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Category:Code Relief or Alternative
MONTHYEARML24052A3662024-02-26026 February 2024 Regulatory Audit Plan in Support of Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML20225A2922020-08-12012 August 2020 Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI ML19079A1482019-04-0101 April 2019 Request for Alternative I4R-05 to Reactor Vessel Nozzle Weld Examination Frequency Requirements (EPID L-2018-LLR-0051 ML18313A0692018-11-26026 November 2018 Request for Relief I4R-01 Related to the Inservice Inspection Program for Class 3 Buried High Density Polyethylene Piping ULNRC-06420, Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds2018-04-0909 April 2018 Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds ML17262A7002017-10-0303 October 2017 Request for Alternative I4R-04 Applicable to the Fourth 10-Year Inspection Program Interval ML17254A1202017-09-25025 September 2017 Request for Alternative No. PR-07 from the Requirements of the ASME Code for the Fourth 10-Year Inservice Testing Interval ML17058A4432017-03-0606 March 2017 Request for Alternative I4R-03 Applicable to the Fourth 10-Year Inservice Inspection Program Interval ML16223A7122016-08-30030 August 2016 Relief Request No. 13R-08 from Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, for Piping Welds, Third 10-Year Inservice Inspection Interval ML16055A4642016-03-17017 March 2016 Relief Requests 13R-09 (Steam Generator Tubesheet Weld), 13R-11 (Pressurizer Welds) from Code Case N-460 and 13R-18 (SG Weld), from Appendix Viii Requirements, Third 10-Year Inservice Inspection Interval (CAC MF6735-MF6737) ML16027A1582016-01-29029 January 2016 Relief Request I4R-02 from Requirements of ASME Code Section XI, Table IWF-2500-1 for 100% Visual Examination of Class 1 Supports, Fourth 10-Year Inservice Inspection Interval ML15064A1252015-05-12012 May 2015 Request for Relief I4R-01 from ASME Code Requirements for Replacement of Class 3 Essential Service Water Buried Piping with High Density Polyethylene Piping, for the Fourth 10-year Inservice Testing Interval ML15035A1482015-02-10010 February 2015 Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency from 10 to 20 Years, Third 10-Year Interval ML14239A0972014-09-0404 September 2014 Request for Relief I3R-15, ASME Code Class 1 Pressure-Retaining Piping/Components Leakage Testing at Full Pressure, Third 10-Year Inservice Inspection Interval ML14234A4512014-09-0404 September 2014 Relief Request I3R-16, Temporary Non-Code Repair of the Train a Component Cooling Water Heat Exchanger to Control ESW Leakage, Third 10-Year Inservice Inspection Interval ML14178A7692014-07-15015 July 2014 Requests for Relief PR-01, PR-02, PR-03, PR-04, and PR-06 (PR-05 Withdrawn), ASME OM Code Cases for Group a and B Pumps for Fourth 10-Year Inservice Testing Interval ML14027A0572014-01-29029 January 2014 Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval ML13246A3042013-08-30030 August 2013 Verbal Authorization Email, Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval ML13126A3202013-05-0707 May 2013 Summary of Telephone Conference, Verbal Authorization of Relief Request I3R-14. Proposed Alternative to ASME Code Requirements for Leakage Testing of RPV Head Flange Leakoff Lines, Third 10-Year ISI Interval. ML12258A0452012-09-18018 September 2012 Relief Request VR-01 from Requirements of ASME OM Code, Mandatory Appendix I, One-time Extension for 5-Year Replacement Interval, from 4/11/12 to 6/2013, Main Steam Isolation Valve Actuator Rupture Disks ML1211502472012-05-0303 May 2012 Memo to File, Verbal Authorization, Relief Request VR-01 from Requirements of ASME OM Code Mandatory Appendix I, One-time Extension Replacement of Main Steam Isolation Valve Actuator Rupture Disks ML1201907482012-02-16016 February 2012 Relief Request 13R-13, Alternative to ASME Code Section XI Requirements for Performance of Second Successive Exam of C Cold Leg Safe-End to Elbow Weld, Third 10-Year Inservice Inspection ML0831002882008-11-0707 November 2008 Relief Request 13R-10 Approved on October 31, 2008, for Third 10-Year Inservice Inspection Interval for Use of Polyethylene Pipe in Lieu of Carbon Steel Pipe in Buried Essential Service Water Piping System ML0818406062008-07-0303 July 2008 Approval of Second Extension Request for Corrective Actions GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. ML0731114422007-12-10010 December 2007 Correction to Authorization of Relief Request ISI-39 for the Second 10-Year Inservice Inspection Interval ML0729803972007-10-30030 October 2007 Relief Request ISI-38, Reactor Pressure Vessel Inlet Safe-End to-Elbow Welds Proposed Alternative Examination for Second 10-Year Inservice Inspection Interval ML0724000922007-09-17017 September 2007 Issuance of Relief Requests (Rrs) ISI-36, ISI-37, and ISI-38 for Second Year Inservice Inspection (ISI) Interval ML0725504882007-08-30030 August 2007 10 CFR 50.55a Request: Proposed Alternative to ASME Section Xi Requirements for Replacement of Class 3 Buried Piping ML0715203292007-07-10010 July 2007 Request for Alternatives for Application of Structural Weld Overlays to Pressurizer Dissimilar Metal Nozzle Welds for Third 10-Year Inservice Inspection Program Interval ML0705803332007-03-15015 March 2007 Authorization of Relief Request No. ISI-33 for Second 10-Year and Third 10-Year ISI Interval ML0635203182007-01-18018 January 2007 Request for Relief No. ISI-35 for Second 10-year Inservice Inspection Interval ML0700303362007-01-18018 January 2007 Relief Request ISI-41 for the Second 10-year Inservice Inspection Interval ML0630604782006-12-0707 December 2006 Relief Request 13R-04 for the Third 10-Year Interval Inservice Inspection ML0629302822006-11-17017 November 2006 Relief Requests I3R-05 and I3R-06 for the Third Inservice Inspection Interval ULNRC-05183, Requests for Relief from ASME Section XI Code Inservice Examination Requirements2006-10-25025 October 2006 Requests for Relief from ASME Section XI Code Inservice Examination Requirements ML0614301312006-06-15015 June 2006 Relief, Third 10-Year Interval Inservice Inspection Program Relief Request I3R-02 ML0520802152005-08-18018 August 2005 Relief, Use a Subsequent Edition of ASME Code Examinations for the Third Inservice Inspection Interval ML0515302072005-06-22022 June 2005 6/22/05 Callaway, Unit 1 - Relief Requests ISI-24,ISI-25 and ISI-26 of the Second 10-Year Inservice Inspection (ISI) Interval (Tacs. MC4435 and MC4436) ML0507601292005-05-19019 May 2005 Relief, Request for Relief from Certain ASME Code Examinations for the Second Inservice Inspection Interval ULNRC-05092, Revision to Approve Request for Relief from ASME Section III Requirements Regarding Non-destructive Examination of Welds Performed Under Site Repair/Replacement Program2004-11-18018 November 2004 Revision to Approve Request for Relief from ASME Section III Requirements Regarding Non-destructive Examination of Welds Performed Under Site Repair/Replacement Program ULNRC-05049, Union Electric Company Callaway Plant Request for Relief from ASME Section XI Code Inservice Examination Requirements2004-09-0303 September 2004 Union Electric Company Callaway Plant Request for Relief from ASME Section XI Code Inservice Examination Requirements ML0414100712004-05-19019 May 2004 Relief, ASME Code Requirements on the Use of Weld Overlay Reinforcement to Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping. ML0414100352004-05-19019 May 2004 Relief, Second Ten-Year Interval Inservice Inspection Program Relief Request to Use an Alternative Examination Method ULNRC-04993, Revision of Request for Relief from ASME Section XI Requirements in Order to Temporarily Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement2004-05-0707 May 2004 Revision of Request for Relief from ASME Section XI Requirements in Order to Temporarily Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement ML0409806642004-04-0707 April 2004 4/7/04 Callaway Plant - Request for Relief from ASME Code Requirements on the Use of Weld Overlay Reinforcement to Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping ULNRC-04879, Requests for Relief Regarding Implementation of ASME Section XI Appendix VII Requirements2003-08-14014 August 2003 Requests for Relief Regarding Implementation of ASME Section XI Appendix VII Requirements ML0318305352003-07-0101 July 2003 Second Ten-Year Interval Inservice Inspection Program Relief Request to Use an Alternative Examination Method (Tac. MB6534) ML0134602652002-01-30030 January 2002 Relief, Application of Risk-Informed Inservice Inspection Program for the American Society of Mechanical Engineers Boilers and Pressure Vessel Code Class 1 and 2 TAC No MB1205) 2024-02-26
[Table view] Category:Letter
MONTHYEARIR 05000483/20253012024-08-0505 August 2024 Notification of NRC Initial Operator Licensing Examination 05000483/2025301 ML24212A2822024-08-0202 August 2024 Regulatory Audit Summary Concerning Review of Request No. C3R-01 for Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections IR 05000483/20240022024-07-18018 July 2024 and Independent Spent Fuel Storage Installation Integrated Inspection Report 05000483/2024002 and 07201045/2024001 ML24185A1032024-07-16016 July 2024 2024 Biennial Problem Identification and Resolution Inspection Report ULNRC-06891, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00052024-06-26026 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0005 ULNRC-06892, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00062024-06-26026 June 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0006 ULNRC-06884, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00022024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0002 ULNRC-06886, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00042024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0004 ULNRC-06885, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00032024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0003 ML24144A0492024-06-11011 June 2024 Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval ML24178A1132024-06-0606 June 2024 Ameren Missouris Intent to Adopt Revision 1 to Amendment 0 of Certificate of Compliance No. 1040 as Applicable to the ISFSI at the Callaway Plant Site ML24158A5222024-06-0606 June 2024 Application to Revise Technical Specifications to Adopt Tstf-569, Rev. 2, Revise Response Time Testing Definition (LDCN 24-0008) ML24143A1632024-05-23023 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Storage Canister HGMPC0001 ML24137A2342024-05-16016 May 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Canister HGMPC0011 ULNRC-06882, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00122024-05-16016 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0012 ML24122A1502024-05-0707 May 2024 Audit Plan to Support Review of Steam Generator License Renewal Response to Commitment Nos 34 and 35 IR 05000483/20244022024-05-0606 May 2024 Security Baseline Inspection Report 05000483/2024402 (Full Report) ULNRC-06877, Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 252024-05-0606 May 2024 Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 25 ULNRC-06856, CFR 50.59 and 10 CFR 72.48 Summary Report2024-05-0101 May 2024 CFR 50.59 and 10 CFR 72.48 Summary Report IR 05000483/20240112024-05-0101 May 2024 NRC Post-Approval Site Inspection for License Renewal (Phase 2) Report 05000483/2024011 ML24122A1132024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radioactive Effluent Release Report ULNRC-06869, Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report ULNRC-06876, Registration of Dry Spent Fuel Storage Canister HGMPC00102024-04-25025 April 2024 Registration of Dry Spent Fuel Storage Canister HGMPC0010 ULNRC-06866, Submittal of Cycle 26 Commitment Change Summary Report2024-04-17017 April 2024 Submittal of Cycle 26 Commitment Change Summary Report ULNRC-06871, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00072024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0007 ULNRC-06872, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00082024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0008 ML24108A1082024-04-17017 April 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0009 IR 05000483/20240012024-04-16016 April 2024 Integrated Inspection Report 05000483/2024001 IR 05000483/20244042024-04-0909 April 2024 Cyber Security Inspection Report 05000483/2024404 05000483/LER-2024-001, Submittal of LER 2024-001-00 for Callaway Plant, Unit 1, Reactor Trip Due to Turbine Trip2024-04-0404 April 2024 Submittal of LER 2024-001-00 for Callaway Plant, Unit 1, Reactor Trip Due to Turbine Trip ML24088A3212024-04-0101 April 2024 Notification of Commercial Grade Dedication Inspection (05000483/2024013) and Request for Information ML24086A5132024-03-26026 March 2024 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06863, Submittal of Annual Exposure Report for 20232024-03-20020 March 2024 Submittal of Annual Exposure Report for 2023 ML24079A1622024-03-19019 March 2024 Re Nuclear Property Insurance Reporting ML24066A1932024-03-0707 March 2024 2024 Callaway Plant Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ULNRC-06852, Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 262024-03-0505 March 2024 Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 26 IR 05000483/20230062024-02-28028 February 2024 Annual Assessment Letter for Callaway Plant Report 05000483/2023006 ML24052A3662024-02-26026 February 2024 Regulatory Audit Plan in Support of Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ULNRC-06858, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-02-21021 February 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation IR 05000483/20230022024-02-21021 February 2024 Amended Integrated Inspection Report 05000483/2023002 ML24036A1712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0079 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 IR 05000483/20230042024-01-19019 January 2024 Integrated Inspection Report 05000483/2023004 ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) ML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23317A0012024-01-12012 January 2024 Audit Summary Regarding LAR to Clarify Support System Requirements for the Residual Heat Removal and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML24011A1492024-01-11011 January 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information (05000483/2024011) 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 2024-08-05
[Table view] Category:Safety Evaluation
MONTHYEARML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML23234A1522023-10-0505 October 2023 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (Letter) ML23240A3692023-10-0505 October 2023 Issuance of Amendment No. 235 to Revise Technical Specifications to Use of Framatome Gaia Fuel (EPID L-2022-LLA-0150) (Non-Proprietary) ML23228A0252023-09-25025 September 2023 Issuance of Amendment No. 234 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 ML23261C3852023-09-25025 September 2023 Safety Evaluation for Operating Quality Assurance Manual Revision 36A ML23166B0882023-09-20020 September 2023 Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications ML22361A0702023-02-24024 February 2023 Issuance of Amendment No. 231 for Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ML23019A1752023-01-30030 January 2023 Issuance of Amendment No. 230 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22301A0072022-12-0202 December 2022 Issuance of Amendment No. 229 to Revise Technical Specifications to Adopt TSTF-505, Revision 2, and TSTF-439, Revision 2 ML22220A1302022-10-21021 October 2022 Exemptions from the Requirements of 10 CFR 50.46 and 10 CFR Part 50 Appendix a, General Design Criteria 35, 38, and 41 (EPID L-2021-LLE-0021) (Cover Letter) ML22220A1322022-10-21021 October 2022 Issuance of Amendment No. 228 Re; Revise Technical Specifications to Address Generic Safety Isusue-191 and Respond to Generic Letter 2004-02 Using Risk-Informed Approach ML22053A2832022-04-0707 April 2022 Issuance of Amendment No. 227 Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-529, Revision 4, Clarify Use and Application Rules ML21344A0052021-12-29029 December 2021 Issuance of Amendment No. 226 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML21053A1262021-03-24024 March 2021 Issuance of Amendment No. 225 to Revise Technical Specification Administrative Control 5.3.1 to Remove Details Specified for the Qualification of Certain Positions within the Unit Staff ML20218A4102020-11-0303 November 2020 Issuance of Amendment No. 224 Performance Based Method Alternative for Thermal Insulation Material ML20246G5702020-10-16016 October 2020 Issuance of Amendment No. 223 One-Time Deferral of the Steam Generator Tube Inspections ML20230A3872020-08-31031 August 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20216A6812020-08-0606 August 2020 Operating Quality Assurance Manual Change Revision 34B (EPID L-2020-LLQ-0004 (COVID-19)) ML20141L7452020-06-0808 June 2020 Operating Quality Assurance Manual Change Revision 34A ML20107H9782020-04-20020 April 2020 COVID-19 Relief Request CC-01 Containment Tendon Inspection ML19283C4812019-12-0606 December 2019 Issuance of Amendment No. 221 Main Turbine Control Slave Relay Testing ML19158A2902019-07-30030 July 2019 Issuance of Amendment No. 220 Regarding Emergency Action Level Scheme Changes ML19073A0012019-04-18018 April 2019 Issuance of Amendment No. 219 to Add New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System ML19079A1482019-04-0101 April 2019 Request for Alternative I4R-05 to Reactor Vessel Nozzle Weld Examination Frequency Requirements (EPID L-2018-LLR-0051 ML18313A0692018-11-26026 November 2018 Request for Relief I4R-01 Related to the Inservice Inspection Program for Class 3 Buried High Density Polyethylene Piping ML18124A0262018-05-30030 May 2018 Issuance of Amendment No. 218 FSAR Revision Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection ML17262A7002017-10-0303 October 2017 Request for Alternative I4R-04 Applicable to the Fourth 10-Year Inspection Program Interval ML17254A1202017-09-25025 September 2017 Request for Alternative No. PR-07 from the Requirements of the ASME Code for the Fourth 10-Year Inservice Testing Interval ML17236A0822017-09-15015 September 2017 Issuance of Amendment No. 217 Replacement of Methodology in Technical Specification 5.6.5, Core Operating Limits Report (Colr), ML17170A3202017-06-20020 June 2017 Safety Evaluation Input - for Ameren Missouri Request to Amend Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report - ML17058A4432017-03-0606 March 2017 Request for Alternative I4R-03 Applicable to the Fourth 10-Year Inservice Inspection Program Interval ML17010A3322017-02-0202 February 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16223A7122016-08-30030 August 2016 Relief Request No. 13R-08 from Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, for Piping Welds, Third 10-Year Inservice Inspection Interval ML16089A1672016-04-0101 April 2016 Review and Approval of Quality Assurance Plan Change Per Nuclear Energy Institute (NEI) 14-05A, Revision 1 ML16055A4642016-03-17017 March 2016 Relief Requests 13R-09 (Steam Generator Tubesheet Weld), 13R-11 (Pressurizer Welds) from Code Case N-460 and 13R-18 (SG Weld), from Appendix Viii Requirements, Third 10-Year Inservice Inspection Interval (CAC MF6735-MF6737) ML16020A5162016-02-29029 February 2016 Issuance of Amendment No. 216, Revise Technical Specification (TS) 2.1.1.1 and TS 5.6.5, to Remove Uncertainties from Departure from Nucleate Boiling Ratio Safety Limit and Adopt WCAP-14565-P-A Methodology ML15324A1142016-02-0202 February 2016 Issuance of Amendment No. 215, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection ML16027A1582016-01-29029 January 2016 Relief Request I4R-02 from Requirements of ASME Code Section XI, Table IWF-2500-1 for 100% Visual Examination of Class 1 Supports, Fourth 10-Year Inservice Inspection Interval ML15328A0592016-01-28028 January 2016 Issuance of Amendment No. 214, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML15258A5102015-10-28028 October 2015 Issuance of Amendment No. 213, Adopt Technical Specification Task Force Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML15251A4932015-10-0707 October 2015 Issuance of Amendment No. 212, Request to Upgrade the Emergency Action Level Scheme by Adopting Nuclear Energy Institute NEI 99-01, Revision 6 ML15064A1252015-05-12012 May 2015 Request for Relief I4R-01 from ASME Code Requirements for Replacement of Class 3 Essential Service Water Buried Piping with High Density Polyethylene Piping, for the Fourth 10-year Inservice Testing Interval ML15064A0282015-03-31031 March 2015 Issuance of Amendment No. 211, Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML15035A1482015-02-10010 February 2015 Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency from 10 to 20 Years, Third 10-Year Interval ML14350B2392015-01-20020 January 2015 Issuance of Amendment No. 210, Revise Technical Specification LCO 3.4.12, Cold Overpressure Mitigation System (Coms), to Clarify No Limitation on Normal Charging Pump Use During Modes 4-6 ML14234A4512014-09-0404 September 2014 Relief Request I3R-16, Temporary Non-Code Repair of the Train a Component Cooling Water Heat Exchanger to Control ESW Leakage, Third 10-Year Inservice Inspection Interval ML14178A7692014-07-15015 July 2014 Requests for Relief PR-01, PR-02, PR-03, PR-04, and PR-06 (PR-05 Withdrawn), ASME OM Code Cases for Group a and B Pumps for Fourth 10-Year Inservice Testing Interval ML14175A3902014-07-0101 July 2014 Issuance of Amendment No. 209, Adoption of Technical Specification Task Force Change Traveler TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using CLIIP ML14027A0572014-01-29029 January 2014 Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval 2024-01-18
[Table view] |
Text
November 17, 2006Mr. Charles D. NaslundSenior Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT, UNIT 1 - RELIEF REQUESTS I3R-05 AND I3R-06 FORTHE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NOS.
MD2031 AND MD2032)
Dear Mr. Naslund:
By letter dated May 18, 2006 (ULNRC-05291), the Union Electric Company (the licensee)submitted relief requests proposing alternatives to certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (the ASME Code) at the Callaway Plant, Unit 1 (Callaway). Specifically, the licensee proposed (1) coordinated qualifications ofASME Code,Section XI, Appendix VIII, Supplements 2 and 10 (Relief Request (RR)No. I3R-05), and (2) using Appendix VIII, Suppl ements 4 and 6, to examine the reactorpressure vessel shell-to-flange and head-to-flange welds (RR No. I3R-06). These relief requests are for the remainder of the third 10-year inservice inspection (ISI) interval.Based on the enclosed safety evaluation, the Commission concludes that RRs I3R-05 andI3R-06 provide an acceptable level of quality and safety and, therefore, are authorized pursuant to paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulation. These two RRs areauthorized for the third 10-year ISI program interval at Callaway. All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.Sincerely,/RA/David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-483
Enclosure:
Safety Evaluation cc w/encl: See next page
ML062930282OFFICENRR/LPL4/PMNRR/LPL4/LACPNB/BCOGC-NLO subject to editNRR/LPL4/BCNAMEJDonohewLFeizollahiTChanTCampbellDTerao DATE11/6/0611/16/069/22/0611/14/0611/17/06 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONTHIRD 10-YEAR INSERVICE INSPECTION PROGRAM INTERVALRELIEF REQUEST NOS. I3R-05 AND I3R-06UNION ELECTRIC COMPANYCALLAWAY PLANT, UNIT 1DOCKET NO. 50-48
31.0INTRODUCTION
By letter dated May 18, 2006 (Agencywide Documents Access and Management System(ADAMS) Accession No. ML061460043), the Union Electric Company (the licensee) submitted relief requests (RRs) proposing alternatives to certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (the ASME Code) at the Callaway Plant, Unit 1 (Callaway). Specifically, the licensee proposed (1) coordinated qualifications ofASME Code,Section XI, Appendix VIII, Supplements 2 and 10 (RR No. I3R-05), and (2) usingAppendix VIII, Supplements 4 and 6, to examine the reactor pressure vessel shell-to-flange andhead-to-flange welds (RR No. I3R-06). The requests are for the remainder of the third 10-year inservice inspection (ISI) interval, which began December 19, 2005, and ends December 18, 2014.RRs I3R-05 and I3R-06 were addressed by the licensee in Attachments 1 and 2, respectively,to the letter dated May 18, 2006.
2.0REGULATORY EVALUATION
The ISI of the ASME Code Class 1, 2, and 3 components is to be performed in accordance withSection XI of the ASME Code and applicable editions and addenda as required by Section 50.55a(g) of Part 50, "Domestic Licensing of Production and Utilization Facilities," of Title 10 of the Code of Federal Regulations (10 CFR 50.55a(g)), except where specific reliefhas been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i) for impracticality.
Paragraph 50.55a(a)(3) of 10 CFR states in part that proposed alternatives to the requirements of paragraph (g) may be used when authorized by the Nuclear Regulatory Commission (NRC),
if the applicant demonstrates that: (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (includingsupports) will meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within thelimitations of design, geometry, and materials of construction of the components.
Pursuant to 10 CFR 50.55a(g)(4)(i) and (ii), the inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals are required to comply with the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. Paragraph 50.55a(g)(4)(iv) of 10 CFR states that inservice examination of components and system-pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modification listed in 10 CFR 50.55a(b), and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met.In its May 18, 2006, letter, the licensee stated that the code of record for the third 10-year ISIinterval at Callaway is the 1998 Edition through 2000 Addenda of the ASME Code.
3.0TECHNICAL EVALUATION
OF RR NO. I3R-053.1Affected ComponentsThe affected components are ASME Code Class 1, pressure-retaining piping welds examinedfrom the inside surface of pressurized-water reactors using procedures, equipment, and personnel qualified to ASME Code,Section XI, Appendix VIII, Supplement 2 or Supplement 10criteria. The specific weld identifications are listed in two tables on safe-end welds in to the licensee's letter dated May 18, 2006.3.2Applicable ASME Code RequirementsThe applicable code requirements are the ASME Code,Section XI, "Rules for InserviceInspection of Nuclear Power Plant Components," 1998 Edition through 2000 Addenda, Appendix VIII, Supplement 2 and Supplement 10, as specified in Table VIII-3110-1. 3.3Proposed AlternativeThe licensee's proposed alternative to the applicable code requirements is described in thetable within RR I3R-05 that is entitled "Supplement 14 - Qualification Requirements for Coordinated Implementation of Supplement 10, 2 and 3 for Piping Examinations Performedfrom the Inside Surface." The alternative is also discussed in ASME Code Case N-696, "Qualification Requirements for Appendix VIII Piping Examinations Conducted from the InsideSurface,Section XI, Division 1," date May 21, 2003.3.4Licensee's Basis for the AlternativeThe licensee provided the basis for its request for relief in Attachment 1 to its letter datedMay 18, 2006. The licensee stated that separate qualifications for Supplements 2, 3, and 10 are redundant when done in accordance with the Electric Power Research Institute Performance Demonstration Initiative (PDI) program and provided the following example. During a personnel qualification to the PDI program, the candidate would be exposed to aminimum of 10 flawed grading units for each individual supplement and personnel qualificationsto Supplements 2, 3, and 10, and would, therefore, require a total of 30 flawed grading units. A full-procedure qualification requires 3 personnel qualifications which is a minimum of 90 flawedgrading units. The licensee stated that this duplication is particularly burdensome for personnel and procedures that use the same essential variables for all three supplements.The licensee also stated that, to resolve these issues, the PDI program recognized that theSupplement 10 qualifications are the most stringent and technically-challenging ultrasonic application and the same essential variables are used for the examinations subject to the requirements of Supplements 2, 3, and 10. A coordinated add-on approach to implementation would be sufficiently stringent for qualification to the requirements of Supplements 2 and 3, if the requirements used for qualification to Supplement 10 are satisfied as a prerequisite. The licensee stated that the basis for this conclusion is the fact that the majority of the flaws addressed in Supplement 10 are located wholly in austenitic weld material. This configuration is known to be challenging for ultrasonic techniques due to the variable dendritic structure of the weld material. Conversely, the flaws addressed in Supplements 2 and 3 initiate in fine-grained base materials.The licensee stated further that the use of the PDI program for implementation of Supplement 2requirements in coordination with Supplement 10 implementation would be more stringent than current ASME Code requirements for detection and length-sizing qualifications. The licensee gave an example that the current ASME Code would allow a detection procedure, personnel, and equipment to be qualified to Supplement 10 requirements with 5 flaws, Supplement 2 requirements with 5 flaws, and Supplement 3 requirements with 5 flaws, for a total of only 15 flaws. The proposed alternative of qualifying to Supplement 10 requirements using 10 flaws and adding 5 Supplement 2 flaws and 3 Supplement 3 flaws results in a total of 18 flaws. For procedure qualification, the PDI program consists of three times the number of flaws as a personnel qualification.Based on the above analysis, the licensee concluded that the use of a limited number ofSupplement 2 or Supplement 3 flaws is sufficient to assess the capabilities of procedures and personnel that have already satisfied Supplement 10 requirements and, therefore, the statistical basis used for screening personnel and procedures is maintained at the same level. The licensee also stated that the proposed alternative is addressed in ASME Code Case N-696, which has been approved by the ASME Code committee.3.5Technical EvaluationThe NRC staff has reviewed the licensee's RR No. I3R-05. The licensee requested relief fromthe qualification requirements of ASME Code,Section XI, Appendix VIII, Supplement 2 criteria. The ASME Code requires separate qualifications for Supplements 2 (austenitic piping welds),
3 (ferritic piping welds), and 10 (dissimilar metal piping welds). Personnel qualifications for each of the three supplements would entail a minimum of 10 flaws for a total of 30 flaws minimum. The minimum number of flaws per supplement established a statistically-based pass/fail objective. The process of qualification, using a single qualification for each supplement, would greatly expand the minimum number of ferritic and austenitic flaws required to be identified, which would also raise the pass/fail acceptance criteria. In Supplement 12, the ASME Code recognized that flaws in austenitic materials are moredifficult to detect and size than flaws in ferritic material. This supplement provides for a Supplement 3 add-on to a Supplement 2 qualification. A Supplement 12 performance demonstration consists of a minimum of 10 flaws with a minimum of six Supplement 2 flaws and a maximum of four Supplement 3 flaws. A statistical evaluation of test results using Supplement 12 acceptance criteria satisfied the pass/fail objective established for Appendix VIII performance demonstration acceptance criteria.The licensee's proposed alternative builds upon the experiences of Supplement 12 by startingwith the most challenging Supplement 10 qualifications, as implemented by the PDI program (PDI Supplement 10), and adding a sufficient number of Supplement 2 flaws to demonstrate personnel skills and procedure effectiveness. The proposed alternative is identified in a table in to the licensee's May 18, 2006, submittal as Supplement 14.PDI Supplement 10 personnel performance demonstration requires a minimum of 10 flaws withat least one flaw and a maximum of 10 percent of the total number of flaws being in the ferritic material. The rest of the flaws (nine or more) are in the more challenging austenitic material (Supplement 2). When expanding PDI Supplement 10 qualification to include Supplement 2,the proposed alternative would add a minimum of five flaws in the austenitic material to the performance demonstration which would bring the total number of flaws in austenitic material to 14 or greater. The performance demonstration results added to the appropriate PDI Supplement 10 results must satisfy the PDI Supplement 10 acceptance criteria. For a procedure qualification which includes equipment, the performance demonstration requirement is the equivalent of three personnel qualifications. The combined number of flaws in austenitic material of a Supplement 10 with an add-on Supplement 2 performance demonstration exceeds a stand-alone Supplement 2 performance demonstration.3.6ConclusionThe NRC staff has determined that qualification to Supplement 2 through the use of a limitednumber of Supplement 2 flaws added to the austenitic flaws of Supplement 10 provides equivalent flaw detection performance to that of a stand-alone Supplement 2 qualification for procedure, equipment, and personnel. As such, the licensee's proposed alternative provides an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the licensee's proposed alternative contained in Relief Request I3R-05 is authorized for the third 10-year ISI interval at Callaway.All other requirements of the ASME Code,Section XI, for which relief has not been specificallyrequested remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
4.0 TECHNICAL EVALUATION
OF RR NO. I3R-064.1Affected ComponentsThe affected components are ASME Code,Section XI, Examination Category B-A pressure-retaining welds in the reactor pressure vessel (RPV), Item B1.30, shell-to-flange weld (2-CH-101-101), and B1.40, head-to-flange weld (2-RV-101-121). 4.2Applicable Code RequirementsThe applicable code requirements are the ASME Code,Section XI, "Rules for InserviceInspection of Nuclear Power Plant Components," 1998 Edition through 2000 Addenda, Subsection IWA-2232 which requires ultrasonic testing (UT) of the RPV-to-flange weld be examined according to ASME Code,Section V, Article 4. Regulatory Guide (RG) 1.150, Revision 1, "Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations," provides guidance for UT examinations of RPV welds. 4.3Proposed AlternativeThe licensee's proposed alternative is to examine the shell-to-flange weld and head-to-flangeweld using qualified procedures in accordance with ASME Code,Section XI, 1998 Edition with 2000 Addenda, Appendix VIII, Supplements 4 and 6 as modified by 10 CFR Part 50 inaccordance with the Final Rule published in the Federal Register (64 FR 51370 through 51400,dated September 22, 1999). The examination of the shell-to-flange weld and head-to-flange weld, when performed from the flange face, will continue to be performed in accordance with ASME Code,Section V, Article 4, and RG 1.150, Revision 1.4.4Licensee's Basis for the AlternativeThe licensee provided the basis for its request for relief in Attachment 2 to its letter datedMay 18, 2006. The licensee proposed to employ personnel, procedures, and equipment that are qualified to the 1998 Edition with 2000 Addenda of ASME Code,Section XI, Appendix VIII, Supplements 4 and 6, as modified by an amendment to 10 CFR 50.55a per the Final Rule published in the Federal Register (64 FR 51370 through 51400) for the examination of the RPVshell-to-flange weld and RPV head-to-flange welds. The qualifications were administered by the PDI program.The licensee stated that Appendix VIII was developed to ensure the effectiveness of UTexaminations within the nuclear industry by means of a rigorous, item-specific performance demonstration. The performance demonstration was conducted on an RPV mockup containing flaws of various sizes at various locations and established the capability of equipment, procedures, and personnel to find flaws that would be detrimental to the integrity of the RPV.The licensee explained that although conformance with Appendix VIII is not a requirementwhen examining these welds, the Appendix VIII personnel and procedure qualifications havebeen demonstrated to be equal or superior to the requirements of paragraph IWA-2232, and the guidance in RG 1.150 demonstrations and requirements.The licensee stated further that the PDI-qualified sizing method is considered more accuratethan the method used in ASME Code,Section V, Article 4. The PDI program is in compliance with the detection and sizing tolerance requirements of Appendix VIII and the PDI sizingmethod is based on a group of representative flaws in samples that are used to demonstrate the sizing accuracy required by Section XI. The sensitivity to detect these flaws is considered to be equal to or greater than the sensitivity used by Section V, Article 4, UT techniques. 1EPRI Report NP-6273, "Accuracy of Ultrasonic Flaw Sizing Techniques for ReactorPressure Vessels," dated March 1989.Based on the above considerations, the licensee concluded that the proposed alternate UTexamination technique provides an acceptable level of quality and examination repeatability as compared to the Section V, Article 4, requirements.4.5Technical EvaluationThe NRC staff has reviewed the licensee's RR No. I3R-06. The 1998 Edition through 2000Addenda of the ASME Code,Section XI, IWA-2232 states, "Ultrasonic examination shall be conducted in accordance with Appendix I." Subparagraph I-2100(b) states, "Ultrasonic examination of reactor vessel-to-flange welds, closure head-to-flange welds, and integral attachment welds shall be conducted in accordance with Article 4 of Section V, except that alternative examination beam angles may be used. These examinations shall be further supplemented by Table I-2000-1." Section V, Article 4, as supplemented by Appendix I provides a prescriptive process for qualifying UT procedures. In lieu of Subparagraph I-2100(b) requirements, the licensee proposed using procedures, equipment, and personnel qualified in accordance with performance-based criteria as administered by the PDI program for the examination of RPV welds. The PDI program implements the requirements of Section XI, Appendix VIII, Supplements 4 and 6, as modified by 10 CFR 50.55a(b)(2)(xv). When prescriptive Section V, Article 4, UT procedures were applied in a controlled settingcontaining real flaws in mockups and the sizing results were statistically analyzed according to the performance-based screening criteria in Section XI, Appendix VIII, the prescriptive-basedsizing results were determined to be equal to or less effective than the sizing results from performance-based Section XI, Appendix VIII, procedures
- 1. The improvement in sizing isattributable to the echo-dynamic motion and tip-diffraction criteria used by performance-based UT, as opposed to the less accurate amplitude-drop criteria of prescriptive Section V, Article 4, requirements.For detection of flaws,Section V, Article 4 and RG 1.150 require indications of 20 percentdistance amplitude correction (DAC) and greater to be evaluated, whereas, performance-based UT requires that the essential variable settings used during the performance demonstration be used for the examinations which usually is DAC above the background noise. The performance-based UT is performed with higher sensitivity, which increases the chances ofdetecting a flaw when compared to prescriptive Section V, Article 4, requirements. Procedures, equipment, and personnel qualified through the PDI program have shown high probability of detection levels.Based on the above evaluation, the NRC staff concludes that this method has resulted in theincreased reliability of inspections for weld configurations within the scope of the PDI program and, therefore, the proposed alternative provides an acceptable level of quality and safety. 4.6ConclusionBased on the increased reliability of inspections within the scope of the PDI program, asdiscussed in the previous section, the NRC staff concludes that the licensee's proposed alternative in RR No. I3R-06 to use UT procedures, equipment, and personnel qualified to the 1998 Edition with 2000 Addenda of the ASME Code,Section XI, Appendix VIII, Supplements 4and 6, as modified by 10 CFR 50.55a(b)(2)(xv) for the RPV shell-to-flange weld and RPV head-to-flange weld, provides an acceptable level of quality and safety and is, therefore, acceptable. Based on this conclusion, pursuant to 10 CFR 50.55a(a)(3)(i), the proposed alternative in I3R-06 is authorized for the subject welds at Callaway for the third 10-year ISI interval. All other ASME Code,Section XI requirements for which relief was not specifically requestedand approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.Principal Contributor: Don Naujock Date: November 17, 2006 Callaway Plant, Unit 1 cc:Professional Nuclear Consulting, Inc.
19041 Raines Drive Derwood, MD 20855John O'Neill, Esq.Pillsbury Winthrop Shaw Pittman LLP 2300 N. Street, N.W.
Washington, D.C. 20037Mr. Keith A. Mills, Supervising EngineerRegional Regulatory Affairs/Safety Analysis AmerenUE P.O. Box 620 Fulton, MO 65251U.S. Nuclear Regulatory CommissionResident Inspector Office
8201 NRC Road Steedman, MO 65077-1302Mr. Les H. KanuckelManager, Quality Assurance AmerenUE P.O. Box 620 Fulton, MO 65251Missouri Public Service CommissionGovernor Office Building 200 Madison Street Jefferson City, MO 65102-0360Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005Mr. H. Floyd GilzowDeputy Director for Policy Missouri Department of Natural Resources P. O. Box 176 Jefferson City, MO 65102-0176Mr. Rick A. MuenchPresident and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KA 66839Mr. Dan I. Bolef, PresidentKay Drey, Representative Board of Directors Coalition for the Environment 6267 Delmar Boulevard University City, MO 63130Mr. Lee Fritz, Presiding CommissionerCallaway County Court House 10 East Fifth Street Fulton, MO 65151Mr. David E. Shafer Superintendent, Licensing Regulatory Affairs AmerenUE P.O. Box 66149, MC 470 St. Louis, MO 63166-6149Mr. Keith D. YoungManager, Regulatory Affairs AmerenUE P.O. Box 620 Fulton, MO 65251Mr. Keith G. Henke, PlannerDivision of Community and Public Health Office of Emergency Coordination 930 Wildwood P.O. Box 570 Jefferson City, MO 65102Certrec Corporation4200 South Hulen, Suite 630 Fort Worth, TX 76109Director, Missouri State Emergency Management Agency P.O. Box 116 Jefferson City, MO 65102-0116