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| | issue date = 01/27/2003 | | | issue date = 01/27/2003 |
| | title = Part 21 - Inadequately Staked Capscrew Renders Residual Heat Removal Pump Inoperable | | | title = Part 21 - Inadequately Staked Capscrew Renders Residual Heat Removal Pump Inoperable |
| | author name = Beckner W D | | | author name = Beckner W |
| | author affiliation = NRC/NRR/DRIP/RORP | | | author affiliation = NRC/NRR/DRIP/RORP |
| | addressee name = | | | addressee name = |
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| | page count = 5 | | | page count = 5 |
| }} | | }} |
| {{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, DC 20555-0001January 27, 2003NRC INFORMATION NOTICE 2003-03:PART 21 - INADEQUATELY STAKEDCAPSCREW RENDERS RESIDUAL HEAT | | {{#Wiki_filter:UNITED STATES |
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| ===REMOVAL PUMP INOPERABLE===
| | NUCLEAR REGULATORY COMMISSION |
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| | OFFICE OF NUCLEAR REACTOR REGULATION |
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| | WASHINGTON, DC 20555-0001 January 27, 2003 NRC INFORMATION NOTICE 2003-03: PART 21 - INADEQUATELY STAKED |
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| | CAPSCREW RENDERS RESIDUAL HEAT |
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| | REMOVAL PUMP INOPERABLE |
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| ==Addressees== | | ==Addressees== |
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| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to informaddressees of recently observed inadequately staked capscrews on casing wear rings of | | The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to inform |
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| | addressees of recently observed inadequately staked capscrews on casing wear rings of |
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| residual heat removal pumps. It is expected that recipients will review the information for | | residual heat removal pumps. It is expected that recipients will review the information for |
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| applicability to their facilities and consider actions, as appropriate, to avoid similar problems. | | applicability to their facilities and consider actions, as appropriate, to avoid similar problems. |
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| ==Description of Circumstances== | | ==Description of Circumstances== |
| At Vogtle Electric Generating Plant (VEGP) Unit 2, on October 22, 2002, while the unit wasdefueled, residual heat removal (RHR) pump A was started for dynamic fill and vent of the RHR | | At Vogtle Electric Generating Plant (VEGP) Unit 2, on October 22, 2002, while the unit was |
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| | defueled, residual heat removal (RHR) pump A was started for dynamic fill and vent of the RHR |
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| system. Moments later, the pump tripped. Personnel found that the pump shaft could not be | | system. Moments later, the pump tripped. Personnel found that the pump shaft could not be |
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| hand-turned. An investigation determined that a casing wear ring capscrew had come loose | | hand-turned. An investigation determined that a casing wear ring capscrew had come loose |
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| and lodged between the impeller and the back casing wear ring. It was found that the pump | | and lodged between the impeller and the back casing wear ring. It was found that the pump |
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| was last operated on October 11, 2002, when the unit was in Mode 6 (refueling). It is believed | | was last operated on October 11, 2002, when the unit was in Mode 6 (refueling). It is believed |
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| that the capscrew came loose and lodged between the impeller and the back casing wear ring | | that the capscrew came loose and lodged between the impeller and the back casing wear ring |
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| as the pump was being placed into standby status on October 11, 2002. The root cause of this event was determined by the licensee to be the failure of themanufacturer to properly stake the back casing wear ring capscrews. Each capscrew is | | as the pump was being placed into standby status on October 11, 2002. |
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| torqued and staked as a redundant measure to hold the capscrews in place. Although the back | | The root cause of this event was determined by the licensee to be the failure of the |
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| | manufacturer to properly stake the back casing wear ring capscrews. Each capscrew is |
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| | torqued and staked as a redundant measure to hold the capscrews in place. Although the back |
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| casing wear rings had been staked, the staking was inadequate to prevent at least one of the | | casing wear rings had been staked, the staking was inadequate to prevent at least one of the |
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| capscrews from backing out of the back casing wear ring after it had lost its torque and become | | capscrews from backing out of the back casing wear ring after it had lost its torque and become |
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| loose. RHR pump B was inspected and found to have a similar condition. Spare back casing | | loose. RHR pump B was inspected and found to have a similar condition. Spare back casing |
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| wear rings in the warehouse were also inspected and found to have inadequately staked | | wear rings in the warehouse were also inspected and found to have inadequately staked |
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| capscrews. Capscrews on the back casing rings of both RHR pumps were properly staked | | capscrews. Capscrews on the back casing rings of both RHR pumps were properly staked |
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| prior to the pumps being returned to service. DiscussionThe improperly staked capscrews on both RHR pumps represented a condition that could haveprevented fulfilment of a safety function of a system needed to remove residual heat. There is | | prior to the pumps being returned to service. |
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| | Discussion |
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| | The improperly staked capscrews on both RHR pumps represented a condition that could have |
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| | prevented fulfilment of a safety function of a system needed to remove residual heat. There is |
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| also the potential for loose parts to result in unpredictable damage to safety related | | also the potential for loose parts to result in unpredictable damage to safety related |
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| components for accident mitigation. Discussions with pump vendor personnel determined that there are approximately 60 of thesepumps in service in the nuclear industry, most with several years of service, and that this was | | components for accident mitigation. |
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| the first failure of this type. Additionally, 15 of these pumps, including the 4 pumps in VEGP | | Discussions with pump vendor personnel determined that there are approximately 60 of these |
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| | pumps in service in the nuclear industry, most with several years of service, and that this was |
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| | the first failure of this type. Additionally, 15 of these pumps, including the 4 pumps in VEGP |
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| Units 1 & 2, had undergone a coupling modification in recent years that replaced the back | | Units 1 & 2, had undergone a coupling modification in recent years that replaced the back |
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| casing ring. However, it is not known if the back casing ring defect is limited to only those | | casing ring. However, it is not known if the back casing ring defect is limited to only those |
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| casing rings that were procured for the modifications or if the original pump back casing rings | | casing rings that were procured for the modifications or if the original pump back casing rings |
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| also have this defect. Nonetheless, this was the first failure of this type for any of the 60 | | also have this defect. Nonetheless, this was the first failure of this type for any of the 60 |
| pumps.Vendor: Ingersoll-RandModel No: 8X20WDFBack Casing Ring Part No: 6BCapscrew No: 118CThis information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact one of the technical contacts | | pumps. |
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| listed below or the appropriate project manager from the NRC's Office of Nuclear Reactor
| | Vendor: Ingersoll-Rand |
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| Regulation (NRR). /RA/William D. Beckner, Program Director | | Model No: 8X20WDF |
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| | Back Casing Ring Part No: 6B |
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| | Capscrew No: 118C |
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| | This information notice requires no specific action or written response. If you have any |
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| | questions about the information in this notice, please contact one of the technical contacts |
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| | listed below or the appropriate project manager from the NRCs Office of Nuclear Reactor |
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| | Regulation (NRR). |
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| | /RA/ |
| | William D. Beckner, Program Director |
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| | Operating Reactor Improvements Program |
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| ===Operating Reactor Improvements Program===
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| Division of Regulatory Improvement Programs | | Division of Regulatory Improvement Programs |
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| Office of Nuclear Reactor RegulationTechnical contacts: D. Billings, NRRG. Bedi, NRR 301-415-1175301-415-1393 E-mail: deb1@nrc.govE-mail: gsb2@nrc.govJ. Zeiler, Region 2706-554-9901 E-mail: jxz@nrc.govAttachment: List of Recently Issued NRC Information Notices DiscussionThe improperly staked capscrews on both RHR pumps represented a condition that could have | | Office of Nuclear Reactor Regulation |
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| prevented fulfilment of a safety function of a system needed to remove residual heat. There is
| | Technical contacts: D. Billings, NRR G. Bedi, NRR |
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| also the potential for loose parts to result in unpredictable damage to safety related
| | 301-415-1175 301-415-1393 E-mail: deb1@nrc.gov E-mail: gsb2@nrc.gov |
| | |
| | J. Zeiler, Region 2 |
| | 706-554-9901 E-mail: jxz@nrc.gov |
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| components for accident mitigation. Discussions with pump vendor personnel determined that there are approximately 60 of thesepumps in service in the nuclear industry, most with several years of service, and that this was
| | Attachment: List of Recently Issued NRC Information Notices |
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| the first failure of this type. Additionally, 15 of these pumps, including the 4 pumps in VEGP
| | *See previous concurrence |
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| Units 1 & 2, had undergone a coupling modification in recent years that replaced the back
| | DOCUMENT NAME: G:\RORP\OES\Staff Folders\Billings\VogCapscrewIN.wpd |
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| casing ring. However, it is not known if the back casing ring defect is limited to only those
| | OFFICE OES:RORP:DRIP Tech Editor Region II Region II |
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| casing rings that were procured for the modifications or if the original pump back casing rings
| | NAME DBillings PKleene* JZeiler* BRBonser* |
| | DATE / /2003 01/14/2003 01/21/2003 01/22/2003 OFFICE DE:EMEB DE:EMEB SC:OES:RORP:DRIP PD:RORP:DRIP |
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| also have this defect. Nonetheless, this was the first failure of this type for any of the 60
| | NAME BSGurjendra DTerao* TReis WDBeckner |
| pumps.Vendor: Ingersoll-RandModel No: 8X20WDFBack Casing Ring Part No: 6BCapscrew No: 118CThis information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact one of the technical contacts
| |
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| listed below or the appropriate project manager from the NRC's Office of Nuclear ReactorRegulation (NRR). /RA/William D. Beckner, Program Director
| | DATE / /2003 01/23/2003 01/24/2003 01/27/2003 |
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| ===Operating Reactor Improvements Program===
| | Attachment LIST OF RECENTLY ISSUED |
| Division of Regulatory Improvement Programs
| |
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| Office of Nuclear Reactor RegulationTechnical contacts: D. Billings, NRRG. Bedi, NRR 301-415-1175301-415-1393 E-mail: deb1@nrc.govE-mail: gsb2@nrc.govJ. Zeiler, Region 2706-554-9901 E-mail: jxz@nrc.govAttachment: List of Recently Issued NRC Information NoticesDISTRIBUTION:ADAMSIN File
| | NRC INFORMATION NOTICES |
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| ADAMS ACCESSION NUMBER:*See previous concurrenceDOCUMENT NAME: G:\RORP\OES\Staff Folders\Billings\VogCapscrewIN.wpdOFFICEOES:RORP:DRIPTech EditorRegion IIRegion IINAMEDBillingsPKleene*JZeiler*BRBonser*DATE / /200301/14/200301/21/200301/22/2003OFFICEDE:EMEBDE:EMEBSC:OES:RORP:DRIPPD:RORP:DRIPNAMEBSGurjendraDTerao*TReisWDBecknerDATE / /200301/23/200301/24/200301/27/2003OFFICIAL RECORD COPY
| | _____________________________________________________________________________________ |
| | Information Date of |
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| ______________________________________________________________________________________OL = Operating License
| | Notice No. Subject Issuance Issued to |
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| CP = Construction PermitAttachment LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICES_____________________________________________________________________________________InformationDate of
| | _____________________________________________________________________________________ |
| | 2003-02 Recent Experience with 01/16/2003 All holders of operating licenses |
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| Notice No. SubjectIssuanceIssued to_____________________________________________________________________________________2003-02Recent Experience withReactor Coolant System
| | Reactor Coolant System or construction permits for |
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| ===Leakage and Boric Acid===
| | Leakage and Boric Acid pressurized water reactors |
| Corrosion01/16/2003All holders of operating licensesor construction permits for
| |
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| pressurized water reactors
| | Corrosion (PWRs). |
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| (PWRs).2003-01Failure of a Boiling WaterReactor Target Rock Main
| | 2003-01 Failure of a Boiling Water 01/15/2003 All holders of operating licenses |
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| Steam Safety/Relief Valve01/15/2003All holders of operating licensesor construction permits for
| | Reactor Target Rock Main or construction permits for |
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| nuclear power reactors, except | | Steam Safety/Relief Valve nuclear power reactors, except |
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| those that have permanently | | those that have permanently |
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| permanently removed from the | | permanently removed from the |
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| reactor.2002-35Changes to 10 CFR Parts 71and 72 Quality Assurance | | reactor. |
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| | 2002-35 Changes to 10 CFR Parts 71 12/20/2002 All holders of 10 CFR Part 71 and 72 Quality Assurance quality assurance program |
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| | Programs approvals and all 10 CFR Part 72 licensees and certificate holders. |
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| | 2002-34 Failure of Safety-Related 11/25/2002 All holders of operating licenses |
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| Programs12/20/2002All holders of 10 CFR Part 71quality assurance program
| | Circuit Breaker External or construction permits for |
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| approvals and all 10 CFR Part 72 licensees and certificate holders.2002-34Failure of Safety-RelatedCircuit Breaker External
| | Auxiliary Switches at Columbia nuclear power reactors. |
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| ===Auxiliary Switches at Columbia===
| | Generating Station |
| Generating Station11/25/2002All holders of operating licensesor construction permits for | |
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| nuclear power reactors.2002-33Notification of PermanentInjunction Against Neutron
| | 2002-33 Notification of Permanent 11/22/2002 All teletherapy and radiation |
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| ===Products Incorporated of===
| | Injunction Against Neutron processing licensees. |
| Dickerson, Maryland11/22/2002All teletherapy and radiationprocessing licensees. 2002-29(Errata)Recent Design Problems in Safety Functions of Pneumatic
| |
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| Systems11/06/2002All holders of operating licensesor construction permits for
| | Products Incorporated of |
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| nuclear power reactors.Note:NRC generic communications may be received in electronic format shortly after they areissued by subscribing to the NRC listserver as follows:To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the followingcommand in the message portion:subscribe gc-nrr firstname lastname
| | Dickerson, Maryland |
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| }} | | 2002-29 Recent Design Problems in 11/06/2002 All holders of operating licenses |
| | |
| | (Errata) Safety Functions of Pneumatic or construction permits for |
| | |
| | Systems nuclear power reactors. |
| | |
| | Note: NRC generic communications may be received in electronic format shortly after they are |
| | |
| | issued by subscribing to the NRC listserver as follows: |
| | To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the following |
| | |
| | command in the message portion: |
| | subscribe gc-nrr firstname lastname |
| | |
| | ______________________________________________________________________________________ |
| | OL = Operating License |
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| | CP = Construction Permit}} |
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| {{Information notice-Nav}} | | {{Information notice-Nav}} |
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Category:NRC Information Notice
MONTHYEARInformation Notice 2003-03, Part 21 - Inadequately Staked Capscrew Renders Residual Heat Removal Pump Inoperable2003-01-27027 January 2003 Part 21 - Inadequately Staked Capscrew Renders Residual Heat Removal Pump Inoperable Information Notice 1999-28, Recall of Star Brand Fire Protection Sprinkler Heads1999-09-30030 September 1999 Recall of Star Brand Fire Protection Sprinkler Heads Information Notice 1999-27, Malfunction of Source Retraction Mechanism in Cobalt-60 Teletherapy Treatment Units1999-09-0202 September 1999 Malfunction of Source Retraction Mechanism in Cobalt-60 Teletherapy Treatment Units Information Notice 1999-26, Safety and Economic Consequences of Misleading Marketing Information1999-08-24024 August 1999 Safety and Economic Consequences of Misleading Marketing Information Information Notice 1999-25, Year 2000 Contingency Planning Activities1999-08-10010 August 1999 Year 2000 Contingency Planning Activities Information Notice 1999-24, Broad-Scope Licensees' Responsibilities for Reviewing and Approving Unregistered Sealed Sources and Devices1999-07-12012 July 1999 Broad-Scope Licensees' Responsibilities for Reviewing and Approving Unregistered Sealed Sources and Devices Information Notice 1999-23, Safety Concerns Related to Repeated Control Unit Failures of the Nucletron Classic Model High-Dose-Rate Remote Afterloading Brachytherapy Devices1999-07-0606 July 1999 Safety Concerns Related to Repeated Control Unit Failures of the Nucletron Classic Model High-Dose-Rate Remote Afterloading Brachytherapy Devices Information Notice 1999-22, 10CFR 34.43(a)(1); Effective Date for Radiographer Certification and Plans for Enforcement Discretion1999-06-25025 June 1999 10CFR 34.43(a)(1); Effective Date for Radiographer Certification and Plans for Enforcement Discretion Information Notice 1999-21, Recent Plant Events Caused by Human Performance Errors1999-06-25025 June 1999 Recent Plant Events Caused by Human Performance Errors Information Notice 1999-20, Contingency Planning for the Year 2000 Computer Problem1999-06-25025 June 1999 Contingency Planning for the Year 2000 Computer Problem Information Notice 1999-19, Rupture of the Shell Side of a Feedwater Heater at the Point Beach Nuclear Plant1999-06-23023 June 1999 Rupture of the Shell Side of a Feedwater Heater at the Point Beach Nuclear Plant Information Notice 1999-18, Update on Nrc'S Year 2000 Activities for Material Licensees and Fuel Cycle Licensees and Certificate Holders1999-06-14014 June 1999 Update on Nrc'S Year 2000 Activities for Material Licensees and Fuel Cycle Licensees and Certificate Holders Information Notice 1999-17, Problems Associated with Post-Fire Safe-Shutdown Circuit Analyses1999-06-0303 June 1999 Problems Associated with Post-Fire Safe-Shutdown Circuit Analyses Information Notice 1999-16, Federal Bureau of Investigation'S Nuclear Site Security Program1999-05-28028 May 1999 Federal Bureau of Investigation'S Nuclear Site Security Program Information Notice 1999-15, Misapplication for 10CFR Part 71 Transportation Shipping Cask Licensing Basis to 10CFR Part 50 Design Basis1999-05-27027 May 1999 Misapplication for 10CFR Part 71 Transportation Shipping Cask Licensing Basis to 10CFR Part 50 Design Basis Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick1999-05-0505 May 1999 Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick Information Notice 1999-13, Insights from NRC Inspections of Low-and Medium-Voltage Circuit Breaker Maintenance Programs1999-04-29029 April 1999 Insights from NRC Inspections of Low-and Medium-Voltage Circuit Breaker Maintenance Programs Information Notice 1999-12, Year 2000 Computer Systems Readiness Audits1999-04-28028 April 1999 Year 2000 Computer Systems Readiness Audits Information Notice 1999-11, Incidents Involving the Use of Radioactive Iodine-1311999-04-16016 April 1999 Incidents Involving the Use of Radioactive Iodine-131 Information Notice 1999-08, Urine Specimen Adulteration1999-03-26026 March 1999 Urine Specimen Adulteration Information Notice 1999-09, Problems Encountered When Manually Editing Treatment Data on the Nucletron Microselectron-HDR (New) Model 105-9991999-03-24024 March 1999 Problems Encountered When Manually Editing Treatment Data on the Nucletron Microselectron-HDR (New) Model 105-999 Information Notice 1999-07, Failed Fire Protection Deluge Valves & Potential Testing Deficiencies in Preaction Sprinkler Systems1999-03-22022 March 1999 Failed Fire Protection Deluge Valves & Potential Testing Deficiencies in Preaction Sprinkler Systems Information Notice 1999-06, 1998 Enforcement Sanctions as a Result of Deliberate Violations of NRC Employee Protection Requirements1999-03-19019 March 1999 1998 Enforcement Sanctions as a Result of Deliberate Violations of NRC Employee Protection Requirements Information Notice 1999-06, 1998 Enforcement Sanctions As a Result of Deliberate Violations of NRC Employee Protection Requirements1999-03-19019 March 1999 1998 Enforcement Sanctions As a Result of Deliberate Violations of NRC Employee Protection Requirements Information Notice 1999-05, Inadvertent Discharge of Carbon Dioxide Fire Protection System and Gas Migration1999-03-0808 March 1999 Inadvertent Discharge of Carbon Dioxide Fire Protection System and Gas Migration Information Notice 1999-04, Unplanned Radiation Exposures to Radiographers, Resulting from Failures to Follow Proper Radiation Safety Procedures1999-03-0101 March 1999 Unplanned Radiation Exposures to Radiographers, Resulting from Failures to Follow Proper Radiation Safety Procedures Information Notice 1999-03, Exothermic Reactors Involving Dried Uranium Oxide Powder (Yellowcake)1999-01-29029 January 1999 Exothermic Reactors Involving Dried Uranium Oxide Powder (Yellowcake) Information Notice 1999-02, Guidance to Users on the Implementation of a New Single-Source Dose-Calculation Formalism and Revised Air-Kerma Strength Standard for Iodine-125 Sealed Sources1999-01-21021 January 1999 Guidance to Users on the Implementation of a New Single-Source Dose-Calculation Formalism and Revised Air-Kerma Strength Standard for Iodine-125 Sealed Sources Information Notice 1999-01, Deterioration of High-Efficiency Particulate Air Filters in a Pressurized Water Reactor Containment Fan Cooler Unit1999-01-20020 January 1999 Deterioration of High-Efficiency Particulate Air Filters in a Pressurized Water Reactor Containment Fan Cooler Unit Information Notice 1998-45, Cavitation Erosion of Letdown Line Orifices Resulting in Fatigue Cracking of Pipe Welds1998-12-15015 December 1998 Cavitation Erosion of Letdown Line Orifices Resulting in Fatigue Cracking of Pipe Welds Information Notice 1998-44, Ten-Year Inservice Inspection (ISI) Program Update for Licensees That Intend to Implement Risk-Informed ISI of Piping1998-12-10010 December 1998 Ten-Year Inservice Inspection (ISI) Program Update for Licensees That Intend to Implement Risk-Informed ISI of Piping Information Notice 1998-43, Leaks in Emergency Diesel Generator Lubricating Oil & Jacket Cooling Water Piping1998-12-0404 December 1998 Leaks in Emergency Diesel Generator Lubricating Oil & Jacket Cooling Water Piping Information Notice 1998-42, Implementation of 10 CFR 55.55a(g) Inservice Inspection Requirements1998-12-0101 December 1998 Implementation of 10 CFR 55.55a(g) Inservice Inspection Requirements Information Notice 1998-41, Spurious Shutdown of Emergency Diesel Generators from Design Oversight1998-11-20020 November 1998 Spurious Shutdown of Emergency Diesel Generators from Design Oversight Information Notice 1998-41, Spurious Shutdown of Emergency Diesel Generators From Design Oversight1998-11-20020 November 1998 Spurious Shutdown of Emergency Diesel Generators From Design Oversight Information Notice 1998-39, Summary of Fitness-for-Duty Program Performance Reports for Calendar Years 1996 and 19971998-10-30030 October 1998 Summary of Fitness-for-Duty Program Performance Reports for Calendar Years 1996 and 1997 Information Notice 1998-40, Design Deficiencies Can Lead to Reduced ECCS Pump Net Positive Suction Head During Design-Basis Accidents1998-10-26026 October 1998 Design Deficiencies Can Lead to Reduced ECCS Pump Net Positive Suction Head During Design-Basis Accidents Information Notice 1990-66, Incomplete Draining and Drying of Shipping Casks1998-10-25025 October 1998 Incomplete Draining and Drying of Shipping Casks Information Notice 1998-38, Metal-Clad Circuit Breaker Maintenance Issues Identified by NRC Inspections1998-10-15015 October 1998 Metal-Clad Circuit Breaker Maintenance Issues Identified by NRC Inspections Information Notice 1998-37, Eligibility of Operator License Applicants1998-10-0101 October 1998 Eligibility of Operator License Applicants Information Notice 1998-36, Inadequate or Poorly Controlled, Non-Safety-Related Maintenance Activities Unnecessarily Challenged Safety Systems1998-09-18018 September 1998 Inadequate or Poorly Controlled, Non-Safety-Related Maintenance Activities Unnecessarily Challenged Safety Systems Information Notice 1998-33, NRC Regulations Prohibit Agreements That Restrict or Discourage an Employee from Participating in Protected Activities1998-08-28028 August 1998 NRC Regulations Prohibit Agreements That Restrict or Discourage an Employee from Participating in Protected Activities Information Notice 1998-34, Configuration Control Errors1998-08-28028 August 1998 Configuration Control Errors Information Notice 1998-31, Fire Protection System Design Deficiencies and Common-Mode Flooding of Emergency Core Cooling System Rooms at Washington Nuclear Project Unit 21998-08-18018 August 1998 Fire Protection System Design Deficiencies and Common-Mode Flooding of Emergency Core Cooling System Rooms at Washington Nuclear Project Unit 2 Information Notice 1998-30, Effect of Year 2000 Computer Problem on NRC Licensees and Certificate Holders1998-08-12012 August 1998 Effect of Year 2000 Computer Problem on NRC Licensees and Certificate Holders Information Notice 1998-29, Predicted Increase in Fuel Rod Cladding Oxidation1998-08-0303 August 1998 Predicted Increase in Fuel Rod Cladding Oxidation Information Notice 1998-28, Development of Systematic Sample Plan for Operator Licensing Examinations1998-07-31031 July 1998 Development of Systematic Sample Plan for Operator Licensing Examinations Information Notice 1998-26, Settlement Monitoring and Inspection of Plant Structures Affected by Degradation of Porous Concrete Subfoundations1998-07-24024 July 1998 Settlement Monitoring and Inspection of Plant Structures Affected by Degradation of Porous Concrete Subfoundations Information Notice 1998-27, Steam Generator Tube End Cracking1998-07-24024 July 1998 Steam Generator Tube End Cracking Information Notice 1998-25, Loss of Inventory from Safety-Related Closed-Loop Cooling Water Systems1998-07-0808 July 1998 Loss of Inventory from Safety-Related Closed-Loop Cooling Water Systems 2003-01-27
[Table view] |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, DC 20555-0001 January 27, 2003 NRC INFORMATION NOTICE 2003-03: PART 21 - INADEQUATELY STAKED
CAPSCREW RENDERS RESIDUAL HEAT
REMOVAL PUMP INOPERABLE
Addressees
All holders of operating licenses or construction permits for nuclear power reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to inform
addressees of recently observed inadequately staked capscrews on casing wear rings of
residual heat removal pumps. It is expected that recipients will review the information for
applicability to their facilities and consider actions, as appropriate, to avoid similar problems.
However, suggestions in this information notice are not NRC requirements; therefore, no
specific action or written response is required.
Description of Circumstances
At Vogtle Electric Generating Plant (VEGP) Unit 2, on October 22, 2002, while the unit was
defueled, residual heat removal (RHR) pump A was started for dynamic fill and vent of the RHR
system. Moments later, the pump tripped. Personnel found that the pump shaft could not be
hand-turned. An investigation determined that a casing wear ring capscrew had come loose
and lodged between the impeller and the back casing wear ring. It was found that the pump
was last operated on October 11, 2002, when the unit was in Mode 6 (refueling). It is believed
that the capscrew came loose and lodged between the impeller and the back casing wear ring
as the pump was being placed into standby status on October 11, 2002.
The root cause of this event was determined by the licensee to be the failure of the
manufacturer to properly stake the back casing wear ring capscrews. Each capscrew is
torqued and staked as a redundant measure to hold the capscrews in place. Although the back
casing wear rings had been staked, the staking was inadequate to prevent at least one of the
capscrews from backing out of the back casing wear ring after it had lost its torque and become
loose. RHR pump B was inspected and found to have a similar condition. Spare back casing
wear rings in the warehouse were also inspected and found to have inadequately staked
capscrews. Capscrews on the back casing rings of both RHR pumps were properly staked
prior to the pumps being returned to service.
Discussion
The improperly staked capscrews on both RHR pumps represented a condition that could have
prevented fulfilment of a safety function of a system needed to remove residual heat. There is
also the potential for loose parts to result in unpredictable damage to safety related
components for accident mitigation.
Discussions with pump vendor personnel determined that there are approximately 60 of these
pumps in service in the nuclear industry, most with several years of service, and that this was
the first failure of this type. Additionally, 15 of these pumps, including the 4 pumps in VEGP
Units 1 & 2, had undergone a coupling modification in recent years that replaced the back
casing ring. However, it is not known if the back casing ring defect is limited to only those
casing rings that were procured for the modifications or if the original pump back casing rings
also have this defect. Nonetheless, this was the first failure of this type for any of the 60
pumps.
Vendor: Ingersoll-Rand
Model No: 8X20WDF
Back Casing Ring Part No: 6B
Capscrew No: 118C
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact one of the technical contacts
listed below or the appropriate project manager from the NRCs Office of Nuclear Reactor
Regulation (NRR).
/RA/
William D. Beckner, Program Director
Operating Reactor Improvements Program
Division of Regulatory Improvement Programs
Office of Nuclear Reactor Regulation
Technical contacts: D. Billings, NRR G. Bedi, NRR
301-415-1175 301-415-1393 E-mail: deb1@nrc.gov E-mail: gsb2@nrc.gov
J. Zeiler, Region 2
706-554-9901 E-mail: jxz@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\RORP\OES\Staff Folders\Billings\VogCapscrewIN.wpd
OFFICE OES:RORP:DRIP Tech Editor Region II Region II
NAME DBillings PKleene* JZeiler* BRBonser*
DATE / /2003 01/14/2003 01/21/2003 01/22/2003 OFFICE DE:EMEB DE:EMEB SC:OES:RORP:DRIP PD:RORP:DRIP
NAME BSGurjendra DTerao* TReis WDBeckner
DATE / /2003 01/23/2003 01/24/2003 01/27/2003
Attachment LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
_____________________________________________________________________________________
Information Date of
Notice No. Subject Issuance Issued to
_____________________________________________________________________________________
2003-02 Recent Experience with 01/16/2003 All holders of operating licenses
Reactor Coolant System or construction permits for
Leakage and Boric Acid pressurized water reactors
Corrosion (PWRs).
2003-01 Failure of a Boiling Water 01/15/2003 All holders of operating licenses
Reactor Target Rock Main or construction permits for
Steam Safety/Relief Valve nuclear power reactors, except
those that have permanently
ceased operations and have
certified that fuel has been
permanently removed from the
reactor.
2002-35 Changes to 10 CFR Parts 71 12/20/2002 All holders of 10 CFR Part 71 and 72 Quality Assurance quality assurance program
Programs approvals and all 10 CFR Part 72 licensees and certificate holders.
2002-34 Failure of Safety-Related 11/25/2002 All holders of operating licenses
Circuit Breaker External or construction permits for
Auxiliary Switches at Columbia nuclear power reactors.
Generating Station
2002-33 Notification of Permanent 11/22/2002 All teletherapy and radiation
Injunction Against Neutron processing licensees.
Products Incorporated of
Dickerson, Maryland
2002-29 Recent Design Problems in 11/06/2002 All holders of operating licenses
(Errata) Safety Functions of Pneumatic or construction permits for
Systems nuclear power reactors.
Note: NRC generic communications may be received in electronic format shortly after they are
issued by subscribing to the NRC listserver as follows:
To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the following
command in the message portion:
subscribe gc-nrr firstname lastname
______________________________________________________________________________________
OL = Operating License
CP = Construction Permit
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list | - Information Notice 2003-01, Failure of a Boiling Water Reactor Target Rock Main Steam Safety/Relief Valve (15 January 2003)
- Information Notice 2003-02, Recent Experience with Reactor Coolant System Leakage & Boric Acid Corrosion (16 January 2003, Topic: Boric Acid, Weld Overlay)
- Information Notice 2003-03, Part 21 - Inadequately Staked Capscrew Renders Residual Heat Removal Pump Inoperable (27 January 2003, Topic: Boric Acid)
- Information Notice 2003-04, Summary of Fitness-For-Duty Program Performance Reports for Calendar Year 2000 (6 February 2003, Topic: Boric Acid, Fitness for Duty)
- Information Notice 2003-06, Failure of Safety-Related Linestarter Relays at San Onofre Nuclear Generating Station (19 June 2003)
- Information Notice 2003-08, Potential Flooding Through Unsealed Concrete Floor Cracks (25 June 2003)
- Information Notice 2003-09, Source Positioning Errors and System Malfunctions Administration of Intravascular Brachytherapy (16 July 2003, Topic: Brachytherapy)
- Information Notice 2003-11, Leakage Found on Bottom-Mounted Instrumentation Nozzles (8 January 2004, Topic: Unanalyzed Condition, Nondestructive Examination)
- Information Notice 2003-12, Problems Involved In Monitoring Dose to Hands Resulting from Handling of Radiopharmaceuticals (22 August 2003)
- Information Notice 2003-12, Problems Involved in Monitoring Dose to Hands Resulting from Handling of Radiopharmaceuticals (22 August 2003)
- Information Notice 2003-13, Steam Generator Tube Degradation at Diablo Canyon (28 August 2003)
- Information Notice 2003-14, Potential Vulnerability of Plant Computer Network to Worm Infection (29 August 2003)
- Information Notice 2003-15, Importance of Followup Activities in Resolving Maintenance Issues (5 September 2003)
- Information Notice 2003-17, Reduced Service Life of Automatic Switch Company (ASCO) Solenoid Valves With Buna-N Material (29 September 2003)
- Information Notice 2003-17, Reduced Service Life of Automatic Switch Company (Asco) Solenoid Valves with Buna-N Material (29 September 2003)
- Information Notice 2003-18, General Electric Type Sbm Control Switches with Defective Cam Followers (26 September 2003)
- Information Notice 2003-18, General Electric Type SBM Control Switches with Defective Cam Followers (26 September 2003)
- Information Notice 2003-19, Unanalyzed Condition of Reactor Coolant Pump Seal Leakoff Line During Postulated Fire Scenarios or Station Blackout (6 October 2003, Topic: Safe Shutdown, Unanalyzed Condition, Boric Acid)
- Information Notice 2003-20, Derating Whiting Cranes Purchased Before 1980 (22 October 2003, Topic: Unanalyzed Condition)
- Information Notice 2003-21, High-Dose-Rate-Remote-Afterloader Equipment Failure (24 November 2003, Topic: Unanalyzed Condition, Brachytherapy)
- Information Notice 2003-22, Heightened Awareness for Patients Containing Detectable Amounts of Radiation from Medical Administrations (9 December 2003, Topic: Unanalyzed Condition, Brachytherapy)
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