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MONTHYEARML1201702412012-01-17017 January 2012 Acceptance Review Determination for LAR to Use Modified Alloy 718 Material for Jet Pump Holddown Beams Project stage: Acceptance Review ML1202302372012-02-0202 February 2012 Federal Register Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed Nshcd and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI Project stage: Other ML1202302332012-02-0303 February 2012 Transmittal Letter - Notice of Consideration of Issuance of Amendment, Proposed NSHC Determination, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI Project stage: Other ML1207200982012-03-15015 March 2012 Request for Withholding Information from Public Disclosure - Proposed LAR Use of Modified Alloy 718 Material in Jet Pump Holddown Beams - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML1209403732012-04-13013 April 2012 Issuance of Amendment Regarding Use of Modified Alloy 718 Material in Jet Pump Holddown Beams Project stage: Approval ML13078A3232013-02-28028 February 2013 XGEN-2012-25-NP, Revision 1, Westinghouse Engineering Report, Technical Basis for the Inspection Frequency of the Modified Alloy 718 Jet Pump Beam, Attachment 2 Project stage: Request ML13130A1582013-05-0303 May 2013 Submittal of Evaluation to Establish Inspection Intervals for Jet Pump Holddown Beams Fabricated from Modified Alloy 718 Material - Supplemented Affidavit Justifying Withholding Proprietary Information Project stage: Request ML13101A2742013-05-23023 May 2013 Request for Withholding Information from Public Disclosure Submittal of Evaluation to Establish Inspection Intervals for Jet Pump Holddown Beams Fabricated from Modified Alloy 718 Material Project stage: Withholding Request Acceptance 2012-03-15
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Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NMP1L3484, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-15015 December 2022 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. NMP1L3467, License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage2022-06-29029 June 2022 License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage NMP2L2799, License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators2022-05-24024 May 2022 License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position NMP2L2762, License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2021-05-26026 May 2021 License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments NMP1L3369, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-12-18018 December 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process NMP2L2716, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-12-26026 December 2019 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors NMP2L2706, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.2019-10-31031 October 2019 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP1L3278, License Amendment Request - Administrative Changes to the Technical Specifications2019-06-26026 June 2019 License Amendment Request - Administrative Changes to the Technical Specifications RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NMP2L2699, License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate2019-05-31031 May 2019 License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. NMP2L2694, Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances2018-12-0606 December 2018 Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances NMP1L3192, License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration2018-06-26026 June 2018 License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) NMP1L3188, License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks2018-02-0909 February 2018 License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks NMP1L3142, License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-15015 December 2017 License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 RS-17-137, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-11-0808 November 2017 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NMP2L2660, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change2017-11-0303 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017 License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note NMP1L3158, Enclosure 4E - Procedure Matrix for Nine Mile Point Nuclear Station, Unit 12017-05-31031 May 2017 Enclosure 4E - Procedure Matrix for Nine Mile Point Nuclear Station, Unit 1 NMP2L2641, License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 02017-05-31031 May 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 0 ML17164A1532017-05-31031 May 2017 Enclosure 4B - EAL Red-Line Basis Document for Nine Mile Point Nuclear Station, Unit 1 ML17164A1552017-05-31031 May 2017 Enclosure 4D - EAL Front Matter for Nine Mile Point Nuclear Station, Unit 1 ML17164A1542017-05-31031 May 2017 Enclosure 4C - EAL Basis Document for Nine Mile Point Nuclear Station, Unit 1 JAFP-17-0050, Exigent License Amendment Request to Revise Emergency Action Level HU1.52017-05-19019 May 2017 Exigent License Amendment Request to Revise Emergency Action Level HU1.5 ML17037C4192017-05-11011 May 2017 Amendment to Operating License/Change to Appendix a of Technical Specification Concerning Certain Repairs at Facility and Concomitantly to Allow a Continuation of a Slightly Lower Water Level in the Reactor... NMP2L2643, License Amendment Request-Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes2017-04-0505 April 2017 License Amendment Request-Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2639, Supplement to License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy- Nuclear 10 CFR Part 21 Safety Communication SC05-032017-02-17017 February 2017 Supplement to License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy- Nuclear 10 CFR Part 21 Safety Communication SC05-03 NMP1L3122, License Amendment Request - Proposed Changes Regarding Partial Length Fuel Rod (PLR) Burnup2017-01-0303 January 2017 License Amendment Request - Proposed Changes Regarding Partial Length Fuel Rod (PLR) Burnup NMP2L2584, License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy - Nuclear 1 O CFR Part 21 Safety Communication SC05-032016-12-13013 December 2016 License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy - Nuclear 1 O CFR Part 21 Safety Communication SC05-03 NMP2L2634, Emergency License Amendment Request - Proposed Changes to the High Pressure Core Spray System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications2016-11-26026 November 2016 Emergency License Amendment Request - Proposed Changes to the High Pressure Core Spray System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications 2023-08-21
[Table view] Category:Safety Evaluation
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 ML23156A6832023-06-22022 June 2023 Authorization and Safety Evaluation of Alternative Relief Request I5R-14 ML23156A6822023-06-22022 June 2023 Authorization and Safety Evaluation of Alternative Relief Request I5R-11 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23103A1912023-04-20020 April 2023 Request for Threshold Determination Under 10 CFR 50.80 ML23082A3502023-04-17017 April 2023 Issuance of Amendment No. 192, Revision of Surveillance Requirements Associated with Emergency Diesel Generator Testing ML23094A1422023-04-0505 April 2023 Approval of Alternative Request I5R-13 to Utilize Specific Provisions of Code Case N-716-3 ML23025A4122023-02-28028 February 2023 Issuance of Amendment No. 248 to Revise Alternative Source Term Calculation for Main Steam Isolation Valve Leakage and Non-MSIV Leakage ML22339A0582022-12-21021 December 2022 Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML22061A0402022-03-11011 March 2022 Relief Request Associated with Excess Flow Check Valves ML22033A3102022-03-0404 March 2022 Issuance of Amendment No. 190, Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21295A7342021-11-15015 November 2021 Issuance of Amendment No. 187 Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21256A1792021-11-0202 November 2021 Issuance of Amendment No. 246 Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21140A1532021-06-0303 June 2021 Correction to April 22, 2021 Safety Evaluation for Requests for Alternative to the Inservice Testing Requirements of the ASME OM Code for the Fifth 10-Year Program Interval ML21082A2212021-04-29029 April 2021 Issuance of Amendment No. 186, Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML21109A2162021-04-22022 April 2021 Proposed Alternative to Inservice Testing Requirements of the ASME OM Code for the Fifth 10-Year Interval ML21105A3382021-04-22022 April 2021 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Concerning Examination Coverage of Certain Class 1 and 2 Component Welds ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21049A0062021-03-16016 March 2021 Issuance of Amendment No. 245 for Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21049A0242021-02-23023 February 2021 Alternative Request to the Requirements of the ASME OM Code for the Testing Intervals for the Instrument-Line Flow Check Valves ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20332A1152021-01-29029 January 2021 Issuance of Amendment No. 183 Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML21005A0612021-01-14014 January 2021 Proposed Alternatives to Extend the Safety Relief Valve Testing Interval (EPID L-2020-LLR-0014 Through L-2020-LLR-0018) ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20241A1902020-10-20020 October 2020 Issuance of Amendment No. 182 to Change Allowable Main Steam Isolation Valve Leak Rates ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20141L0532020-06-0202 June 2020 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML19301B0052019-11-25025 November 2019 Issuance of Amendment No. 239 Administrative Edits to the Technical Specifications ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques 2023-08-21
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 13, 2012 Mr. Kenneth Langdon Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO.2 - ISSUANCE OF AMENDMENT REGARDING A CHANGE TO THE UPDATED SAFETY ANALYSIS REPORT ALLOWING THE USE OF MODIFIED ALLOY 718 MATERIAL IN JET PUMP HOLDDOWN BEAMS (TAC NO. ME7800)
Dear Mr. Langdon:
The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 141 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station, Unit No.2 (NMP2), in response to your application dated December 30, 2011, as supplemented by letter dated March 20, 2012. The proposed amendment authorizes changes to the NMP2 Updated Safety Analysis Report allowing the use of Modified Alloy 718 material for fabrication of the NMP2 reactor recirculation system jet pump holddown beams.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosures:
- 1. Amendment No. 141 to NPF-69
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 NINE MILE POINT NUCLEAR STATION, LLC (NMPNS)
DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION. UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 141 Renewed License No. NPF-69 1, The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Nine Mile Point Nuclear Station, LLC (the licensee) dated December 30,2011, as supplemented on March 20,2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; S. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly. the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-69 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix S, both of which are attached hereto, as revised through Amendment No. 141 are hereby incorporated into this license.
Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
-2
- 3. Further, Renewed Facility Operating License No. DPR-69 is hereby amended to authorize changes to the NMP2 Updated Safety Analysis Report (USAR) as set forth in the license amendment application dated December 30, 2011, as supplemented by letter dated March 20, 2012, and evaluated in the safety evaluation dated Apri113 ,2012. The amendment provides authorization to use Modified Alloy 718 material for fabrication of the NMP2 reactor recirculation system jet pump holddown beams.
- 4. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION George A. Wilson, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Page 4 of Renewed Facility Operating License No. NPF-69 Date of Issuance: Apr; 1 13, 2012
ATTACHMENT TO LICENSE AMENDMENT NO. 141 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page 4 4
-4 (1) Maximum Power Level Nine Mile Point Nuclear Station, LLC is authorized to operate the facility at reactor core power levels not in excess of 3988 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 141 are hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Fuel Storage and Handling (Section 9.1, SSER 4)*
- a. Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
- b. When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or storage racks in the New Fuel Vault or Spent Fuel Storage Facility.
- c. The above three fuel assemblies shall maintain a minimum edge to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.
- d. The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at anyone time.
(4) Turbine System Maintenance Program (Section 3.5.1.3.10, SER)
The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities.
(Submitted by NMPC letter dated October 3D, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, III).
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed.
Amendment 141
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 141 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 NINE MILE POINT NUCLEAR STATION, LLC NINE MILE POINT NUCLEAR STATION, UNIT NO.2 DOCKET NO. 50-410
1.0 INTRODUCTION
By letter dated December 30, 2011, (Agencywide Documents Access Management System
{ADAMS} Accession No. ML12009A118), as supplemented on March 20, 2012 (ADAMS Accession No. ML120820407), Nine Mile Point Nuclear Station. LLC (NMPNS. the licensee) submitted a License Amendment Request (LAR) to amend Renewed Facility Operating License NPR-69 for Nine Mile Point, Unit No.2 (NMP2). The licensee requests Nuclear Regulatory Commission (NRC) approval to use Alloy 718 with a modified heat treatment for fabrication of the jet pump holddown beams (JP beams) at NMP2. NRC approval of this proposed change to the NMP2 current licensing basis would be reflected in a revision to Section 4.5 of the NMP2 Updated Safety Analysis Report (USAR), which provides a description of the materials used in the reactor internals. including the jet pump assemblies. The Technical Specifications would not be affected by this LAR.
The supplemental letter dated March 20, 2012, provided additional information that clarified the application and did not expand the scope of the application as originally noticed, and did not change the NRC staff's initial proposed no significant hazards consideration determination.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations Part 50 (10 CFR 50). Appendix A. includes the general design criterion for nuclear power plants. General Design Criterion (GDC) 1, "Quality standards and records," requires that structures, systems and components (SSC) important for safety be designed. fabricated, and tested to quality standards commensurate with the importance of the safety functions to be performed, and that, where generally recognized codes and standards are used, they be identified and evaluated to determine their applicability.
adequacy, and sufficiency, and are supplemented or modified as necessary to assure a quality product in keeping with the required safety function.
In 10 CFR 50.55a(b), "Standards approved for incorporation by reference," the requirements that must be met for the systems and components of boiling water reactors (BWR) are addressed.
Part of those requirements is the NRC Regulatory Guide (RG) 1.84, Revision 35 {July 2010}.
-2 Code Case N-60-S, "Material for Core Support Structures,Section III, Division 1" (Feb. 20, 2004) is the current code case that covers the jet pump assembly.
The JP beam is specifically included in the NMP2 USAR under Section 4.S.2.1 that states:
The inlet-mixer contains a pin, insert, and beam made of Inconel X-7S0 to Specification ASTM A637, Grade 688, or ASTM B637, Grade UNS N077S0, Type 3.
The USAR section goes on to say that non-American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code (ASME Code) components, like the JP beams, are required to be fabricated from American Society for Testing and Materials (ASTM) or ASME specification materials, which is consistent with the acceptance criteria in NUREG-0800, Standard Review Plan (SRP), Section 4.S.2. In addition, the SRP states that additional permitted materials are identified in ASME Code Cases approved for use by an NRC RG 1.84.
3.0 TECHNICAL EVALUATION
The information provided by the licensee in support of the LAR to evaluate the use of the Modified Alloy 718 to fabricate the JP beams at NMP2 has been reviewed and the basis for disposition is documented below.
3.1 Licensee's Request
Background
The licensee is requesting NRC approval to use a Modified Alloy 718 material for fabrication of the JP beams in the reactor recirculation system at NMP2. The existing material is Alloy X-7S0.
The Modified Alloy 718 material, specified as SB-637 and identified as Grade 718 Type 2 in ASME Code Case N-60-6, has the same chemical composition as the conventional Grade 718 Type 1 material, but the heat treatment conditions have been modified to improve alloy's resistance to stress-corrosion cracking (SCC).
The jet pump assemblies are part of the reactor vessel internals, but are not core support structures. As noted in the NMP2 USAR, such reactor internals are not ASME Code components, but are fabricated from ASTM or ASME specification materials which are consistent with the acceptance criteria in NUREG-0800, SRP Section 4.S.2. In addition, the Modified Alloy 718 material has been included in ASME Code Case N-60-6. This code case revision was approved by ASME on December 6,2011; however, it has not yet been approved for use by the NRC in RG 1.84. Therefore, the licensee has submitted this LAR for NRC approval.
Licensee's Basis for Request Each jet pump assembly contains one jet pump beam, which is designed to hold the transition piece in contact with the riser pipe and the inlet mixer by maintaining sufficient bolt preload on the transition piece. The preload must be large enough to overcome the hydraulic force applied to the transition piece by the flow inside the jet pump assembly. To accommodate the high preload on the beams, the currently installed beams are fabricated from Alloy X-7S0 material
-3 with a minimum yield strength (YS) of 85 kilopounds per square inch (ksi). As an alternative to the Alloy X-7S0 material, the licensee is proposing to use the Modified Alloy 718 with a minimum YS of 100 ksi, which has been developed based on the conventional Alloy 718 material. The Modified Alloy 718 has similar or improved material properties and improved resistance to SCC initiation and propagation as compared to Alloy X-7S0 material.
Information that supported the addition of Modified Alloy 718 material to Code Case N-60-S has been provided in Enclosure 3 to the December 30, 2011, submittal, including data on YS, tensile strength, stress intensity, fatigue, and other physical and material properties. The data and evaluations demonstrate that Modified Alloy 718 is comparable to Alloy X-7S0. Details of the modified heat treatment process and the SCC resistance of Modified Alloy 718 are also included. Based on the direct comparison with Alloy X-7S0, the licensee concludes that the proposed change of JP beam material from Alloy X-7S0 to Modified Alloy 718 will not affect the design function of the ~IP beams and will improve the beam's resistance to SCC.
The inspection intervals for the Modified Alloy 718 beams are not currently addressed in any BOiling-Water Reactor Vessel and Internals Project (BWRVIP) documents; however, the licensee has committed to performing evaluations to establish inspection intervals for the Modified Alloy 718 beams, and expects that inspection intervals similar to those for Alloy X-7S0 Group 3 beams in BWRVIP-41 and BWRVIP-138 can be demonstrated. Specifically, in its December 30, 2011, submittal, NMPNS makes the following regulatory commitment regarding the inspection intervals for the Modified Alloy 718 jet pump holddown beams:
In accordance with BWRVIP guidelines, NMPNS will submit to the NRC an evaluation to support establishment of inspection intervals for the new holddown beams in accordance with criteria contained in the latest revision of BWRVIP-41, "BWR Vessel and Internals Project, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines." This NMPNS evaluation will be submitted approximately 1 year prior to the next scheduled NMP2 refueling outage following installation of the Modified Alloy 718 jet pump holddown beams.
The licensee requests NRC approval of their proposed license amendment request in time to support jet pump modifications scheduled for implementation during the planned NMP2 refueling outage, scheduled to begin in April 2012.
3.2 NRC Staff Evaluation The NRC staff has reviewed the submittal consistent with the SRP, Section 4.5.2, Revision 3, March 2007. The review has considered the adequacy and suitability of the Modified Alloy 718 material proposed for the JP beams at NMP2 in terms of the alloy's fabricability, strength, ductility, fracture toughness, stress corrosion resistance, and other physical and mechanical properties.
Fabricability The NRC staff considers the main fabricability issue to consider for this LAR is the heat treatment given to the Modified Alloy 718 component, which is the last major step in the
- 4 fabrication process. Enclosure 4, Section 2.6 of the licensee's December 30, 2011, submittal describes the heat treatment as follows:
Solution heat treatment (SHT) for modified alloy 718 shall be 1850°F-1922°F (1010°C-1050°C), target temperature of 1886°F (1030'C), for 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, followed by rapid quenching in oil or water. SHT for modified alloy 718 shall be followed by precipitation hardening heat treatment at 1300°F+15°F (704°C+8°C) for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, +1 1-0 hours, followed by air cooling. Solution and precipitation hardening heat treatment conditions were determined from the T-T-P (time-temperature-precipitation) curve (Reference 3 and Figure 2-3) and isothermal aging curves for yield strength and elongation of alloy 718 (Figure 2-4). In order to improve SCC resistance and ductility, SHT temperature 1010-1 050'C was selected for complete solution and the precipitation hardening heat treatment condition 704°C/6 hours was selected to avoid the precipitation of 8-phase ...
Microstructure has been shown to playa determinant role in the SCC behavior of high-strength Ni-based alloys [Reference 1]. The two most important microstructural characteristics of alloy Modified Alloy 718 are grain structure (size and distribution) and is-phase structure. After the recommended solution heat treatment for this alloy (1850 °F-1922 OF for 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />), the grain structure should be relatively uniform (an average grain size of ASTM No.2 to NO.6 is considered optimum for Alloy X-750 and would be similar for the Modified Alloy 718) while the is phase is completely dissolved in the matrix. The grain boundaries should be free of precipitates.
The final, low-temperature, aging step (1300 °F+15 OF for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />) is sufficient to increase the YS to the desired range through intragranular precipitation of y" and avoid any grain-boundary precipitation.
The March 30, 2012, submittal for Modified Alloy 718 and other related sources of information
[Reference 1 and 2] include extensive microstrucural characterization for the different versions of Alloy 718. With the microstructural characterization available for the Modified Alloy 718 components to be installed at NMP-2, the staff is satisfied that the resistance to SCC will be similar to that which has been demonstrated in the December 30, 2011 submittal.
Tensile Properties of the licensee's December 30, 2011, submittal describes the tensile properties of the Modified Alloy 718. The Alloy 718 material with the modified heat treatment exhibits consistent tensile properties that meet the specification requirement.
Fracture Toughness Properties The licensee's December 30, 2011, submittal does not include any information related to the fracture toughness properties of the Modified Alloy 718. A reference from the open literature for the fracture toughness properties of Alloy 718, Type 1 (higher YS than the Modified Alloy 718) in the unirradiated condition demonstrates that the typical fracture toughness properties are relatively high [Reference 3]. A second reference indicates that the fracture toughness properties are degraded after neutron irradiation, but the testing showed that fracture toughness is still acceptable up to 8 displacements per atom (dpa) [Reference 4]. The NRC staff considers this to be an adequate demonstration of acceptable fracture toughness for the Modified Alloy
-S this to be an adequate demonstration of acceptable fracture toughness for the Modified Alloy 718 JP beams at NMP2 Stress Corrosion Resistance of the licensee's December 30, 2011, submittal describes the resistance to SCC in the Modified Alloy 718. For the initiation of SCC in high temperature (SSO OF) water, two different industry-standard tests were used. In a uniaxial-constant load (UCL) test, the Modified Alloy 718 displayed a higher stress threshold for cracking than the X-7S0 samples; no failures in 10,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> at 900 MPa (130 ksi) for two UCL samples of Modified Alloy 718 while 1 of the 2 UCL samples of Alloy X-7S0 failed before 10,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. In the creviced bent beam (CBB) test, the Alloy X7S0 samples displayed more numerous cracking over the whole range of test conditions (chloride contents) tested.
The low temperature (200 OF) susceptibility to SCC initiation was characterized in a rising load test (RLT) included in BWRVIP-84, "BWR Vessel and Internals Project: Guidelines for Selection and Use of Materials for Repairs to BWR Internals." The test is really a rising displacement test where a constant displacement rate is imposed on a fatigue precracked 3-point bend specimen.
For a given test environment of interest, the results are defined in terms of the peak load (elastic stress intensity factor, K) and the time for the load to drop from the peak to SO% of the peak load. When comparing the performance of the Modified Alloy 718 with that of Alloy X-7S0, both sets of samples met the acceptance criteria in BWRVIP-84, but the Modified Alloy 718 exhibited better results, i.e., Modified Alloy 718 always displayed higher peak loads and longer times for the load to drop to SO% of the maximum load than for the Alloy X-750 samples.
The resistance to SCC crack growth was characterized in a fracture mechanics test using the direct current (DC) potential drop method to monitor crack growth under a constant applied K, (described in Reference 2 and 5) that was varied from about 27 to 45 ksi-in 112. The SCC growth rate for Modified Alloy 718 was always below the proposed curves in BWRVIP-138 for Alloy X-750 and was at least an order of magnitude lower than for the Alloy X-750 samples at each applied K level.
In summary, the NRC staff has reviewed the test results discussed in the December 30,2011, submittal, and finds that the licensee has demonstrated that the resistance of the Modified Alloy 718 to SCC is superior to that for Alloy X-750.
Other Properties of the licensee's December 30, 2011, SUbmittal, describes several other mechanical and physical properties of the Modified Alloy 718, including fatigue testing (both load- and strain controlled), radiation relaxation rate, spring property, thermal expansion, thermal conductivity, and elastic properties. In each case, the Modified Alloy 718 samples performed as well or better than the Alloy X-7S0 samples.
Summary The NRC staff has reviewed the licensee's December 30, 2011, and March 20, 2012, submittals, and other pertinent references. The NRC staff agrees that the properties of the Modified Alloy
-6 718 material were as good as or better than the same properties of the Alloy X-750 material; therefore, the NRC staff finds that the use of Modified Alloy 718 for the JP beams at NMP2 is acceptable.
The NRC staff has reviewed the licensee's submittal and concludes that the licensee's evaluation regarding the mechanical and physical properties of Modified Alloy 718 is adequate to support the approval of the LAR for the use of Modified Alloy 718 material for the JP beams at NMP2. The NRC staff concludes that the change of material for the NMP2 JP beams meets the 10 CFR 50.90 process and the ASME Code,Section III requirements. Therefore, the NRC staff concludes that the licensee's change in material for the JP beams to provide improved resistance to SCC is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (February 8,2012 (77 FR 6601 >>. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 1. T. Yonezawa, N. Yamaguchi, Y. Okada, and M. Igarashi, "Effects of Chemical Compositions and Heat Treatment on the Stress Corrosion Cracking Resistance of Precipitation Hardened Nickel Base Alloys in High Temperature Water," J. Japan Inst.
Metals, Vol. 51, No.4, 1987, pp. 309-318.
- 2. Y. Katayama, M. Tsubota, Y. Saito, N. Tanaka, and S. Tanaka, "SCC Properties of th Modified Alloy 718 in BWR Plant." 15 International Conference on Environmental
-7 Degradation, Edited by J.T. Busby, G. Hevbare, and P.L. Andresen, TMS (The Minerals, Metals, and materials Society) 2011.
- 3. W. J. Mills and L. D. Blackburn, "Variations in Fracture Toughness for Alloy 718 Given a Modified Heat Treatment," J. Eng. Mater. Technol., January 1990, Volume 112, Issue 1, pp. 116-124.
- 4. W. J. Mills, "Effect of Irradiation on the Fracture Toughness for Alloy 718 Plate and Weld", J. Nuclear Materials. December 1992, Volume 199, Issue 12, pp. 68-78.
- 5. P.L. Andresen, J. Flores-Preciado, M.M. Morra, and R. Carter, "Microstructure and SCC of Alloy X-750," 15th International Conference on Environmental Degradation, Edited by J.T. Busby, G. Hevbare, and P.L. Andresen, TMS (The Minerals, Metals, and materials Society) 2011.
Principal Contributor: P. Purtscher Date: April 13, 2012
ML120940373
- Concurrence via e-mail, **SE provided by memo. No substantial chan~es made. NRR-106 OFFICE LPL 1-1/PM LPL 1-1/LA* EVIB/BC** OGC LPL 1-1/BC NAME RGuzman SUttle SRosenberg DRoth GWilson DATE 4/4/12 4/4/12 3/26/12 4/7112 4/12112