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02, of ULNRC-06526 ML21280A3812021-10-0707 October 2021 License Amendment Request for Risk-Informed Approach to Resolution of Generic Letter 2004-02 ML21272A1702021-09-28028 September 2021 Enclosure 2 - Full Scope Implementation of Alternative Source Term Evaluation of Proposed Changes (Redacted) ML21237A1372021-08-23023 August 2021 Enclosure 1: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - Baseline Weld Input ML21237A1382021-08-23023 August 2021 Enclosure 2: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Critical Breaks) ULNRC-06683, Enclosure 3: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Non-Isolable Breaks)2021-08-23023 August 2021 Enclosure 3: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Non-Isolable Breaks) 2024-05-01
[Table view] Category:Technical
MONTHYEARML24122C6372024-05-0101 May 2024 CFR 50.59 and 10 CFR 72.48 Summary Report November 24, 2022 to May 1 2024 ML24065A2992024-03-0505 March 2024 Enclosure - Callaway Nuclear Plant: Form Oar-1 Owners Activity Report ULNRC-06849, Cracking Assessment for Framatome RSG Channel Head Assembly2023-12-20020 December 2023 Cracking Assessment for Framatome RSG Channel Head Assembly ML23215A1992023-08-31031 August 2023 ANP-4012NP, Callaway, Unit 1, Rod Ejection Accident Analysis Revision 2, August 2023 ML23299A1982023-06-16016 June 2023 Enclosure 2: Callaway RR Tech Report Containment Post-Tensioning System Inservice Inspection Technical Report Basis for Proposed Extension of Examination Interval, Revision 0 ML23150A1892023-05-18018 May 2023 EIP-ZZ-00245 Addendum H, Revision 004, Security Coordinator Checklist for the Alternate Tsc/Osa Assembly Area ML23110A0712023-04-0606 April 2023 Procedure Review Form (PRF) for EIP-ZZ-A0066, Revision 28, RERP Training Program ULNRC-06796, Enclosure 7 - Holtec International Report HI-2230125, Revision 0, Supplemental Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station, Revision 0, Dated February 14, 20232023-02-14014 February 2023 Enclosure 7 - Holtec International Report HI-2230125, Revision 0, Supplemental Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station, Revision 0, Dated February 14, 2023 ML22349A6322022-12-15015 December 2022 Enclosure 8 - 10-K Filed 02/23/2022 ML22349A6272022-12-15015 December 2022 Enclosure 3 - 2022 Proxy Statement of Ameren Corporation ML22349A6362022-12-15015 December 2022 Enclosure 11 - 10-Q Filed 09/30/2022 ML22349A6342022-12-15015 December 2022 Enclosure 9 - 10-Q Filed 03/31/2022 ML22349A6402022-12-15015 December 2022 Enclosure 14 - Schedule 14C Information for Union Electric Company March 2022 ML22349A6352022-12-15015 December 2022 Enclosure 10 - 10-Q Filed 06/30/2022 ML22327A2242022-11-23023 November 2022 Enclosure 1: Callaway Plant - Report Period: 10 CFR 50.59 and 10 CFR 72.48 Summary Report June 16, 2021 to November 23, 2022 ML22335A5012022-11-16016 November 2022 Enclosure 3: ANP-4012NP, Revision 1, Callaway Rod Ejection Accident Analysis ML22318A1902022-11-14014 November 2022 Enclosure 2 - Pressurized Water Reactor Owners Group Letter, OG-22-187, Subject: PWR Owners Group Mode 4 LOCA Analysis for Westinghouse NSSS Plants ULNRC-06774, HI-2220020, Revision 2, Non Proprietary Version of Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station2022-10-21021 October 2022 HI-2220020, Revision 2, Non Proprietary Version of Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station ULNRC-06768, Attachment 8 to Enclosure 1: ANP-3969NP, Callaway Non-LOCA Summary Report, Revision 2, Dated October 20222022-10-12012 October 2022 Attachment 8 to Enclosure 1: ANP-3969NP, Callaway Non-LOCA Summary Report, Revision 2, Dated October 2022 ML22285A1242022-10-12012 October 2022 Attachment 7 to Enclosure 1: ANP-3943NP, Callaway Small Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22285A1232022-10-12012 October 2022 Attachment 6 to Enclosure 1: ANP-3944NP, Callaway Realistic Large Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22285A1222022-10-12012 October 2022 Attachment 5 to Enclosure 1: ANP-3947NP, Callaway Unit 1 License Amendment Request Inputs for Use of Framatome Fuel, Revision 3, Dated October 2022 ML22181B1412022-06-30030 June 2022 Enclosure 4 - Replacement for Enclosure 4, Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models, of ULNRC-06688 ML22181B1402022-06-30030 June 2022 Enclosure 1 - Replacement for Enclosure 1, List of Revised Required Actions to Corresponding PRA Functions, of ULNRC-06688 ML22181B1362022-06-30030 June 2022 Attachment 6 - Replacement for Attachment 6, Description and Assessment Specific to TSTF-439, of ULNRC-06688 ULNRC-06729, Attachment 8 - Non-Proprietary Version of Non-LOCA Summary Report2022-06-0202 June 2022 Attachment 8 - Non-Proprietary Version of Non-LOCA Summary Report ML22153A1822022-06-0202 June 2022 Attachment 6 - Non-Proprietary Version of Rlbloca Summary Report ML22153A1832022-06-0202 June 2022 Attachment 7 - Non-Proprietary Version of SBLOCA Summary Report ML22027A8082022-01-27027 January 2022 Enclosure 3: Callaway, Unit 1, Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ML21272A1702021-09-28028 September 2021 Enclosure 2 - Full Scope Implementation of Alternative Source Term Evaluation of Proposed Changes (Redacted) ULNRC-06683, Enclosure 3: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Non-Isolable Breaks)2021-08-23023 August 2021 Enclosure 3: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Non-Isolable Breaks) ML21237A1382021-08-23023 August 2021 Enclosure 2: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Critical Breaks) ML21237A1372021-08-23023 August 2021 Enclosure 1: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - Baseline Weld Input ULNRC-06526, Methodology for a Risk-Informed Approach to Address Generic Letter 2004-022021-07-22022 July 2021 Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ULNRC-06660, Cycle 24 Commitment Change Summary Report2021-06-22022 June 2021 Cycle 24 Commitment Change Summary Report ML21090A1882021-03-31031 March 2021 Enclosure 3 - Callaway Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ML21090A2502021-03-31031 March 2021 Attachment 1 - Changes to the Westinghouse ECCS Evaluation Model and PCT Penalty Assessments ML20178A6712020-06-26026 June 2020 Attachment 1 - Discussion of Change ML20178A6732020-06-26026 June 2020 Attachment 3 - Callaway Unit 1, Steam Generator Operational Assessment to Support Deferral of Planned Inspections from 1R24 to 1R25, Revision 1 (Redacted) ULNRC-06571, 10 CFR 50.46 Annual Report, ECCS Evaluation Model Revisions2020-03-31031 March 2020 10 CFR 50.46 Annual Report, ECCS Evaluation Model Revisions ML20070R1212020-03-10010 March 2020 Technical Specification Page Markup ML20070R1142020-03-10010 March 2020 Description and Assessment of the Proposed Change ULNRC-06534, RERP Appendix J, Revision 005 Callaway Plant On-Shift Staffing Analysis Report2019-09-26026 September 2019 RERP Appendix J, Revision 005 Callaway Plant On-Shift Staffing Analysis Report ML19024A4742019-01-23023 January 2019 Attachment 4 - FSAR Technical Requirements I 6.7.13 ML18208A1682018-06-19019 June 2018 Revised Site Addendum Item - Chapter 10, Steam and Power Conversion System ML18208A1672018-06-19019 June 2018 Revised Site Addendum Item - Chapter 9.0, Auxiliary Systems ML18208A1662018-06-19019 June 2018 Revised Site Addendum Item - Chapter 9.0, Figures ML18208A1652018-06-19019 June 2018 Revised Site Addendum Item - Chapter 8.0, Electric Power ML18208A1642018-06-19019 June 2018 Revised Site Addendum Item - Chapter 8.0, Figures ML18208A1632018-06-19019 June 2018 Revised Site Addendum Item - Chapter 4.0, Reactor 2024-05-01
[Table view] |
Text
)Westinghouse W estin houseWestinghouse Electric Company Nuclear Services P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA U.S. Nuclear Regulatory Commission Direct tel: (412) 374-4419 Document Control Desk Direct fax: (412) 374-4011 Washington, DC 20555-0001 e-mail: maurerbf@westinghouse.com Our ref: LTR-NRC-07-24 April 26, 2007
Subject:
SER Compliance with WCAP-16260-P-A "The Spatially Corrected Inverse Count Rate (SCICR)
Method for Subcritical Reactivity Measurement" (Proprietary/Non-Proprietary)
Enclosed are copies of the Proprietary/Non-Proprietary SER Compliance with WCAP-16260-P-A "The Spatially Corrected Inverse Count Rate (SCICR) Method for Subcritical Reactivity Measurement."
Per SER Limitations and Conditions documented in the NRC's SER for WCAP-16260, Limitation and Condition # 2 specifies the following:
"2. Reactivity-sensitivity analyses must be conducted and submitted to the NRC staff for review/audit on a plant-specific basis to predetermine the masking effect (biases) so that they can be accounted for in SCICR applications to the plant."
The first application of this methodology for Callaway Unit 1 is planned for Cycle 16. Enclosed are the reactivity-sensitivity analyses to determine the masking effect presented in the topical bound that of Callaway Unit 1.
Also enclosed is:
- 1. One (1) copy of the Application for Withholding, AW-07-2274 (Non-Proprietary) with Proprietary Information Notice.
- 2. One (1) copy of Affidavit (Non-Proprietary).
This submittal contains proprietary information of Westinghouse Electric Company LLC. In conformance with the requirements of 10 CFR Section 2.390, as amended, of the Commission's regulations, we are enclosing with this submittal an Application for Withholding from Public Disclosure and an affidavit. The affidavit sets forth the basis on which the information identified as proprietary may be withheld from public disclosure by the Commission.
Correspondence with respect to this affidavit or Application for Withholding should reference AW-07-2274 and should be addressed to B. F. Maurer, Acting Manager, Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.
Very truly yours, B. F. Maurer, Acting Manager Regulatory Compliance and Plant Licensing Enclosures cc: A. Mendiola, NRR A. Attard, NRR J. Thompson, NRR H. Cruz, NRR L. M. Feizollahi, NRR AmerenUE c/o Callaway Unit 1 TDGc7
Westinghouse Electric Company Nuclear Services P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA U.S. Nuclear Regulatory Commission Direct tel: 412/374-4419 ATTN: Document Control Desk Direct fax: 412/374-4011 Washington, DC 20555 e-mail: maurerbf@westinghouse.com Our ref: AW-07-2274 April 26, 2007 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
LTR-NRC-07-24 P-Attachment, SER Compliance with WCAP-16260-P-A "The Spatially Corrected Inverse Count Rate (SCICR) Method for Subcritical Reactivity Measurement" (Proprietary)
The application for withholding is submitted by Westinghouse Electric Company LLC (Westinghouse) pursuant to the provisions of paragraph (b)(1) of Section 2.390 of the Commission's regulations. It contains commercial strategic information proprietary to Westinghouse and customarily held in confidence.
The proprietary material for which withholding is being requested is identified in the proprietary version of the subject report. In conformance with 10 CFR Section 2.390, Affidavit AW-07-2274 accompanies this application for withholding, setting forth the basis on which the identified proprietary information may be withheld from public disclosure.
Accordingly, it is respectfully requested that the subject 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 this application for withholding or the accompanying affidavit should reference AW-07-2274 and should be addressed to B. F. Maurer, Acting Manager of Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, P. 0. Box 355, Pittsburgh, Pennsylvania 15230-0355.
Very truly yours, B. F. Maurer, Acting Manager Regulatory Compliance and Plant Licensing cc: A. Mendiola, NRR A. Attard, NRR J. Thompson, NRR H. Cruz, NRR L. M. Feizollahi, NRR AmerenUE c/o Callaway Unit 1
AW-07-2274 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
sS COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared B. F. Maurer, 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:
B. F. Maurer, Acting Manager Regulatory Compliance and Plant Licensing Sworn to and subscribed
./
before me this
- day of ' 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 AW-07-2274 (1) I am Acting Manager, Regulatory Compliance and Plant Licensing, in Nuclear Services, Westinghouse Electric Company LLC (Westinghouse) and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rulemaking proceedings, and am authorized to apply for its withholding on behalf of Westinghouse.
(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 of the Commission's regulations and in conjunction with the Westinghouse "Application for Withholding" 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 constitutes Westinghouse policy and provides the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(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.
3 AW-07-2274 (d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable.
There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
b) It is information which is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.
c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
(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.
4 AW-07-2274 (v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in LTR-NRC-07-24 P-Attachment, SER Compliance with WCAP-16260-P-A "The Spatially Corrected Inverse Count Rate (SCICR) Method for Subcritical Reactivity Measurement,"
(Proprietary), for submittal to the Commission, being transmitted by Westinghouse letter (LTR- NRC-07-24) and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted by Westinghouse Electric Company is for NRC review/audit.
This information is part of that which will enable Westinghouse to:
(a) Demonstrate the applicability of the SCICR Methodology for a specific plant.
(b) Assist customers in implementing an improved measurement technique.
Further this information has substantial commercial value as follows:
(a) Westinghouse can use this methodology to further enhance their licensing position over their competitors.
(b) Assist customers to obtain license changes.
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 methodology 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.
Westinghouse Non-Proprietary Class 3 LTR-NRC-07-24 NP-Attachment SER Compliance with WCAP-16260-P-A "The Spatially Corrected Inverse Count Rate (SCICR)
Method for Subcritical Reactivity Measurement" (Non-Proprietary)
Westinghouse Electric Company P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355
© 2007 Westinghouse Electric Company LLC All Rights Reserved Page 1 of 2
Westinghouse Non-Proprietary Class 3 Reactivity-Sensitivity Analyses of SCICR Application at Callaway Unit 1 The first application of the spatially corrected inverse count rate (SCICR) method for subcritical reactivity measurement is planned for initial application at Callaway Unit 1. This method of reactivity measurement is described in the approved Westinghouse Topical Report WCAP-16260-P-A. The final safety evaluation performed by the NRC staff (TAC No. MC3065) included the condition that reactivity-sensitivity analyses must be conducted and submitted to the NRC staff for review/audit on a plant-specific basis to predetermine any masking effect (biases) in the SCICR applications at each plant.
The sensitivity calculations were performed in the same manner as described in Section 5.3 of WCAP-16260-P-A. The results of the core reactivity bias and control rod constant bias cases are presented below. These are equivalent to Tables 5-2 and 5-4 of WCAP-16260-P-A.
Callaway Unit 1 Quality of the SCICR Line Fit in the Simulated Cases With Core Reactivity and Control Rod Constants Biases (RMS = Root Mean Squared, pcm = 10-5) a, c The reactivity-sensitivity results for Callaway Unit 1 exhibit similar trends as those presented in WCAP-16260-P-A for the applicable plant/core type. Therefore, it is concluded that the sensitivity of the SCICR methodology to a core reactivity bias is very small or conservative and non-masking for Callaway Unit 1. [
]a, c.
LTR-NRC-07-24 NP-Attachment Page 2 of 2