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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:Technical
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 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 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 ML22349A6402022-12-15015 December 2022 Enclosure 14 - Schedule 14C Information for Union Electric Company March 2022 ML22349A6272022-12-15015 December 2022 Enclosure 3 - 2022 Proxy Statement of Ameren Corporation ML22349A6352022-12-15015 December 2022 Enclosure 10 - 10-Q Filed 06/30/2022 ML22349A6322022-12-15015 December 2022 Enclosure 8 - 10-K Filed 02/23/2022 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 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 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 ML22285A1252022-10-12012 October 2022 Attachment 8 to Enclosure 1: ANP-3969NP, Callaway Non-LOCA Summary Report, Revision 2, 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 ML22153A1852022-06-0202 June 2022 Attachment 8 - Non-Proprietary Version of Non-LOCA Summary Report ML22153A1832022-06-0202 June 2022 Attachment 7 - Non-Proprietary Version of SBLOCA Summary Report ML22153A1822022-06-0202 June 2022 Attachment 6 - Non-Proprietary Version of Rlbloca 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 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) ML20178A6712020-06-26026 June 2020 Attachment 1 - Discussion of Change 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 ML18208A1622018-06-19019 June 2018 Revised Site Addendum Item - Chapter 3.0, Design of Structures, Components, Equipment and Systems ML18208A1612018-06-19019 June 2018 Revised Site Addendum Item - Chapter 3.0, Figures 2023-08-31
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Union Electric One Ameren Plaza 1901 Chouteau Avenue PO Box 66149 St. Louis, MO 63166-6149 314 621.3222 February 13, 2003 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Ladies and Gentlemen: ULNRC-04807 DOCKET NUMBER 50-483 UNION ELECTRIC COMPANY CALLAWAY PLANT WAmeren REVISION TO REQUEST FOR RELIEF FROM ASME SECTION II REQUIREMENTS REGARDING 11E NON-DESTRUCTIVE EXAMINATION OF WELDS PERFORMED UNDER SITE REPAIR/REPLACEMENT PROGRAM (TAC# MB6534)
References (1) AmerenUE Letter ULNRC-04760 from John D. Blosser to USNRC Document Control Desk, dated October 17, 2002, "Request for Relief from ASME Section III Requirements Regarding Non-Destructive Examination of Welds Under Site Repair/Replacement Program" (2) AmerenUE Letter ULNRC-04768 from John D. Blosser to USNRC Document Control Desk, dated October 30, 2002, "Revision to Request for Relief from ASME Section III Requirements Regarding Non-Destructive Examination of Welds Performed Under Site Repair/Replacement Program (TAC #MB6534)"
By letter dated October 17, 2002 (Reference 1) Union Electric (AmerenUE) submitted an American Society of Mechanical Engineers (ASME) Code relief request pursuant to 10 CFR 50.55a(a)(3)(i) for use of a proposed alternative to the non destructive examination (NDE) requirements of Subarticle NC 5200 of Section III of the ASME Code, as applicable to a particular group of piping welds for certain Class 2 piping sections at the Callaway plant. A follow-up letter dated October 30, 2002 (Reference 2) was submitted to support and reflect revision of AmerenUE's request, which was prompted in response to a request for additional information received from the NRC staff on October 23, 2002 based on their preliminary review of AmerenUE's request. This letter is also a follow-up to that request since planning activities that have occurred subsequent to the October submittals have prompted AmerenUE to revise its request.
a subsidiaryofAmeren Corporation
ULNRC-04807 February 13, 2003 Page 2 At the time of our request last October, AmerenUE was anticipating the completion of certain inspection activities that had been planned for Refuel 12 (Fall 2002) at Callaway. The inspections were planned in response to the previous identification of pipe wall thinning [due to flow-accelerated corrosion (FAC)] in certain sections of the main feedwater system during Refuel 11 (Spring 2001). The intent of the inspections was to assess the extent and rate of pipe wall thinning and replace any pipe sections if required based on the inspection results. The welds performed for the replaced pipe sections would require NDE, and the relief requested by AmerenUE in its October submittals would support the performance of ultrasonic examination in lieu of radiography which would otherwise be required by Subarticle NC 5200 of Section III of the ASME Code. The basis for this alternative approach, including details of the ultrasonic examination method to be used, was provided in the relief request that was included as an attachment to Reference 1 (and then as to Reference 2, as revised).
In planning for the inspections and potential replacement activities in the outage, the pipe sections requiring inspection and subject to replacement were known.
Which ones would actually be replaced, however, would not be known until after the inspections were performed and the results were evaluated. As it was desired to process the relief request in advance of the replacement work (if required), and since the NRC staff had indicated that the scope of the relief request should be limited and defined, the pipe sections subject to replacement were identified in the relief request.
The inspections were subsequently completed during Refuel 12. The inspection results indicated, however, that no pipe sections required immediate replacement during the outage. Therefore, although the NRC staff was prepared to process the requested relief at that time, the relief was not immediately needed and was not pursued further at that time.
Notwithstanding the inspection results obtained in RF-12, pipe-wall thinning continues to be monitored under the FAC program established at Callaway, and the subject pipe sections will continue to be inspected and subject to replacement if required. In fact, during the current ten-year Inservice Inspection interval, the potentially affected pipe sections are to be inspected again during Refuel-13 (Spring 2004) and/or Refuel 14 (Fall 2005). AmerenUE is therefore still pursuing the requested relief, as the basis for the relief remains.
In addition to the anticipated FAC inspections, plans have been completed for additional activities that will require repair or replacement of certain other sections of Class 2 piping. These activities include replacement of all four steam generators at Callaway during RF-14 and modification of the feedwater control system in RF-13, both of which will require feedwater piping replacement. (The latter will require replacement of the actuators on the main feedwater control valves, one of which
[AEFV0040] is seal welded and will need to be completely removed and replaced.)
ULNRC-04807 February 13, 2003 Page 3 As a result of these planned activities, some additional feedwater system welds (- 8 additional welds) are being added to the scope of AmerenUE's pending relief request.
Further, steam generator replacement will also affect piping in the main steam system such that welds on sections associated with the pipe, reducer and elbow downstream of the A, B, C and D steam generator outlets have been identified for inclusion in the scope of the relief request.
Due to this change in scope of the subject Class 2 system pipe welds, the relief request has been revised to reflect the new scope. In addition, the revision reflects a change that was made to clarify information provided with regard to the directions of the examination scans to be used for the ultrasonic examination method. The revised relief request is therefore attached. It supersedes the last version provided in the October 30, 2002 submittal.
AmerenUE appreciates the NRC staffs continued review of this relief request.
Because this relief request significantly affects the planning of work activities for Refuel 13, please note that AmerenUE requests approval of this request by September 30, 2003. For any further questions or requests for additional information that you may have, please contact David Shafer at 314-554-3104, or Thomas Elwood at 314 554-4593.
Very truly yours, John D. Blosser Manager - Regulatory Affairs TBE/jdg Attachment
ULNRC-04807 February 13, 2003 Page 4 cc: U. S. Nuclear Regulatory Commission (Original and 1 copy)
Attn: Document Control Desk Mail Stop P1-137 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 7El Washington, DC 20555-2738 Manager, Electric Department Missouri Public Service Commission PO Box 360 Jefferson City, MO 65102
ULNRC-04807 Attachment Relief Request Request to Use Alternative Ultrasonic Examination Method in Lieu of the Radiography Required by ASME Section III, Subarticle NC-5200 Note Revisions made to the text of this Relief Request since original submittal (October 17, 2002) are shown in italics and are indicated by a revision bar in the left margin. Changes also include new welds added to Table I and the addition of new Table 2 for welds associated with main steam piping.
ULNRC-04807 Attachment Page 1 of 6 Request to Use Alternative Ultrasonic Examination Method in Lieu of the Radiography Required by ASME Section III, Subarticle NC-5200
Background:
The 1989 Edition with no Addenda of ASME Section XI currently governs repair/replacement activities at the Callaway Nuclear Plant. Callaway Plant is currently in the second 10-year inservice inspection Interval which began on August 1, 1995. ASME Class 2 welds installed under the Callaway Repair/Replacement Program are nondestructively examined in accordance with the 1974 Edition with Summer 1975 Addenda of ASME Section III. Alternatively, when pressure testing is performed in accordance with Code Case N-416-1, the welds are nondestructively examined In accordance with the 1992 Edition with no Addenda of ASME Section III. Pursuant to the provisions of 10CFR 50.55a(a)(3)(i), Callaway Plant requests permission to use an alternative ultrasonic examination method in accordance with the justification, requirements, and provisions detailed below in lieu of the radiography required by ASME Section III, NC-5200.
Components for Which Alternative Ultrasonic Examination is Requested:
Alternative ultrasonic examination is requested for Class 2 feedwater pipe welds listed in Table 1 and Class 2 main steam pipe welds listed in Table 2. These tables list a piping description, weld Identification number, nominal pipe size, pipe schedule, and base material for each weld.
Justification for Alternative Ultrasonic Examination in Lieu of Radioaraphv:
The proposed alternative ultrasonic examination will ensure an adequate level of safety and quality and will provide adequate verification that the Class 2 welds are free of significant flaws that could affect structural integrity. The examination will cover 100% of the weld volume and include base material for a distance of 1/2 the nominal through-wall weld thickness on each side of the weld. A demonstration of the ultrasonic examination system capability to detect both subsurface and surface workmanship type flaws (i.e., slag, porosity, lack of fusion, and incomplete penetration) will be performed on a qualification block. All flaws and indications will be evaluated in accordance with the standard acceptance criteria of NC-5330. In addition, an automated scan and data acquisition system will be used to improve examination repeatability and provide permanent storage of the raw data. Finally, the proposed alternative ultrasonic examination will be limited to base material and weld material that is conducive to ultrasonic examination.
Ultrasonic and radiographic examination methods are complimentary and are not directly comparable or equivalent. Depending on flaw type (i.e., volumetric or planar) and orientation, ultrasonic examination may be superior to radiography or vice versa. Radiography is most effective in detection of volumetric type flaws (i.e., slag and porosity) and detection of planar type flaws (i.e., lack of fusion and cracks) that are oriented in a plane parallel to the x-ray beam.
However, radiography is limited in detection of planar flaws not oriented parallel to the beam. In contrast, ultrasonic examination is very effective in detection of planar type flaws that are not oriented in a plane parallel to the sound beam and less effective in detecting flaws in a plane parallel to the sound beam. Finally, ultrasonic examination is capable of detecting volumetric type flaws such as slag or porosity but is limited, compared to radiography, in ability to characterize volumetric flaws.
The proposed alternative ultrasonic examination requirements and provisions address the known limitations of the ultrasonic method to ensure both planar and volumetric flaws in all orientations are detected and properly evaluated. First, examination using two angle beams (i.e., 45 and 60 degree nominally) or a procedure qualified on 100% of the weld volume in accordance with the performance demonstration methodology of Section XI, Appendix VIII is required. Second, examination scans in two directionsperpendicularto the weld axis and two directionsparallelto the weld axis or examination scans as qualified on 100% of the weld volume in accordance with
ULNRC-04807 Attachment Page 2 of 6 the performance demonstrationmethodology of Section XI, Appendix VIII are required. Third, to ensure laminar type flaws are detected, a supplemental examination using straight beam Is also required. Finally, if an indication, such as slag or porosity, is not characterized as volumetric, the indication will be characterized as a planar type flaw and evaluated in accordance with the acceptance criteria of NC-5330. The acceptance criteria of NC-5330 specify acceptable lengths of indications only and do not differentiate between planar and volumetric type flaws. Most importantly, planar type flaws such as cracks, incomplete penetration, and lack of fusion, which are rejectable by NC-5330 for any size, are more readily and properly characterized by ultrasonic examination.
In addition to the effectiveness of the proposed altemative, use of ultrasonic examination in lieu of radiography will provide a significant reduction In personnel radiation exposure during refueling outage maintenance work. Also, outage duration and costs will be reduced by allowing parallel path work to progress uninterrupted during examination of welds. Finally, the personnel safety risk of inadvertent or accidental exposure and also the normal anticipated exposure associated with transporting, positioning and exposing a source for radiography is eliminated.
Proposed Alternative Ultrasonic Examination Requirements and Provisions:
For ASME Class 2 welds installed under the Callaway Repair/Replacement Program where ultrasonic examination will be performed in lieu of radiography the following requirements shall apply:
(1) The nominal weld thickness shall be 1/2 inch or greater.
(2) The ultrasonic examination shall not be applied to welds that include austenitic cast product forms or austenitic corrosion-resistant-clad piping butt welds.
(3) The ultrasonic examination area shall include 100% of the volume of the entire weld plus 0.5T on each side of the weld, where T is the nominal thickness of the weld.
The ultrasonic examination area shall be accessible for angle beam examination in four directions, two directions perpendicular to the weld axis and two directions parallel to the weld axis. Where perpendicular scanning is limited on one side of the weld, a technique using the second leg of the V-path may be credited as access for the second perpendicular examination direction provided that the detection capability of that technique is included in the procedure demonstration described in (5) and (6) below.
(4) The ultrasonic examination shall be in accordance with (a) or (b) below:
(a) Examination shall be performed in accordance with Section V, Article 5 up to and including the 2001 Addenda. Two angle beams having nominal angles of 45 and 60 degrees should generally be used; however, other pairs of angle beams may be used provided the measured difference between the angles is at least 10 degrees. Examination scans shall be in four directions; two beam path directions perpendicularto the weld axis and two beam path directionsparallelto the weld axis. Where the examination scan perpendicularto the weld is limited on one side, the second leg of the V-path may be used to achieve the two beam path directions. A supplemental straight beam shall also be used.
(b) Examination shall be performed by a procedure qualified in accordance with the performance demonstration methodology of Section XI, Appendix VIII provided the entire volume of the weld examination is included in the demonstration.
Examination scans shall be in four directions;two beam path directions perpendicularto the weld axis and two beam path directions parallelto the weld axis. A supplemental straight beam shall also be used.
(5) A written procedure shall be followed. The procedure shall be demonstrated to perform acceptably on a qualification block or specimen that includes a weld with both surface and subsurface flaws as described in (7) below.
ULNRC-04807 Attachment Page 3 of 6 (6) The qualification block material shall conform to the requirements applicable to the calibration block and in addition meet the following requirements:
(a) The material from which blocks are fabricated shall be one of the following: a nozzle dropout from the component; a component prolongation; or material of the same material specification, product form, and heat treatment condition as one of the materials joined. For piping, if material of the same product form and specification is not available, material of similar chemical analysis 1 , tensile properties, and metallurgical structure2 may be used.
(b) Where two or more base material thicknesses are involved, the calibration block thickness shall be of a size sufficient to contain the entire examination path.
(c) Qualification block configuration shall contain a weld representative of the joint to be ultrasonically examined, including, for austenitic materials, the same welding process.
(7) The qualification block shall include flaws in accordance with (a) or (b) below:
(a) At least two planar flaws shall be included in the qualification block weld, one surface and one subsurface oriented parallel to the fusion line. The flaws shall be no larger in the through-wall direction than the diameter of the applicable side-drilled hole in the calibration block shown in Figure T-542.2.1 of Section V, Article 5, and no longer than the shortest unacceptable elongated discontinuity length listed in NC-5330 for the thickness of the weld that will be examined.
(b) Where a Section XI, Appendix VIII, performance demonstration methodology is used, supplemental qualification to a previously approved procedure may be demonstrated through the use of a blind test with appropriate specimens that contain a minimum of three different construction-type and fabrication-type flaws distributed throughout the thickness of the specimen(s).
(8) A documented examination plan shall be provided showing the transducer placement, movement and component coverage that provides a standardized and repeatable methodology for weld acceptance. The examination plan shall also include the ultrasonic beam angle used, beam directions with respect to weld centerline, and volume examined for each weld.
(9) The ultrasonic examination shall be performed using a device with an automated computer data acquisition system.
(10) Data shall be recorded in unprocessed form. A complete data set with no gating, filtering, or thresholding for response from the examination volume in paragraph (3) above shall be included in the data record.
(11) Personnel who acquire and analyze ultrasonic data shall be qualified and trained using the same type of equipment as in (9) above, and demonstrate their capability to detect and characterize the flaws using the procedure as described in (5) above.
(12) The evaluation and acceptance criteria shall be in accordance with Section III NC 5330.
(13) Flaws exceeding the applicable acceptance criteria referenced in (12) above shall be repaired, and the weld subsequently reexamined using the same ultrasonic examination procedure that detected the flaw.
(14) Review and acceptance of the ultrasonic examination procedure by the Authorized Nuclear Inservice Inspector is required.
(15) All other related requirements of the Callaway Repair/Replacement Program shall be met.
1 Chemicalcomposition is within the same ranges as requiredin the originalmaterialspecification.
2 Same phase and grain shape as produced by the thermalprocess for the originalspecification.
ULNRC-04807 Attachment Page 4 of 6 (16) Use of ultrasonic examination in lieu of radiography shall be documented in accordance with the Callaway Repair/Replacement Program on a Form NIS-2A and/or Section XA Repair/Replacement Plan, as applicable.
ULNRC-04807 Attachment Page 5 of 6 Table 1: FeedwaterPipe Welds Description Weld ID No. (1) NPS Sch. Mat.
2-AE-04-F014 (2) 14 80 CS 5-Dia. bend & expander upstream of A S/G inlet 2-AE-04-SO10-A 14 80 CS 2-AE-04-S010-C 16 80 CS 2-AE-04-F015 16 80 CS 2-AE-04-F030 (2) 14 80 CS 2-AE-04-FW8 14 80 CS 5-Dia. bend & expander upstream of B S/G inlet 2-AE-04-FW7 14 80 CS 2-AE-04-S021-C 16 80 CS 2-AE-04-F035 16 80 CS 2-AE-05-F030 (2) 14 80 CS 5-Dia. bend & expander upstream of C S/G inlet 2-AE S021-A 14 80 CS 2-AE-05-S021-C 16 80 CS 2-AE-05-F036 16 80 CS 2-AE-05-F015 (2) 14 80 CS 5-Dia. bend & expander upstream of D S/G inlet 2-AE-05-S022-A 14 80 CS 2-AE-05-S022-C 16 80 CS 2-AE-05-F035 16 80 CS Feedwater isolation valve AEFV0040 2-AE-04-F020 14 120 CS 2-AE-04-F019 14 120 CS 2-AE-04-S017-A 14 80 CS Elbow & pipe upstream of valve AEV0120 (B loop) 2-AE-04-F027 14 80 CS 2-AE-04-F067 14 80 CS 2-AE-04-F070 14 80 CS Elbow & pipe downstream of valve AEV0120 (B loop) 2-AE-04-SO1 9-A 14 80 CS 2-AE-04-FW10 14 80 CS Elbow downstream of valve AEV0123 (C loop) 2-AE-05-F029 14 80 CS 2-AE-05-S020-A 14 80 CS 2-AE-05-F012 14 80 CS Elbow & pipe upstream of valve AEV0122 (D loop) 2-AE-05-S008-A 14 80 CS 2-AE-05-F073 14 80 CS Notes:
(1) Listed Weld ID Numbers are those currently identified in the Callaway ISI Program Plan.
(2) New weld will be at this weld location or several inches upstream.
ULNRC-04807 Attaclhnent Page6 of6 Table 2: Main Steam Pipe Welds Description Weld ID No. (1) NPS Sch.(2) Mat.
2-AB-01-FOOl 32 1.068" CS Pipe, reducer & elbow downstream of A S/G outlet 2-AB-01-SO01-A 32 1.068" CS 2-AB-01-SOO1-D 28 0.934" CS new pipe weld (3) 28 0.934" CS 2-AB-01-F020 32 1.068" CS Pipe, reducer & elbow downstream of B S/G outlet 2-AB-01-S013-A 32 1.068" CS 2-AB-01-S013-D 28 0.934" CS new pipe weld (3) 28 0.934" CS 2-AB-01 -F044 32 1.068" CS Pipe, reducer & elbow downstream of C S/G outlet 2-AB-01-S027-A 32 1.068" CS 2-AB-01-S027-D 28 0.934" CS new pipe weld (3) 28 0.934" CS 2-AB-01-F068 32 1.068" CS Pipe, reducer & elbow downstream of D S/G outlet 2-AB-01-S041-A 32 1.068" CS 2-AB-01-S041-D 28 0.934" CS new pipe weld (3) 28 0.934" CS Notes:
(1) Listed Weld ID Numbers are those currently identified in the Callaway ISI Program Plan.
(2) Minimum wall thickness is listed in pipe schedule column.
(3) New weld to be in pipe section downstream of 1st elbow from S/G outlet.