Letter Sequence Request |
---|
EPID:L-2023-LLR-0011, Submittal of Emergency 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) (Approved, Closed) |
|
MONTHYEARML23087A2912023-03-28028 March 2023 Request for Additional Information (3/28/2023 E-mail) - Proposed Emergent I5R-11 Alternative Associated with a Weld Overlay on RPV Recirculation Nozzle N2E DM Weld Project stage: RAI ML23090A1302023-03-31031 March 2023 Verbal Authorization for Relief Request I5R-11, Proposed Alternative Repair of Recirculation Inlet Nozzle N2E Dissimilar Metal Weld Project stage: Approval ML23156A6822023-06-22022 June 2023 Authorization and Safety Evaluation of Alternative Relief Request I5R-11 Project stage: Approval 2023-03-31
[Table View] |
|
---|
Category:Letter type:NMP
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 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report 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 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 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) 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 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 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 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 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 . 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 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 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) NMP1L3523, Annual Radioactive Environmental Operating Report2023-05-12012 May 2023 Annual Radioactive Environmental Operating Report NMP1L3522, Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report2023-04-30030 April 2023 Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report NMP1L3525, Core Operating Limits Report2023-04-19019 April 2023 Core Operating Limits Report NMP1L3526, Submittal of Emergency Relief Request I5R-14 Concerning a Proposed Alternative Associated with N2E Safe End-to-Nozzle Dissimilar Metal Weld Repair with Laminar Indication2023-04-13013 April 2023 Submittal of Emergency Relief Request I5R-14 Concerning a Proposed Alternative Associated with N2E Safe End-to-Nozzle Dissimilar Metal Weld Repair with Laminar Indication NMP1L3520, Supplemental Information for License Amendment Request Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 22023-04-0404 April 2023 Supplemental Information for License Amendment Request Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2 NMP1L3519, Submittal of Emergency 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)2023-03-30030 March 2023 Submittal of Emergency 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) NMP1L3516, Submittal of Emergency 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)2023-03-29029 March 2023 Submittal of Emergency 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) NMP1L3517, Proposed Alternative Associated with a Weld Overlay Repair to the Torus2023-03-29029 March 2023 Proposed Alternative Associated with a Weld Overlay Repair to the Torus NMP1L3518, Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 12023-03-29029 March 2023 Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 1 NMP1L3515, Submittal of Emergency 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)2023-03-27027 March 2023 Submittal of Emergency 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) NMP1L3513, Submittal of Emergency 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)2023-03-24024 March 2023 Submittal of Emergency 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) NMP1L3499, CFR 50.46 Annual Report2023-01-27027 January 2023 CFR 50.46 Annual Report 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 NMP1L3486, Radiological Emergency Plan Document Revision2022-12-15015 December 2022 Radiological Emergency Plan Document Revision 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 NMP1L3485, Proposed Alternative Associated with a Weld Overlay Repair to the Torus2022-12-0808 December 2022 Proposed Alternative Associated with a Weld Overlay Repair to the Torus NMP2L2823, Supplemental Information for License Amendment Request Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators2022-10-28028 October 2022 Supplemental Information for License Amendment Request Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators NMP1L3481, Constellation Energy Generation, LLC, 10 CFR 50, Appendix E - Development of Evacuation Time Estimates2022-09-15015 September 2022 Constellation Energy Generation, LLC, 10 CFR 50, Appendix E - Development of Evacuation Time Estimates 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. NMP1L3478, Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-08-0505 August 2022 Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits 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 NMP1L3465, Independent Spent Fuel Storage Installation - General License 30-day Cask Registration Notifications2022-06-17017 June 2022 Independent Spent Fuel Storage Installation - General License 30-day Cask Registration Notifications NMP1L3462, Independent Spent Fuel Storage Installation, General License 30-day Cask Registration Notifications2022-06-0909 June 2022 Independent Spent Fuel Storage Installation, General License 30-day Cask Registration Notifications 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 NMP2L2811, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations2022-05-13013 May 2022 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations NMP1L3459, 2021 Annual Radiological Environmental Operating Report2022-05-0808 May 2022 2021 Annual Radiological Environmental Operating Report NMP1L3457, 2021 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 22022-04-30030 April 2022 2021 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2 NMP2L2805, Annual Environmental Operating Report2022-04-23023 April 2022 Annual Environmental Operating Report NMP2L2807, Core Operating Limits Report2022-04-0707 April 2022 Core Operating Limits Report NMP1L3458, Constellation Energy Generation, LLC, Annual Property Insurance Status Report2022-04-0101 April 2022 Constellation Energy Generation, LLC, Annual Property Insurance Status Report NMP1L3454, Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-03-0202 March 2022 Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs NMP1L3444, CFR 50.46 Annual Report2022-01-27027 January 2022 CFR 50.46 Annual Report NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2793, Supplemental Information - Relief Request Associated with Excess Flow Check Valves2021-12-17017 December 2021 Supplemental Information - Relief Request Associated with Excess Flow Check Valves NMP2L2789, Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-12-16016 December 2021 Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 2024-02-01
[Table view] Category:Report
MONTHYEARNMP1L3563, 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) 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 . NMP1L3515, Submittal of Emergency 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)2023-03-27027 March 2023 Submittal of Emergency 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) NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20190A1482020-07-0808 July 2020 FAQ 20-01 NMP Scram Final Approved ML20100F6822020-04-0909 April 2020 Submittal of Analytical Evaluation of Recirculation Discharge Nozzle-to-Safe End Weld Indication ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018 Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The. NMP1L3229, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ...2018-08-20020 August 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ... ML18018B2922018-01-18018 January 2018 Appendix a, Justification for Continued Operation, Component Review Summary Sheet ML18018B2912018-01-18018 January 2018 Pipe Crack Task Force Report ML18018A9652018-01-18018 January 2018 Nine Mile Point, Unit 1 - Equipment Qualification Program and Tables I - Equipment Qualification Reports and Table Ii - TMI Action Plan ML18018B0122018-01-18018 January 2018 Semi-Annual Radioactive Effluent Release Report July-December 1999 ML17251A0452017-09-20020 September 2017 - Staff Assessment of Flooding Focused Evaluation (CACs No. MG0087 and MG0088) ML17109A3652017-04-13013 April 2017 Pressure and Temperature Limits Report ML17079A3842017-03-24024 March 2017 Summary of the U.S. Nuclear Regulatory Commission Staff'S Review of the Spring 2016 Steam Generator Tube Inservice Inspections ML17037A6862017-02-0606 February 2017 Table 7.2-1 ML17037A7032017-02-0606 February 2017 Table 7.2-1 (Cont'D) ML17027A0162017-01-27027 January 2017 10 CFR 50.46 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors RS-16-178, High Frequency Supplement to Seismic Hazard Screening Report2016-11-0202 November 2016 High Frequency Supplement to Seismic Hazard Screening Report ML16231A4522016-08-30030 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) ML16223A8532016-08-25025 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) RS-16-091, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2016-06-14014 June 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML16160A0942016-06-0808 June 2016 ASP ANALYSIS- REJECT- Nine Mile Point Unit 1 Automatic Reactor Scram Due to Main Steam Isolation Valve Closure (LER 220-2015-004) ML15153A6602015-06-16016 June 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Re ML15028A1492015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109, Severe Accident Capable Hardened Vents RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML15022A6612014-07-31031 July 2014 Stress Re-Evaluation of Nine Mile Point Unit 2 Steam Dryer at 115% CLTP, CDI Report No. 14-08NP, Revision 0, Non-proprietary Version ML14153A4102014-07-24024 July 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14167A3492014-06-20020 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac. MF0249 & MF0250) ML15022A6622014-05-31031 May 2014 Acoustic and Low Frequency Hydrodynamic Loads at 115% CLTP Target Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1R, C.D.I. Report No. 14-09NP, Revision 1, Non-proprietary Version ML15023A0312014-04-30030 April 2014 Computation of Cumulative Usage Factor for the 115% CLTP Power Level at Nine Mile Point Unit 2 with the Inboard RCIC Valve Closed, C.D.I. Technical Note No. 14-04NP, Revision 0, Non-proprietary Version ML14099A1962014-03-31031 March 2014 Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task. ML14064A3242014-02-28028 February 2014 000N2495-R1-NP, Rev. 0, Nine Mile Point Nuclear Station Unit 2 Comparison of Mellla+ Reference Design to Cycle 15 Design Characteristics. ML14071A4782014-02-21021 February 2014 Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments ML14351A4272014-01-31031 January 2014 000N2528-SRLR, Revision 1, Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988 Mwt) / MELLLA (99-105% Flow). ML14064A3222014-01-31031 January 2014 00N0123-SRLR, Rev. 2, Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2) Reload 14 Cycle 15 Extended Power Uprate (Epu)/Maximum Extended Load Line Limit Plus (Mellla+). ML14024A4422014-01-0707 January 2014 Submittal of Report in Accordance with 10 CFR 26.719(c)(1) Regarding Unsatisfactory Blind Performance Sample Testing ML14064A3232013-12-31031 December 2013 000N0123-FBIR-NP, Rev. 0, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15. ML13225A5842013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13338A6642013-12-11011 December 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 2, TAC No.: MF1130 ML13338A6632013-12-11011 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 1, TAC No.: MF1129 ML13311A0542013-11-0404 November 2013 Pressure and Temperature Limits Report (PTLR) PTLR-2, Revision 0 (Draft B) ML13316B1102013-11-0101 November 2013 Attachment 9 - Global Nuclear Fuel Report GNF-0000-0156-7490-RO-NP, Gnf Additional Information Regarding the Requested Change to the Technical Specification SLMCPR, Dated August 26, 2013 (Non-proprietary) ML13311A0552013-09-30030 September 2013 Fluence Extrapolation in Support of NMP2 P-T Cure Update, MPM-913991, September 30, 2013, Attachment 3 ML13197A2222013-07-12012 July 2013 Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3, Seismic ML13066A1712013-02-28028 February 2013 R.E. Gina, Overall Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events 2023-08-04
[Table view] Category:Miscellaneous
MONTHYEARNMP1L3563, 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) NMP1L3515, Submittal of Emergency 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)2023-03-27027 March 2023 Submittal of Emergency 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) ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20190A1482020-07-0808 July 2020 FAQ 20-01 NMP Scram Final Approved ML18018B2912018-01-18018 January 2018 Pipe Crack Task Force Report ML18018B2922018-01-18018 January 2018 Appendix a, Justification for Continued Operation, Component Review Summary Sheet ML17251A0452017-09-20020 September 2017 - Staff Assessment of Flooding Focused Evaluation (CACs No. MG0087 and MG0088) ML17079A3842017-03-24024 March 2017 Summary of the U.S. Nuclear Regulatory Commission Staff'S Review of the Spring 2016 Steam Generator Tube Inservice Inspections ML17027A0162017-01-27027 January 2017 10 CFR 50.46 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors RS-16-178, High Frequency Supplement to Seismic Hazard Screening Report2016-11-0202 November 2016 High Frequency Supplement to Seismic Hazard Screening Report ML16231A4522016-08-30030 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) ML16223A8532016-08-25025 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) RS-16-091, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2016-06-14014 June 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML16160A0942016-06-0808 June 2016 ASP ANALYSIS- REJECT- Nine Mile Point Unit 1 Automatic Reactor Scram Due to Main Steam Isolation Valve Closure (LER 220-2015-004) ML15153A6602015-06-16016 June 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Re ML15028A1492015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109, Severe Accident Capable Hardened Vents ML14153A4102014-07-24024 July 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML14167A3492014-06-20020 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac. MF0249 & MF0250) ML14099A1962014-03-31031 March 2014 Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task. ML14024A4422014-01-0707 January 2014 Submittal of Report in Accordance with 10 CFR 26.719(c)(1) Regarding Unsatisfactory Blind Performance Sample Testing ML13066A1712013-02-28028 February 2013 R.E. Gina, Overall Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events ML13037A0822013-01-31031 January 2013 Submittal of Supplemental Seismic Walkdown Report ML12312A0142012-09-17017 September 2012 Transmittal of Pressure and Temperature Limits Report Revision 02.00 ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML11154A0982011-05-25025 May 2011 License Amendment Request Pursuant to 10 CFR 50.90: Revision to License Condition 2.B.(2) to Delete Outdated Reference ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages ML1019504972010-07-0909 July 2010 Attachment 1, CDI Report No. 10-11NP, Stress Assessment of Nine Mile Point Unit 2 Steam Dryer Using the Acoustic Circuit Model Rev. 4.1, Rev. 0, Cover Through Chapter 5 ML1007000882010-03-0303 March 2010 Pressure and Temperature Limits Report Revision ML0911802792009-04-21021 April 2009 Core Operating Limits Report, COLR1-19, Revision 0 ML12220A1012008-11-24024 November 2008 Constellation Energy Group, Inc. Definitive Proxy Statement Schedule 14A ML0629702462006-10-16016 October 2006 Special Report: Channel #12 of the Containment Hydrogen Monitoring System Inoperable for Planned Preventive Maintenance ML0627700442006-09-29029 September 2006 State Pollutant Discharge Elimination System, Permit No. Ny 000 1015, Request for Information Re Environmental Benefit Permit Strategy ML0619503912006-07-0505 July 2006 Post Accident Monitoring Instrumentation Report: Division 2 of the Containment Monitoring System Inoperable ML0611804852006-04-28028 April 2006 NRC 2006 a, Gen&Sis - Census 2000 Low Income Ej Nine Mile Point License Renewal ML0610906202006-04-19019 April 2006 NYSDEC 2003k, Website Reference Used in Chapter 2 NMP FSEIS, Round Whitefish Fact Sheet. ML0608804422006-03-24024 March 2006 GE Evaluation of OPRM Performance During Instability Events at Nine Mile Point, Unit 2 and Perry Nuclear Power Plant ML0606703632006-02-27027 February 2006 Special Report: Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Planned Preventive Maintenance ML0609404802005-06-15015 June 2005 Doe/Eia 2005, Website Reference Used in Chapter 8 NMP FSEIS ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0430003332004-10-26026 October 2004 to Audit and Review Plan for Plant Aging Management Reviews and Programs for the Nine Mile Point Nuclear Station, Units 1 and 2. ML0609401922004-10-0505 October 2004 Ohio Department of Natural Resources, Website Reference Used in Chapter 2 NMP FSEIS ML0609401352004-08-24024 August 2004 NYSDEC 2003a, Website Reference Used in Chapter 2 NMP FSEIS ML0609400532004-07-28028 July 2004 Campus Program.Com 2004, Website Reference Used in Chapter 2 NMP FSEIS ML0421203072004-07-20020 July 2004 2004 Owner'S Activity Report for Inservice Examinations for Nine Mile Point Unit 2 ML0419501842004-07-0606 July 2004 Special Report, Channel #11 of the Containment Hydrogen Monitoring System Removed from Service for Planned Maintenance ML0330702722003-10-23023 October 2003 10CFR50.59 Evaluation Summary Report for 2003 ML0323304182003-08-13013 August 2003 Guarantee of Retrospective Premium ML0318909502003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-duty Enhancements for Nuclear Security Force Personnel for Calvert Cliffs, ML0619303922002-10-31031 October 2002 Identification of Changes, Reasons and Bases for Nine Mile Point Nuclear Station, L.L.C., Quality Assurance Program Topical Report, Nine Mile Point Nuclear Station - Unit 2 (USAR Appendix B) ML0226103802002-09-0303 September 2002 Submittal of Special Report Re Inoperability of Channel #12 Containment Hydrogen Monitoring System at Nine Mile Point Unit 1 2023-03-27
[Table view] |
Text
200 Exelon Way Kennett Square, PA 19348 www.constellation.com 10 CFR 50.55a NMP1L3515 March 27, 2023 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-63 NRC Docket No. 50-220
Subject:
Submittal of Emergency 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)
Reference:
- 1) Letter from D. Gudger (Constellation Energy Generation, LLC) to U.S.
Nuclear Regulatory Commission, Submittal of Emergency 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) dated March 24, 2023 (ML23083B991)
In the Reference 1 letter, Constellation Energy Generation, LLC (CEG) requested emergency approval of the proposed alternative associated with the repair of the recirculation inlet nozzle N2E safe end-to-nozzle dissimilar metal (DM) weld. In a conference call on March 27, 2023, the U.S. Nuclear Regulatory Commission requested additional information regarding the design of the weld overlay. Attached is the requested information.
If you have any questions concerning this letter, please contact Tom Loomis at Thomas.Loomis@constellation.com.
Respectfully, David T. Gudger Senior Manager - Licensing & Regulatory Affairs Constellation Energy Generation, LLC
Attachment:
Evaluation of a Leakage Barrier Weld Overlay cc: Regional Administrator, Region I, NRC NRC Senior Resident Inspector, NMP Project Manager NRC, NMP A. L. Peterson, NYSERDA
ATTACHMENT Evaluation of a Leakage Barrier Weld Overlay
5215 Hellyer Avenue, Suite 210, San Jose, CA 95138 March 25, 2023 REPORT NO. 2300376.401 REVISION: 0 PROJECT NO. 2300376.00 Quality Program: Nuclear Commercial Jennifer Bianculli Nine Mile Point P.O. Box 63 Lycoming NY 13093
Subject:
Evaluation of a Leakage Barrier Weld Overlay
Dear Ms. Bianculli,
Nine Mile Point Nuclear Station, Unit 1 (NMP) identified a flaw in the recirculation discharge N2E nozzle-to-safe end dissimilar metal weld (DMW), 32-WD-208 [1]. Based on the size and location of the flaw, the installation of a fully compliant full structural weld overlay (FSWOL) was initially considered using the rules of ASME Code Case N-740-2 [4].
However, given the protracted welding time that would be required to install a FSWOL, and that the inspection identified the presence of only one axial flaw, NMP is proposing to apply what was historically called a Design weld overlay using guidance from Section XI, Nonmandatory Appendix Q, Weld Overlay Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping Weldments [2].
A Relief Request will be required and will be prepared separately from this document. This document will develop the sizing requirements for a Design weld overlay taking guidance from Appendix Q, Code Case N-740-2 and utilizing other engineering principles.
It is noted that the Relief Request to be submitted is based on the use of ASME Code Case N-740-2 as the weld overlay material will be Alloy 52M (Alloy 690) deposited over an existing Alloy 82/182 weldment. Guidance from Appendix Q will also be invoked in the Relief Request as providing guidance for the design requirements for a Design weld overlay.
© 2023 by Structural Integrity Associates, Inc. All rights reserved. No part of this document or the related files may be reproduced or transmitted in any form, without the prior written permission of Structural Integrity Associates, Inc.
MCG00700 08.21.20
March 25, 2023 Jennifer Bianculli Evaluation of a Leakage Barrier Weld Overlay NONMANDATORY APPENDIX Q / CODE CASE N-740-2 Article Q-3000(a)(5) of Appendix Q states:
For weldments with four or fewer axial flaws, each shorter than 1.5 in. (38 mm), and no circumferential flaws, the weld reinforcement shall satisfy the requirements of Q-2000(d). No additional structural reinforcement is required. The axial length of the overlay shall cover the weldment and the heat-affected zones, and shall extend at least 1/2 in. (13 mm) beyond the ends of the observed flaws. The requirements of (b)(1), (b)(3), and (b)(4) need not be met.
Per Reference [1], the flaw is sized at 1.65 in length, 1.52 in depth (~83% through thickness) and is axially oriented. Thus, there is only one flaw, and it is axially oriented. However, the flaw is slightly longer than that allowed in Q-3000(a)(5), and thus will also require relief. A justification is provided below.
Article Q-2000(d) of Appendix Q states:
The weld reinforcement shall consist of at least two weld layers having asdeposited delta ferrite content of at least 7.5 FN. The first layer of weld metal with delta ferrite content of at least 7.5 FN shall constitute the first layer of the weld reinforcement that may be credited toward the required thickness. Alternatively, first layers of at least 5 FN are acceptable, provided the carbon content of the deposited weld metal is determined by chemical analysis to be less than 0.02%.
The Article Q-2000(d) delta ferrite requirement is specific for a stainless steel weld overlay material. Given that the nozzle-to-safe end weld is Inconel 82, Style A, Class 5 [3], the necessary weld overlay material would be ASME Code,Section II, SFA-5.14, ERNiCrFe-7A (Alloy 52M). Per ASME Code Case N-740-2 [4], Section 1.2(e)(2):
The austenitic nickel alloy weld overlay shall consist of at least two weld layers deposited using a filler material with a Cr content of at least 28%. The first layer of weld metal deposited may not be credited toward the required thickness.
Alternatively, for BWR applications, a diluted layer may be credited toward the required thickness, provided the portion of the layer over the austenitic base material, austenitic filler material weld, and the associated dilution zone from an adjacent ferritic base material contain at least 20% Cr, and the Cr content of the deposited weld metal is determined by chemical analysis of the production weld or of a representative coupon taken from a mockup prepared in accordance with the WPS for the production weld.
Therefore, the weld filler metal requirements of ASME Code Case, N-740-2 are invoked.
Report No. 2300376.401 R0 PAGE l 2
March 25, 2023 Jennifer Bianculli Evaluation of a Leakage Barrier Weld Overlay OVER-SIZED (LENGTH) FLAW JUSTIFCATION As stated, earlier, the measured axial flaw length is 1.65, but Appendix Q, Q-3000(a)(5), limits the axial flaw length to 1.5.
Per ASME Code,Section XI, C-5410 [2], the maximum flaw length for which the stability of a through-wall flaw is maintained is defined as, 1.58 1 (1)
- where, f = flow stress, defined in C-8200 as f = (y + u) / 2 h = hoop stress, with structural factor, = SFaxial*pRm/t Rm = mean pipe radius t = pipe wall thickness p = internal pipe pressure for appropriate Service Level condition This equation actually provides the critical flaw length, crit, for a through-wall axial flaw, if the unfactored hoop stress is used. To determine the allowable flaw length, a structural factor must be applied to the hoop stress (h). Per ASME Code,Section XI, Appendix C, C-2622, the Service Level A structural factor for an axial flaw is SFaxial = 2.7.
The material properties of the nozzle (SA-336), the weld (Alloy 82/182. N06600) and the safe end (SA-182, F316) are extracted at the Design Temperature of 570°F along with the Design Pressure of 1200 psig [3].
Reference [3.a] indicates that at the nozzle-to-safe end weld, the safe end side outside diameter is 29.118 and the inside diameter is 25.780, which gives a wall thickness of 1.669.
Reference [3.b] indicates that at the nozzle-to-safe end weld, the nozzle outside diameter is 29-1/16 with a base metal inside diameter of 26.188, which gives a wall thickness of 1.43725.
The nozzle cladding will be conservatively excluded. When evaluating the Alloy 600 weld metal, the safe dimensions are used.
Using Equation 1, and the Service Level A structural factor of 2.7 applied to the hoop stress, the resulting allowable axial flaw length, allow, for a through-wall axial flaw under the Service Level A conditions is calculated for the three materials as follows:
Report No. 2300376.401 R0 PAGE l 3
March 25, 2023 Jennifer Bianculli Evaluation of a Leakage Barrier Weld Overlay Rm t P h f crit allow Material (inches) (inches) (psig) (psi) (psi) (inches) (inches)
SA336 13.813 1.437 1200 11533 61215 36.7 11.9 Alloy 600 13.725 1.669 1200 9868 58430 44.1 14.8 SA182 F316 13.725 1.669 1200 9868 45515 34.0 10.5 As can be seen in the resulting table, the shortest critical flaw length is 34.0 inches, while the shortest allowable flaw length (which includes the structural factor) is 10.5 inches. The measured indication length of 1.65 is only 15.7% of the allowable length and 4.9% of the critical flaw length. Thus, the fact that the flaw is slightly longer than the Article Q-3000(a)(5) length of 1.5 is not adverse.
SIZING - LENGTH As indicated above, Appendix Q states that the length of the Design overlay is:
The axial length of the overlay shall cover the weldment and the heat-affected zones, and shall extend at least 1/2 in. (13 mm) beyond the ends of the observed flaws.
Per Reference [7] the flaw is 1.65 long and is centered on the DMW, and the DMW crown width is 1.88. As weld overlay installations are measured from the toes of the weld, and in this case, the toes of the weld will extend beyond the flaw ends, the 0.5 inch additional length will be applied outside of the weld crown toes. Thus, the minimum weld overlay length is 1.88 + (0.5 x
- 2) = 2.88. Note that this length will have to be increased beyond this value in order to facilitate ultrasonic (UT) examination of the overlay inspection box, Figure 2 of ASME Code Case N-740-2.
Report No. 2300376.401 R0 PAGE l 4
March 25, 2023 Jennifer Bianculli Evaluation of a Leakage Barrier Weld Overlay SIZING - THICKNESS While Appendix Q (Q-2000(d)) requires two layers minimum be deposited, it does not define the layer thickness required. Per Reference [6], Westinghouse indicates that a layer of weld metal after cleanup is 0.070. Thus, two layers would be approximately 0.14 thick.
However, the Design weld overlay will be applied to the ferritic nozzle material. Thus, ambient temperature temper bead welding will be required to avoid post-weld heat treatment of the nozzle. The temper bead requirements of ASME Code Case N-638-10 [8] will be used for qualification of the welding process. However, Section I-3(c) of ASME Code Case N-740-2 [4]
states:
The area to be welded shall be buttered with a deposit of at least three layers to achieve at least 18 in. (3 mm) overlay thickness with the heat input for each layer controlled to within
+/-10% of that used in the procedure qualification test. The heat input of the first three layers shall not exceed 45 kJ/in. (1.8 kJ/mm) under any conditions. Particular care shall be taken in the placement of the weld layers of the austenitic overlay filler material at the toe of the overlay to ensure that the HAZ and ferritic base metal are tempered. Subsequent layers shall be deposited with a heat input not exceeding that used for layers beyond the third layer in the procedure qualification.
It is Structural Integrity Associates (SI) understanding that NMP intends to complete the rest of the weld overlay at a later date thereby converting the Design weld overlay into a FSWOL. SI Report No. 2300376.401 R0 PAGE l 5
March 25, 2023 Jennifer Bianculli Evaluation of a Leakage Barrier Weld Overlay therefore recommends the entire temper bead process be completed as part of the Design weld overlay implementation and be consistent with the temper bead layer requirements of ASME Code Case N-740-2. Thus, three layers should be applied, resulting in a minimum weld overlay thickness of 0.21 (at on the nozzle side).
Finally, a simplified crack growth evaluation is performed using IGSCC growth only to access the resistance of the Design weld overlay to future Intergranular Stress Corrosion Cracking (IGSCC) for one operating cycle. While, fatigue crack growth is certainly possible, the flaw is located in the recirculation system, which does not see significant pressure cycling, which is the driving load for axial flaw crack growth. Therefore, any fatigue crack growth within a single operating cycle is considered to be insignificant.
For this simplified evaluation, the axial flaw will be conservatively assumed to be 100% through-wall (i.e., it has reached the interface of the base metal and Design weld overlay (the actual flaw is only 83% through-wall)) and will immediately start to grow into the Alloy 52M overlay. The necessary Design overlay thickness must be such that the flaw will not grow through the overlay within one operating cycle (i.e., 2 years).
Per Reference [5], IGSCC growth in Alloy 52M weld material is computed using a constant, K-independent, rate of 4x10E-9 mm/s = 5.67x10E-7 in/hr = 4.97x10E-3 in/yr. This is the highest rate shown in Figure 47 of Reference [5] (see the following figure).
Report No. 2300376.401 R0 PAGE l 6
March 25, 2023 Jennifer Bianculli Evaluation of a Leakage Barrier Weld Overlay The proposed Design overlay requires a thickness of Alloy 52M weld filler metal over the ferritic nozzle of 0.21. Because potential use of stainless steel buffer layers and bridge beads, the Alloy 52M over the safe end/buffer layer can have a thickness as little as 0.10. Using this smaller thickness of Alloy 52M over the safe end (0.10), it would take 0.10 / 4.97x10E-3/yr. =
20.1 years to grow through the safe end weld overlay thickness by IGSCC alone. Note that this conservatively neglects the thickness of the buffer layer and/or bridge beads as additional crack growth margin.
Report No. 2300376.401 R0 PAGE l 7
March 25, 2023 Jennifer Bianculli Evaluation of a Leakage Barrier Weld Overlay RECOMMENDATION In conclusion, it is recommended that the Design weld overlay be at least 2.88 long and 0.21 thick over the ferritic nozzle.
The weld overlay length is conservatively based on the width of the weld crown (1.88),
which is greater than the flaw length (1.65), which is also contained within the weld crown width.
The thickness is based on the ASME Code Case N-740-2, Appendix I requirement that the first three layers of a weld overlay be applied to a ferritic material using ambient temperature temper bead rules. It is acknowledged that the rules of ASME Code Case N-638-10 will be used for qualification of the welding process.
Note that these dimensions do not include any added length or thickness that might be required to facilitate ultrasonic examination.
In addition, the use of these dimensions will require a Relief Request to support the use of Code Case N-740-2 [4], the use of elements of Nonmandatory Appendix Q [2], and the allowance of the slightly larger length of the axial indication.
Report No. 2300376.401 R0 PAGE l 8
March 25, 2023 Jennifer Bianculli Evaluation of a Leakage Barrier Weld Overlay REFERENCES
- 1. GE/Hitachi Customer Notification Form (CNF), Project: Nine Mile Point, Project No.
N1R27, CNF# CNF-ISI-006, Identification No. 32-WD-208 (N2E), dated 3-18-23, SI File No. 2300376.202.
- 2. ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2013 Edition.
- 3. Constellation Transmittal of Design Information, ID#: TODI-23-001, Revision 1, SI File No. 2300376.201.
- a. Ref 4 - CWI-1399K-4-15.pdf
- b. Ref 8 - E231-5650000.pdf
- 4. ASME Boiler and Pressure Vessel Code, Code Case N-740-2, Full Structural Dissimilar Metal Weld Overlay for Repair or Mitigation of Class 1, 2, and 3 Items,Section XI, Division 1.
- 5. Andresen, Peter L., SCC of High Cr Alloys in BWR Environments, 15th International Conference on Environmental Degradation, TMS (The Minerals, Metals & Materials Society), 2011, SI File No. 2300376.205.
- 6. Email from Davis Barton (Westinghouse) to Richard Mattson (SI), dated March 22, 2023, at 10:28 AM,
Subject:
RE: Follow up Question on N2E weld, SI File No. 2300376.204.
- 7. Email from Michael Sally (Constellation) to Dick Mattson (SI),
Subject:
RE: Flaw Orientation and Sizing, dated March 24, 2023, SI File No. 2300376.202.
- 8. ASME Boiler and Pressure Vessel Code, Code Case N-638-10, Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique,Section XI, Division 1.
Report No. 2300376.401 R0 PAGE l 9
March 25, 2023 Jennifer Bianculli Evaluation of a Leakage Barrier Weld Overlay Prepared by: Verified by:
Richard L. Bax Jr. James W. Axline, P.E.
Associate Associate Approved by:
Richard A. Mattson, P.E.
Senior Associate Report No. 2300376.401 R0 PAGE l 10