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Category:Report
MONTHYEARL-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) ML23172A1112023-06-21021 June 2023 SLRA - Requests for Confirmation of Information - Set 1 L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022 Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-004, Technical Specification 5.6.4 Post Accident Monitoring Report2022-01-20020 January 2022 Technical Specification 5.6.4 Post Accident Monitoring Report ML21211A5962021-06-30030 June 2021 Attachments 9a, B, 10a, B, 11a, 12a and 13a and 13b, Including ANP-3933NP, Revision 0, Monticello ATWS-I Evaluation for Atrium 11 Fuel, Affidavit L-MT-21-016, Nuclear Material Transaction Report2021-03-25025 March 2021 Nuclear Material Transaction Report L-MT-20-002, 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange2020-01-31031 January 2020 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange ML19308A0562019-10-0808 October 2019 Enclosure 1 - Notification of Changes to the Emergency Response Data System (ERDS) L-MT-19-020, 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 Accident Conditions ..2019-04-25025 April 2019 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 Accident Conditions .. L-MT-17-060, Steam Dryer Visual Inspection Report2017-08-10010 August 2017 Steam Dryer Visual Inspection Report L-MT-17-055, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 42017-07-26026 July 2017 Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 4 ML17088A5272017-03-31031 March 2017 NSIR Dpcp Confirmatory Review Report, 10 CFR 50.54(p)(2) Changes to the Security Plan, Revision 16, Northern States Power Company, Monticello Nuclear Generating Plant L-MT-17-015, Mitigating Strategies Flood Hazard Assessment (MSA) Submittal2017-03-28028 March 2017 Mitigating Strategies Flood Hazard Assessment (MSA) Submittal ML16302A2462016-10-28028 October 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima.. ML16221A2752016-07-31031 July 2016 ANP-3274NP, Revision 2, Analytical Methods for Monticello ATWS-I. L-MT-16-037, ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I.2016-07-31031 July 2016 ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I. L-MT-16-010, Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+).2016-02-29029 February 2016 Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+). ML15274A4742015-09-29029 September 2015 Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) Setpoints ML15274A4752015-09-29029 September 2015 Enclosure 6, Areva Report ANP-3435NP, Revision 0 to Are VA Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW LAR (Non-Proprietary) L-MT-15-065, Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits2015-09-29029 September 2015 Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits ML15175A3362015-07-0808 July 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 ML15169A3582015-06-11011 June 2015 PSP Rev 14 Technical Review 06-11-15 ML16035A1852015-01-30030 January 2015 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 1 of 3 ML16035A1862015-01-30030 January 2015 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 2 of 3 ML16035A1842015-01-30030 January 2015 Document 51-9234641-001, Technical Report of the Demonstration of UT NDE Procedure 54-UT-114-000, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. L-MT-14-103, Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-1032014-12-31031 December 2014 Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-103 ML16005A1102014-09-25025 September 2014 Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant L-MT-14-075, LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set 8.2014-09-19019 September 2014 LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set #8. ML14269A3252014-09-0505 September 2014 LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process. ML14269A3232014-09-0505 September 2014 LTR-BWR-ENG-14-034-NP, Investigation Into the Cause of Exceeding the Level 1 (L1) and Level 2 (L2) Limit Curves Generated Based on 2011 Monticello Main Steam Line Strain Gauge Data. ML14204A6232014-07-18018 July 2014 Enclosure 3, Attachment - Response to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Accoustic/Structural Ananlyses Set #7 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 ML18100A1902014-05-22022 May 2014 Enclosure 8 - Structural Integrity Associates, Inc. Report 130415.403, Revision 2, Assessment of Monticello Spent Fuel Canister Closure Plate Welds Based on Welding Video Records ML14136A2892014-05-12012 May 2014 14C4229-RPT-001, Revision 3, Monticello Nuclear Generating Plant Seismic Hazard and Screening Report. L-MT-14-041, ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.2014-05-0909 May 2014 ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis. ML14069A0052014-04-11011 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of NTTF Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14014A2682014-02-28028 February 2014 Staff Review and Evaluation of the Fifth 10-Year Interval Inservice Inspection Program Plan ML14064A1862014-02-25025 February 2014 Structural Integrity Associates, Inc., Evaluation File No. 1301525.301, Monticello Shroud Support Structure Flaw Evaluation Review and Support Plate Weld Inspection Recommendations L-MT-14-003, Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information2014-01-31031 January 2014 Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information ML14077A0952014-01-30030 January 2014 BWROG-TP-14-001, Rev. 0, Containment Accident Pressure Committee (344) Task 1 - Cfd Report and Combined Npshr Uncertainty for Browns Ferry/ Peach Bottom Cvic RHR Pumps, Attachment 8 ML13358A3732013-12-31031 December 2013 Enclosure 1, Reload 26 Cycle 27 Supplemental Reload Licensing Report, 000N0154-SRLR, Revision 5, Extended Power Uprate and Maximum Extended Load Line Limit Plus ML14077A0902013-12-31031 December 2013 BWROG-TP-13-021, Rev. 0, Containment Accident Pressure Committee (344) Task 4 - Operation in Maximum Erosion Rate Zone (Cvic Pump), Attachment 11 L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit2013-12-20020 December 2013 Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages2013-10-0404 October 2013 GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages ML13282A1422013-10-0404 October 2013 GE-MNGP-AEP-3304R1, Enclosure 2, GEH Response to Mella + RAI 2 L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 142013-08-29029 August 2013 WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14 ML13248A3452013-08-29029 August 2013 WCAP-17251-NP, Revision 2 - Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report, Enclosure 11 ML13248A3462013-08-29029 August 2013 WCAP-17252-NP, Revision 4 - Acoustic Loads Definition for the Monticello Steam Dyer Replacement Project, Enclosure 12 ML13248A3442013-08-29029 August 2013 WCAP-17548-NP, Revision 2 - Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data, Enclosure 10 ML13248A3482013-08-29029 August 2013 WCAP-17549-NP, Revision 2 - Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, Enclosure 13 2024-06-10
[Table view] Category:Technical
MONTHYEARL-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022 Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-004, Technical Specification 5.6.4 Post Accident Monitoring Report2022-01-20020 January 2022 Technical Specification 5.6.4 Post Accident Monitoring Report ML21211A5962021-06-30030 June 2021 Attachments 9a, B, 10a, B, 11a, 12a and 13a and 13b, Including ANP-3933NP, Revision 0, Monticello ATWS-I Evaluation for Atrium 11 Fuel, Affidavit L-MT-21-016, Nuclear Material Transaction Report2021-03-25025 March 2021 Nuclear Material Transaction Report L-MT-20-002, 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange2020-01-31031 January 2020 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange ML19308A0562019-10-0808 October 2019 Enclosure 1 - Notification of Changes to the Emergency Response Data System (ERDS) L-MT-19-020, 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 Accident Conditions ..2019-04-25025 April 2019 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 Accident Conditions .. L-MT-17-055, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 42017-07-26026 July 2017 Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 4 L-MT-16-010, Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+).2016-02-29029 February 2016 Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+). ML15274A4742015-09-29029 September 2015 Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) Setpoints ML15274A4752015-09-29029 September 2015 Enclosure 6, Areva Report ANP-3435NP, Revision 0 to Are VA Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW LAR (Non-Proprietary) L-MT-15-065, Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits2015-09-29029 September 2015 Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits ML16035A1862015-01-30030 January 2015 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 2 of 3 ML16035A1842015-01-30030 January 2015 Document 51-9234641-001, Technical Report of the Demonstration of UT NDE Procedure 54-UT-114-000, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. ML16035A1852015-01-30030 January 2015 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 1 of 3 L-MT-14-103, Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-1032014-12-31031 December 2014 Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-103 ML16005A1102014-09-25025 September 2014 Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant L-MT-14-075, LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set 8.2014-09-19019 September 2014 LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set #8. ML14269A3252014-09-0505 September 2014 LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process. ML14269A3232014-09-0505 September 2014 LTR-BWR-ENG-14-034-NP, Investigation Into the Cause of Exceeding the Level 1 (L1) and Level 2 (L2) Limit Curves Generated Based on 2011 Monticello Main Steam Line Strain Gauge Data. 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 ML18100A1902014-05-22022 May 2014 Enclosure 8 - Structural Integrity Associates, Inc. Report 130415.403, Revision 2, Assessment of Monticello Spent Fuel Canister Closure Plate Welds Based on Welding Video Records L-MT-14-041, ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.2014-05-0909 May 2014 ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis. ML14069A0052014-04-11011 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of NTTF Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14064A1862014-02-25025 February 2014 Structural Integrity Associates, Inc., Evaluation File No. 1301525.301, Monticello Shroud Support Structure Flaw Evaluation Review and Support Plate Weld Inspection Recommendations L-MT-14-003, Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information2014-01-31031 January 2014 Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information ML14077A0952014-01-30030 January 2014 BWROG-TP-14-001, Rev. 0, Containment Accident Pressure Committee (344) Task 1 - Cfd Report and Combined Npshr Uncertainty for Browns Ferry/ Peach Bottom Cvic RHR Pumps, Attachment 8 ML13358A3732013-12-31031 December 2013 Enclosure 1, Reload 26 Cycle 27 Supplemental Reload Licensing Report, 000N0154-SRLR, Revision 5, Extended Power Uprate and Maximum Extended Load Line Limit Plus ML14077A0902013-12-31031 December 2013 BWROG-TP-13-021, Rev. 0, Containment Accident Pressure Committee (344) Task 4 - Operation in Maximum Erosion Rate Zone (Cvic Pump), Attachment 11 ML13200A1962013-07-31031 July 2013 ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel. ML13200A1922013-07-31031 July 2013 ANP-3092(NP), Rev. 0, Monticello Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies. ML14077A1022013-06-30030 June 2013 BWROG-TP-13-009, Rev. 0, Containment Accident Pressure Committee (344) Task 3 Pump Operation at Reduced Npsha Conditions (Cvic Pump), Attachment 10 ML14077A0932013-06-30030 June 2013 BWROG-TP-13-011, Containment Accident Pressure Committee (344) Task 5 Effects of Non-Condensable Gases on Seals (Cvic Pump), Attachment 12 ML14077A0922013-06-30030 June 2013 BWROG-TP-13-010, Containment Accident Pressure Committee (344) Task 6 - Npshr Test Instrument Accuracy Effect on the Published Results (Cvic Pump), Attachment 13 ML14077A0912013-06-30030 June 2013 BWROG-TP-13-008, Rev. 0, Containment Accident Pressure Committee (344) Task 2 - Equation for Pump Speed Correction (Cvic Pump), Attachment 9 ML13200A1902013-06-30030 June 2013 ANP-3224NP, Rev. 2, Applicability of Areva Np BWR Methods to Monticello. ML13200A1952013-06-30030 June 2013 ANP-3213(NP), Rev. 1, Monticello Fuel Transition Cycle 28 Reload Licensing Analysis (Epu/Mellla). ML13191B1282013-06-26026 June 2013 NEDO-33820, Revision 0, Monticello Nuclear Generating Plant Upper Shelf Energy Evaluation for Plate C2220 Material for 54 EFPY, Enclosure 5 ML13200A1942013-05-31031 May 2013 ANP-3215(NP), Rev. 0, Monticello Fuel Transition Cycle 28 Fuel Cycle Design (Epu/Mellla). ML13200A1972013-05-31031 May 2013 ANP-3212(NP), Rev. 0, Monticello EPU LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel. ML13200A1992013-05-31031 May 2013 ANP-3221NP, Rev. 0, Fuel Rod Thermal-Mechanical Design for Monticello Atrium 10XM Fuel Assemblies, Cycle 28. ML13200A2002013-05-31031 May 2013 ANP-3139(NP), Rev. 1, Nuclear Fuel Design Report Monticello Cycle 28 Atrium 10XM Fuel. L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project.2013-03-29029 March 2013 Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project. ML13092A3492013-03-29029 March 2013 Enclosure 10 to L-MT-13-029 - WCAP-17548-NP, Revision 1, Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data. ML13092A3502013-03-29029 March 2013 Enclosure 11 to L-MT-13-029 - WCAP-17251-NP, Revision 1, Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report. ML13092A3522013-03-29029 March 2013 Enclosure 13 to L-MT-13-029 - WCAP-17549-NP, Revision 1, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using Ace. ML13092A3512013-03-29029 March 2013 Enclosure 12 to L-MT-13-029 - WCAP-17252-NP, Revision 3, Acoustic Loads Definition for the Monticello Steam Dryer Replacement Project. ML13037A2012013-01-31031 January 2013 NEDO-33800, Rev. 0, Monticello Nuclear Generating Plant Automatic Depressurization System Bypass Timer Extended Power Uprate. ML13200A1892012-11-30030 November 2012 ANP-2637, Rev. 4, Boiling Water Reactor Licensing Methodology Compendium. 2024-06-10
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Containment Accident Pressure Committee Task 4 - Operation in the Maximum Erosion Rate Zone (CVDS Pump)
Author: Ankur Kalra (Sulzer Pump) Project Manager: Kenneth Welch (GEH) Committee Chairman: John Freeman (Exelon) BWROG-TP-12-012 Revision 0 August 20 12 BWROG-TP-12-012 REV 0 INFORMATION NOTICE Recipients of this document have no authority or rights to release these products to anyone or organization outside their utility.
The recipient shall not publish or otherwise disclose this document or the information therein to others without the prior written consent of the BWROG, and shall return the document at the request of BWROG. These products can, however, be shared with contractors performing related work directly for the participating utility, conditional upon appropriate proprietary agreements being in place with the contractor protecting these BWROG products. With regard to any unauthorized use, the BWROG participating Utility Members make no warranty, either express or implied, as to the accuracy, completeness, or usefulness of this guideline or the information, and assumes no liability with respect to its use. BWROG Utility Members CENG - Nine Mile Point Chubu Electric Power Company DTE - Fermi Chugoku Electric Power Company Energy Northwest
- Columbia Comisión Federal de Electricidad Entergy - FitzPatrick Hokuriku Electric Power Company Entergy - Pilgrim Iberdrola Generacion, S.A. Entergy - River Bend/Grand Gulf Japan Atomic Power Company Entergy - Vermont Yankee J-Power (Electric Power Development Co.) Exelon (Clinton) Kernkraftwerk Leibstadt Exelon (D/QC/L) South Texas Project Exelon (Oyster Creek) Taiwan Power Company Exelon (PB/Limerick) Tohoku Electric Power Company FirstEnergy
- Perry Tokyo Electric Power Company NPPD - Cooper NextEra - Duane Arnold PPL - Susquehanna PSEG - Hope Creek Progress Energy
- Brunswick SNC - Hatch TVA - Browns Ferry Xcel - Monticello
BWROG-TP-12-012 REV 0 2 Executive Summary This BWROG Technical Product provides an evaluation of the impact of cavitation on the service life of the Sulzer CVDS pump model used at the Monticello station and other BWR stations. The evaluation considers the potential effects of operating in the range of NPSH A that result in the maximum erosion rate.
Implementation Recommendations This product is intended for use to address (in part) issues raised in the NRC Guidance Document for the Use of Containment Accident Pressure in Reactor Safety Analysis (ADAMS Accession No. ML102110167). Implementation will be part of the BWROG guidelines on the use of Containment Accident Pressure credit for ECCS pump NPSH analyses.
Benefits to Site This product provides a technical response to the NRC concerns raised about the potential for cavitation wear during long term pump operation in a post-accident environment.
QUALITY LEVEL SULZER PUMPS (US) INC. DOCUMENT ASME CODE SECTION Direct DOC. NO: E12.5.1912 Indirect ORDER NO:
CLASS NO. CODE EDITION (YEAR) TITLE: Task 4 - Operation in Maximum Erosion Rate Zone Sulzer Pumps (US) Inc.
SEASON YEAR Monticello - 12x14x14.5 CVDS RHR Pump CUSTOMER GE-HITACHI Nuclear Energy Americas LLC PROJECT Monticello Nuclear Power Station, Monticello, MN CUSTOMER P.O. NO.
437054820 CONTRACT NUMBER SPECIFICATION NO.
ITEM / TAG NUMBER CUSTOMER APPROVAL NUMBER: CUS TOMER APPROVAL REQUIREMENT Yes No Information Only SPACE FOR CUSTOMER APPROVAL STAMP CERTIFIED AS A VALID SULZER PUMPS (US) INC. DOCUMENT (when applicable/available)
For Outside Vendor
For Manufacture at Sulzer Pumps (US) Inc.
Risk Release Inspection Report # ________________
Other (specify)
_______________________ APPROVALS (SIGNATURE) Date Engineering 04/23/12 Quality Assurance CERTIFICATION (when applicable)
Originating Advance Engineering This Document is certified to be in compliance Dept: with THE APPLICABLE PURCHASE ORDER, By: SPECIFICATIONS, PROCEDURES, AND ADDITIONAL REQUIREMENTS LISTED IN Ankur Kalra THE APPENDICES. Title: Hydraulic Design Engineer Date: 11/7/2011
__________________________________________ Professional Engineer APPLICABLE S.O. NUMBERS: ___________ _____________________________
100072780 State Registration No.
Date _______________
E12.5.1912 0 Rev. DOCUMENT IDENTIFICATION Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 1 TABLE OF CONTENTS 1.0 PURPOSE .......................................................................................................................
.......................................... 2 2.0 BACKGROUND ....................................................................................................................
.................................. 2 3.0 SCOPE .........................................................................................................................
............................................. 3 4.0 ANALYSIS.......................................................................................................................
......................................... 4
5.0 CONCLUSION
..............................................................................................................................
......................... 12 6.0 BIBLIOGRAPHY ..............................................................................................................................
..................... 13
Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 2 1.0 PURPOSE To evaluate the impact of cavitation on the service life of a Monticello RHR pump impeller. Cavitation in a pump can result in pump vibration, noise and component erosion. This report addresses the
material erosion aspects of an impeller under cavitation. The material erosion of an impeller under
cavitation is predicted using formulae from Gülich's Book; Centrifugal Pumps [Ref 1]. These formulae
were developed in an EPRI study [6] from empiri cal data collected for various pump types for predicting the number of hours an impeller will su rvive under reduced Net Positive Suction Head (NPSH). The purpose of this evaluation is to show t hat the impeller service life is at least 30 days (720
hours) of operation when operating at reduced NPSH margin.
2.0 BACKGROUND The service life of an impeller can be predicted based on a defined percentage of material loss due to cavitation erosion and on a known or predicted cavitation bubble length. The three primary factors
influencing cavitation erosion are : 1) The hydrodynamic cavitation intensity. 2) The cavitation
resilience of the material. 3) Time duration over which the cavitation is acting. The hydrodynamic
cavitation intensity is related to the volume of the cavitation vapor (related to bubble length) in the flow
and the differential pressure (p-p v) driving the implosion of the bubbles. The cavitation resilience is purely a function of the mechanical properties of the material. The rate of cavitation erosion will then
depend on the hydrodynamic cavitation intensity, the material cavitation resilience and the time
duration during which the cavitation is occurring. The service life of an impeller undergoing cavitation
depends strongly on absolute pressure of the fluid (suction pressure minus vapor pressure) which
drives the gas-bubble implosion, the impeller materi al properties (strength and modulus of elasticity), and on the flow characteristics and liquid properties. Gülich [Ref 1] explains that cavitation erosion
occurs only when the hydrodynamic cavitation intensity (dependent on flow and fluid properties)
exceeds the cavitation resistance (dependent on material properties; fixed for a given material and
temperature) of the impeller material and that "hydrodynamic cavitation intensity increases with the
total volume of all vapor bubbles created in the flow".
The length of the cavitation bubble is related to the bubble volume, which in turn is an indicator of the
damage producing potential. The optimal way to determine the true bubble length for a given impeller geometry while operating under a given set of inlet conditions (flow rate and NPSHa) is by flow
visualization from model testing. Recently, with the advent of advanced CFD techniques it is possible to simulate the bubble length as a function of inlet conditions.
[[
Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 3 ]] Relationships between cavitation bubble length and the rate of material erosion have been derived empirically.
3.0 SCOPE For evaluating impeller damage due to cavitation erosion; impeller material properties, flow properties, and available NPSH are considered for this analysis.
a) Impeller life due to cavitation damage is predicted using Gülich's empirical formulae and CFD analysis results [8]. b) Validity of the impeller life prediction formulae conducted during experimental and field operation analysis work is briefly discussed. c) Impeller life prediction method is presented in a step-by-step format. Calculation steps include methods for bubble length, material resilience, erosion power, erosion rate and impeller life
calculation. Several conservatisms, which are listed in section 5, are incorporated in the
calculation.
Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 4 4.0 ANALYSIS A CFD study of the Monticello RHR impellers using a commercial CFD package was conducted to
predict NPSH 3%, bubble lengths, and bubble location under varying flow rates and NPSH margins
[8]. Figure 1 shows bubble lengths versus NPSH margin predicted by the CFD analysis for four
different pump flow rates. As would be expected, Figure 1 shows the bubble length grows as the
NPSH margin decreases.
[[ ]] Figure 1: Bubble Growth versus NPSH margin
Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 5 The bubble lengths and the corresponding NPSHa values obtained from the CFD results are then
used in the Gulich formulae to predict maximum erosion rate at different pump flow rates and NPSH
margins. Figure 2 shows impeller erosion rate (µm/hr) versus NPSH margins at different flow rates. It is observed that the maximum erosion occurs at
[[ ]] for an NPSHa margin of
[[ ]]. A sample maximum erosion rate calculation for the
[[ ]] flow is provided in the following sections of the report along with the corresponding impeller service life calculation.
[[ ]] Figure 2: Erosion Rate versus NPSH Margin NPSH values corresponding to the full diameter impeller (14.5") are used for this analysis. The current
Monticello trim diameter is
[[ ]] (approximately
[[ ]] trim). [[ ]]
Given:
Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 6 Impeller Material:
[[ ]] SI units Imperial units Tensile strength, R m [[ ]] [[ ]] [Ref 3] Young's modulus, E 2.01 x 10 11 N/m 2 29,200 kpsi [Ref 4]
Impeller blade thickness at
cavitation length 2 , e [[ ]] [[ ]] Density of water, (at 95ºF) 994 kg/m³ 0.994 S.G. Gravitational constant, g 9.81 m/s² 32.2 ft/sec²
Impeller outer diameter, D 2 [[ Impeller eye diameter, D 1 Circumferential velocity 3 at impeller eye, u 1
Eye Area (each side)
]]
[[ ]]
Meridional velocity 4 , c 1 [[ ]] NPSH 3% [[ ]] (as predicted by CFD)
The formulae used in this report for predicting im peller erosion rate and impeller service life have been empirically derived from a large pool of cavi tation test results obtained from several pump manufacturers for different pump types [6]. These test results were used to develop a correlation between NPSH, cavitation resistance, vapor density, speed of sound, gas content, and the erosion
rate.
These formulae have been verified through experimentation using visual inspection techniques. Bruno
Schiavello in paper, "Pump Cavitation - Various NPSHR Criteria, NPSHA Margins, and Impeller Life
Expectancy" [Ref 5] validates Gülich's erosion rate formulae by comparing the cavitation damage depth on impellers in the field with the predicted values. Several other field tests and research papers
have verified the use of these formulae for accurately predicting impeller service life.
2 [[
]]
3 Calculated as x (impeller eye diameter) x (revolutions per second) 4 Meridional velocity is calculated as flow rate, Q, divided by eye area
Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 7 Following steps outline the impeller life prediction method in a step-by-step approach.
Step 1: Calculate resistance to cavitation damage (U R) for the impeller material This quantity depends only on the impeller material properties. For
[[ ]] at 35°C (95°F):
[[ ]] Step 2: Estimate cavity length Cavity length data is generally obtained experimenta lly using flow visualization techniques or analytically from CFD simulation results. In the case of the Monticello RHR pumps, cavity lengths
were determined via CFD, see Figure 1. A bubble length of 0.05 m, obtained from the CFD analysis
for 3900 gpm at the NPSH margin of 2.0 (predicted maximum erosion zone), is used for this sample
calculation.
When the cavity length data is absent and there is an NPSH margin (additional NPSH available above
the NPSH 3% required), the following formula can be used to estimate cavity length based on impeller geometry and coefficients derived from the NPSH values.
[[
]]
Depending upon flow conditions and the impeller inlet geometry the bubble formation can occur at the suction side, the pressure side or both sides of the impeller blade inlet (Figure 3 shows the general
effect of incidence angle on cavitation bubble formation). Generally, zero incidence angle (i = 0)
occurs at the BEP flow rate. However, 1-D Excel based flow calculation tools, and the CFD analysis
results provide evidence that for the Monticello impeller design the positive flow incidence angle is
observed at the blade inlet (suction side cavitation) even at the highest flow rate considered for the analysis ([[ ]]). Therefore, only suction side erosion calculation methods are used for the impeller life analysis. In the case of Monticello RHR impeller, the vertical red line (Figure 3), zero
incidence occurs at approximately
[[ ]] of BEP flow. Further, Figure 3 below also shows a Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 8 general trend for NPSH i (inception cavitation), NPSH 3%, Noise and Erosion as a function of inlet flow incidence.
Figure 3: NPSH, Noise and Erosion versus Inlet Incidence The erosion formulae and the CFD results have been used to develop the relationship between
erosion rate and the flow incidence angle (Figure 4) for the different flow rates. As shown in Figure 4, the lowest erosion rate zones are found at BEP ([[ ]]) and at low incidence angles
([[ ]]). i < 0i > 0 NPSH [m] Inception3% 0% Erosion, noise Inlet Incidence (i = 0)
NPSH A Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 9 [[ ]] Figure 4: Maximum Erosion Rate versus Incidence angle Step 3: Determine absolute pressure p at the impeller inlet
This is the differential pressure that drives bubble implosion. It is dependent upon NPSH A. For this calculation, NPSHa is equal to
[[ ]] times the NPSH 3% ( See Figure 2 - maximum erosion zone at
[[ ]]). 2 3 2 3 2 1 1)47.6(2/994)2.13)(/81.9)(/994(2)(mkgsmmkg cNPSHgppp A V = [[ ]] p 1 = suction pressure at impeller inlet p v = vapor pressure at impeller inlet Step 4: Determine erosion power P ER [[
Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 10 ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° °
° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° °
° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° °
° ° ° ° °
° ° ° ]] Erosion power is calculated as follows (Gülich, equation 6.1.2):
44.0'36.0 3 1 2 ref ref ref x ref cav mat cor ref ER a a L L F F p p C P Where:
C 1 = 5.4 x 10
-24 W/m² for suction side erosion (constant from empirical data) p =
[[° ° ° ° ° ° ° ° ° ° °
° ° ° ]] (for [[° ° ° ° ° ° ° °
° ° ° ]] flow rate) p ref = 1 N/m² (used by Gülich in empirical calculations)
F cor = corrosion factor = 1 for fresh water (Sulzer Handbook 1.008.004 Table 3)
F mat = material factor = 1 for ferritic steel (Sulzer Handbook 1.008.004 Table 3)
Lcav
= [[° ° ° ° ° °
° ° ° ]] (From CFD analysis for
[[° ° ° ° ° ° ° °
° ° ° ]] flow rate)
L ref = 0.010m (used by Gülich in empirical calculations) x 2 = 2.83 for suction side erosion (constant from empirical data)
a = speed of sound in the fluid = [[° ° ° ° ° ° ° °
° ° ° ]] (water at
° ° ° ° ° ° ° ) (Using Lubber and Graff's eqs) a ref = 1497 m/s (water at 20°C) (Using Lubber and Graff's eqs) = gas content of fluid = [[° ° ° ° ° ° ° °
° ° ° ]] ([[° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° ° °
° ° ° ]]) ref = 24ppm (reference: ordinary, untreated water) " = density of saturated vapor = [[° ° ° ° ° ° ° ° ° °
° ° ° ]] (water at
° ° ° ° ° ° ° ) " ref = 0.02 kg/m³ (water at 20°C)
For [[° ° ° ° ° ° ° °
° ° ° ]]: ° ° ° ° ° ° °
Step 5: Calculate erosion rate E R
Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 11 [[ ]] E R = [[ ]] for [[ ]] flow Step 6: Calculate expected impeller life LI, exp )))(((3600))((exp, R I Een L
LI, exp = expected impeller life in hours n = defined proportion of impeller material lost at end of service life e = original thickness of impeller blade at site of cavitation
= [[ ]] = duration of service at particular load considered The function would be used in situations where the impeller was subject to different cavitation conditions over the course of its service life. In this study only one cavitation situation is being considered for the estimation of impeller service life, so = 1. [[ ]] [[ ]]
Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 12
5.0 CONCLUSION
The cavitation erosion and the impeller service life calculations for the maximum erosion zone show that the Monticello RHR impeller would operate for at least
[[ ]] while operating at the flow rate and NPSH margin corresponding to the maximum erosion rate, [[ ]] and [[ ]] respectively. This service life is
[[ ]] times the minimum required service life of
[[
]] Based on the above analysis, the impeller life at the maximum erosion rate greatly exceeds the
[[ ]] mission time. Hence, it can be concluded that the impeller integrity is assured.
Task 4 - Operation in Maximum Erosion Rate Zone E12.5.1912 12x14x14.5 CVDS 13 6.0 BIBLIOGRAPHY
[1] J. Gülich Centrifugal Pumps (2008), Springer-Verlag publishers Section 6.6 "Cavitation erosion" [2] Speed of Sound in water -
http://resource.npl.co.uk/acoustics/techguides/soundpurewater/content.html#LUBBERS
[3] ASTM Standards A487A/487M-93 (Reapproved 2007)
[4] ASME B31.1-1995
[5] Bruno Schiavello, "Pump Cavitation - Various NPSHR Criteria, NPSHA Margins, and Impeller Life Expectancy".
[6] Gülich JF: Guidelines for prevention of cavitation in centrifugal feedpumps. EPRI Report GS-6398, Nov 1989.
[7] Philippe Dupont and Gary Fitch, "Impeller Life Prediction in Pumps", 10 th European Fluid Machinery Congress, April 2008.
[8] Philippe Dupont, Bruno Maroccia - Investigation Report 2012, Numerical prediction of NPSH 3% by means of an impeller only CFD calculation for Monticello 12x14x14.5CVDS.