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| =Text= | | =Text= |
| {{#Wiki_filter:Containment Accident Pressure Committee Task 2 - Equation for Pump Speed Correction (CVDS Pump) | | {{#Wiki_filter:BWROG-TP-12-011 Revision 0 August 2012 Containment Accident Pressure Committee Task 2 - Equation for Pump Speed Correction (CVDS Pump) |
| Author: Ankur Kalra (Sulzer Pump) Project Manager: Kenneth Welch (GEH) Committee Chairman: John Freeman (Exelon) BWROG-TP-12-011 Revision 0 August 20 12 BWROG-TP-12-011 REV 0 INFORMATION NOTICE Recipients of this document have no authority or rights to release these products to anyone or organization outside their utility. | | Author: Ankur Kalra (Sulzer Pump) |
| 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
| | Project Manager: Kenneth Welch (GEH) |
| - 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
| | Committee Chairman: John Freeman (Exelon) |
| - 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-12-011 REV 0 2Executive Summary This BWROG Technical Product provides a technical evaluation of the applicability of a standard equation to the Sulzer CVDS pump model used at the Monticello station 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. | | BWROG-TP-12-011 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. |
| QUALITY LEVEL SULZER PUMPS (US) INC. DOCUMENT ASME CODE SECTION Direct DOC. NO: E12.5.1910 Indirect ORDER NO:
| | 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. |
| 100072780 CLASS NO.CODE EDITION (YEAR)TITLE:Task 2 - Equation for Pump Speed Correction Sulzer Pumps (US) Inc.
| | 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. |
| SEASON YEARMonticello - RHR & CS Pumps CUSTOMERGE-HITACHI Nuclear Energy Americas LLC PROJECT Monticello Nuclear Power Station, Monticello, MN CUSTOMER P.O. NO.
| | Entergy - River Bend/Grand Gulf Japan Atomic Power Company Entergy - Vermont Yankee J-Power (Electric Power Development Co.) |
| 437054820CONTRACT NUMBER SPECIFICATION NO.
| | 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 |
| 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 03/12/12QualityAssurance 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 KalraTHE APPENDICES. Title: Hydraulic Design Engineer Date: 11/7/2011__________________________________________Professional Engineer APPLICABLE S.O. NUMBERS:
| |
| ___________ _____________________________
| |
| 0State Registration No.
| |
| Date _______________
| |
| E12.5.1910 0 Rev.DOCUMENT IDENTIFICATION Task 2 - Pump Speed Correction E12.5.1910 MONTICELLO -RHR & CS PUMPS 1/4 TABLE OF CONTENTS 1.0PURPOSE ..............................................................................................................................
| |
| ..................................
| |
|
| |
|
| ==22.0BACKGROUND==
| | BWROG-TP-12-011 REV 0 Executive Summary This BWROG Technical Product provides a technical evaluation of the applicability of a standard equation to the Sulzer CVDS pump model used at the Monticello station and other BWR stations. The equation correlates changes in pump speed to changes in pump NPSHR. |
| ..............................................................................................................................
| | 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. |
| ........................ 23.0SCOPE .............................................................................................................................. | | Benefits to Site This product provides a technical response to the NRC concerns raised in the reference above regarding the potential for changes in NPSHR as pump operating speed is changed. |
| ........................................ 34.0ANALYSIS ..............................................................................................................................
| | 2 |
| .................................. 35.0RESULTS AND CONCLUSION
| |
| ............................................................................................................................ 46.0BIBLIOGRAPHY ..............................................................................................................................
| |
| ....................... 4 Task 2 - Pump Speed Correction E12.5.1910 MONTICELLO -RHR & CS 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
| |
|
| |
|
| and CS pumps installed in the Monticello nuclear facility. These pumps, when tested at the
| | QUALITY LEVEL SULZER PUMPS (US) INC. DOCUMENT ASME CODE Direct DOC. NO: E12.5.1910 SECTION Indirect ORDER NO: 100072780 CLASS NO. |
| | CODE EDITION TITLE: Task 2 - Equation for Pump Speed Correction (YEAR) |
| | Sulzer Pumps (US) Inc. SEASON Monticello - RHR & CS Pumps 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 03/12/12 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: |
| | ___________ _____________________________ 0 State Registration No. |
| | Date _______________ 0 E12.5.1910 Rev. |
| | DOCUMENT IDENTIFICATION |
|
| |
|
| Sulzer Pumps factory, were operated at a fixed speed using electrical induction motors. Test
| | E12.5.1910 Task 2 - Pump Speed Correction MONTICELLO -RHR & CS PUMPS TABLE OF CONTENTS 1.0 PURPOSE ................................................................................................................................................................ 2 |
|
| |
|
| motors have a slip factor that is dependent upon motor design (efficiency and motor power
| | ==2.0 BACKGROUND== |
| | | ...................................................................................................................................................... 2 3.0 SCOPE ...................................................................................................................................................................... 3 4.0 ANALYSIS................................................................................................................................................................ 3 5.0 RESULTS AND CONCLUSION............................................................................................................................ 4 6.0 BIBLIOGRAPHY ..................................................................................................................................................... 4 1/4 |
| 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 | | E12.5.1910 Task 2 - Pump Speed Correction MONTICELLO -RHR & CS PUMPS 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 and CS pumps installed in the Monticello nuclear facility. 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. |
| | |
| the tested pump thus increasing the required NPSH. | |
|
| |
|
| ==2.0 BACKGROUND== | | ==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 | | 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 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. |
| | | 2/4 |
| 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 | |
| | |
| 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
| | E12.5.1910 Task 2 - Pump Speed Correction MONTICELLO -RHR & CS PUMPS 3.0 SCOPE The NPSHr prediction equation for pump speed correction from HI/ANSI 1.6 standard is: |
| | 2 |
| | § n2 |
| | * NPSH 2 ¨¨ ¸¸ u NPSH 1 , ------- (1) |
| | © n1 ¹ Where; NPSH1 = Net positive suction head at test speed; NPSH2 = Net positive suction head at specified speed; n1 = Test speed in rpm; n2 = 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 Monticello 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 manufacturers. Johann Gulich's book; Centrifugal Pumps [2], uses test data from eight pump 3/4 |
|
| |
|
| 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
| | E12.5.1910 Task 2 - Pump Speed Correction MONTICELLO -RHR & CS PUMPS manufacturers for developing an equation for lower speed NPSHr prediction. |
| | |
| 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 E12.5.1910 MONTICELLO -RHR & CS 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 Monticello 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
| |
| | |
| manufacturers. Johann Gulich's book; Centrifugal Pumps [2], uses test data from eight pump Task 2 - Pump Speed Correction E12.5.1910 MONTICELLO -RHR & CS PUMPS 4/4 manufacturers for developing an equation for lower speedNPSHr prediction.
| |
| Gulich's Equation: | | Gulich's Equation: |
| 1 2 1 2 NPSH n n NPSH x , where x (exponent) =
| | 0.3 |
| 3.0 3 2 ref NPSH NPSH , ---- (2)
| | § n2 |
| Where, NPSH ref= 20 m. If we use Gulich's equation (2) above, that is based on empirical data, to predict the NPSHr at | | * x |
| [[° ° ° ° ° ° ° ° | | § NPSH 3 |
| ° ° ° ]] we would obtain x = | | * NPSH 2 ¨ ¸ u NPSH 1 , where x (exponent) = 2 u ¨¨ ¸ , ---- (2) |
| [[° ° ° ° ° ° ° ]] and new NPSHr as | | ¸ |
| [[° ° ° ° ° ° ° ° ° ° ° ° | | © n1 ¹ © NPSH ref ¹ Where, NPSHref = 20 m. |
| ° ° ° ]] less than the[[° ° ° ° ° ° ° | | If we use Gulich's equation (2) above, that is based on empirical data, to predict the NPSHr at |
| ° ° ° ]] 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 | | [[° ° ° ° ° ° ° ° ° ° ° ]] 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. |
| [[° ° ° ° ° ° ° ]] 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 and CS pumps. For speed decreases, an empirical correlation such as that prescribed by Gulich is | | 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 and CS pumps. For speed decreases, an empirical correlation such as that prescribed by Gulich is recommended. |
| | | 6.0 BIBLIOGRAPHY |
| recommended. | |
| 6.0 BIBLIOGRAPHY | |
| [1]: ANSI/HI 1.6, 2000, American National Standard for Centrifugal Pump Tests | | [1]: ANSI/HI 1.6, 2000, American National Standard for Centrifugal Pump Tests |
| [2]: Centrifugal Pumps, Johann Gulich, 2 nd Edition. | | [2]: Centrifugal Pumps, Johann Gulich, 2nd Edition. |
| [3]: Centrifugal Pumps Book, Stepanoff.}} | | [3]: Centrifugal Pumps Book, Stepanoff. |
| | 4/4}} |
|
|---|
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
[Table view] |
Text
BWROG-TP-12-011 Revision 0 August 2012 Containment Accident Pressure Committee Task 2 - Equation for Pump Speed Correction (CVDS Pump)
Author: Ankur Kalra (Sulzer Pump)
Project Manager: Kenneth Welch (GEH)
Committee Chairman: John Freeman (Exelon)
BWROG-TP-12-011 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-12-011 REV 0 Executive Summary This BWROG Technical Product provides a technical evaluation of the applicability of a standard equation to the Sulzer CVDS pump model used at the Monticello station and other BWR stations. The equation correlates changes in pump speed to changes in pump NPSHR.
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 NPSHR as pump operating speed is changed.
2
QUALITY LEVEL SULZER PUMPS (US) INC. DOCUMENT ASME CODE Direct DOC. NO: E12.5.1910 SECTION Indirect ORDER NO: 100072780 CLASS NO.
CODE EDITION TITLE: Task 2 - Equation for Pump Speed Correction (YEAR)
Sulzer Pumps (US) Inc. SEASON Monticello - RHR & CS Pumps 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 03/12/12 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:
___________ _____________________________ 0 State Registration No.
Date _______________ 0 E12.5.1910 Rev.
DOCUMENT IDENTIFICATION
E12.5.1910 Task 2 - Pump Speed Correction MONTICELLO -RHR & CS PUMPS 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 1/4
E12.5.1910 Task 2 - Pump Speed Correction MONTICELLO -RHR & CS PUMPS 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 and CS pumps installed in the Monticello nuclear facility. 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 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.
2/4
E12.5.1910 Task 2 - Pump Speed Correction MONTICELLO -RHR & CS PUMPS 3.0 SCOPE The NPSHr prediction equation for pump speed correction from HI/ANSI 1.6 standard is:
2
§ n2
© n1 ¹ Where; NPSH1 = Net positive suction head at test speed; NPSH2 = Net positive suction head at specified speed; n1 = Test speed in rpm; n2 = 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 Monticello 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 manufacturers. Johann Gulich's book; Centrifugal Pumps [2], uses test data from eight pump 3/4
E12.5.1910 Task 2 - Pump Speed Correction MONTICELLO -RHR & CS PUMPS manufacturers for developing an equation for lower speed NPSHr prediction.
Gulich's Equation:
0.3
§ n2
§ NPSH 3
- NPSH 2 ¨ ¸ u NPSH 1 , where x (exponent) = 2 u ¨¨ ¸ , ---- (2)
¸
© n1 ¹ © NPSH ref ¹ Where, NPSHref = 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 and CS 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, 2nd Edition.
[3]: Centrifugal Pumps Book, Stepanoff.
4/4
