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MONTHYEARML17058A4432017-03-0606 March 2017 Request for Alternative I4R-03 Applicable to the Fourth 10-Year Inservice Inspection Program Interval Project stage: Other 2017-03-06
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Category:Code Relief or Alternative
MONTHYEARML20225A2922020-08-12012 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) 2020-08-12
[Table view] Category:Letter
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 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 ML23346A0392023-12-14014 December 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Relief from Requirements of ASME Code, Section Xl, Examination and Testing Unbonded Post-Tensioning System 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 05000483/LER-2023-001, Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications2023-11-29029 November 2023 Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications 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) IR 05000483/20230102023-11-15015 November 2023 NRC License Renewal Phase 1 Inspection Report 05000483 2023010 IR 05000483/20233012023-11-0909 November 2023 NRC Examination Report 05000483-2023301 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23297A2502023-11-0606 November 2023 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - Letter IR 05000483/20240122023-10-24024 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012) ML23293A2652023-10-24024 October 2023 3rd Quarter 2023 Integrated Inspection Report 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) 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) ML23305A0942023-10-0202 October 2023 10-CW-2023-09 Post-Exam Submittal ML23270B9662023-09-27027 September 2023 10 CFR 50.55a(z)(I) Request for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval 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 ML23206A1992023-09-15015 September 2023 Regulatory Audit Summary Regarding License Amendment and Regulatory Exemptions Request for Fuel Transition to Framatome Gaia Fuel (Epids L-2022-LLA-0150 and L-2022-LLE-0030) IR 05000483/20234012023-09-13013 September 2023 NRC Security Baseline Inspection Report 05000483/2023401 ML23240A7572023-08-31031 August 2023 NRC Initial Operator Licensing Examination Approval 05000483/2023301 IR 05000483/20230052023-08-23023 August 2023 Updated Inspection Plan for Callaway Nuclear Power Plant, Unit 1 (Report 05000483/2023005) - Mid Cycle Letter 2023 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 ML23219A1392023-08-15015 August 2023 Request for Withholding Information from Public Disclosure 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 ML23215A1972023-08-0303 August 2023 Supplement to License Amendment and Exemption Request Regarding Use of Framatome Gaia Fuel (LDCN 22-0002) 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 IR 05000483/20230022023-07-10010 July 2023 Integrated Inspection Report 05000483/2023002 ML23174A1272023-06-23023 June 2023 Cw FFD Document Request List 2023 ML23171A9942023-06-22022 June 2023 Acceptance of Request for Approval of Operating Quality Assurance Manual Revision 36a 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) IR 05000483/20230112023-06-15015 June 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000483/2023011 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 ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) 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 . ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage 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) ML23129A7942023-05-0909 May 2023 Post-Audit Supplement to License Amendment Request and Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (Iepid L-2022-LLA-0150 and EPID L-2022-LLE-0030) ML23122A3172023-05-0808 May 2023 Review of the Spring 2022 Steam Generator Tube Inservice Inspections ML23118A3492023-05-0808 May 2023 Request for Withholding Information from Public Disclosure 2024-01-29
[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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 3, 2017 Mr. Fadi Diya Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT, UNIT NO. 1 -REQUEST FOR ALTERNATIVE 14R-03 APPLICABLE TO THE FOURTH 10-YEAR INSERVICE INSPECTION PROGRAM INTERVAL (CAC NO. MF7700)
Dear Mr. Diya:
By letter dated May 11, 2016, Union Electric Company (Ameren Missouri, the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements for system leakage testing of the reactor pressure vessel (RPV) head flange leakoff lines at the Callaway Plant, Unit No. 1 (Callaway).
The proposed alternative in Relief Request 14R-03 is to perform the system leakage test of the RPV flange leakoff lines at Callaway, using the static pressure developed when the refueling cavity is filled to the normal refueling water level in lieu of the pressure required by ASME Code,Section XI, paragraph IWC-5221. Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR) 50.55a(z)(2), the licensee proposed an alternative system leakage test on the basis that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Therefore, the NRC authorizes the licensee's proposed alternative for system leakage testing of the RPV for the duration of the fourth 10-year inservice inspection interval at Callaway ending on December 18, 2024.
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
F. Diya If you have any questions, please contact the Project Manager, John Klos, at 301-415-5136 or via e-mail at John.Klos@nrc.gov.
Sincerely, Robert J. Pascarelli, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ALTERNATIVE 14R-03 REGARDING PRESSURE TESTING OF REACTOR PRESSURE VESSEL FLANGE SEAL LEAKOFF LINES UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT NO. 1 DOCKET NO. 50-483
1.0 INTRODUCTION
By letter dated May 11, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16132A330), Union Electric Company (Ameren Missouri, the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code),Section XI requirements for system leakage testing of the reactor pressure vessel (RPV) head flange leakoff lines at the Callaway Plant, Unit No. 1 (Callaway).
The proposed alternative in Relief Request 14R-03 is to perform the system leakage test of the RPV flange leakoff lines at Callaway, using the static pressure developed when the refueling cavity is filled to the normal refueling water level in lieu of the pressure required by ASME Code,Section XI, paragraph IWC-5221. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee proposed an alternative system leakage test on the basis that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
2.0 REGULATORY REQUIREMENTS Pursuant to 10 CFR 50.55a(g)(4), "lnservice inspection standards requirement for operating plants," throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) that are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI of editions and addenda of the ASME Code that become effective subsequent to editions specified in paragraphs (g)(2) and (3) of 10 CFR 50.55a and that are incorporated by reference in paragraph (a)(1)(ii) of 10 CFR 50.55a, to the extent practical within the limitations of design, geometry, and materials of construction of the components.
Pursuant to 10 CFR 50.55a(g)(4)(ii), "Applicable ISi Code: Successive 120-month Intervals,"
inservice examination of components and system pressure tests conducted during successive 120-month inspection intervals must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (a) of 10 CFR 50.55a 12 months Enclosure
before the start of the 120-month inspection interval (or the optional ASME Code Cases listed in NRC Regulatory Guide 1.147, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 17, August 2014 (ADAMS Accession No. ML13339A689}, when using Section XI, that is incorporated by reference in paragraph (a)(3)(ii) of 10 CFR 50.55a), subject to the conditions listed in paragraph (b) of 10 CFR 50.55a. However, a licensee whose inservice inspection interval commences during the 12 through 18-month period after July 21, 2011, may delay the update of its Appendix VIII program by up to 18 months after July 21, 2011.
Section 50.55a(z), "Alternatives to codes and standards requirements," of 10 CFR states, in part:
Alternatives to the requirements of paragraphs (b) through (h) of [10 CFR 50.55a]
or portions thereof may be used when authorized by the Director, Office of Nuclear Reactor Regulation, or Director, Office of New Reactors, as appropriate.
A proposed alternative must be submitted and authorized prior to implementation.
The applicant or licensee must demonstrate that:
(1) Acceptable level of quality and safety, the proposed alternative would provide an acceptable level of quality and safety; or (2) Hardship without a compensating increase in quality and safety, compliance with the specified requirements of 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the NRC to authorize the alternative requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 Background By letter dated August 13, 2013 (ADAMS Accession No. ML13221A091}, the NRC authorized Relief Request 13R-14, which was the same alternative system leakage test of the RPV head flange seal leakoff lines for the third 10-year inservice inspection (ISi) interval of Callaway.
3.2 Component Affected The component affected is ASME Code Class 2 RPV head flange seal leakoff line piping. In accordance with IWC-2500 (Table IWC-2500-1), this component is classified as Examination Category C-H, Item Number C7.10.
The licensee stated that scope of this relief request includes:
Line Numbers: BB-075-BCB-o/.i", BB-075-BCB-1", BB-075-BCB-2",
BB-076-BCB-o/.i", BB-076-BCB-1 ", BB-076-BCB-2",
BB-077-BCB-%"
Valve Numbers: BBV0079, BBV0080,BBV0081,BBHV8032
The licensee stated that the materials of construction for piping is austenitic stainless steel SA-312, TP-304, Schedule 160. The design and service pressure and temperature for the piping are as follows:
Design pressure: 2485 pounds per square inch gauge (psig)
Design temperature: 650 degrees Fahrenheit (°F)
Service pressure: 2235 psig Service temperature: 618 °F In a letter dated May 6, 2013 (ADAMS Accession No. ML13126A304), the licensee submitted additional information related to another request, Relief Request 13R-14, including that the total length of the pipe from the outer monitor tube, line BB-075-BCB, to valve BBHV8032, which is the outermost limit of the system subject to the pressure test, is 79 feet. This system does have 21 socket welds, 8 of which are inaccessible behind the primary shield wall, with the rest located outside of the bioshield wall.
3.3 Applicable Code Edition and Addenda As stated by the licensee, the code of record for the fourth 10-year ISi interval is the 2007 Edition with 2008 Addenda of the ASME Code,Section XI.
3.4 Duration of Relief Request The licensee submitted this relief request for the fourth 10-year ISi interval, which started on December 19, 2014, and is scheduled to end on December 18, 2024.
3.5 ASME Code Requirement The ASME Code requirements applicable to this request originate in IWC-2500 of Section XI (Table IWC-2500-1, Examination Category C-H, Item No. C7.10). As required by Item No. C7 .10, the pressure retaining components shall be subjected to system leakage test according to IWC-5220 and the associated VT-2 visual examination according to IWA-5240 during each inspection period. As required by IWC-5221 and stated in the licensee's application, The system leakage test shall be conducted at the system pressure obtained while the system, or portion of the system, is in service performing its normal operating function or at the system pressure developed during a test conducted to verify system operability (e.g., to demonstrate system safety function or satisfy technical specification surveillance requirements).
3.6 Proposed Alternative The licensee proposed to perform system leakage test of the RPV head flange seal leakoff line piping with the static pressure head developed from the elevation of at least 23 feet of normal refueling water above the RPV closure flange when the reactor cavity is flooded for refueling, for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The licensee stated that this yields a pressure of at least 1O psig at the flange and 17 psig at the lowest elevation of piping.
- 3. 7 Basis for Alternative The licensee stated that the RPV head flange 0-ring leakoff lines direct leakage, if any, from the RPV head flange to the reactor coolant drain tank (RCDT) and provide alarms to alert the control room of leakage. These lines are separated from the reactor coolant system (RCS) operating pressure by an inner and outer RPV flange 0-ring. The inner 0-ring, in conjunction with the reactor vessel and reactor vessel head flange surfaces, functions to isolate the inner and outer RPV head flange leakoff lines from RCS pressure. The outer 0-ring functions as a backup in the event of the inner 0-ring failing to perform its intended function. Therefore, the affected leakoff lines are not expected to experience RCS pressure during normal operation.
During normal operation, the lines are typically pressurized to the RCDT pressure of 4 psig.
The licensee stated that the Class 2 portions from the reactor vessel flange to the Class 2 boundaries are required to be subject to the associated VT-2 visual examination.
Lines BB-075-BCB and BB-076-BCB run parallel to each other and are inaccessible for the first 32 feet due to being located in the annulus area between the RPV and primary shield wall.
The annulus can only be accessed by way of the refueling cavity, which is filled with water during the test, or by way of the incore tunnel underneath the RPV, which is prohibited from being entered due to high radiation dose rates from the incore flux mapping thimbles being withdrawn from the reactor vessel. Accessible portions of the lines subject to the VT-2 visual examination include 22 feet of piping that is not insulated and 2 feet of piping that is insulated.
The licensee stated that Callaway's work history, as well as corrective action history, was reviewed for service-related failures of the piping and components in this relief request. The review identified no occurrences of leakage or other failures on these piping and welded connections.
3.8 Basis for Hardship The licensee stated that with the new 0-rings installed and performing their intended function, the leakoff lines are not expected to be pressurized above the RCDT pressure of 4 psig during the system leakage test following a refueling outage. Pressurizing by a hydrostatic test pump to perform the Code-required pressure test could unseat the installed inner 0-ring and damage it.
This would result for additional maintenance, which would require depressurizing and removing the RPV head, reinstalling new sets of 0-rings, and reinstalling the head. The above activities would take additional time and expose personnel to additional radiation dose.
The licensee stated that performing a leakage test during shutdown prior to removal of the head for refueling activities would require the plant to be maintained in Mode 3 at normal operating temperature and pressure at higher decay heat loads, resulting in an incremental increase in core damage frequency. This would be contrary to site efforts to reduce the outage sequence/time to cold shutdown in order to minimize shutdown risk. Performing such a test would result in additional radiation exposure.
The licensee stated that with the RPV head removed, the configuration of the leakoff piping would require the lines to be plugged at the RPV flange to establish a boundary for leakage testing at system operating pressure. This would require a design modification to install mechanical threads into each leakoff line at the location of the RPV flange. Threaded plugs would then have to be installed prior to the pressure test and removed after the test was complete. Failure of either plug during the test would result in a personnel safety hazard, in addition to creating a foreign material exclusion (FME) issue. Performing the modification, as
well as installation and removal of the plugs for each pressure test, would result in additional dose, which would be contrary to keeping dose as low as reasonably achievable (ALARA), and would present FME issues.
3.9 NRC Staff Evaluation The NRC staff has evaluated Relief Request 14R-03 pursuant to 10 CFR 50.55a(z)(2). The NRC staff focused on whether compliance with the specified requirements of 10 CFR 50.55a(g),
or portions thereof, would result in hardship or unusual difficulty, and if there is a compensating increase in the level of quality and safety despite the hardship.
The NRC staff found that requiring the licensee to comply with IWC-5221 and conduct the ASME Code system leakage test of the RPV head flange seal leakoff lines at the RCS operating pressure would result in hardship. The basis for the hardship is as follows.
- When the RPV head is removed for refueling, the licensee would have to modify the existing RPV head flange taps to install plugs to facilitate for pressurizing the leakoff piping by use of a hydrostatic test pump. The activities associated with installing the plugs, pressurizing the piping to the RCS pressure and conducting the ASME Code required system leakage test, and removing the plugs after completion of test would cause personnel to incur additional radiation dose, and could introduce foreign materials into the reactor pool as well as the lines.
- When the RPV head is installed after refueling, pressurizing the lines would not be possible due to design and configuration of the RPV head flange taps and the inner 0-ring. The inner 0-ring is designed to withstand pressure in one direction only.
Pressurizing in the opposite direction could damage the inner 0-ring, and even result in an unsuccessful test. Activities associated with replacing the 0-rings due to damage to the inner 0-ring would expose personnel to additional radiation dose.
- At the beginning of the refueling outage when the RPV head is on, externally pressurizing the lines would result in pressurizing the inner 0-ring in the opposite direction, which could damage the 0-ring, result in an unsuccessful test, and subject personnel to additional radiation dose. The entire containment has access limitations due to high radiation levels.
Therefore, the NRC staff determined that concerns from the FME program and ALARA constitute a hardship.
Test Pressure In evaluating the licensee's proposed alternative, the NRC staff assessed whether it appeared that the licensee used the highest achievable test pressure to conduct system leakage testing and the manner in which the licensee adequately preformed the testing and the associated VT-2 visual examinations of the piping for leakage. The NRC staff found that:
- The licensee will use the highest pressure that is obtainable without major modifications to existing configuration of the lines to test the leakoff piping for leakage. Specifically, the leakoff piping in this relief request will be subject to the static pressure of at least
10 psig. This static pressure head is developed from the elevation of 23 feet of refueling water above the vessel flange during the refueling cavity floodup.
- The licensee will conduct the associated VT-2 visual examination of the insulated area of the piping (according to IWA-5242) and the non-insulated area of the piping (according to IWA-4241) after attaining and maintaining the test pressure for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to allow for leakage accumulate at the potential leak location and be detected by the examination.
- The proposed system leakage test will be conducted at frequency of each inspection period as required by Table IWC-2500-1, Examination Category C-H, Item No. C7.10.
Therefore, the NRC staff determines that the proposed system leakage test is adequate because the leakoff piping in this relief request will be pressurized to a test pressure that is as high as reasonably achievable, and will be subject to the IWA-5240 required VT-2 visual examination after hold time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> that is equal or greater than hold time required by IWA-5213.
Structural Integrity and Leak Tightness In addition to the analysis described above, the NRC staff considered whether performance of the system leakage test at an alternative reduced pressure provided reasonable assurance of structural integrity and leak tightness of the piping and associated welded connections.
The NRC staff notes that although the proposed test pressure is lower than the ASME Code required test pressure, it still allows for adequate pressurization of the components, and as accompanied with the ASME Code required VT-2 visual examination, it allows for detection of potential leakage.
- As part of pressure test, the licensee will perform the VT-2 visual examination of the components (accessible, inaccessible, insulated, and non-insulated) in accordance with the IWA-5240 requirements to identify any through wall leak.
- The VT-2 visual examination of accessible, inaccessible, insulated, and non-insulated segment of piping will be performed after attaining and holding test pressure for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to allow for leakage accumulate at the potential leak location, and be detected by the examination.
Therefore, the NRC staff determines that based on the alternative system leakage testing that subject these piping to the maximum obtainable pressure and the performance of the ASME Code required VT-2 visual examinations, it is reasonable to conclude that if significant service induced degradation had occurred, evidence of it would be detected by the examinations that the licensee performed.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the proposed alternative provides reasonable assurance of structural integrity and leak tightness of the Class 2 RPV head flange seal leakoff lines and complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set
forth in 10 CFR 50.55a(z)(2). Therefore, the NRC staff authorizes the use of the licensee's proposed alternative at Callaway, for the fourth 10-year ISi interval which started on December 19, 2014, and is scheduled to end on December 18, 2024.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved remain applicable, including the third party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: Ali Rezai Date: March 3, 2017
ML17058A443 *concurrence via SE OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA N RR/DE/EPN B/BC* NRR/DORL/LPL4/BC NAME JKlos PBlechman DAiiey RPascarelli DATE 03/01/17 02/28/17 09/27/16 03/03/17