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Category:Report
MONTHYEARML23172A1112023-06-21021 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 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 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 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 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 ML13282A1422013-10-0404 October 2013 GE-MNGP-AEP-3304R1, Enclosure 2, GEH Response to Mella + RAI 2 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 ML13248A3462013-08-29029 August 2013 WCAP-17252-NP, Revision 4 - Acoustic Loads Definition for the Monticello Steam Dyer Replacement Project, Enclosure 12 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 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 ML13248A3442013-08-29029 August 2013 WCAP-17548-NP, Revision 2 - Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data, Enclosure 10 ML13248A3452013-08-29029 August 2013 WCAP-17251-NP, Revision 2 - Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report, Enclosure 11 ML13200A1922013-07-31031 July 2013 ANP-3092(NP), Rev. 0, Monticello Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies. ML13200A1962013-07-31031 July 2013 ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel. 2023-06-21
[Table view] Category:Technical
MONTHYEARL-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 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 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) 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 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 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 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. 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 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 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 ML13200A1992013-05-31031 May 2013 ANP-3221NP, Rev. 0, Fuel Rod Thermal-Mechanical Design for Monticello Atrium 10XM Fuel Assemblies, Cycle 28. ML13200A1942013-05-31031 May 2013 ANP-3215(NP), Rev. 0, Monticello Fuel Transition Cycle 28 Fuel Cycle Design (Epu/Mellla). ML13200A2002013-05-31031 May 2013 ANP-3139(NP), Rev. 1, Nuclear Fuel Design Report Monticello Cycle 28 Atrium 10XM Fuel. ML13200A1972013-05-31031 May 2013 ANP-3212(NP), Rev. 0, Monticello EPU LOCA-ECCS Analysis MAPLHGR Limits for 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. 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. 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. 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. 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. 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. ML12300A2202012-10-31031 October 2012 Attachment 10: BWROG-TP-12-018, Revision 0, Task 3 - Pump Operation at Reduced Npsha Conditions (Cvds Pump) ML13200A1912012-10-31031 October 2012 ANP-3119NP, Rev. 0, Mechanical Design Report for Monticello Atrium 10XM Fuel Assemblies. 2022-06-06
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Text
BWROG-TP-12-013 Revision 0 August 2012 Containment Accident Pressure Committee Task 5 - Effects of Non-Condensible Gases on Seals (CVDS Pump)
Author: Ankur Kalra (Sulzer Pump)
Project Manager: Kenneth Welch (GEH)
Committee Chairman: John Freeman (Exelon)
BWROG-TP-12-013 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-12-013 REV 0 Executive Summary This BWROG Technical Product provides an evaluation of the effect of non-condensable gases which come out of solution and migrate to a pump seal purge piping. The evaluation is based on the seal purge piping arrangement of the Monticello RHR pump (model CVDS).
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 in the reference document above about the potential pump seal damage resulting from gases which come out of solution and migrate into the pump seal purge piping.
2
QUALITY LEVEL SULZER PUMPS (US) INC. DOCUMENT ASME CODE Direct DOC. NO: E12.5.1913 SECTION Indirect ORDER NO: CLASS NO.
CODE EDITION TITLE: Task 5 - Effect of Non-Condensable Gases on Seals (YEAR)
Sulzer Pumps (US) Inc. SEASON Monticello - 12x14x14.5 CVDS RHR Pump YEAR 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: CUSTOMER 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 Risk Release Inspection Report # ________________
_For Manufacture at Sulzer Pumps (US) Inc. 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, SPECIFICATIONS, PROCEDURES, AND By:
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 _______________ 0 E12.5.1913 Rev.
DOCUMENT IDENTIFICATION
E12.5.1913 Task 5 - Non-Condensable Gases 12x14x14.5 CVDS TABLE OF CONTENTS 1.0 PURPOSE ................................................................................................................................................................. 2
2.0 BACKGROUND
...................................................................................................................................................... 2 3.0 SCOPE ...................................................................................................................................................................... 2 4.0 ANALYSIS................................................................................................................................................................ 3 5.0 RESULTS AND CONCLUSIONS .......................................................................................................................... 7 6.0 BIBLIOGRAPHY .................................................................................................................................................... 8 1/8
E12.5.1913 Task 5 - Non-Condensable Gases 12x14x14.5 CVDS 1.0 PURPOSE The purpose of this report is to evaluate the potential impact of the evolution of non-condensable gases on the mechanical seals of Monticello RHR pumps.
2.0 BACKGROUND
Dissolved gases are present in water depending on the fluid temperature, gas solubility, pressure, and duration of contact. For extended time duration, the gas and liquid will come to an equilibrium state according to Henry's Law. As a liquid passes through a centrifugal pump, the reduced pressure at the pump inlet can result in some of the dissolved gas coming out of solution as gas bubbles. Since the pump seals are continuously cooled using flush water from the pump discharge, the flush water will contain small amounts of gas bubbles. In addition, it is also possible that air bubbles can migrate within the pump casing into the pump seals.
3.0 SCOPE The following are evaluated in this report.
x Froude number and critical flow calculation are used to determine the possibility of bubble accumulation in the discharge end and mechanical seal piping.
x Mechanical seal flush piping orientation, seal flush, and internal bearing flush injection system's role in permitting entrained air to accumulate in the stuffing box region of the pump.
2/8
E12.5.1913 Task 5 - Non-Condensable Gases 12x14x14.5 CVDS 4.0 ANALYSIS This report evaluates the potential for the accumulation of the non-condensable gases at the mechanical seal faces that could cause the lack of lubrication and cooling of the seal faces leading to damage and eventual seal failure. To predict gas accumulation it is important to understand the piping configuration and the flow characteristics of the two-phase (liquid along with the entrained gas) fluid.
Figure 1 shows examples of two phase flows. The Froude number, a ratio of inertial force on a liquid to gravitation force, is a useful parameter for predicting non-condensable gas dynamics in a fluid carrying duct.
Figure 1: Entrained Air in Pipes [Ref 1]
4.1 According to BWROG, The suppression pool water is normally at a range of (( )) to
(( )) and is at equilibrium with the suppression pool air space, which is composed of ((
))
4.2 In the case of the Monticello RHR pumps the mechanical seals are lubricated and cooled by pumpage (flush) that is tapped off from the discharge nozzle (See Fig. 2). Water at high pressure enters the cyclone separator where any debris in the flush is separated out.
A Froude number calculation for the discharge and the seal piping can show if the bubbles trapped in the fluid will travel through the mechanical seal flush piping and reach the internal bearings. It is important to note that; 3/8
E12.5.1913 Task 5 - Non-Condensable Gases 12x14x14.5 CVDS Froude number (Fr) > 1 Supercritical Flow Froude number (Fr) < 1 Subcritical Flow According to several studies done on bubble propagation in circular water pipes it is found that in a supercritical flow a bubble will travel with the fluid in its direction of flow [4]. In other words, bubble/entrained air will not stagnate and accumulate which may block the flow path.
Following is a calculation of the froude number for the RHR pump discharge side.
Froude( Fr ) V / g u D Where, Equation 1 [5]
V = Flow velocity, ft/sec g = Acceleration due to gravity = 32.2 ft/sec^2 D = Pipe ID, ft For RHR Pump, discharge ID is (( ))
FlowRate FlowVelocity (V ) ,
Cross SectionalArea At the flow rate of (( )), and cross sectional area of (( )),
V = (( )) and Fr = (( )).
In case of RHR pump mechanical seals, pipe used is (( )), with an ID of
(( )).
Flow is typically (( )), which is (( ))
2 3 uD and Cross SectionalArea = (( ))
4 V = (( )) and Fr = (( )).
Since Fr is above 1 the flow is supercritical in both the discharge and the mechanical seal piping. This shows that bubbles will not accumulate in the piping and block the flow of flush through the discharge end or the mechanical seal piping.
In addition to the above calculation, another equation derived from experimental tests predicts the flow below which the air bubbles will accumulate in the discharge piping and the seal piping. This flow is called the critical flow (Qc).
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E12.5.1913 Task 5 - Non-Condensable Gases 12x14x14.5 CVDS 5 1 Qc 0.38 u D 2 ug 2 Equation 2 [4]
Where, D = Pipe ID, in g = 32.2 ft^2/sec Using the above equation, critical flow for the discharge piping equals (( )) and for the seal piping (( )). Hence, blockage of flow due to bubble accumulation is possible if flow rate in the discharge piping falls below (( )) or below (( ] ]in the seal piping. The expected flow through the discharge piping is (( )) and seal piping is
(( )), both of which are well above the critical flow values.
4.3 After passing through the mechanical seal flush piping, entrained air would reach the internal bearings. However, due to the vertical orientation of the pump and the seal, the less dense entrained air entering from point A (See Fig 3) would rise up in the stuffing box outlet to connection point B located above the seal faces and exit to the pump suction. Arrows (Fig 3) show anticipated bubble flow path.
4.4 As long as the flush flow is above the critical flow, the possibility of air accumulation in the seal piping is not present. Also, stagnation or accumulation of air around the seal faces is unlikely due to the orientation of the seal and the location of the stuffing box outlet B. Therefore, due to the above reasons the likelihood of the seals running dry is negligible.
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E12.5.1913 Task 5 - Non-Condensable Gases 12x14x14.5 CVDS
((
))
Figure 2: Monticello - RHR Mechanical Seal Layout
((
))
Figure 3: Mechanical Seal Connections 6/8
E12.5.1913 Task 5 - Non-Condensable Gases 12x14x14.5 CVDS 5.0 RESULTS AND CONCLUSIONS Two methods; Froude Number and Critical Flow calculations indicate that air bubbles will not stagnate and accumulate in the seal piping. The vertical orientation of the pump and the location of the flush inlet and outlet on the seal stuffing box significantly reduce the possibility of air accumulation in the vicinity of the mechanical seals.
Some of the concerns, regarding air entrainment in mechanical seals, raised in the NRC guidelines can be addressed through this report.
a) Entrained air released due to NPSH margin reduction - As explained in this report, the vertical setup of the mechanical seal system will flush out the bubbles, and therefore, as long as a minimum flow through the mechanical seal piping is maintained, the possibility of void fraction accumulating at the seal faces is negligible.
b) Use of Dual Mechanical Seals - For a vertical mechanical seal setup with seal flush outlet located at the top of the seal, dual mechanical seals with external flush system will not provide an additional benefit. Vertical setup ensures constant flushing of the seal faces.
c) Excessive entrained air centrifuged inward to the shaft - Forced lubricated bearings are located between the impeller inlet and the mechanical seals. This high pressure liquid will prevent any bubbles to flow from the impeller inlet to the mechanical seal faces.
Therefore, the entrained air that may be present in the suction line of the RHR pumps following a LOCA has no significant impact on the performance of the mechanical seals.
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E12.5.1913 Task 5 - Non-Condensable Gases 12x14x14.5 CVDS 6.0 BIBLIOGRAPHY
[1]: Gas entrainment at a propagating slug front, Ruben Shulkes, Hydro Oil and Energy
[2]: Centrifugal Pumps, Johann Gulich, 2nd Edition.
[3]: Centrifugal Pumps Book, Stepanoff.
[4]: Air in Water Pipes, A manual for designers of spring supplied gravity driven rural water delivery system, Gilles Corcos, 2nd Edition.
[5]: Froude Number, Wikipedia, http://en.wikipedia.org/wiki/Froude_number
[6]: Henry's Law Calculation. http://www.engineeringtoolbox.com/air-solubility-water-d_639.html 8/8