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Category:Letter type:ULNRC
MONTHYEARULNRC-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 ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023 Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak ULNRC-06223, Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)2023-07-25025 July 2023 Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004) ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023 Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) ULNRC-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023 Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023 Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate . ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023 Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06812, Submittal of 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ULNRC-06806, Submittal of Radiological Emergency Response Plan, Revision 552023-04-12012 April 2023 Submittal of Radiological Emergency Response Plan, Revision 55 ULNRC-06807, Submittal of Single Positive Test Forms2023-04-0303 April 2023 Submittal of Single Positive Test Forms ULNRC-06798, Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan2023-03-30030 March 2023 Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan ULNRC-06801, CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions2023-03-30030 March 2023 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06804, Submittal of Nuclear Property Insurance Reporting2023-03-29029 March 2023 Submittal of Nuclear Property Insurance Reporting ULNRC-06751, Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control2023-03-29029 March 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control ULNRC-06803, Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection2023-03-29029 March 2023 Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection ULNRC-06805, Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days2023-03-21021 March 2023 Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days ULNRC-06802, Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument2023-03-0909 March 2023 Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument ULNRC-06795, Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms2023-01-24024 January 2023 Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms ULNRC-06794, Submittal of Fitness for Duty Program Data for 20222023-01-24024 January 2023 Submittal of Fitness for Duty Program Data for 2022 ULNRC-06787, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-12-0808 December 2022 Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06781, License Amendment Request 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 (LDCN 22-0029)2022-12-0101 December 2022 License Amendment Request 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 (LDCN 22-0029) ULNRC-06780, Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-0072022-11-30030 November 2022 Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-007 ULNRC-06772, 10 CFR 50.59 and 10 CFR 72.48 Summary Report2022-11-23023 November 2022 10 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06777, Operating Quality Assurance Manual (Oqam) Revision 362022-11-16016 November 2022 Operating Quality Assurance Manual (Oqam) Revision 36 ULNRC-06779, ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves2022-11-14014 November 2022 ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves ULNRC-06765, License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Testing Frequencies (LDCN 2020-0004)2022-11-0303 November 2022 License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Testing Frequencies (LDCN 2020-0004) ULNRC-06773, Results of Steam Generator Tube In-Service Inspection2022-11-0101 November 2022 Results of Steam Generator Tube In-Service Inspection ULNRC-06775, Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days2022-10-27027 October 2022 Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days ULNRC-06771, Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013)2022-10-25025 October 2022 Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013) ULNRC-06770, Cycle 25 Commitment Change Summary Report2022-10-19019 October 2022 Cycle 25 Commitment Change Summary Report ULNRC-06766, Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014)2022-09-0808 September 2022 Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014) ULNRC-06767, Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies2022-09-0606 September 2022 Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies ULNRC-06764, Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-09-0101 September 2022 Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06763, Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013)2022-09-0101 September 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013) ULNRC-06762, Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 252022-08-25025 August 2022 Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 25 ULNRC-06758, Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002)2022-08-0404 August 2022 Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002) ULNRC-06755, Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals2022-07-13013 July 2022 Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ULNRC-06754, Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications2022-07-0505 July 2022 Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ULNRC-06739, Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007)2022-06-30030 June 2022 Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007) ULNRC-06752, Evacuation Time Estimates Report2022-06-27027 June 2022 Evacuation Time Estimates Report ULNRC-06753, Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis2022-06-23023 June 2022 Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis ULNRC-06750, Submittal of Cycle 26 Core Operating Limits Report (COLR)2022-06-13013 June 2022 Submittal of Cycle 26 Core Operating Limits Report (COLR) ULNRC-06735, Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014).2022-05-27027 May 2022 Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014). 2024-01-29
[Table view] Category:Report
MONTHYEARML23354A2462023-12-20020 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 ML23068A0992023-03-0909 March 2023 Special Report 2023-01 PAM Report ML23052A0492023-02-14014 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 ML22299A2352022-10-21021 October 2022 HI-2220020, Revision 2, Non Proprietary Version of Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station ML22285A1252022-10-12012 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 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 ML22153A1852022-06-0202 June 2022 Attachment 8 - Non-Proprietary Version of Non-LOCA Summary Report ULNRC-06715, Enclosure 3: Attachment a to the NPDES Permit Modification Application2022-03-0101 March 2022 Enclosure 3: Attachment a to the NPDES Permit Modification Application ML22027A8092022-01-27027 January 2022 Enclosure 4: Callaway, Unit 1, Acronyms and Definitions ML22027A8082022-01-27027 January 2022 Enclosure 3: Callaway, Unit 1, Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 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) 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 ML21173A3412021-06-22022 June 2021 CFR 50.59 and 10 CFR 72.48 Summary Report - May 16, 2019 to June 15, 2021 ML21090A2502021-03-31031 March 2021 Attachment 1 - Changes to the Westinghouse ECCS Evaluation Model and PCT Penalty Assessments ML21090A1882021-03-31031 March 2021 Enclosure 3 - Callaway Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 2023-08-31
[Table view] Category:Miscellaneous
MONTHYEARML23156A6712023-06-0505 June 2023 Description and Justification for Changes 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 ML23068A0992023-03-0909 March 2023 Special Report 2023-01 PAM Report ULNRC-06715, Enclosure 3: Attachment a to the NPDES Permit Modification Application2022-03-0101 March 2022 Enclosure 3: Attachment a to the NPDES Permit Modification Application ML22027A8062022-01-27027 January 2022 Enclosure 1: Request for Exemptions for Risk-Informed Approach to Resolution for Generic Letter 2004-02 ML22027A8092022-01-27027 January 2022 Enclosure 4: Callaway, Unit 1, Acronyms and Definitions 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 ML21173A3412021-06-22022 June 2021 CFR 50.59 and 10 CFR 72.48 Summary Report - May 16, 2019 to June 15, 2021 ULNRC-06437, Cycle 22 Commitment Change Summary Report2018-06-0707 June 2018 Cycle 22 Commitment Change Summary Report ULNRC-06349, Callaway, Unit 1 - Enclosure 2 to ULNRC-06349 - Minimum Decommissioning Cost - Per 10 CFR 50.75 Formula Process2017-03-30030 March 2017 Callaway, Unit 1 - Enclosure 2 to ULNRC-06349 - Minimum Decommissioning Cost - Per 10 CFR 50.75 Formula Process ML17097A5582017-03-30030 March 2017 Enclosure 2 to ULNRC-06349 - Minimum Decommissioning Cost - Per 10 CFR 50.75 Formula Process ML16160A0952016-06-0808 June 2016 ASP ANALYSIS-REJECT- Callaway Unit 1 Auxiliary Feedwater Control Valves in Motor Driven Pump Train Inoperable due to Faulty Electric positioner Cards (LER 483-2015-003 and 483-2015-004) ULNRC-06292, Transmittal of 10 CFR50.46 Annual Report ECCS Evaluation Model Revisions2016-03-30030 March 2016 Transmittal of 10 CFR50.46 Annual Report ECCS Evaluation Model Revisions ULNRC-06199, Nuclear Property Insurance Reporting2015-03-18018 March 2015 Nuclear Property Insurance Reporting ULNRC-06173, Submits Owner'S Activity Reports (OAR-1 Forms) for Cycle 20 and Refuel 202015-02-19019 February 2015 Submits Owner'S Activity Reports (OAR-1 Forms) for Cycle 20 and Refuel 20 ML14310A8362015-02-0909 February 2015 NRC Staff Evaluation of Final Rule for Continued Storage of Spent Nuclear Fuel for the License Renewal Environmental Review for Callaway, Unit 1 ULNRC-06168, Enclosure 10 - Articles of Incorporation Ameren Corporation Restated 10/17/19952014-12-18018 December 2014 Enclosure 10 - Articles of Incorporation Ameren Corporation Restated 10/17/1995 ULNRC-06168, Enclosure 7 - 10-Q Filed Period 6/30/2014 Ameren2014-12-18018 December 2014 Enclosure 7 - 10-Q Filed Period 6/30/2014 Ameren ULNRC-06168, Enclosure 16 - Articles of Incorporation - Union Electric Company Restated 04/12/19942014-12-18018 December 2014 Enclosure 16 - Articles of Incorporation - Union Electric Company Restated 04/12/1994 ULNRC-06168, Enclosure 5 - 10-K Filed Period 12/31/2013 - Ameren2014-12-18018 December 2014 Enclosure 5 - 10-K Filed Period 12/31/2013 - Ameren ULNRC-06168, Enclosure 8 - 10-Q Filed Period 9/30/2014 Ameren2014-12-18018 December 2014 Enclosure 8 - 10-Q Filed Period 9/30/2014 Ameren ULNRC-06168, Enclosure 9 - Articles of Incorporation Ameren Corporation Dated 08/07/19952014-12-18018 December 2014 Enclosure 9 - Articles of Incorporation Ameren Corporation Dated 08/07/1995 ULNRC-06168, Enclosure 14 - Defc 14c Filed Period 3/11/2014 - Union Electric2014-12-18018 December 2014 Enclosure 14 - Defc 14c Filed Period 3/11/2014 - Union Electric ULNRC-06168, Enclosure 6 - 10-Q Filed Period 3/31/2014 - Ameren2014-12-18018 December 2014 Enclosure 6 - 10-Q Filed Period 3/31/2014 - Ameren ULNRC-06168, Enclosure 11 - Ameren Corporation By-Laws Effective 12/14/20122014-12-18018 December 2014 Enclosure 11 - Ameren Corporation By-Laws Effective 12/14/2012 ULNRC-06168, Enclosure 15 - Articles of Incorporation - Missouri Electric Light and Power Company Dated 11/20/19222014-12-18018 December 2014 Enclosure 15 - Articles of Incorporation - Missouri Electric Light and Power Company Dated 11/20/1922 ULNRC-06168, Enclosure 4 - 2013 Annual Report (Includes 2013 Form 10-K) - Ameren2014-12-18018 December 2014 Enclosure 4 - 2013 Annual Report (Includes 2013 Form 10-K) - Ameren ULNRC-06168, Enclosure 17 - By-Laws of Union Electric Company as Amended to 12/10/20102014-12-18018 December 2014 Enclosure 17 - By-Laws of Union Electric Company as Amended to 12/10/2010 ML14352A4292014-12-18018 December 2014 Enclosure 15 - Articles of Incorporation - Missouri Electric Light and Power Company Dated 11/20/1922 ML14352A4302014-12-18018 December 2014 Enclosure 17 - By-Laws of Union Electric Company as Amended to 12/10/2010 ML14352A4472014-12-18018 December 2014 Enclosure 3 - 2014 Proxy Statement of Ameren Corporation - Ameren ML14352A4322014-12-18018 December 2014 Enclosure 16 - Articles of Incorporation - Union Electric Company Restated 04/12/1994 ML14352A4332014-12-18018 December 2014 Enclosure 4 - 2013 Annual Report (Includes 2013 Form 10-K) - Ameren ML14352A4342014-12-18018 December 2014 Enclosure 11 - Ameren Corporation By-Laws Effective 12/14/2012 ML14352A4352014-12-18018 December 2014 Enclosure 6 - 10-Q Filed Period 3/31/2014 - Ameren ML14352A4362014-12-18018 December 2014 Enclosure 14 - Defc 14c Filed Period 3/11/2014 - Union Electric ML14352A4382014-12-18018 December 2014 Enclosure 9 - Articles of Incorporation Ameren Corporation Dated 08/07/1995 ML14352A4392014-12-18018 December 2014 Enclosure 8 - 10-Q Filed Period 9/30/2014 Ameren ML14352A4402014-12-18018 December 2014 Enclosure 5 - 10-K Filed Period 12/31/2013 - Ameren ML14352A4412014-12-18018 December 2014 Enclosure 7 - 10-Q Filed Period 6/30/2014 Ameren ML14352A4432014-12-18018 December 2014 Enclosure 10 - Articles of Incorporation Ameren Corporation Restated 10/17/1995 ULNRC-06157, Special Report 2014-04: Inoperability of a Seismic Instrument for Greater than 30 Days2014-11-14014 November 2014 Special Report 2014-04: Inoperability of a Seismic Instrument for Greater than 30 Days ML14290A5322014-10-29029 October 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood -Causing Mechanism Reevaluation ULNRC-06139, Special Report 2014-01 - PAM Report Inoperability of a Post Accident Monitoring (PAM) Instrument2014-09-0202 September 2014 Special Report 2014-01 - PAM Report Inoperability of a Post Accident Monitoring (PAM) Instrument 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 2023-06-05
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Union Electric PO Box 620 CallawayPlant Fulton, MO 65251 November 19, 2002 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 ULNRC-04776 Ladies and Gentlei wAmeren men:
UFE DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 SPECIAL REPORT 2002-03 C-3 Classified Inservice Inspection Results for Steam Generator Tube Inspections The enclosed Special Report is submitted in accordance with Technical Specification 5.5.9, Table 5.5.9-2, which states:
"Results of steam generator tube inspections, which fall into Category C-3, shall be reported to the Commission within 30 days and prior to resumption of plant operation. This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence."
The required failure mechanism determination investigation and corrective measures taken to prevent recurrence have been completed and are detailed in the enclosed report.
Warren A. Witt Manager, Callaway Plant WAW/ewh 0, k Enclosure a subsidiaryof Ameren Corporation
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ULNRC-04776 November 19, 2002 Page 2 cc: U. S. Nuclear Regulatory Commission (Original and 1 copy)
Attn: Document Control Desk Mail Stop P 1-137 Washington, DC 20555-0001 Mr. Ellis W. Merschoff Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)
Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7E1 Washington, DC 20555-2738 Manager, Electric Department Missouri Public Service Commission PO Box 360 Jefferson City, MO 65102
SPECIAL REPORT TO THE NRC STEAM GENERATOR A (EBB01A) CATEGORIZED AS C-3 CONDITION IN REFUEL 12 At 1110 on 11/05/02, AmerenUE Callaway Plant determined that steam generator A (EBB01) qualified as Category C-3 in accordance with the requirements of Technical Specification (T/S) 5.5.9, Table 5.5.9-2. At 1419 of that same day, the required ENS notification was made to the NRC Operations Center per 10CFR50.72(b)(2).
Additionally, T/S 5.5.9 refers to T/S 5.6.10 for further reporting requirements. T/S 5.6.10(c) states, "Results of steam generator tube inspections, which fall into Category C-3, shall be reported to the Commission within 30 days and prior to resumption of plant operations. This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence."
This report is intended to satisfy that requirement.
Callaway Steam Generator History The Westinghouse Model F steam generators installed at Callaway consist of approximately 78% low temperature mill annealed (LTMA) Alloy 600 tubing and 22%
(innermost 10 rows) Alloy 600 thermally treated (TT) tubing.
Callaway Plant first identified primary and secondary side Stress Corrosion Cracking (SCC) of the steam generator tubes in 1995 (Refuel 7). Since that outage, all four steam generators have been inspected each refueling, with the result that an increasing number of tubes have been repaired due to corrosion of the tubes at the hot leg top of tube sheet as shown in Figure 1 and Table 1. Sample RPC inspections are performed each outage at the support plates (dents), low row U-bends, and free span (dings) areas to provide early identification of any cracking that may occur in these locations. None has been identified to date.
The trend of top of tube sheet indications in all four steam generators is provided in Figure 1.
The extent of the tube degradation found during Refuel 12 was not unexpected. Past inspection results and tube degradation prediction models indicated that the degradation of the mill-annealed tubing would accelerate as the plant ages. This has generally been true of other plants with original Westinghouse steam generators fabricated with Alloy 600 MA tubing.
The tube degradation model for Callaway was updated prior to Refuel 12. Based on past experience, plant operating conditions, and experience at other plants, 123 tubes were predicted to be defective due to SCC (IDand OD) and IGA/SCC. The actual number identified was 113 in all four steam generators at the expansion transition or in the expanded portion of the tubing found using a Rotating Pancake Coil (RPC). Of the tubes with tubesheet defects, 84 were found in steam generator A as shown in Table 2 and Attachment 1. Since the number of defective tubes exceeded 1% of the inspected tubes for RPC inspection, the inspection results are classified as C-3.
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As Figure 1 demonstrates, Steam Generator A has consistently had more SCC indications than any other steam generator.
No service-induced degradation was identified in the 600TT tubing.
---.-- S/G A o B
- **-* S/G 20 50, 040 20 40___________, ___
10
Jun-94 Oct-95 Mar-97 Mu,-98 Dec-99 Apr-01 Sep-02 Jan-04 DATE Figure 1 Top of Tubesheet Cracks Trending by Steam Generator Examination of Steam Generator A The original inspection scope for 'A' steam generator was as follows:
- 100% (5431 tubes) of the hot leg top-of-tubesheet with a +Point RPC probe
- 100% (5431 tubes) full-length of the tubes with a standard bobbin coil probe Upon completion of the original scope of inspection, a total of ninety-one (91) tubes (as identified in Attachment 1) required repair:
"* Three tubes as a result of anti-vibration bar (AVB) wear greater than 40%
through-wall
"* Four tubes due to small volumetric indications near support (or flow baffle) plates Page 2 of 8
- 84 tubes due to Stress-Corrosion Cracking (SCC) or Inter-Granular Attack (IGA) indications at the expansion transition region or in the expanded tube Seven of the 84 indications discovered in Steam Generator A were found in the region added to the inspection scope using the new H-Star requirements for the top of-tube sheet inspections.
Investigation for Cause of Degradation Stress-corrosion cracking (PWSCC/ODSCC) has been identified in the hot leg tube sheet expansion and transition regions in all Westinghouse-designed steam generators (operating at 607'F or above) fabricated with LTMA tubing which were not peened prior to the start of plant operations.
Callaway Plant has determined that, based on the definition of active damage mechanism provided in the EPRI PWR Steam Generator Examination Guidelines, hot leg expansion axial/circumferential PWSCC and hot leg top of tube sheet ODSCC/IGA are active damage mechanisms in Callaway's steam generators.
Stress Corrosion Cracking occurs in the high stress expansion transition located at or below the top of the tube sheet and can initiate from either the primary or secondary side, and occurs due to the combination of the following:
- high residual stresses in and slightly above the expansion transition,
- the concentration of bulk water impurities to aggressive levels in the residual crevice between tube and tubesheet at the TTS, and in occluded areas formed by sludge,
- the insulating effect of sludge at the "TSwhich can raise the tube OD metal temperature up to primary water temperature in some cases, and
- the presence of a thin cold worked layer on the tube OD from abrasive polishing, often with high residual stresses, which increases susceptibility to crack initiation.
All indications identified at the top of the tube sheet in Refuel 12 are small in size as shown in Figure 2 and 3. None exceeded the condition monitoring limits for the specific type of degradation identified. In-situ testing was performed on indications based on screening criteria developed in the Plant's Degradation Assessment. The screening criteria are specified based on the type of degradation that exists or could potentially exist in the steam generators. Five indications in Steam Generator A exceeded these screening criterion. All indications were tested to 3 times Normal Operating Primary to Secondary Pressure Differential (4350 psi). None of the indications exhibited any leakage at any target pressure up to 3 times normal operating differential pressure during the test sequence. A list of tubes tested in steam generator A and target pressures are attached. (Table 3)
There were no new forms of degradation found in steam generator A. All forms of degradation were anticipated and addressed in the Refuel 12 Degradation Assessment.
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110 100 M 80 0
S70 CL 60 - -
4)
E5
- 4O 30 20 Length of axial indication Figure 2 Refuel 12 Steam Generator Axial Indications 140 CO 120 a_
"2. 100 C
X x
a1 80 CU 260 E
""S 40 0 0 r1 111A ' BU PDA (percent degraded area)
Figure 3 Refuel 12 Steam Generator A Circumferential Indications Page 4 of 8
Table I Steam Generator A Indications and Tubes Repaired Since Refuel 7 Indication RF07 *RF08 RF09 **RF10 RFlI RF12 Axial ID 5 9 14 15 23 39 Circumferential ID 4 26 17 21 2 43 Axial OD 0 0 1 0 0 0 Axial unknown 1 3 0 0 0 0 Circumferential OD 2 1 0 3 1 0 Circumferential 0 6 0 0 0 0 unknown Volumetric Indications 0 5 0 3 0 4 Total tubes with TTS 11 47 32 41 26 84 indications Tubes plugged due to 0 0 0 0 0 3 AVB wear Tubes plugged due to 0 0 0 1 0 4 TSP wear Tubes plugged due to 0 0 0 0 0 0 loose parts Total tubes repaired 11 48 32 42 26 91
- 44 tubes were sleeved with Westinghouse Laser Welded Sleeves at the top of the tubesheet.
- 31 tubes were sleeved with Framatome Electrosleeves at the top of the tubesheet.
Seven indications in RF12 are due to an expanded scope in the tubesheet based on the H-star criteria.
Refuel 7 - 1 tube has both axial PWSCC and circumferential ODSCC Refuel 12 - 2 tubes have both axial and circumferential PWSCC Table 2 Steam Generator A Tubes Plugged Inspection Period Steam Generator A Pre-service 8 Refuel 1 0 Spring '87 Refuel 2 3 Refuel 3 Refuel 4 6 Refuel 5 Refuel 6 19 Refuel 7 11 Refuel 8 4 Refuel 9 32 Refuel 10 11 Refuel 11 26 Refuel 12 91 TOTAL 211 Steam Generator A is 3.75% plugged Equivalent plugging due to sleeves is 3.79%
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90 80 70 M
" 60 C0.
0-0 10 Jun-94 Oct-95 Mar-97 Jul-98 Dec-99 Apr-01 Sep-02 Jan-04
,Outages Figure 4 Steam Generator A Cumulative TTS Degradation rn 45
--- Axial PWSCC 40= Circ PWSCC
-*Axial ODSCC J "CL35 ---- Circ ODSCC I--unknown circ /
30 -- *unknown axial 0
E 0._
25 r
20 15 10 0
Jun-94 Oct-95 Mar-97 Jul-98 Dec-99 Apr-01 Sep-02 Jan-04 outages Figure 5 Steam Generator A Cumulative TTS Degradation by Type Page 6 of 8
Table 3 Steam Generator A In-situ Pressure Testing Results Steam Generator A Tube/Defect/ Test Pressures Hold Time Leak Rate Average Pressurization Location (psi) (min) (gpm) Rate (psifsec)
Row Column 1550 2 0 15 23 97 2900 2 0 24 SCI @ TSH -8.4 3400 2 0 15 3900 2 0 14 4350 2 0 16 24 88 1550 2 0 15 SCI @ TSH -5.6 2900 2 0 29 3400 2 0 17 3900 2 0 14 4350 2 0 14 25 71 1550 2 0 12 MCI @ SBH-1.72 2900 2 0 14 3400 2 0 14 3900 2 0 17 4350 2 0 14 34 80 1550 2 0 8 SCI @ TSH -4.76 2900 2 0 15 3400 2 0 15 3900 2 0 11 4350 2 0 10 46 73 1550 2 0 14 SAI @ TSH +0.03 2900 2 0 17 3400 2 0 13 3900 2 0 15 4350 2 0 11 SAI - Single Axial Indication SCI - Single Circumferential Indication MCI - Multiple Circumferential Indication SBH - Bottom Hot Leg Sleeve TSH - Top of Tubesheet Hot Leg Actions to Prevent Recurrence All tubes with detected degradation at the top of the tubesheet were plugged in Steam Generator A. Additionally, all tubes with circumferential crack indications were stabilized and plugged. Callaway Plant anticipates similar degradation discovered in Refuel 12 at the end of Cycle 13. This is based on industry operating experience with Alloy 600 LTMA tubing and plant specific inspections results for the last 6 inspections. Callaway Plant will continue to perform a 100% top of tubesheet inspection with a RPC probe to the H-star distance during the next scheduled inspection. Callaway Plant anticipates replacing the existing steam generators in Refuel 14 with new Steam Generators utilizing Alloy 690 TT tubing. Industry experience has shown that this tubing is less susceptible to stress corrosion cracking.
Callaway Plant will continue to follow the requirements of NEI 97-06 and the referenced EPRI guidelines for future cycles of operation. These guidelines include maintaining primary and secondary water chemistry below recommended levels, primary to secondary leakage monitoring, inspection scope and frequency, pressure testing Page 7 of 8
degraded tubes, and performing integrity assessments to ensure tube structural and leakage integrity.
The Condition Monitoring and Preliminary Operational Assessment, performed in accordance with the EPRI Integrity Assessment Guidelines, during Refuel 12 addresses the as-found condition of the steam generator tubing and justifies operation for Cycle 13.
The assessment is based on degradation identified and conservative analysis to assure tube structural and leakage integrity for the entire cycle length.
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ATTACHMENT 1 - INDICATIONS IDENTIFIED IN STEAM GENERATOR A DURING REFUEL 12 ROW COL REPAIR REASON FOR IN-SERVICE REPAIR HOT LEG COLD LEG 1 34 PLUGGED PLUGGED MVI @ 01C -0.39 NO 11 68 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.12 NO 11 98 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.06 NO 12 64 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.23 NO 12 65 PLUGGED PLUGGED SAI @ TSH +0.1 NO 12 99 PLUGGED PLUGGED SVI @ TSH +0.07 NO 13 66 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.16 NO 13 75 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.16 NO 14 83 PLUGGED PLUGGED SAI @ TSH +0.08 NO 15 48 PLUGGED PLUGGED SVI @ 07H +0.26 NO 16 72 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.17 NO 17 43 PLUGGED PLUGGED SCI @ TSH -0.1 NO 17 51 PLUGGED PLUGGED SAI @ TSH +0.12 NO 17 101 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.06 NO 18 42 PLUGGED-STABILIZED PLUGGED MCI @ TSH -6.02 NO 18 44 PLUGGED-STABILIZED PLUGGED SCI @ TSH -0.96 NO 18 49 PLUGGED PLUGGED MAI @ TSH +0.01 NO 18 50 PLUGGED PLUGGED SAI @ TSH -0.01 NO 19 42 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.05 NO 19 68 PLUGGED-STABILIZED PLUGGED MCI @ TSH +0.24 NO 19 69 PLUGGED-STABILIZED PLUGGED SCI @ TSH -5.45 NO 20 39 PLUGGED PLUGGED SAI @ TSH -0.01 NO 20 50 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.11 NO 20 82 PLUGGED PLUGGED SAI @ TSH +0.08 NO 21 45 PLUGGED-STABILIZED PLUGGED SCI @ TSH -2.3 NO 21 59 PLUGGED PLUGGED SAI @ TSH +0.09 NO 21 64 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.06 NO 22 58 PLUGGED PLUGGED SAI @ TSH +0.05 NO 22 72 PLUGGED PLUGGED SAI @ TSH +0.07 NO 23 43 PLUGGED-STABILIZED PLUGGED SCI @ TSH -0.33 NO 23 78 PLUGGED-STABILIZED PLUGGED SCI @ TSH -7.88 NO 23 84 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.16 NO 23 97 PLUGGED-STABILIZED PLUGGED SCI @ TSH -8.4 NO 24 80 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.2 NO 24 88 PLUGGED-STABILIZED PLUGGED SCI @ TSH -5.6 NO 24 103 PLUGGED PLUGGED SAI @ TSH +0.1 NO 25 62 PLUGGED PLUGGED SAI @ TSH +0.06 NO 25 71 PLUGGED PLUGGED MCI @ SBH-1.72 NO*
25 88 PLUGGED PLUGGED SAI @ TSH +0.1 NO 25 91 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.00 NO 25 99 PLUGGED PLUGGED SAI @ TSH +0.00 NO 26 53 PLUGGED-STABILIZED PLUGGED SCI ( TSH -2.59 NO SAI @ TSH +0.06 NO 26 77 PLUGGED-STABILIZED PLUGGED MCI @ TSH +0.11 NO 26 109 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.07 NO 27 60 PLUGGED PLUGGED SAI @ TSH +0.05 NO 27 68 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.07 NO 27 83 PLUGGED-STABILIZED PLUGGED MCI @ TSH +0.05 NO Page 1 of 3
ATTACHMENT 1 - INDICATIONS IDENTIFIED IN STEAM GENERATOR A DURING REFUEL 12 ROW COL REPAIR REASON FOR IN-SERVICE REPAIR HOT LEG COLD LEG 27 100 PLUGGED-STABILIZED PLUGGED MCI @ TSH +0.14 NO 30 64 PLUGGED PLUGGED SAI @ TSH -0.03 NO 31 76 PLUGGED PLUGGED SAI @ TSH +0.08 NO 31 101 PLUGGED PLUGGED SAI @ TSH +0.13 NO 32 65 PLUGGED-STABILIZED PLUGGED SCI @ TSH -3.18 NO 32 82 PLUGGED PLUGGED SAI @ TSH +0.07 NO 33 74 PLUGGED PLUGGED SAI @ TSH +0.08 NO 33 108 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.08 NO 34 73 PLUGGED-STABILIZED PLUGGED SCI @ TSH -3.53 NO 34 80 PLUGGED-STABILIZED PLUGGED SCI @ TSH -4.76 NO 34 89 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.05 NO 34 98 PLUGGED PLUGGED SAI @ TSH +0.08 NO 37 83 PLUGGED PLUGGED SAI @ TSH +0.06 NO 38 88 PLUGGED PLUGGED SAI @ TSH +0.05 NO 39 37 PLUGGED PLUGGED 42% @ AV5 +0.15 NO 40% @ AV4 +0.00 NO 39 41 PLUGGED PLUGGED 42% @ AV4 -0.05 NO 39 61 PLUGGED PLUGGED SAI @ TSH +0.00 NO 39 83 PLUGGED PLUGGED SAI @ TSH +0.04 NO 39 88 PLUGGED-STABILIZED PLUGGED SCI @ TSH -1.98 NO 39 90 PLUGGED PLUGGED SAI @ TSH +0.02 NO 39 92 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.13 NO 41 54 PLUGGED PLUGGED SAI @ TSH +0.00 NO 41 82 PLUGGED PLUGGED SAI @ TSH +0.06 NO 41 95 PLUGGED PLUGGED MAI @ TSH +0.03 NO 42 62 PLUGGED-STABILIZED PLUGGED SCI @ TSH -0.62 NO 43 36 PLUGGED PLUGGED SVI @ TSH +0.03 NO 44 35 PLUGGED PLUGGED SVI @ TSH +0.09 NO 44 36 PLUGGED PLUGGED SVI @ TSH +0.13 NO 44 59 PLUGGED PLUGGED SAI @ TSH +0.05 NO 44 62 PLUGGED-STABILIZED PLUGGED SCI @ TSH -0.67 NO 44 75 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.09 NO 44 81 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.1 NO 46 48 PLUGGED PLUGGED 47% @ AV2 +0.00 NO 41% @ AV3 +0.00 NO 44% @ AV4 +0.00 NO 46 50 PLUGGED PLUGGED MAI @ TSH +0.00 NO 46 61 PLUGGED-STABILIZED PLUGGED MAI @ TSH -0.75 NO SCI @ TSH -0.74 NO 46 73 PLUGGED PLUGGED SAI @ TSH +0.03 NO 47 49 PLUGGED PLUGGED SAI @ TSH +0.00 NO 47 50 PLUGGED PLUGGED SAI @ TSH +0.01 NO 47 57 PLUGGED PLUGGED SVI @ FBH +0.07 NO 48 61 PLUGGED-STABILIZED PLUGGED SCI @ TSH -0.98 NO 48 70 PLUGGED-STABILIZED PLUGGED SCI @ TSH +0.06 NO Page 2 of 3
ATTACHMENT 1 - INDICATIONS IDENTIFIED IN STEAM GENERATOR A DURING REFUEL 12 ROW COL REPAIR REASON FOR IN-SERVICE REPAIR HOT LEG COLD LEG 49 48 PLUGGED PLUGGED SAI @ TSH +0.02 NO 59 62 PLUGGED PLUGGED SAI @ TSH +0.17 NO 59 167 PLUGGED PLUGGED SVI @ 02C +0. 13 NO
- Tube 25-71 does not require additional stabilization due to a 12.00" Westinghouse Laser Welded Sleeve installed at the Hot Leg Tube Sheet area.
SAI Single Axial Indication MAI Multiple Axial Indication SCI Single Circumferential Indication MCI Multiple Circumferential Indication SVI Single Volumetric Indication MVI Multiple Volumetric Indication TSH Tube Sheet Hot TSC Tube Sheet Cold AV# Anti-Vibration Bar (where # is the anti-vibration bar number)
O1H First Support Plate Hot TSH Top of Tubesheet Hot SBH Bottom of Sleeve Hot Page 3 of 3