Letter Sequence Acceptance Review |
---|
|
|
MONTHYEARML0307708822003-04-0202 April 2003 DC Cook, Units 1 & 2, Relief, Use of Alternatives to Pressure Retaining Bolting Inspection Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Relief Isir 11 Thru 13, MB6352, MB6353, MB6354, MB6355, MB63 Project stage: Acceptance Review 2003-04-02
[Table View] |
DC Cook, Units 1 & 2, Relief, Use of Alternatives to Pressure Retaining Bolting Inspection Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Relief Isir 11 Thru 13, MB6352, MB6353, MB6354, MB6355, MB63ML030770882 |
Person / Time |
---|
Site: |
Cook |
---|
Issue date: |
04/02/2003 |
---|
From: |
Raghavan L NRC/NRR/DLPM/LPD3 |
---|
To: |
Bakken A Indiana Michigan Power Co |
---|
stang J, NRR/DLPM, 415-1345 |
References |
---|
TAC MB6352, TAC MB6353, TAC MB6354, TAC MB6355, TAC MB6356, TAC MB6357 |
Download: ML030770882 (10) |
|
Similar Documents at Cook |
---|
Category:Code Relief or Alternative
MONTHYEARML22363A5622023-01-0404 January 2023 Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML21295A0092021-11-0303 November 2021 Relief Request ISIR-4-11 Limited Coverage Examinations During the Fourth 10 Year Inservice Inspection Interval ML21141A2612021-06-0202 June 2021 Alternative Request REL-PP2 Related to Fifth 10-Year Inservice Testing Program Interval ML21130A0082021-05-12012 May 2021 Relief Request ISIR-5-05 Related to ASME Code Case N 729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles (EPID L-2021-LLR-0033 (COVID-19)) ML21034A1552021-02-12012 February 2021 Relief Request ISIR-5-04 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML20290A4252020-10-15015 October 2020 Verbal Authorization of Relief Request ISIR-5-04 Regarding Alternative to N-729-6 for RPV Head Visual Examination AEP-NRC-2020-65, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-042020-10-0505 October 2020 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-04 ML20247J6562020-09-10010 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML19196A0642019-08-23023 August 2019 Relied Request ISIR-4-10 Regarding Fourth Inservice Inspection Program Interval ML18284A3102018-10-26026 October 2018 Approval of Alternative to the ASME Code Regarding Reactor Vessel Weld Examination - Relief Request ISIR-4-08 AEP-NRC-2018-33, Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination2018-06-14014 June 2018 Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination AEP-NRC-2018-20, Request for Alternative from Volumetric/Surface Examination Frequency Requirement of ASME Code Case N-729-4, Request Number Isir 04-5, Revision 12018-03-14014 March 2018 Request for Alternative from Volumetric/Surface Examination Frequency Requirement of ASME Code Case N-729-4, Request Number Isir 04-5, Revision 1 ML17096A6272017-04-12012 April 2017 Proposed Alternative to Use ASME OM Code Case OMN-20 ML16054A5722016-03-0404 March 2016 Relief Request REL-002 Associated with Valve Seat Leakage Testing ML15299A0482015-10-29029 October 2015 Alternative Isir 4-06 to the Requirements of the ASME Code AEP-NRC-2015-31, Submittal of 10 Cer 50.55a Requests Associated with the Fifth Ten-Year Inservice Testing Interval2015-07-31031 July 2015 Submittal of 10 Cer 50.55a Requests Associated with the Fifth Ten-Year Inservice Testing Interval ML15156A9062015-06-11011 June 2015 Request for Use of Alternative Isir 04-02 Associated with Reactor Vessel Closure Head Volumetric/Surface Examination Frequency Requirements for the Inservice Inspection Program AEP-NRC-2011-23, Relief Requests for Limited Coverage Examinations Performed in the Third 10-Year Inspection Interval2011-04-0808 April 2011 Relief Requests for Limited Coverage Examinations Performed in the Third 10-Year Inspection Interval AEP-NRC-2009-52, Third and Fourth Ten-Year Interval Inservice Inspection Program Relief Request ISIR-312009-08-21021 August 2009 Third and Fourth Ten-Year Interval Inservice Inspection Program Relief Request ISIR-31 AEP-NRC-2009-26, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-302009-02-27027 February 2009 Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-30 ML0903300652009-02-18018 February 2009 Relief Requests ISIR-23, ISIR-24 and ISIR-25 on End-of-Interval System Pressure Testing of Class 1 Components ML0830102372008-10-0707 October 2008 Relief Requests for Reactor Vessel Shell-to-Flange, and Nozzle to Safe-end Weld Examination AEP-NRC-2008-25, Use of Weld Inlays as an Alternative Repair Technique for Reactor Vessel Safe End-to-Primary Nozzle Alloy 82/182 Welds2008-10-0707 October 2008 Use of Weld Inlays as an Alternative Repair Technique for Reactor Vessel Safe End-to-Primary Nozzle Alloy 82/182 Welds ML0634200332006-12-29029 December 2006 Correction of Safety Evaluation Associated with Authorization of an Alternative ML0617301752006-06-28028 June 2006 D.C. Cook, Relief, Relief Requests for the Fourth 10-Year Pump and Valve Inservice Testing Program Interval ML0616403122006-06-0202 June 2006 Fourth 10-Year Interval Pump and Valve Inservice Testing Program - Request for Additional Information ML0607606732006-04-0303 April 2006 Relief Request REL-PP6 Regarding the West Essential Service Water Pump Test Frequency ML0603206912006-02-16016 February 2006 Alternatives Regarding Requirements for Examination of Dissimilar Metal Piping Welds ML0526503262005-09-13013 September 2005 Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI Repair Requirements ML0517200062005-06-27027 June 2005 6/27/05, D.C. Cook, Unit 1, Alternative to Repair Requirements of Section XI of the American Society of Mechanical Engineers Code ML0307708822003-04-0202 April 2003 DC Cook, Units 1 & 2, Relief, Use of Alternatives to Pressure Retaining Bolting Inspection Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Relief Isir 11 Thru 13, MB6352, MB6353, MB6354, MB6355, MB63 2023-01-04
[Table view] Category:Letter
MONTHYEARIR 05000315/20230042024-01-31031 January 2024 Integrated Inspection Report 05000315/2023004 and 05000316/2023004 ML24004A1582024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0039 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) AEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024 Emergency Plan Revision 48 AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023 Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor ML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23338A2642023-12-0505 December 2023 Confirmation of Initial License Examination AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation IR 05000315/20234042023-11-0606 November 2023 Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404 ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 IR 05000315/20234032023-09-19019 September 2023 Security Baseline Inspection Report 05000315/2023403 and 05000316/2023403 IR 05000315/20230112023-08-31031 August 2023 Functional Engineering Inspection - Commercial Grade Dedication Report 05000315/2023011 and 05000316/2023011 ML23242A1832023-08-30030 August 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report05000315/2023004 AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes IR 05000315/20234022023-08-11011 August 2023 Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402 AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation2023-08-0202 August 2023 Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation IR 05000315/20230022023-07-24024 July 2023 Integrated Inspection Report 05000315/2023002 and 05000316/2023002 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000315/20230122023-06-22022 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012 IR 05000315/20235012023-06-21021 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000315/2023501 and 05000316/2023501 AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023 Core Operating Limits Report ML23159A0192023-06-13013 June 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023 Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023 Renewable Operating Permit AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023 Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report ML23131A3282023-05-11011 May 2023 D.C. Cook Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000315/2023404 and 05000316/2023404 IR 05000315/20230012023-05-0303 May 2023 Integrated Inspection Report 05000315/2023001 and 05000316/2023001 AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023 Annual Radioactive Effluent Release Report ML23117A0062023-04-27027 April 2023 Review of the Spring 2022 Steam Generator Tube Inspections Report ML23114A1142023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2023-23, Annual Report of Individual Monitoring for 20222023-04-24024 April 2023 Annual Report of Individual Monitoring for 2022 AEP-NRC-2023-24, Notification of Ph Non-Compliance for Turbine Room Sump2023-04-12012 April 2023 Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-20, Annual Report of Property Insurance2023-04-0303 April 2023 Annual Report of Property Insurance AEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023 Decommissioning Funding Status Report ML23076A0212023-03-20020 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection; Inspection Report 05000315/2023011; 05000316/2023011 IR 05000315/20234012023-03-16016 March 2023 Security Baseline Inspection Report 05000315/2023401 and 05000316/2023401 ML23066A1882023-03-0707 March 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Donald C. Cook Nuclear Plant IR 05000315/20220062023-03-0101 March 2023 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022006 and 05000316/2022006) IR 05000315/20220042023-02-0101 February 2023 Integrated Inspection Report 05000315/2022004 and 05000316/2022004 and Exercise of Enforcement Discretion AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023 Form OAR-1, Owner'S Activity Report IR 05000315/20230102023-01-31031 January 2023 Phase 4 Post-Approval License Renewal Inspection Report 05000315/2023010 and 05000316/2023010 AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation2023-01-26026 January 2023 Request for Approval of Change Regarding Neutron Flux Instrumentation ML22363A5622023-01-0404 January 2023 Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022 Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in ML22340A1392022-11-30030 November 2022 Submittal of Revision 31 to Updated Final Safety Analysis Report and 10CFR50.71(e) Updated and Related Site Change Reports IR 05000315/20220112022-11-0404 November 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000315/2022011 and 05000316/2022011 IR 05000315/20220032022-10-28028 October 2022 Integrated Inspection Report 05000315/2022003 and 05000316/2022003 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-062022-10-24024 October 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06 2024-01-08
[Table view] Category:Safety Evaluation
MONTHYEARML22363A5622023-01-0404 January 2023 Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML22214A0012022-10-0707 October 2022 Issuance of Amendment Nos. 361 and 343 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22166A3302022-07-26026 July 2022 Review of Quality Assurance Program Changes ML22046A2332022-06-21021 June 2022 Issuance of Amendment Nos. 360 and 342 Regarding Change to the Technical Specification Requirement for Containment Water Level Instrumentation ML22055A0012022-06-0808 June 2022 Issuance of Amendment No. 341 Updating the Reactor Coolant System Pressure Temperature Limits ML22102A0122022-05-0202 May 2022 Issuance of Amendment Nos. 359 and 340 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21295A0092021-11-0303 November 2021 Relief Request ISIR-4-11 Limited Coverage Examinations During the Fourth 10 Year Inservice Inspection Interval ML21141A2612021-06-0202 June 2021 Alternative Request REL-PP2 Related to Fifth 10-Year Inservice Testing Program Interval ML21130A0082021-05-12012 May 2021 Relief Request ISIR-5-05 Related to ASME Code Case N 729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles (EPID L-2021-LLR-0033 (COVID-19)) ML21062A1882021-03-23023 March 2021 Issuance of Amendment No. 339 One Cycle Extension of Appendix J, Type a, Integrated Leakage Rate Test Interval (EPID L-2020-LLA-0280 (COVID-19)) ML21041A0862021-03-0303 March 2021 Issuance of Amendment No. 338 Regarding One-Time Deferral of the Steam Generator Tube Inspections ML21034A1552021-02-12012 February 2021 Relief Request ISIR-5-04 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML21006A4582021-02-0202 February 2021 Issuance of Amendments Nos. 358 and 337 Regarding Revision to Technical Specifications to Adopt Technical Specifications Task Force Traveler 541, Revision 2 ML20366A1552021-01-15015 January 2021 Issuance of Amendments Nos. 357 and 336 Regarding Revision to Technical Specifications Bases Control Program ML20366A1342021-01-13013 January 2021 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML20329A0012021-01-12012 January 2021 Issuance of Amendment No. 356 Regarding Updating the Reactor Coolant System Pressure-Temperature Limits ML20322A4282021-01-0606 January 2021 Issuance of Amendment Nos. 355 and 335, Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML20315A4832020-12-30030 December 2020 Issuance of Amendment Nos. 354 and 334 Adopt Technical Specification Task Force Traveler TSTF-412, Revision 3, Provide Actions for One Steam Supply to the Turbine Driven Afw/Efw Pump Inoperable ML20247J6562020-09-10010 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20213C7042020-09-0303 September 2020 Issuance of Amendment No. 353 One Cycle Extension of Appendix J, Type a, Integrated Leakage Rate Test Interval ML19347B3762020-01-31031 January 2020 Issuance of Amendment Nos. 350 and 331, Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in Accordance with Technical Specification Task Force TSTF-421 ML19329A0112020-01-23023 January 2020 Issuance of Amendment Numbers 349 and 330 to Apply Leak Before-Break Methodology to Reactor Coolant System Branch Lines and Deletion of Containment Humidity Monitor ML19304B6722019-12-31031 December 2019 Issuance of Amendment Numbers 348 and 329 to Revise Operating Licenses DPR-58 and DPR-74, to Address Issues Identified in Westinghouse Document NSAL-15-1 ML19259A0542019-10-15015 October 2019 Issuance of Amendment to Revise Operating Licenses DPR-58 and DPR-74, Appendix B, Environmental Technical Specifications, Part II, Non-Radiological Environment Protection Plan ML19196A0642019-08-23023 August 2019 Relied Request ISIR-4-10 Regarding Fourth Inservice Inspection Program Interval ML19170A3622019-08-0101 August 2019 Issuance of Amendment Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping ML19134A3552019-07-11011 July 2019 Issuance of Amendments Technical Specification Task Force (TSTF) Traveler 563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19031B9662019-04-10010 April 2019 Issuance of Amendments 344, 326 Regarding Request to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules ML18346A3582019-02-0505 February 2019 Issuance of Amendments 343 and 325 Regarding the Battery Monitoring and Maintenance Program ML18348A4182019-01-0909 January 2019 Units and 2 Approval of Request for Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N 729-4 ML18337A3942018-12-11011 December 2018 Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination ML18284A2542018-11-16016 November 2018 Issuance of Amendments Request for Deviation from National Fire Protection Association 805 Requirements ML18249A0192018-11-13013 November 2018 Issuance of Amendment Nos. 341 and 323 Technical Support Center Relocation ML18284A3102018-10-26026 October 2018 Approval of Alternative to the ASME Code Regarding Reactor Vessel Weld Examination - Relief Request ISIR-4-08 ML18131A2532018-07-0606 July 2018 Issuance of Amendments Request for Deviation from National Fire Protection Association 805 Requirements ML18103A0592018-04-19019 April 2018 Request for Use of Alternative Isir 04-05, Revision 1, Associated with Reactor Vessel Closure Head Volumetric/Surface Examination Frequency Requirements for the Inservice Inspection Program ML17312B0302017-12-19019 December 2017 Issuance of Amendments License Amendment Request to Revise Technical Specifications Section 3.7.2, Steam Generator Stop Valves (CAC Nos. MF9539 and MF9540; EPID L-2017-LLA-0198) ML17214A5502017-09-21021 September 2017 Issuance of Amendments License Amendment Request Regarding Technical Specification 3.9.3, Containment Penetrations ML17131A2772017-06-0707 June 2017 Issuance of Amendments License Amendment Request Regarding Containment Leakage Rate Testing Program ML17103A1062017-05-24024 May 2017 Issuance of Amendments Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML17096A6272017-04-12012 April 2017 Proposed Alternative to Use ASME OM Code Case OMN-20 ML17045A1502017-03-31031 March 2017 Issuance of Amendments Adopting of TSTF0425-A, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML16327A1102016-12-28028 December 2016 Cover Letter for Revised Safety Evaluation for Amendment Nos. 332 and 314 Adoption of TSTF-490, Rev. 0, and Implementation of Full-Scope Alternative Source Term ML16242A1112016-10-20020 October 2016 DC Cook, Units 1 and 2 - Issuance of Amendments Adoption of TSTF-490,REV.0,Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and Implementation of Full-Scope Alternative Source Ter ML16216A1812016-08-19019 August 2016 Issuance of Amendment to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation ML16195A0042016-08-0404 August 2016 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008 01, Managing Gas Accumulation ML16032A0312016-02-0404 February 2016 Request for Use of Alternative REL-PP1 Associated with Pump Inservice Testing (CAC Nos. MF6548 and MF6549) ML15327A2172015-12-11011 December 2015 Issuance of Amendments Technical Specifications Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.15 ML14197A0972015-11-30030 November 2015 Issuance of Amendment Regarding Restoration of Normal Reactor Coolant System Pressure and Temperature Consistent with Previously Licensed Conditions ML15264A8512015-11-0909 November 2015 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 2023-01-04
[Table view] |
Text
April 2, 2003 Mr. A. Christopher Bakken III, Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - REQUESTS FOR CODE RELIEF ISIR -11, ISIR-12 AND ISIR-13 (TAC NOS. Mb6352, MB6353, MB6354, MB6355, MB6356 AND MB6357)
Dear Mr. Bakken:
By letter dated September 12, 2002, the Indiana Michigan Power Company, submitted Relief Requests ISIR-11, ISIR-12 and ISIR-13 requesting the use of proposed alternatives to the pressure retaining bolting inspection requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code.
The Nuclear Regulatory Commission (NRC) staff has reviewed the Relief requests. The NRC staffs safety evaluation is enclosed. Pursuant to Title 10 of the Code of Federal Regulation, Part 50.55a(a)(3)(i), the proposed alternatives described in Relief Requests ISIR-11, ISIR-12 and ISIR-13 are authorized on the basis that the alternative inspections provides an acceptable level of quality and safety. The proposed alternatives are authorized for the third 10-year inservice inspection interval.
Sincerely,
/RA/
L. Raghavan, Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosures:
Safety Evaluation cc w/encls: See next page
ML030770882 *See previous concurrence OFFICE PM:PD3-1 LA:PD3-1 SC:EMCB* OGC* SC:PD3-1 NAME JStang THarris /RA/ by TChan AFernandez LRaghavan JStang DATE 04/02/03 04/02/03 03/31/03 04/01/03 04/02/03 Donald C. Cook Nuclear Plant, Units 1 and 2 cc:
Regional Administrator, Region III Drinking Water and Radiological U.S. Nuclear Regulatory Commission Project Division 801 Warrenville Road Michigan Department of Lisle, IL 60532-4351 Environmental Quality 3423 N. Martin Luther King Jr. Blvd.
Attorney General P. O. Box 30630, CPH Mailroom Department of Attorney General Lansing, MI 48909-8130 525 West Ottawa Street Lansing, MI 48913 Scot A. Greenlee Director, Nuclear Technical Services Township Supervisor Indiana Michigan Power Company Lake Township Hall Nuclear Generation Group P.O. Box 818 500 Circle Drive Bridgman, MI 49106 Buchanan, MI 49107 U.S. Nuclear Regulatory Commission David A. Lochbaum Resident Inspectors Office Union of Concerned Scientists 7700 Red Arrow Highway 1616 P Street NW, Suite 310 Stevensville, MI 49127 Washington, DC 20036-1495 David W. Jenkins, Esquire Michael J. Finissi Indiana Michigan Power Company Plant Manager One Cook Place Indiana Michigan Power Company Bridgman, MI 49106 Nuclear Generation Group One Cook Place Mayor, City of Bridgman Bridgman, MI 49106 P.O. Box 366 Bridgman, MI 49106 Joseph E. Pollock Site Vice President Special Assistant to the Governor Indiana Michigan Power Company Room 1 - State Capitol Nuclear Generation Group Lansing, MI 48909 One Cook Place Bridgman, MI 49106
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ASME SECTION XI INSERVICE INSPECTION PROGRAM THIRD INTERVAL RELIEF REQUEST INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316
1.0 INTRODUCTION
By letter dated September 12, 2002, the Indiana Michigan Power Company, submitted Relief Requests ISIR-11, ISIR-12 and ISIR-13 requesting the use of proposed alternatives to the pressure retaining bolting inspection requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code).
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(g), requires inservice inspection of pressure retaining bolting be performed in accordance with Section XI of the ASME Code, except where relief has been requested and granted or proposed alternatives have been authorized by the Commission pursuant to 10 CFR 50.55a(a)(3)(i), (a)(3)(ii) or (g)(6)(i). In the case of the subject relief requests the licensee has proposed alternatives to the code which provide an acceptable level of quality and safety. In proposing the alternatives the licensee must demonstrate that: (1) the proposed alternatives would provide an acceptable level of quality and safety, or (2) compliance would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety.
3.0 TECHNICAL EVALUATION
3.1 Inservice Inspection Program Alternative Request ISIR-11, Use Of Code Case N-616, Alternative Requirements For VT-2 Visual Examination of Class 1, 2, and 3 Insulated Pressure Retaining Bolted Connections 3.1.1 Code Requirements for which Relief is Requested 1989 Edition (No Addenda), of the ASME Boiler and Pressure Vessel (B&PV) Code Section XI:
Table IWB-2500-1 requires that the Class 1 connections be VT-2 examined each outage.
Tables IWC-2500-1 and IWD-2500-1, for Class 2 and 3 connections respectively, require that Class 2 and 3 connections be VT-2 examined each inspection period.
Subparagraph IWA-5242(a): For systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for VT-2 visual examination.
3.1.2 Licensees Proposed Alternative to Code Indiana Michigan Power Company (I&M) proposes the use of ASME Code Case N-616 for Class 1, 2, and 3 insulated systems borated for the purpose of controlling reactivity. VT-2 visual examinations during the system pressure tests required by IWB-5000, IWC-5000, and IWD-5000 would be performed without insulation removal, when the bolting material is resistant to boric acid degradation. The following restrictions will apply to those locations where this alternative request is used:
- 1. Pressure testing hold times will comply with ASME Section XI requirements (e.g., 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> for insulated components).
- 2. This alternative request will not apply to:
(1) Type 17-4PH stainless steel (SA-564 Grade 630) heat treated below1100°F or with a hardness (Rc) greater than 30.
(2) Type 17-4PH (SA-193 Grade B6) bolting heat treated below 1100°F or with Rc greater than 30.
(3) A-286 (SA-453 Grade 660) that is preloaded to greater than 100 ksi.
- 3. Use of Code Case N-616 will not apply to bolted connections where the associated piping, valve bodies, and pump casings contain less than 10%chromium, and are not in the proper heat treatment condition.
3.1.3 Licensees Basis for Relief Pursuant to 10 CFR 50.55a(a)(3)(i), authorization is sought to utilize ASME Code Case N-616 as an alternative to the requirements specified in the ASME B&PV Code Section XI, 1989 Edition, Subparagraph IWA-5242(a). Corrosion resistant bolted connections on borated systems consist of materials with chromium content greater than or equal to 10%, which are resistant to boric acid degradation. The basis for a minimum chromium content being used as a measure of susceptibility to degradation is established in Code Case N-616. In previous refueling outages, Class 1 bolted connections were inspected with insulation removed in accordance with IWA-5242(a). Where boric acid residues were identified and corrosion resistant bolting removed, no degradation was evident on the bolting material. These results were consistent with expectations that no boric acid corrosion degradation mechanism exists on the corrosion resistant materials.
The licensee contends that unnecessary physical hazard and radiation exposure exists to personnel in erecting and removing scaffolding, and removing and reinstalling insulation at nominal operating pressures and elevated temperatures.
The licensee conducts pressure tests utilizing a four-hour hold time on systems borated for the purpose of controlling reactivity in accordanace with ASME Section XI requirements.
3.1.4 NRC Staff Evaluation Cold working of the material that ultimately leaves the surface in tension provides a driving force for accelerated cracking. Heat treatment that does not sufficiently anneal the material to increase toughness leaves the material brittle and more susceptible to cracking; therefore, in employing Code Case N-616 certain actions must be taken in order to ensure that these factors are addressed. Code Case N-616 was approved by the ASME code committee on May 7, 1999, and is listed in Draft Regulatory Guide DG-1091, Table 2, Conditionally Acceptable Section XI Code Cases. The stipulations stated in the Draft Regulatory Guide are:
- 1. Insulation must be removed for VT-2 examination during the system pressure test for any 17-4 PH stainless steel or 410 stainless steel stud or bolt aged at a temperature below 1,100 oF or with hardness above Rc 30.
- 2. For A-286 stainless steel studs or bolts, the preload must be verified to be below 100 Ksi or the thermal insulation must be removed and the joint visually examined.
- 3. For nuts conforming to SA-194, removal of the insulation for visual inspection is not necessary.
- 4. A 4-hour hold time at operating temperature and pressure is required prior to conducting the VT-2 examination.
The licensee has committed to meeting these conditions. Therefore, the use of Code Case N-616 with the limitations committed to by the licensee is acceptable.
3.1.5 Summary Based on the previous discussion, the staff concludes that the use of Code Case N-616 with the limitations committed to by the licensee under the alternative proposed in Proposed Alternative ISIR-11, will provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the staff authorizes the proposed alternative for the third 10-year ISI interval at Donald C. Cook Nuclear Plant, Units 1 and 2.
3.2 Inservice Inspection Program Alternative Request ISIR-12, Use Of Code Case N-307-3, for Pressure Retaining Bolting Greater than 2 inches in Diameter 3.2.1 Relief Request ISIR-12 System/Components for Which Relief is Requested Examination of Class 1 bolting, ASME Code Category B-G-1.
3.2.2 Code Requirements for Which Relief is Requested The licensee is requesting relief from the 1989 Edition of ASME Section XI, Table IWB-2500-1, Examination Category B-G-1 for the third 10-year interval.
(a) Examination Figure IWB-2500-12 for Item B6.30 requires the examination volume be defined as the full volume of the load-bearing portion of the stud.
(b) Table IWB-2500-1, Examination category B-G-1, requires that the examinations include both a surface and volumetric methods when the studs are removed (Item B6.30).
3.2.3 Licensees Proposed Alternative to Code Pursuant to 10 CFR 50.55a(a)(3)(i), the licensee requests approval to use the proposed alternative to Code.
For ultrasonic examinations (UT) inspections, the licensee proposes to use the ASME Code Case N-307-3. The volumetric examinations will be performed with procedures and personnel qualified in accordance with ASME Section XI, Appendix VIII 3.2.4 Licensees Bases for Requesting Relief (a) In ASME Code Case N-307-2, which was passed by ASME on September 24, 1999 and incorporated in the 2000 Addenda of the ASME Section XI Code, the required volume was reduced to include the outside diameter to a radial depth of 1/4" when performing volumetric examinations on RPV (reactor pressure vessel) studs. (Code Case N-307-3 was passed by the ASME Main Committee on February 16, 2001, and is scheduled for publication in the next ASME Supplement.)
(b) Table IWB-2500-1 in the 2000 Addenda of the ASME Section XI Code specifies that a volumetric or surface examination be performed when RPV studs are removed. Code Case N-307-3 was developed to allow similar provisions for earlier editions of the Code.
The only difference is the surface examination may be eliminated when performing volumetric examinations from the end of the stud or from the center-drilled hole. Changing the examination requirements to a volumetric examination only reduces the necessary manpower and is consistent with the as low as reasonably achievable (ALARA) principle.
Typically, extensive cleaning of the heavy and contaminated studs is required prior to the fluorescent magnetic particle (MT) examinations, which creates logistic problems.
Performing only a volumetric (UT) examination does not require extensive cleaning and does not generally create logistic problems. To perform the volumetric examination, only one end of the stud is required to be accessible and the total preparation and examination time is reduced by a factor of 10.
3.2.5 NRC Staff Evaluation In lieu of the examination requirements of Section XI, Figure IWB-2500-12, Item B6.30, Code Case N-307-3 reduces the examination volume to that of a volumetric cylinder 1/4" deep from the root of the threads. The root of the threads are stress risers and preferred sites for crack initiation. Cracks at the root of the threads would be perpendicular to straight beam UT performed from the stud ends, and the cracks would create a corner trap for angle beam UT examinations performed from a center hole in the stud. The capabilities of a UT examination finding cracks in a stud is demonstrated through procedure and personnel qualifications. These are performance-based qualifications according to the requirements of Section XI, Appendix VIII, Supplement 8.
In lieu of the examination requirements of Section XI, Table IWB-2500-1, Item B6.30, Code Case N-307-3 eliminates surface examination of the RPV closure stud when removed. The function of UT examination is to find cracks in the stud volume. These cracks, if they exist, initiate from the surface. The function of the surface examination is to find cracks on the surface. Performing both volumetric and surface examinations on a stud duplicates the intent of the examinations which is to find cracks. Of the two nondestructive examination methods, surface examinations are tedious and subjective, and performance-based UT provides demonstrated assurances for finding cracks. Therefore, elimination of the surface examination does not diminish the effectiveness in detecting cracks.
Code Case N-307-3, was developed through a consensus building process. The NRC, through its normal participation in the ASME committee process, participated in this process through which it expressed the staffs opinion and support.
3.2.6 Summary Based on the above information, the NRC staff has concluded that the proposed alternative (ISIR-12) to reduce the ultrasonic testing volume, and eliminate the surface examination will provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the proposed alternative (ISIR-12) is authorized for the third 10-year ISI interval.
3.3 Inservice Inspection Program Alternative Request ISIR-13 Use Of Code Case N-627, for Pressure Retaining Bolting Greater than 2 inches in Diameter 3.3.1 Components for Which Relief is Requested Class 1 reactor pressure vessel closure head nuts.
3.3.2 ASME Code Requirement from Which Relief is Requested ASME Code,Section XI, 1989 Edition, Rules for Inservice Inspection of Nuclear Plant Components, Table IWB-2500-1, Examination Category B-G-1, Reactor Vessel, Item No.
B6.10, closure head nuts, requires a surface examination of all closure head nuts each interval.
3.3.3 Content of the Relief Request Relief is requested to conduct a VT-1 visual inspection in lieu of the surface examinations of RPV closure head nuts as required by the 1989 Edition of ASME Code,Section XI, Table IWB-2500-1, Code Category B-G-1, Item No. B6.10.
3.3.4 Basis for Requesting Relief and Justification for Granting Relief The licensee states that only the outside surface of the RPV closure head nuts is readily available for surface examination. The inside of the nuts is difficult to clean for either liquid penetrant or magnetic particle examination. It is also possible that pooling of the liquid penetrant or magnetic particles can occur because the nut must be placed on its side for examination. The licensee also stated that damage could occur to the nuts during handling due to the weight of the nuts and the difficulty of moving them.
The 1989 Edition of ASME Code,Section XI, does not provide acceptance criteria for Examination Category B-G-1 surface flaws found during the examinations. Beginning with the 1989 Addenda of ASME Code,Section XI, the examination requirement for RPV closure head nuts was changed from a surface examination to a visual VT-1 examination. In addition, the acceptance standards of IWB-3517 were adopted, which is the same standard for B-G-2 bolting. This examination technique and acceptance standard has not been changed in later editions of the Code.
The 1995 Edition of ASME Code,Section XI, with Addenda through 1996 includes a requirement to perform a VT-1 on RPV nuts instead of a surface examination. This Code edition and addenda have been approved for use in the latest revision to 10 CFR 50.55a.
3.3.5 Proposed Alternative Examination The licensee proposes to use the alternative requirements of ASME Code Case N-627, Visual Examination in Lieu of Surface Examination for RPV Closure Head Nuts,Section XI, Division 1.
The acceptance criteria of the 1995 Edition with Addenda through 1996, IWB-3517, will be used for the evaluation of the indications noted during examinations.
3.3.6 NRC Staff Evaluation The examination requirement for RPV closure head nuts was changed from a surface examination to a VT-1 examination in the 1989 Addenda of ASME Code,Section XI. This change to the Code has been retained in later editions of the Code. There were two major reasons for making this change. The first reason is that the closure head nuts were susceptible to damage as a result of handling during the surface examination. The second reason was that due to the way that nuts are loaded (the threads are in compression), they are not susceptible to primary water stress corrosion cracking (PWSCC). The purpose of the surface examination is to identify evidence of PWSCC. The NRC staff is not aware of any occurrences of PWSCC in any kind of nuts. Therefore, performance of a VT-1 visual examination in lieu of a surface examination will provide adequate assurance of structural integrity of the RPV closure head nuts, while at the same time, eliminate the likelihood of damage associated with handling during a surface examination.
3.3.7 Summary Based on the above evaluation, the NRC staff concludes that the use of ASME Code Case N-627 with the VT-1 examination requirements of the 1995 Edition of ASME Code,Section XI, Paragraph IWA-3517, provides an acceptable level of quality and safety for examination of the RPV closure head nuts. Therefore, the licensees proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for the third ISI interval at D. C. Cook Units 1 and 2.
4.0 CONCLUSION
The NRC staff has concluded, based on the considerations discussed above, that there is reasonable assurance that the health and safety of the public will not be endangered by implementation of the proposed alternatives, and that such activities will be conducted in
compliance with the Commissions regulations, therefore, Relief Requests ISIR-11, ISIR-12 and ISIR-13 are authorized. 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 Inservice Inspector.
Principal Contributor: John Stang Date: April 2, 2003