BWROG-TP-13-008, Rev. 0, Containment Accident Pressure Committee (344) Task 2 - Equation for Pump Speed Correction (Cvic Pump), Attachment 9ML14077A091 |
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Site: |
Peach Bottom, Browns Ferry, Boiling Water Reactor Owners Group |
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Issue date: |
06/30/2013 |
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From: |
Kalra A BWR Owners Group, Sulzer Pumps (US) |
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To: |
GE-Hitachi Nuclear Energy Americas, Office of Nuclear Reactor Regulation |
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Shared Package |
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ML14077A088 |
List: |
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References |
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100072780, BWROG-14014 BWROG-TP-13-008, Rev. 0, E12.5.1940, Rev. 0 |
Download: ML14077A091 (8) |
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Category:Report
MONTHYEARML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) ML24177A1512024-06-24024 June 2024 Post Accident Monitoring Instrumentation Report ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML23346A2392024-01-17017 January 2024 Seismic Hazard Report by the Office of Nuclear Reactor Regulation ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information ML23025A0752023-01-25025 January 2023 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report Cycle . ML22363A3922022-12-28028 December 2022 Cycle 14 Mellla+ Eigenvalue Tracking Data CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information 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 ML22154A4042022-06-0303 June 2022 Unit 3 Cycle 20 Mellla+ Eigenvalue Tracking Data CNL-22-057, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use2022-05-27027 May 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use CCN:22-15, (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/212022-01-31031 January 2022 (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/21 ML21277A1232021-10-0404 October 2021 Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw Evaluation ML21246A2952021-09-29029 September 2021 Memo to File ML21246A2942021-09-29029 September 2021 Enclosufinal Ea/Fonsi for Tva'S Initial and Updated Triennial Decommissioning Funding Plans for Browns Ferry Nuclear Plant ISFSIs 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 CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User ML20329A3452020-11-24024 November 2020 Relief Request Associated with N-16A Reactor Pressure Vessel Instrument Nozzle Repairs - Submittal of Analyses ML20314A0282020-11-0606 November 2020 Verbal Relief for Penetration Nozzle ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20255A0002020-09-24024 September 2020 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic ML20112F4852020-05-0606 May 2020 Staff Assessment of Flooding Focused Evaluation CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report2019-09-0404 September 2019 Extended Power Uprate - Flow Induced Vibration Summary Report ML19053A4692019-06-10010 June 2019 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluation Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic CNL-19-004, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2019-06-0707 June 2019 Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions CNL-19-041, Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report2019-04-16016 April 2019 Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report CNL-19-032, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information2019-03-13013 March 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information ML19007A3302019-01-0707 January 2019 Final Report PBAPS Thermal Study ML18354B0662018-12-20020 December 2018 Summary of Monitoring Well Installation Details CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report2018-11-29029 November 2018 Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report ML18283B5472018-10-10010 October 2018 Responding to Letter of 11/18/1977 from E. G. Case to G. Williams, Providing Environmental Qualification Information for Electrical Connectors in Reference of IE Bulletins 77-05 & 77-05A RS-18-113, 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...2018-09-28028 September 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 Accident... CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report2018-09-13013 September 2018 Extended Power Uprate - Flow Induced Vibration Summary Report RS-18-098, Seismic Probabilistic Risk Assessment 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 ...2018-08-28028 August 2018 Seismic Probabilistic Risk Assessment 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 ... CNL-18-060, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-05-31031 May 2018 Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ML18093A3822018-03-30030 March 2018 Decommissioning Status Report - 2017 ML18079B1402018-02-23023 February 2018 Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus RS-18-002, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2018-01-0505 January 2018 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML17222A3282017-09-0505 September 2017 Flood Hazard Mitigation Strategies Assessment ML17170A0732017-06-15015 June 2017 Report Pursuant to 10 CFR 71.95 (a)(3) and (B) - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233 ML17114A3712017-04-20020 April 2017 Errata for BWRVIP-271NP: BWR Vessel and Internals Project, Testing and Evaluation of the Browns Ferry, Unit 2, 120 Degree Capsule ML17093A6972017-03-30030 March 2017 Decommissioning Status Report - 2016 ML19064B2232017-02-24024 February 2017 Final Report for Post-EPU Thermal and Biological Monitoring Peach Bottom Atomic Power Station ML17033B1642017-02-0202 February 2017 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement - Cycle 11 Operation Programs ML17027A0152017-01-27027 January 2017 ISFSI - Biennial 1OCFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2015 Through 12/31/2016 and Annual Commitment Revision Report for the Period 1/1/16 Through 12/31/16 ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16342B6212016-12-0707 December 2016 Results of Visual Inspections of Replacement Steam Dryer 2024-06-26
[Table view] Category:Technical
MONTHYEARML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) ML23346A2392024-01-17017 January 2024 Seismic Hazard Report by the Office of Nuclear Reactor Regulation ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information ML22363A3922022-12-28028 December 2022 Cycle 14 Mellla+ Eigenvalue Tracking Data CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information 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 ML22154A4042022-06-0303 June 2022 Unit 3 Cycle 20 Mellla+ Eigenvalue Tracking Data CNL-22-057, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use2022-05-27027 May 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use ML21277A1232021-10-0404 October 2021 Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw Evaluation 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 CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User ML20329A3452020-11-24024 November 2020 Relief Request Associated with N-16A Reactor Pressure Vessel Instrument Nozzle Repairs - Submittal of Analyses ML20314A0282020-11-0606 November 2020 Verbal Relief for Penetration Nozzle ML20255A0002020-09-24024 September 2020 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic ML20112F4852020-05-0606 May 2020 Staff Assessment of Flooding Focused Evaluation CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report2019-09-0404 September 2019 Extended Power Uprate - Flow Induced Vibration Summary Report ML19053A4692019-06-10010 June 2019 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluation Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic CNL-19-004, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2019-06-0707 June 2019 Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions CNL-19-041, Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report2019-04-16016 April 2019 Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report CNL-19-032, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information2019-03-13013 March 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information ML19007A3302019-01-0707 January 2019 Final Report PBAPS Thermal Study ML18354B0662018-12-20020 December 2018 Summary of Monitoring Well Installation Details CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report2018-11-29029 November 2018 Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report ML18283B5472018-10-10010 October 2018 Responding to Letter of 11/18/1977 from E. G. Case to G. Williams, Providing Environmental Qualification Information for Electrical Connectors in Reference of IE Bulletins 77-05 & 77-05A RS-18-113, 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...2018-09-28028 September 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 Accident... CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report2018-09-13013 September 2018 Extended Power Uprate - Flow Induced Vibration Summary Report RS-18-098, Seismic Probabilistic Risk Assessment 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 ...2018-08-28028 August 2018 Seismic Probabilistic Risk Assessment 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 ... ML18079B1402018-02-23023 February 2018 Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus RS-18-002, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2018-01-0505 January 2018 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML17222A3282017-09-0505 September 2017 Flood Hazard Mitigation Strategies Assessment ML17114A3712017-04-20020 April 2017 Errata for BWRVIP-271NP: BWR Vessel and Internals Project, Testing and Evaluation of the Browns Ferry, Unit 2, 120 Degree Capsule CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision2016-10-28028 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision ML16196A0882016-08-0505 August 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation ML16048A4412016-02-17017 February 2016 Transmittal of Extended Power Uprate: Results of Replacement Steam Dryer Power Ascension Testing ML16027A0592016-01-27027 January 2016 Snubbers Added to Lnservice Testing Program ML15275A1682015-10-0202 October 2015 Attachment 2, LTR-BWR-ENG-15-076-NP, Revision 1, Replacement Steam Dryer Report at Predicted EPU Conditions (Non-Proprietary) and Attachment 3, Affidavit CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)2015-09-25025 September 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) NL-15-169, Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program2015-09-21021 September 2015 Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program NL-15-169, Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 72015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 ML15282A1812015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 ML15282A2392015-09-21021 September 2015 Flow Induced Vibration Analysis and Monitoring Program ML15282A2402015-09-21021 September 2015 Startup Test Plan NL-15-169, Browns Ferry, Units 1, 2, and 3, Startup Test Plan2015-09-21021 September 2015 Browns Ferry, Units 1, 2, and 3, Startup Test Plan NL-15-169, ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu).2015-08-31031 August 2015 ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu). NL-15-169, ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 92015-08-31031 August 2015 ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 NL-15-169, ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu).2015-08-31031 August 2015 ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). ML15282A1822015-08-31031 August 2015 ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 ML15282A2362015-08-31031 August 2015 NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. NL-15-169, NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis.2015-08-31031 August 2015 NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. 2024-06-26
[Table view] |
Text
Containment Accident Pressure Committee (344) Task 2 - Equation for Pump Speed Correction (CVIC Pump) Authors: Ankur Kalra (Sulzer Pump)
Project Manager: Kenneth Welch (GEH)
Committee Chair: John Freeman (Exelon) BWROG-TP-13-008 Revision 0 June 2013 BWROG-TP-13-008 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-13-008 REV 0 2 Executive Summary This BWROG Technical Product provides a technical evaluation of the applicability of a standard equation to the Sulzer CVIC pump model used at the Browns Ferry, Peach Bottom, and other BWR stations. The equation correlates changes in pump speed to changes in pump NPSH R.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 above regarding the potential for changes in NPSH R as pump operating speed is changed.
QUALITY LEVEL SULZER PUMPS (US) INC. DOCUMENT ASME CODE SECTION Direct DOC. NO: E12.5.1940 Indirect ORDER NO:
100072780 CLASS NO. CODE EDITION (YEAR) TITLE: Task 2 - Equation for Pump Speed Correction Sulzer Pumps (US) Inc.
SEASON YEAR Browns Ferry & Peach Bottom - RHR Pumps CUSTOMER GE-HITACHI Nuclear Energy Americas LLC PROJECT Browns Ferry - Peach Bottom Power Station 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
For Manufacture at Sulzer Pumps (US) Inc.
Risk Release Inspection Report # ________________
Other (specify)
_______________________ APPROVALS (SIGNATURE) Date Engineering 08/31/12 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: 4/11/2012
__________________________________________ Professional Engineer APPLICABLE S.O. NUMBERS: ___________ _____________________________
0 State Registration No.
Date _______________
E12.5.1940 0 Rev. DOCUMENT IDENTIFICATION Task 2 - Pump Speed Correction E12.5.1940 BROWNS FERRY & PEACH BOTTOM -RHR PUMPS 1/4 TABLE OF CONTENTS
1.0 PURPOSE
..............................................................................................................................
.................................. 2
2.0 BACKGROUND
..............................................................................................................................
........................ 2
3.0 SCOPE
..............................................................................................................................
........................................ 3
4.0 ANALYSIS
..............................................................................................................................
.................................. 3
5.0 RESULTS
AND CONCLUSION
............................................................................................................................ 4
6.0 BIBLIOGRAPHY
..............................................................................................................................
....................... 4
Task 2 - Pump Speed Correction E12.5.1940 BROWNS FERRY & PEACH BOTTOM -RHR PUMPS 2/4 1.0 PURPOSE To evaluate the use of the equation provided in standard HI/ANSI 1.6 2000 [1] for predicting NPSHr at different pump speeds. More specifically, this analysis is being performed for RHR
pumps installed in the Browns Ferry and Peach Bottom nuclear facilities. These pumps, when
tested at the Sulzer Pumps factory, were operated at a fixed speed using electrical induction
motors. Test motors have a slip factor that is dependent upon motor design (efficiency and
motor power ratings) and applied load. In the nuclear facility, operation at less than full-rated
motor power or with high-efficiency motor tends to reduce motor slip, which can cause the
pump to operate at slightly higher speeds in the field compared to factory test speed. In
addition, an increase in the frequency of the motor power source may result in pumps running
at higher speeds than the tested pump thus increasing the required NPSH.
2.0 BACKGROUND
The physical process of cavitation (boiling) involves a phase change. In the context of a centrifugal pump inlet, the energy, or latent heat of evaporation, required to facilitate the phase
change associated with cavitation must be supplied by the liquid surrounding the cavitation
vapor bubbles. This heat transfer process from the supporting fluid to the vapor gives rise to
important physical characteristics of the cavitation process in pumps, one of which includes a
temporal component. That is, it takes some finite amount of time for the heat transfer
associated with the formation of cavitation bubble to take place. The implication of this in the
context of a pump inlet is that the longer the residence time of the flowing fluid in the low
pressure zone at the blade leading edges, the greater the bubble formation. And conversely, the shorter the residence time of the fluid in the low pressure zone the less bubble formation
there will be. This explains why the exponent 2 (square law as discussed in section 3 below)
overpredicts the NPSHr when scaling up in speed and why it underpredicts the NPSHr when
scaling down in speed.
Task 2 - Pump Speed Correction E12.5.1940 BROWNS FERRY & PEACH BOTTOM -RHR PUMPS 3/4 3.0 SCOPE The NPSHr prediction equation for pump speed correction from HI/ANSI 1.6 standard is:
1 2 1 2 2 NPSH n n NPSH, ------- (1)
Where; NPSH 1 = Net positive suction head at test speed; NPSH 2 = Net positive suction head at specified speed; n 1 = Test speed in rpm; n 2 = Operating speed in rpm;
The above equation (1) provides a square law relationship between the pump speed and
NPSHr. This relationship is evaluated for speed changes encountered in the field. The range of assessment will be limited to
[[ ]] of the nominal pump speed, which should bound all speed variations that could be encountered in the field. Moreover, alternative NPSHr speed correction methods are compared to equation (1) for predicting NPSHr speed dependence.
These sources also provide physical reasoning for using equations derived from empirical data
when predicting NPSHr at speeds lower than the test speed.
4.0 ANALYSIS
Equation (1) has been endorsed in several centrifugal pump books and papers on cavitation and has been termed as a conservative approach to NPSHr speed correction when adjusting
for higher speeds because it tends to overestimate NPSHr. As an example of the application of equation (1) for increased pump speed, consider that at
[[
]], test curves for the Browns Ferry/Peach Bottom RHR pumps show an NPSHr of
[[ ]] at a test speed of [[ ]]. A [[ ]] increase in pump nominal speed equals
[[ ]]. In equation (1) we substitute this speed and obtain an NPSHr of
[[ ]]. This is
[[ ]] higher than the test NPSHr.
For predicting NPSHr at speeds below the test speed, equation (1) tends to underestimate
NPSHr. This can lead to pumps experiencing degraded performance due to cavitation if the
NPSHa provided by the plant is insufficient due to an optimistic prediction of the pump NPSHr
at a reduced speed. For estimating NPSHr under certain conditions (e.g., speed reduction)
HI/ANSI 1.6 standard allows the use of empirical data obtained by respective pump Task 2 - Pump Speed Correction E12.5.1940 BROWNS FERRY & PEACH BOTTOM -RHR PUMPS 4/4 manufacturers. Johann Gulich's book; Centrifugal Pumps [2], uses test data from eight pump manufacturers for developing an equation for lower speed NPSHr prediction.
Gulich's Equation:
1 2 1 2 NPSH n n NPSH x , where x (exponent) =
3 0 3 2 ref NPSH NPSH , ---- (2)
Where, NPSH ref = 20 m. If we use Gulich's equation (2) above, that is based on empirical data, to predict the NPSHr at
[[ ]] we would obtain x =
[[ ]] and new NPSHr as
[[
]] less than the [[ ]] predicted by equation (1). This illustrates that the use of exponent 2 (square law approach) is a conservative approach when correcting NPSHr for higher operating speeds.
5.0 RESULTS
AND CONCLUSION For speed variations of
[[ ]] of the test speed, the HI/ANSI 1.6 2000 square law equation is suitable for determining changes in NPSHr for speed increases for the RHR pumps. For speed decreases, an empirical correlation such as that prescribed by Gulich is
recommended.
6.0 BIBLIOGRAPHY
[1]: ANSI/HI 1.6, 2000, American National Standard for Centrifugal Pump Tests
[2]: Centrifugal Pumps, Johann Gulich, 2 nd Edition.
[3]: Centrifugal Pumps Book, Stepanoff.