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Category:Report
MONTHYEARNLS2024065, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2024-10-0707 October 2024 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report NLS2024055, Data from Metamic Coupon Sampling Program2024-07-29029 July 2024 Data from Metamic Coupon Sampling Program ML23129A2792023-04-20020 April 2023 1 to Updated Safety Analysis Report, Plant Unique Analysis Report Mark I Containment Program NLS2023010, Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station2023-02-0909 February 2023 Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station NLS2023005, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20222023-01-19019 January 2023 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2022 NLS2022050, Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library2022-11-0909 November 2022 Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library NLS2022042, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2022-10-0707 October 2022 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report NLS2022003, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20212022-01-20020 January 2022 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2021 ML19262G9042019-11-0808 November 2019 Staff Assessment of Flood Hazard Integrated Assessment (Public) NLS2019040, 3-EN-DC-147, Rev. 5C1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 54 Effective Full-Power Years (Efpy). (Non-proprietary)2019-08-0707 August 2019 3-EN-DC-147, Rev. 5C1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 54 Effective Full-Power Years (Efpy). (Non-proprietary) NLS2019028, Enclosure 2 - Calculation Package, File No. 1801303.301, Cooper Nuclear Station Core Shroud H3 Weld Evaluation - 2018, Revision 02018-10-24024 October 2018 Enclosure 2 - Calculation Package, File No. 1801303.301, Cooper Nuclear Station Core Shroud H3 Weld Evaluation - 2018, Revision 0 ML18184A2732018-07-18018 July 2018 Staff Review of Mitigation Strategies Assessment Report of the Impact of the Reevaluated Seismic Hazard Developed in Response to the March 12, 2012, 50.54(f) Letter (CAC No. MF7819; EPID L-2016-JLD-0006) NLS2018024, Report 004N7680-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Coo(Er Nuclear Station Cycle 31.2018-04-30030 April 2018 Report 004N7680-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Coo(Er Nuclear Station Cycle 31. NLS2018003, Submittal of Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20172018-01-15015 January 2018 Submittal of Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2017 NLS2017070, Seismic Mitigating Strategies Assessment Report for the Reevaluated Seismic Hazard Information2017-08-24024 August 2017 Seismic Mitigating Strategies Assessment Report for the Reevaluated Seismic Hazard Information ML17244A2812017-05-0808 May 2017 16C4384-RPT-005, Rev 005, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation. NLS2016070, Completion of Required Action by NRC Order EA-12-049 - Mitigation Strategies for Beyond-Design-Basis External Events2017-01-0404 January 2017 Completion of Required Action by NRC Order EA-12-049 - Mitigation Strategies for Beyond-Design-Basis External Events NLS2016066, Completion of Required Action by NRC Order EA-12-051 - Reliable Spent Fuel Pool Instrumentation2016-12-20020 December 2016 Completion of Required Action by NRC Order EA-12-051 - Reliable Spent Fuel Pool Instrumentation ML16351A2472016-12-12012 December 2016 Review of SIA Calculation 1601004.301, Cooper High Pressure RHRSW Thinning Evaluation Per Code Case N-513 ML17018A1522016-11-0101 November 2016 Pressure and Temperature Limits Report, Revision 1 NLS2016058, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report of Evaluations for 08/01/2014 - 07/31/20162016-10-0707 October 2016 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report of Evaluations for 08/01/2014 - 07/31/2016 ML16351A2512016-09-15015 September 2016 SW-E-3-2851-3, Ultrasonic Thickness Measurement System. ML16351A2502016-09-13013 September 2016 SW-Z4-2851-7, Altrasonic Thickness Measurement System. NLS2016021, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Nuclear Station Cycle 30 (Non-Proprietary)2016-04-21021 April 2016 Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Nuclear Station Cycle 30 (Non-Proprietary) ML16084A1832016-03-0202 March 2016 Er 15-019, Rev. 1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary Version of Er 15-015). NLS2015128, Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-10-29029 October 2015 Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168 ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al NLS2015073, Er 15-019, Rev. 0, Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary), Enclosure 22015-08-0606 August 2015 Er 15-019, Rev. 0, Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary), Enclosure 2 NLS2015091, 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-07-28028 July 2015 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168 NLS2015043, Expedited Seismic Evaluation Process Report2015-04-29029 April 2015 Expedited Seismic Evaluation Process Report ML15006A2342015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) ML17018A1532014-12-31031 December 2014 BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program Data Source Book and Plant Evaluations NLS2016014, Er 15-019, Supplement 1, BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations.2014-12-31031 December 2014 Er 15-019, Supplement 1, BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations. NLS2014074, Submittal of 10 CFR 71.95 Report Involving Areva Certificate of Compliance No. 92332014-07-30030 July 2014 Submittal of 10 CFR 71.95 Report Involving Areva Certificate of Compliance No. 9233 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 NLS2014044, and ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.2102014-05-13013 May 2014 and ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.210 NLS2014027, Enclosure - Seismic Hazard Evaluation and Screening Report for Cooper Nuclear Station2014-03-20020 March 2014 Enclosure - Seismic Hazard Evaluation and Screening Report for Cooper Nuclear Station ML14007A6502014-02-11011 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14037A1672014-02-10010 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Cooper Nuclear Station, TAC No.: MF0972 NLS2012130, Problem Identification and Resolution P. 1(c) Substantive Cross-Cutting Issue2012-12-13013 December 2012 Problem Identification and Resolution P. 1(c) Substantive Cross-Cutting Issue ML12340A2752012-11-27027 November 2012 Engineering Evaluation 12-E18, Revision 0, Attachment E Through J ML12340A2732012-11-27027 November 2012 Engineering Evaluation 12-E18, Revision 0, Attachment D - Area Walk-By Checklists ML12340A2692012-11-27027 November 2012 Engineering Evaluation 12-E18, Revision 0, Attachment C - Page 76 of 322 ML12340A2682012-11-27027 November 2012 CNS Memo DED12-0003 Response to 10 CFR 50.54(f) Section 2.3 Seismic, Enclosing Engineering Evaluation 12-E18, Revision 0 NLS2012124, Enclosure to NLS2012124, Cooper Nuclear Station Flooding Walkdown Report2012-11-26026 November 2012 Enclosure to NLS2012124, Cooper Nuclear Station Flooding Walkdown Report NLS2012085, CFR 50.59(d)(2) Summary Report Covering Time Period from August 1, 2012 to July 31, 20122012-10-10010 October 2012 CFR 50.59(d)(2) Summary Report Covering Time Period from August 1, 2012 to July 31, 2012 NLS2012089, Submittal of Nuclear Material Transaction Report2012-08-29029 August 2012 Submittal of Nuclear Material Transaction Report ML1216000292012-06-11011 June 2012 Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident NLS2012040, Enclosure 2, Gnf S-0000-0140-2518-R0-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 282012-05-30030 May 2012 Enclosure 2, Gnf S-0000-0140-2518-R0-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 28 NLS2012006, Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c)2012-04-24024 April 2012 Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c) 2024-07-29
[Table view] Category:Technical
MONTHYEARML23129A2792023-04-20020 April 2023 1 to Updated Safety Analysis Report, Plant Unique Analysis Report Mark I Containment Program NLS2023010, Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station2023-02-0909 February 2023 Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station NLS2022050, Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library2022-11-0909 November 2022 Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library NLS2019040, 3-EN-DC-147, Rev. 5C1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 54 Effective Full-Power Years (Efpy). (Non-proprietary)2019-08-0707 August 2019 3-EN-DC-147, Rev. 5C1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 54 Effective Full-Power Years (Efpy). (Non-proprietary) NLS2019028, Enclosure 2 - Calculation Package, File No. 1801303.301, Cooper Nuclear Station Core Shroud H3 Weld Evaluation - 2018, Revision 02018-10-24024 October 2018 Enclosure 2 - Calculation Package, File No. 1801303.301, Cooper Nuclear Station Core Shroud H3 Weld Evaluation - 2018, Revision 0 NLS2018024, Report 004N7680-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Coo(Er Nuclear Station Cycle 31.2018-04-30030 April 2018 Report 004N7680-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Coo(Er Nuclear Station Cycle 31. NLS2017070, Seismic Mitigating Strategies Assessment Report for the Reevaluated Seismic Hazard Information2017-08-24024 August 2017 Seismic Mitigating Strategies Assessment Report for the Reevaluated Seismic Hazard Information ML17018A1522016-11-0101 November 2016 Pressure and Temperature Limits Report, Revision 1 ML16351A2512016-09-15015 September 2016 SW-E-3-2851-3, Ultrasonic Thickness Measurement System. ML16351A2502016-09-13013 September 2016 SW-Z4-2851-7, Altrasonic Thickness Measurement System. ML16084A1832016-03-0202 March 2016 Er 15-019, Rev. 1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary Version of Er 15-015). NLS2015073, Er 15-019, Rev. 0, Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary), Enclosure 22015-08-0606 August 2015 Er 15-019, Rev. 0, Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary), Enclosure 2 NLS2015091, 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-07-28028 July 2015 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168 NLS2015043, Expedited Seismic Evaluation Process Report2015-04-29029 April 2015 Expedited Seismic Evaluation Process Report NLS2016014, Er 15-019, Supplement 1, BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations.2014-12-31031 December 2014 Er 15-019, Supplement 1, BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations. ML17018A1532014-12-31031 December 2014 BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program Data Source Book and Plant Evaluations 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 NLS2014027, Enclosure - Seismic Hazard Evaluation and Screening Report for Cooper Nuclear Station2014-03-20020 March 2014 Enclosure - Seismic Hazard Evaluation and Screening Report for Cooper Nuclear Station ML14007A6502014-02-11011 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14037A1672014-02-10010 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Cooper Nuclear Station, TAC No.: MF0972 NLS2012130, Problem Identification and Resolution P. 1(c) Substantive Cross-Cutting Issue2012-12-13013 December 2012 Problem Identification and Resolution P. 1(c) Substantive Cross-Cutting Issue ML12340A2752012-11-27027 November 2012 Engineering Evaluation 12-E18, Revision 0, Attachment E Through J ML12340A2732012-11-27027 November 2012 Engineering Evaluation 12-E18, Revision 0, Attachment D - Area Walk-By Checklists ML12340A2692012-11-27027 November 2012 Engineering Evaluation 12-E18, Revision 0, Attachment C - Page 76 of 322 ML12340A2682012-11-27027 November 2012 CNS Memo DED12-0003 Response to 10 CFR 50.54(f) Section 2.3 Seismic, Enclosing Engineering Evaluation 12-E18, Revision 0 NLS2012040, Enclosure 2, Gnf S-0000-0140-2518-R0-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 282012-05-30030 May 2012 Enclosure 2, Gnf S-0000-0140-2518-R0-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 28 NLS2012006, Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c)2012-04-24024 April 2012 Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c) NLS2012002, Enclosure 2 to NLS2012002, Core Plant Bolt Stress Analysis Report (Non-Proprietary)2012-01-16016 January 2012 Enclosure 2 to NLS2012002, Core Plant Bolt Stress Analysis Report (Non-Proprietary) NLS2010075, Data from Metamic Coupon Sampling Program2010-08-0202 August 2010 Data from Metamic Coupon Sampling Program ML0830302432008-09-24024 September 2008 Cooper Nuclear Station, License Renewal Application, Appendix C, Response to BWRVIP Applicant Action Items ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0815403772008-05-0808 May 2008 Enclosure 1 - PRA 08004, Human Error Probability for Recoveries Associated with the Fire Protection Triennial Inspection Finding Related to RHR-MO-25B ML0733005732007-11-30030 November 2007 NEDO-33385, Rev. 0, Safety Analysis Report for Cooper Nuclear Station Thermal Power Optimization, Enclosure 3 ML0722901672007-08-17017 August 2007 Final Significance Determination for a White Finding and Notice of Violation - NRC Special Inspection Report 05000298/2007007 NLS2007032, SSP-07/405-C, Rev. 1, Gardel BWR - Power Distribution Uncertainties, Enclosure 52007-05-11011 May 2007 SSP-07/405-C, Rev. 1, Gardel BWR - Power Distribution Uncertainties, Enclosure 5 ML0712403472007-05-0101 May 2007 Enclosure 2, Cooper - Offsite Dose Assessment Manual NLS2006028, Holtec Report HI-2043224, Licensing Report on the Wet Fuel Storage Capacity Expansion at Cooper Nuclear Station.2006-10-17017 October 2006 Holtec Report HI-2043224, Licensing Report on the Wet Fuel Storage Capacity Expansion at Cooper Nuclear Station. NLS2006002, License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval2006-01-30030 January 2006 License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval ML0628305332004-12-22022 December 2004 Root Cause Investigation, CR-CNS-2004-07409, Unexpected Service Water System Pressure Drop NLS2004128, CNS Regulatory Conference Request for Additional Information2004-10-12012 October 2004 CNS Regulatory Conference Request for Additional Information NLS2004126, Letter to NRC from Fleming, Nebraska Public Power District, Service Water Pump Test Report, Cooper2004-10-0707 October 2004 Letter to NRC from Fleming, Nebraska Public Power District, Service Water Pump Test Report, Cooper ML0619801862004-08-0505 August 2004 Johnston Pump Company - Engineering Evaluation Regarding Short Term Dry-run of Rubber Column Bearings, Report Serial Number JP04-20, Revision 2 NLS2003033, Safeguards Plan, Revision 422003-03-14014 March 2003 Safeguards Plan, Revision 42 NLS2009057, Nedc 87-131B, Revision 8, Cooper Nuclear Station, 250 Vdc Division II Load and Voltage Study.2002-11-20020 November 2002 Nedc 87-131B, Revision 8, Cooper Nuclear Station, 250 Vdc Division II Load and Voltage Study. NRC Generic Letter 1979-451979-09-25025 September 1979 NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences 2023-04-20
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p.-~,y~O '71 I i Ril~-5A4 3q Jolrnson"PUiMP Company Engineering Evaluation Regarding Short Term Dty-run of-Rubber Column Bearings Cooper Nuclear Station, Nebraska Public Power District fByron Jackson 28KXL I-STG! Chattanooga Sei'ice Center Report Serial No.: 3P04-20)Rev. 02
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Johnston Pump Company Engineering Evaluation Regarding Short Term Dry-run of Rubber Column Bearings Cooper Nuclear Station, Nebraska Public Power District Byron Jackson 28KXL I-STG, Chattanooga Service.Center Report Serial No.: JP04-20 Rev. 02 I
Originating Department:
Engineering Dept., Brookshire.
Revision No.: 02 Prepared By: Michael Cuga], PE Initial:
Date: 07/] 6/04 Checked By: Lanka Pannila, P.E.
Initial:
{~ I i
Table of Contents
- 1. Introduction 1
- 2. Discussion
- 4. Summary/ Conclusions
JOHNSTON PUMPS 800 Koomey Road Tel: (800) 926-6688 Brookshire, IX 77423 Fax: (281) 934-6056 Engineering Evaluation on Short-term Dry-run Job Number Customer NPPD - Cooper Nuclear Station Pump Size and Model BJ 28KXL 1-STG Project Manager Jerry Harrelson
- 1. Introduction T"he.purpose of this report is to provide an engineering evaluation of the following question:
Given conditions that existed at Cooper Nuclear Station(l), will the Service Wat6r pumps(2) continue to function 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after Gland Water low is reduced to zero flow for 90 minutes and then restored to normal?
(1) During Janiary 21, 2004 - February 11,.2004:
River water level 875.5 MSL - 877.5 MSL.
Service water temperature 545°F.
Pump running at capacity (5500 gpm).
Average discharge pressure 50 psig average.
Gland water flow -678 gpm to the enclosing tube (16-24 psi).
Vibration (1ST) normal.. .......
-(2) Byron Jackson 28KXL 1-Stage VCT pumps with 180 rpm, 300 lip Motors..
The following material conditions existed as of February 2003: 1). New pump assembly, packing, coupling, shafts,.cutlass bearings, and impeller. 2). Rebuilt outer column, discharge nozzle, registers, and spider bushing supports.
- 2. Discussion
Background
The function of the Gland Water flow is to provide clean water lubrication lo the pump's stuffing box area, and column bearings during the pump operation.
In vertical pumps, the column bearings provide 'bumper" bearing support. Due to negligible pressure differences
-across the bearings, they do not behave as typical hydrostatic bearings. However, a thin"fluid film between the bearing and the shaft results in some bearing damping and fluid stiffness.....
For the'subject pump, at the given river level, if the gland water flow is stopped, the top 7 bearings (including the stuffing box bearing) would not receive the lubrication. The bottom 5 bearings (3 bottom column bearings and 2 bowl bearings) 'wouldbe submerged in the *umping fluid.
In order to provide the answer to the posed question, we underook the following steps:
Prepared By Checked By , Report No. Date Revision Rev. Date Rev. By Mike Cugal Lanka Pannila JP04-20 07/16)04* 02 08105104 MC J
JOHNSTON PUMPS 800 Koomey Road Tel: (800) 926-6688 Brookshire, TX 77423 Fax: (281) 934-6056 Engineering Evaluation on Short-term Dry-run Job Number Customer NPPD - Cooper Nuclear Station Pump Size and Model BJ 28KXL 1-STG I Project Manager Jerry Harrelson
] Technical assessment by the Johnston Pump engineering staff.
- 2. General review and study of the field repair history of similar cases.
- 3. Rotor dynamics analvsis.
2.1 Technical assessment After gland flow is stopped, the packing ]hebox area will not receive proper lubrication and cooling flow, and the top 6 column bearings will not receive lubrication. The packing box bearing will heat up due to contact from the shaft. The effect of this could depend on the amount and force of the contact with the rotating shaft. If the shaft rotates without much wobble, it is conceivable that damage to the bearing or shaft can be minimal, Ifthe shaft contacts the stuffing box bearing constantly, the packing gland will get over-heated and dry, and the bearing clearance will increase.
A typical vertical shaft is in tension and, in theory, it will rotale freely without any contact if the alignment and register fits are true and no manufacturing and machinin2 tolerances exist. In real operation, hov%,,.ver,.ThejriduaL unbalance of theorotor, Some hydraulic unbalance, allowable manufacturing tolerances, and the natural frequency of the rotor could cause the rotor to wobble and contact the column bearings.,If lubrication to the bearings is not present, we can foresee local heating of the rubber bearings and wveakening of the rubber material. The constant contact with the shaft could result in loss of the bearing material. The severity of the mhaterial loss would highly depend on the nature and amount of contact. However, wye do believe that in general the bearing clearances will increase significantly due to the contact of the shaft.
.... hbearing clearances increase, the pump can experience higher vibration of the pum shaft and possibly the ump stfuctures m general. The severity and effect o e vi ration are difficult to predict, but a catastrop ic pump failure within 9U minutes of operation without the gland water supply and subsequent 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of operation with the gland water supply is not likely to happen due to the vibration from increased bearing clearances.
There is a remote chance of a pump shaft seizure when it is operated without lubrication against rubber bearings.
However, the probability of a seizure is very low if the pump does not have to stop and restart.
2.2 Field repair history We were not able to locate any written repair rep6rt that dealt with the exact nature of this case. No record was'.
found w',here the exact duration of the dry-running was documented. Our assessment was based on verbal communications with various Johnston Pump service centers. In most cases, operating pumps withoutlubrication to the rubber fa-lure, bearings the shaft was seized, butinthe resulted severe damage duration to ihe of the operation bearings columnseemed and shalts.
to have In somecases been longer ofpump than a day or so. In ih-es'e cases, tme gland water supply was not restored.
Prepared By Checked By Report No. " Date Revision Rev. Date Rev. By Mike Cugal Lanka Pannila JP04-20 07/16/04 02 08/05/04 MC 2
JOHNSTON PUMPS 800 Koomey Road Tel: (800).926-6688 Brookshire, TX 77423 Fax: (281) 934-6056
_ _ _Engineering Evaluation on Short-term Dry-run i Job Number Customer NPPD - Cooper Nuclear Station' I Pump Size and Model BJ 28KXL 1-STG Project Manager Jerry Harrelson Our interviews with senior field service technicians resulted in similar conclusions. In their experience, when the gland water supply is stopped, the rubber bearings get over-heated, and in some cases they have seen smoke coming out of the column. In most cases, the pump will begin to vibrate, and eventually it will be pulled for a repair.. There were some cases where one or two bearings w,.ere completely damaged and pumps operated for over 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The general opinion of the service technicians is that the pump could have survive the 90 minutes of dry-operation though the bearings may have gotten severely damaged, and operation of the pump for the subs.equent 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with re-introduction of the gland water supply would have been possible.
2.3 Rotor dynamics analysis We believe that the loss of gland water supply will cause loss of bearing damping effect (by losing the fluid film between the bearing and shaft) and could open up the running clearances (which will change the bearing stiffness). In order to study the rotor dynamics behavior in more detail, we conducted a lateral rotor dynamics analysis (report JP04-18).
Due to time constraints and the unavailability of some pertinenilgeometrv information (i.e. mnotor rotor details),.
we had to use this study diligently. Our conclusions from the analysis are as follows:
0 It is quite typical for. a vertical, pump rotor system to have a number of critical speeds that are close to the excitation frequency. Such a case was proven to be true in this analysis. In this study, we focused on the modal shapes of the rotor in order to study the effect of the shaft and bearing contact.
0 The baseline analysis (pump in normnal operating condition with gland water supply) indicated that there is indeed a natural frequency mode within 4.5% of the running frequency. The mode shape, however, indicated that the shaft and the inner column deflect in the same phase, providing a non-contacting mode (refer to report JP04-] 8).
" The worst case analysis (pump without gland w,ater supply and assuming all 7 top'bearings are lost and do not provide any bearing support) indicated that a higher mode natural frequency is near the running speed (within 6 %), and that the deflection mode of the shaft and inner column are not in the same phase. This would indicate a contact between the shaft and bearing, and that severe damages to the bearings can be expected.
" Based on the mode shape analysis, we believe that the worst case scenario would not happen during the pump operation. The mode shape indicated ihat two bearings may have come in severe contact with the shaft, but not all dry-running bearings would have been damaged.
Our conclusion based on the rotor analysis is that when the pump is run dry some shaft contact with the bearings will occur. Based on the modal shape in the worse case scenario, we believe that contact will be made on some of the bearings, but loss of all column bearing support is not likely to happen.
Prepared By Checked By Report No. Date Revision Rev. Date Rev. By Mike Cugal Lanka Pannila JP04-20 07/16/04 .02 08/05/04 ,- MC 3
JOHNSTON PUMPS 800 Koorney Road Tel: (800) 926-6688 Brookshire, TX 77423 Fax: (281) 934-6056 Engineering Evaluation on Short-term Dry-run Job Number I Customer NPPD - Cooper Nuclear Station Pump Size and Model BJ 28KXL 1-SIG Project Manager Jerry Harrelson Based 0i the modal shape analysis, the inner column mode shape was detected near the running speed. If the inner column fails, the result could be a re-supply of the lubrication to the column bearings as the discharge pressure pushes the fluid into the column. This would become somewhat beneficial in this case (depending on the nature of the failure), as it would introduce the lubrication and damping back to the column bearings.
3.0 Summary and conclusions It is general knowledge and recommended practice never to operate a vertical pump withfrubber bearings without proper lubrication*. We wish to clearly state that the evaluations and statements of this report regarding this issue does not change such views. We also wish to state that the statements and summary of this report are intended only to share our views on this particular operation case, and we do not recommend or accept any future operation of the pump without the gland water supply for any length of time without a change to the existing pump bearing design.
Our database search and study of-past field service records (.written and verbal) did s-ow that some damage to the
. bearings and/or shaft can occur due to the lack of pump.gland water supply. HQ'wev-e,_-e.do.-noLhave-conclusive data which indicates a catastrophic pump failure would have resulted within 90 minutes of operation without the gland water supply and subsequent 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with re-supply of gland water. Our rotor dynamics analysis indicated that it is highly unlikely to damage all top rubber bearings subjected to the dry-running condition.
We believe that given the ample motor horsepower and the good existing maintenance practice in this case (ali mament, good fits and registers, etc.), the pump could have survived the 90 minutes of "dry" operation. When the gland water supply was re-introduced, the pump could have operated (possibly with higher vibration and some damaged bearings) for an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Prepared By Checked By Report No. Date Revision Rev. Datel Rev. By Mike.Cugal Lanka Pannila JP04-20 07/16/04 02 08/05104 MC 4