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| | issue date = 09/30/1992 | | | issue date = 09/30/1992 |
| | title = Partial Plugging of Suppression Pool Strainers at a Foreign BWR | | | title = Partial Plugging of Suppression Pool Strainers at a Foreign BWR |
| | author name = Rossi C E | | | author name = Rossi C |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = | | | addressee name = |
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| | document type = NRC Information Notice | | | document type = NRC Information Notice |
| | page count = 7 | | | page count = 7 |
| | revision = 0
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| }} | | }} |
| {{#Wiki_filter:_~K)UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555September 30, 1992NRC INFORMATION NOTICE 92-71: PARTIAL PLUGGING OF SUPPRESSION POOLSTRAINERS AT A FOREIGN BWR | | {{#Wiki_filter:_~K) |
| | UNITED STATES |
| | |
| | NUCLEAR REGULATORY COMMISSION |
| | |
| | OFFICE OF NUCLEAR REACTOR REGULATION |
| | |
| | WASHINGTON, D.C. 20555 September 30, 1992 NRC INFORMATION NOTICE 92-71: PARTIAL PLUGGING OF SUPPRESSION POOL |
| | |
| | STRAINERS AT A FOREIGN BWR |
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| |
|
| ==Addressees== | | ==Addressees== |
| All holders of operating licenses or construction permits for nuclear powerreactors. | | All holders of operating licenses or construction permits for nuclear power |
| | |
| | reactors. |
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| |
|
| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to the potential-for loss of emergency core coolingsystems (ECCS) that was identified as a result of an event at a Swedishboiling water reactor (BWR). It is expected that recipients will review thelinformation for applicability to their facilities and consider actions, asappropriate, to avoid similar problems. However, suggestions contained inthis information notice are not NRC requirements; therefore, no specificaction or written response is required. | | The U.S. Nuclear Regulatory Commission (NRC) is issuing this information |
| | |
| | notice to alert addressees to the potential-for loss of emergency core cooling |
| | |
| | systems (ECCS) that was identified as a result of an event at a Swedish |
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| | boiling water reactor (BWR). It is expected that recipients will review thel |
| | |
| | information for applicability to their facilities and consider actions, as |
| | |
| | appropriate, to avoid similar problems. However, suggestions contained in |
| | |
| | this information notice are not NRC requirements; therefore, no specific |
| | |
| | action or written response is required. |
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| |
|
| ==Description of Circumstances== | | ==Description of Circumstances== |
| :On July 28, 1992, Sydkraft AB, the utility licensed by the Swedish regulatoryagency for the BarsebAck nuclear power plant, was restarting Unit 2 after theannual outage. While the reactor was at 1 or 2 percent power and at 435 psi,a leaking pilot valve caused a safety valve for the reactor vessel to open.This valve discharges directly to the drywell. Reactor scram, high pressuresafety injection, core spray, and containment spray systems initiatedautomatically in response to the event. Steam from the open safety valve,impinging on thermally-insulated equipment, dislodged 440 pounds of metal-jacketed, mineral wool. An estimated 220 pounds of insulating material waswashed into the suppression pool. Two of five strainers on the suction sideof the ECCS pumps were in service and became partially plugged with mineralwool. Plugging caused pressure to decrease significantly across the strainersand caused indications of cavitation in one pump in about an hour after theevent began. The operators successfully back flushed the strainers and shutdown the reactor without additional problems.DiscussionIn the safety analysis for Unit 2 of the Barsebdck plant, the licenseeconcluded that the strainers would not require back flushing during the first10 hours after a loss-of-coolant accident. Because of the event of July 28,the Swedish regulatory agency required Barseback Unit 2 and four other unitsof similar design to remain shut down until this problem is resolved.9209290014 e IIIIN 92-71September 30, 1992 This event at BarsebAck is directly applicable to an earlier study conductedby the NRC. That study evaluated the potential for displaced thermalinsulation to form debris and to be drawn to the sump screen. The results ofthe study are documented in "Containment Sump Performance," NUREG-0897,Revision 1, dated March 1984. The NRC concluded that the risk associated withthe sump clogging concern did not warrant backfitting of domestic plants.However, based on the Barsebdck event, this conclusion is being reevaluated.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.(arles si, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contact: Robert L. Dennig, NRR(301) 504-1156 | | : |
| | On July 28, 1992, Sydkraft AB, the utility licensed by the Swedish regulatory |
| | |
| | agency for the BarsebAck nuclear power plant, was restarting Unit 2 after the |
| | |
| | annual outage. While the reactor was at 1 or 2 percent power and at 435 psi, a leaking pilot valve caused a safety valve for the reactor vessel to open. |
| | |
| | This valve discharges directly to the drywell. Reactor scram, high pressure |
| | |
| | safety injection, core spray, and containment spray systems initiated |
| | |
| | automatically in response to the event. Steam from the open safety valve, impinging on thermally-insulated equipment, dislodged 440 pounds of metal- jacketed, mineral wool. An estimated 220 pounds of insulating material was |
| | |
| | washed into the suppression pool. Two of five strainers on the suction side |
| | |
| | of the ECCS pumps were in service and became partially plugged with mineral |
| | |
| | wool. Plugging caused pressure to decrease significantly across the strainers |
| | |
| | and caused indications of cavitation in one pump in about an hour after the |
| | |
| | event began. The operators successfully back flushed the strainers and shut |
| | |
| | down the reactor without additional problems. |
| | |
| | Discussion |
| | |
| | In the safety analysis for Unit 2 of the Barsebdck plant, the licensee |
| | |
| | concluded that the strainers would not require back flushing during the first |
| | |
| | 10 hours after a loss-of-coolant accident. Because of the event of July 28, the Swedish regulatory agency required Barseback Unit 2 and four other units |
| | |
| | of similar design to remain shut down until this problem is resolved. |
| | |
| | 9209290014 e |
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| | III |
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| | IN 92-71 September 30, 1992 This event at BarsebAck is directly applicable |
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| | by the NRC. That study evaluated the potential to an earlier study conducted |
| | |
| | insulation to form debris and to be drawn to for displaced thermal |
| | |
| | the study are documented in "Containment Sump the sump screen. The results of |
| | |
| | Revision 1, dated March 1984. The NRC concluded Performance," NUREG-0897, that the risk associated with |
| | |
| | the sump clogging concern did not warrant backfitting |
| | |
| | However, based on the Barsebdck event, this of domestic plants. |
|
| |
|
| ===Attachment:===
| | conclusion is being reevaluated. |
| List of Recently Issued NRC Information Notices AttachmentIN 92-71September 30, 1992 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to92-7092-6991-29,Supp.92-6892-671Westinghouse Motor-OperatedValve Performance DataSupplied to Nuclear PowerPlant LicenseesWater Leakage from YardArea Through ConduitsInto BuildingsDeficiencies IdentifiedDuring Electrical Dis-tribution System Func-tional InspectionsPotentially SubstandardSlip-On, Welding Neck,and Blind FlangesDeficiency in DesignModifications to Ad-dress Failures ofHiller Actuators UponA Gradual Loss ofAir PressureAccess Denied to NRCInspectors at Five StarProducts, Inc. andConstruction ProductsResearch, Fairfield,ConnecticutSafety System ProblemsCaused by ModificationsThat Were Not AdequatelyReviewed and Tested09/25/9209/22/9209/14/9209/10/9209/10/9209/01/9209/03/9208/28/92All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactorsand all recipients ofNUREG-0040, "Licensee, Con-tractor and Vendor Inspec-tion Status Report" (White.Book).All holders of OLs or CPsfor nuclear power reactors.All holders of -OLs or CPsfor nuclear power reactors.92-6692-6592-64Nozzleon LowReliefRing SettingsPressure Water-ValvesOL = Operating LicenseCP = Construction Permit K><YIN 92-71September 30, 992This event at Barseback is directly applicable to an earlier study conductedby the NRC. That study evaluated the potential for displaced thermalinsulation to form debris and to be drawn to the sump screen. The results ofthe study are documented in "Containment Sump Performance," NUREG-0897,Revision 1, dated March 1984. The NRC concluded that the risk associated withthe sump clogging concern did not warrant backfitting of domestic plants.However, based on the BarsebAck event, this conclusion is being reevaluated.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Original Signed byCharles E. RossiCharles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical conitact: Robert L. Dennig, NRR(301) 504-1156List of Recently Issued NRC Information Notices
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|
| |
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| ===Attachment:===
| | This information notice requires no specific |
| Document Name: 92-71.IN*SEE PREVIOUS CONCURRENCES*OEAB:DOEA:NRR*SC/OEAB:DOEA:NRRRWWoodruff RLDennig09/24/92 09/24/92V CEp/azeSC~hLAt_- Jest)o1i A e- ,L .IDO *C/OGCB:DOEA:NRR*RPB:ADMC GHMarcus TechEd09/; 92 09/28/92 09/24/24*C/OEAB:DOEA:NRR*C/SPLB:DST:NRR ICEP/OIPwAChaffee CEMcCracken AKenqeke09/k8/92 09/1r/92 09/dg/92ago,. 4 e, am ASCo-- -I rw W. 4.4a NRCIN 92-XXSeptember xx, 1991 documented in "Containment Sump Performance," NUREG-0897, Revision 1, dated March1984. The NRC concluded that the risk associated with the sump clogging concerndid not warrant backfitting of domestic plants. However, based on the Barsebackevent and NUREG-0897, Revision 1, this conclusion is being reevaluated.This information notice requires no specific action or written response. If youhave any question about the information in this notice, please contact thetechnical contact listed below or the appropriate Office of Nuclear ReactorRegulation project manager.-Charles E. Rossi, DirectorDivision of OperationalEvents AssessmentOffice of Nuclear Reactor RegulationTechnmical Contact:Robert L. Dennig, NRR(301) 504-1156
| |
|
| |
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| ===Attachment:===
| | action or written response. If |
| 1. List of Recently Issued Information Notices* See previous page for concurrence.CONCURRENCE:OEAB*RWWoodruff09/24/92D:DOEACERossi09/ /92LevA^-t l40-m'-is -DcNpu P I 0 u; "rcz- NX,-,I- PO T-P'TECH EDITORS*JDMain09/24/92SC:OEAB*RLDennig09/24/92:SPLBCEMcCrcken092/9209 3-1n I -KcBC:OEABAEChaffee09/4&/92BC:OGCBGHMarcus09/ /92Or? oSSC.l1er- Duesc,?/Xl/q;;410a.inCovCO LV V% ecceLpCAPt"XU I4posh4aDSCet.C do Lue g;Al CLL4e.?.-
| |
| V- IN 92-71September 29, 992This event at Barseback is directly applicable to an earlier study conductedby the NRC. That study evaluated the potential for displaced thermalinsulation to form debris and to be drawn to the sump screen. The results ofthe study are documented in "Containment Sump Performance," NUREG-0897,Revision 1, dated March 1984. The NRC concluded that the risk associated withthe sump clogging concern did not warrant backfitting of domestic plants.However, based on the Barsebdck event and NUREG-0897, Revision 1, thisconclusion is being reevaluated.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contact: Robert L. Dennig, NRR(301) 504-1156List of Recently Issued NRC Information Notices
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|
| |
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| ===Attachment:=== | | you have any questions about the information |
| Document Name: 92-71.IN*SEE PREVIOUS CONCURRENCES*OEAB:DOEA:NRR*SC/OEAB:DOEA:NRRRWWoodruff RLDennig09/24/92 09/24/92DOEA:NRR C/OGCB:DOEA:NRR*RPB:ADMCERossi GHMarcus)GLK- TechEd09/ /92 09/,S/92 &o 09/24/24*C/OEAB:DOEA:NRR*C/SPLB:DST:NRR CEP/OIPAChaffee CEMcCracken AKenneke09/ /92 09/ /92 09/ /92 K>-NRCIN 92-XXSeptember xx, 1991 technical contact listed below or the appropriate Office of Nuclear ReactorRegulation project manager.Charles E. Rossi, DirectorDivision of OperationalEvents AssessmentOffice of Nuclear Reactor Regulation | | |
| | in this notice, please contact |
| | |
| | the technical contact listed below or the appropriate |
| | |
| | Reactor Regulation (NRR) project manager. Office of Nuclear |
| | |
| | (arles si, Director |
| | |
| | Division of Operational Events Assessment |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical contact: Robert L. Dennig, NRR |
| | |
| | (301) 504-1156 Attachment: List of Recently Issued NRC Information Notices |
| | |
| | Attachment |
| | |
| | IN 92-71 September 30, 1992 LIST OF RECENTLY ISSUED |
| | |
| | NRC INFORMATION NOTICES |
| | |
| | Information Date of |
| | |
| | Notice No. Subject Issuance Issued to |
| | |
| | 92-70 Westinghouse Motor-Operated 09/25/92 All holders of OLs or CPs |
| | |
| | Valve Performance Data for nuclear power reactors. |
| | |
| | Supplied to Nuclear Power |
| | |
| | Plant Licensees |
| | |
| | 92-69 Water Leakage from Yard 09/22/92 All holders of OLs or CPs |
| | |
| | Area Through Conduits for nuclear power reactors. |
| | |
| | Into Buildings |
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| | 91-29, Deficiencies Identified 09/14/92 All holders of OLs or CPs |
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| | Supp. 1 During Electrical Dis- for nuclear power reactors. |
| | |
| | tribution System Func- tional Inspections |
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| | 92-68 Potentially Substandard 09/10/92 All holders of OLs or CPs |
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| | Slip-On, Welding Neck, for nuclear power reactors. |
| | |
| | and Blind Flanges |
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| | 92-67 Deficiency in Design 09/10/92 All holders of OLs or CPs |
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| | Modifications to Ad- for nuclear power reactors. |
| | |
| | dress Failures of |
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| | Hiller Actuators Upon |
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| | A Gradual Loss of |
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| | Air Pressure |
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| | 92-66 Access Denied to NRC 09/01/92 All holders of OLs or CPs |
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| | Inspectors at Five Star for nuclear power reactors |
| | |
| | Products, Inc. and and all recipients of |
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| | Construction Products NUREG-0040, "Licensee, Con- Research, Fairfield, tractor and Vendor Inspec- Connecticut tion Status Report" (White. |
| | |
| | Book). |
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| | 92-65 Safety System Problems 09/03/92 All holders of OLs or CPs |
| | |
| | Caused by Modifications for nuclear power reactors. |
| | |
| | That Were Not Adequately |
| | |
| | Reviewed and Tested |
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| | 92-64 Nozzle Ring Settings 08/28/92 All holders of-OLs or CPs |
| | |
| | on Low Pressure Water- for nuclear power reactors. |
| | |
| | Relief Valves |
| | |
| | OL = Operating License |
| | |
| | CP = Construction Permit |
| | |
| | K> <YIN 92-71 September 30, 1992 This event at Barseback is directly applicable to an earlier study conducted |
| | |
| | by the NRC. That study evaluated the potential for displaced thermal |
| | |
| | insulation to form debris and to be drawn to the sump screen. The results of |
| | |
| | the study are documented in "Containment Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded that the risk associated with |
| | |
| | the sump clogging concern did not warrant backfitting of domestic plants. |
| | |
| | However, based on the BarsebAck event, this conclusion is being reevaluated. |
| | |
| | This information notice requires no specific action or written response. If |
| | |
| | you have any questions about the information in this notice, please contact |
| | |
| | the technical contact listed below or the appropriate Office of Nuclear |
| | |
| | Reactor Regulation (NRR) project manager. |
| | |
| | Original Signed by |
| | |
| | Charles E. Rossi |
| | |
| | Charles E. Rossi, Director |
| | |
| | Division of Operational Events Assessment |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical con itact: Robert L. Dennig, NRR |
| | |
| | (301) 504-1156 Attachment: List of Recently Issued NRC Information Notices |
| | |
| | Document Name: 92-71.IN |
| | |
| | *SEE PREVIOUS CONCURRENCES |
| | |
| | DO *C/OGCB:DOEA:NRR*RPB:ADM |
| | |
| | C GHMarcus TechEd |
| | |
| | 09/; 92 09/28/92 09/24/24 |
| | *OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR *C/OEAB:DOEA:NRR*C/SPLB:DST:NRR ICEP/OIPw |
| | |
| | RWWoodruff RLDennig AChaffee CEMcCracken AKenqeke |
| | |
| | 09/24/92 09/24/92 09/k8/92 09/1r/92 09/dg/92 V CEp/aze |
| | |
| | SC~hLAt_- Jest) |
| | o1i A e- rw W. |
| | |
| | ,L .I |
| | |
| | 4.4a |
| | |
| | -- - I |
| | |
| | 4 ago,. ?. e |
| | |
| | , am ASCo |
| | |
| | NRCIN 92-XX |
| | |
| | September xx, 1991 documented in "Containment Sump Performance," NUREG-0897, Revision 1, dated March |
| | |
| | 1984. The NRC concluded that the risk associated with the sump clogging concern |
| | |
| | did not warrant backfitting of domestic plants. However, based on the Barseback |
| | |
| | event and NUREG-0897, Revision 1, this conclusion is being reevaluated. |
| | |
| | This information notice requires no specific action or written response. If you |
| | |
| | have any question about the information in this notice, please contact the |
| | |
| | technical contact listed below or the appropriate Office of Nuclear Reactor |
| | |
| | Regulation project manager.- |
| | Charles E. Rossi, Director |
| | |
| | Division of Operational |
| | |
| | Events Assessment |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technmical Contact: Robert L. Dennig, NRR |
| | |
| | (301) 504-1156 Attachment: |
| | 1. List of Recently Issued Information Notices |
| | |
| | * See previous page for concurrence. |
| | |
| | CONCURRENCE: |
| | OEAB TECH EDITORS SC:OEAB :SPLB BC:OEAB BC:OGCB |
| | |
| | *RWWoodruff *JDMain *RLDennig CEMcCrcken AEChaffee GHMarcus |
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| | 09/24/92 09/24/92 09/24/92 092/92 09/4&/92 09/ /92 D:DOEA Or? o |
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| | SSC.l1er- Dues |
| | |
| | 09 3-1 CERossi |
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| | 09/ /92 c,?/Xl/q;; |
| | nI -Kc |
| | |
| | 410a.in |
| | |
| | LevA^-t l40-m'- |
| | CovCO |
| | |
| | LV ecc |
| | |
| | V% |
| | is- DcNpu I P0u;"r t.C do Lue g; |
| | eLpCAPt"XU I4 posh 4 aDSCe Al CLL4e.?.- |
| | cz- NX,-,I- PO T-P' |
| | |
| | V- IN 92-71 September 29, 1992 This event at Barseback is directly applicable to an earlier study conducted |
| | |
| | by the NRC. That study evaluated the potential for displaced thermal |
| | |
| | insulation to form debris and to be drawn to the sump screen. The results of |
| | |
| | the study are documented in "Containment Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded that the risk associated with |
| | |
| | the sump clogging concern did not warrant backfitting of domestic plants. |
| | |
| | However, based on the Barsebdck event and NUREG-0897, Revision 1, this |
| | |
| | conclusion is being reevaluated. |
| | |
| | This information notice requires no specific action or written response. If |
| | |
| | you have any questions about the information in this notice, please contact |
| | |
| | the technical contact listed below or the appropriate Office of Nuclear |
| | |
| | Reactor Regulation (NRR) project manager. |
| | |
| | Charles E. Rossi, Director |
| | |
| | Division of Operational Events Assessment |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical con tact: Robert L. Dennig, NRR |
| | |
| | (301) 504-1156 Attachment: List of Recently Issued NRC Information Notices |
| | |
| | Document Name: 92-71.IN |
| | |
| | *SEE PREVIOUS CONCURRENCES |
| | |
| | DOEA:NRR C/OGCB:DOEA:NRR*RPB:ADM |
| | |
| | CERossi GHMarcus)GLK- TechEd |
| | |
| | 09/ /92 09/,S/92 &o 09/24/24 |
| | *OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR *C/OEAB:DOEA:NRR*C/SPLB:DST:NRR CEP/OIP |
| | |
| | RWWoodruff RLDennig AChaffee CEMcCracken AKenneke |
| | |
| | 09/24/92 09/24/92 09/ /92 09/ /92 09/ /92 |
| | |
| | K>- |
| | NRCIN 92-XX |
| | |
| | September xx, 1991 technical contact listed below or the appropriate Office of Nuclear Reactor |
| | |
| | Regulation project manager. |
| | |
| | Charles E. Rossi, Director |
| | |
| | Division of Operational |
| | |
| | Events Assessment |
| | |
| | Office of Nuclear Reactor Regulation |
|
| |
|
| ===Technical Contact:=== | | ===Technical Contact:=== |
| Robert L. Dennig, NRR(301) 504-1156
| |
|
| |
|
| ===Attachment:=== | | ===Robert L. Dennig, NRR=== |
| 1. List of Recently Issued Information NoticesCONCTRRENCE:OEAB W'RWWoodruff09 5/92D : DOEACERossi09/ /92TECH EDITORirgaln Pl09/2,1/9209/; f92BC: SPLUCEMcCracken09/ /92BC: OEKBAEChaffee09/ /92BC: KCBGHMarcus09/ /92410.in}} | | (301) 504-1156 Attachment: |
| | 1. List of Recently Issued Information Notices |
| | |
| | CONCTRRENCE: |
| | OEAB W' TECH EDITOR BC: SPLU BC: OEKB BC: KCB |
| | |
| | RWWoodruff irgaln Pl CEMcCracken AEChaffee GHMarcus |
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| | 09 5/92 09/2,1/92 09/; f92 09/ /92 09/ /92 09/ /92 D: DOEA |
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| | CERossi |
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| | 09/ /92 |
| | 410.in}} |
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| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Partial Plugging of Suppression Pool Strainers at a Foreign BWRML031200327 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
09/30/1992 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-92-071, NUDOCS 9209290014 |
Download: ML031200327 (7) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
_~K)
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 September 30, 1992 NRC INFORMATION NOTICE 92-71: PARTIAL PLUGGING OF SUPPRESSION POOL
STRAINERS AT A FOREIGN BWR
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 alert addressees to the potential-for loss of emergency core cooling
systems (ECCS) that was identified as a result of an event at a Swedish
boiling water reactor (BWR). It is expected that recipients will review thel
information for applicability to their facilities and consider actions, as
appropriate, to avoid similar problems. However, suggestions contained in
this information notice are not NRC requirements; therefore, no specific
action or written response is required.
Description of Circumstances
On July 28, 1992, Sydkraft AB, the utility licensed by the Swedish regulatory
agency for the BarsebAck nuclear power plant, was restarting Unit 2 after the
annual outage. While the reactor was at 1 or 2 percent power and at 435 psi, a leaking pilot valve caused a safety valve for the reactor vessel to open.
This valve discharges directly to the drywell. Reactor scram, high pressure
safety injection, core spray, and containment spray systems initiated
automatically in response to the event. Steam from the open safety valve, impinging on thermally-insulated equipment, dislodged 440 pounds of metal- jacketed, mineral wool. An estimated 220 pounds of insulating material was
washed into the suppression pool. Two of five strainers on the suction side
of the ECCS pumps were in service and became partially plugged with mineral
wool. Plugging caused pressure to decrease significantly across the strainers
and caused indications of cavitation in one pump in about an hour after the
event began. The operators successfully back flushed the strainers and shut
down the reactor without additional problems.
Discussion
In the safety analysis for Unit 2 of the Barsebdck plant, the licensee
concluded that the strainers would not require back flushing during the first
10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after a loss-of-coolant accident. Because of the event of July 28, the Swedish regulatory agency required Barseback Unit 2 and four other units
of similar design to remain shut down until this problem is resolved.
9209290014 e
III
IN 92-71 September 30, 1992 This event at BarsebAck is directly applicable
by the NRC. That study evaluated the potential to an earlier study conducted
insulation to form debris and to be drawn to for displaced thermal
the study are documented in "Containment Sump the sump screen. The results of
Revision 1, dated March 1984. The NRC concluded Performance," NUREG-0897, that the risk associated with
the sump clogging concern did not warrant backfitting
However, based on the Barsebdck event, this of domestic plants.
conclusion is being reevaluated.
This information notice requires no specific
action or written response. If
you have any questions about the information
in this notice, please contact
the technical contact listed below or the appropriate
Reactor Regulation (NRR) project manager. Office of Nuclear
(arles si, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: Robert L. Dennig, NRR
(301) 504-1156 Attachment: List of Recently Issued NRC Information Notices
Attachment
IN 92-71 September 30, 1992 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
92-70 Westinghouse Motor-Operated 09/25/92 All holders of OLs or CPs
Valve Performance Data for nuclear power reactors.
Supplied to Nuclear Power
Plant Licensees
92-69 Water Leakage from Yard 09/22/92 All holders of OLs or CPs
Area Through Conduits for nuclear power reactors.
Into Buildings
91-29, Deficiencies Identified 09/14/92 All holders of OLs or CPs
Supp. 1 During Electrical Dis- for nuclear power reactors.
tribution System Func- tional Inspections
92-68 Potentially Substandard 09/10/92 All holders of OLs or CPs
Slip-On, Welding Neck, for nuclear power reactors.
and Blind Flanges
92-67 Deficiency in Design 09/10/92 All holders of OLs or CPs
Modifications to Ad- for nuclear power reactors.
dress Failures of
Hiller Actuators Upon
A Gradual Loss of
Air Pressure
92-66 Access Denied to NRC 09/01/92 All holders of OLs or CPs
Inspectors at Five Star for nuclear power reactors
Products, Inc. and and all recipients of
Construction Products NUREG-0040, "Licensee, Con- Research, Fairfield, tractor and Vendor Inspec- Connecticut tion Status Report" (White.
Book).
92-65 Safety System Problems 09/03/92 All holders of OLs or CPs
Caused by Modifications for nuclear power reactors.
That Were Not Adequately
Reviewed and Tested
92-64 Nozzle Ring Settings 08/28/92 All holders of-OLs or CPs
on Low Pressure Water- for nuclear power reactors.
Relief Valves
OL = Operating License
CP = Construction Permit
K> <YIN 92-71 September 30, 1992 This event at Barseback is directly applicable to an earlier study conducted
by the NRC. That study evaluated the potential for displaced thermal
insulation to form debris and to be drawn to the sump screen. The results of
the study are documented in "Containment Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded that the risk associated with
the sump clogging concern did not warrant backfitting of domestic plants.
However, based on the BarsebAck event, this conclusion is being reevaluated.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Original Signed by
Charles E. Rossi
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical con itact: Robert L. Dennig, NRR
(301) 504-1156 Attachment: List of Recently Issued NRC Information Notices
Document Name: 92-71.IN
- SEE PREVIOUS CONCURRENCES
DO *C/OGCB:DOEA:NRR*RPB:ADM
C GHMarcus TechEd
09/; 92 09/28/92 09/24/24
- OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR *C/OEAB:DOEA:NRR*C/SPLB:DST:NRR ICEP/OIPw
RWWoodruff RLDennig AChaffee CEMcCracken AKenqeke
09/24/92 09/24/92 09/k8/92 09/1r/92 09/dg/92 V CEp/aze
SC~hLAt_- Jest)
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NRCIN 92-XX
September xx, 1991 documented in "Containment Sump Performance," NUREG-0897, Revision 1, dated March
1984. The NRC concluded that the risk associated with the sump clogging concern
did not warrant backfitting of domestic plants. However, based on the Barseback
event and NUREG-0897, Revision 1, this conclusion is being reevaluated.
This information notice requires no specific action or written response. If you
have any question about the information in this notice, please contact the
technical contact listed below or the appropriate Office of Nuclear Reactor
Regulation project manager.-
Charles E. Rossi, Director
Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technmical Contact: Robert L. Dennig, NRR
(301) 504-1156 Attachment:
1. List of Recently Issued Information Notices
- See previous page for concurrence.
CONCURRENCE:
OEAB TECH EDITORS SC:OEAB :SPLB BC:OEAB BC:OGCB
- RWWoodruff *JDMain *RLDennig CEMcCrcken AEChaffee GHMarcus
09/24/92 09/24/92 09/24/92 092/92 09/4&/92 09/ /92 D:DOEA Or? o
SSC.l1er- Dues
09 3-1 CERossi
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V- IN 92-71 September 29, 1992 This event at Barseback is directly applicable to an earlier study conducted
by the NRC. That study evaluated the potential for displaced thermal
insulation to form debris and to be drawn to the sump screen. The results of
the study are documented in "Containment Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded that the risk associated with
the sump clogging concern did not warrant backfitting of domestic plants.
However, based on the Barsebdck event and NUREG-0897, Revision 1, this
conclusion is being reevaluated.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical con tact: Robert L. Dennig, NRR
(301) 504-1156 Attachment: List of Recently Issued NRC Information Notices
Document Name: 92-71.IN
- SEE PREVIOUS CONCURRENCES
DOEA:NRR C/OGCB:DOEA:NRR*RPB:ADM
CERossi GHMarcus)GLK- TechEd
09/ /92 09/,S/92 &o 09/24/24
- OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR *C/OEAB:DOEA:NRR*C/SPLB:DST:NRR CEP/OIP
RWWoodruff RLDennig AChaffee CEMcCracken AKenneke
09/24/92 09/24/92 09/ /92 09/ /92 09/ /92
K>-
NRCIN 92-XX
September xx, 1991 technical contact listed below or the appropriate Office of Nuclear Reactor
Regulation project manager.
Charles E. Rossi, Director
Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Robert L. Dennig, NRR
(301) 504-1156 Attachment:
1. List of Recently Issued Information Notices
CONCTRRENCE:
OEAB W' TECH EDITOR BC: SPLU BC: OEKB BC: KCB
RWWoodruff irgaln Pl CEMcCracken AEChaffee GHMarcus
09 5/92 09/2,1/92 09/; f92 09/ /92 09/ /92 09/ /92 D: DOEA
CERossi
09/ /92
410.in
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list | - Information Notice 1992-01, Cable Damage Caused by Inadequate Cable Installation Procedures and Controls (3 January 1992)
- Information Notice 1992-02, Relap5/MOD3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992)
- Information Notice 1992-02, Relap5/Mod3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992)
- Information Notice 1992-03, Remote Trip Function Failures in General Electric F-Frame Molded-Case Circuit Breakers (6 January 1992)
- Information Notice 1992-04, Potter and Brumfield Model Mdr Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment)
- Information Notice 1992-04, Potter and Brumfield Model MDR Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs RXMH2 Relays (8 January 1992)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs Rxmh2 Relays (8 January 1992)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in ABS RXMH2 Relays (8 January 1992)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment Not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-07, Rapid Flow-induced Erosion/Corrosion of Feedwater Piping (9 January 1992)
- Information Notice 1992-08, Revised Protective Action Guidance for Nuclear Incidents (23 January 1992)
- Information Notice 1992-09, Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions (30 January 1992)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire Used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-11, Soil and Water Contamination at Fuel Cycle Facilities (5 February 1992, Topic: Brachytherapy)
- Information Notice 1992-12, Effects of Cable Leakage Currents on Instrument Settings and Indications (10 February 1992, Topic: Brachytherapy)
- Information Notice 1992-13, Inadequate Control Over Vehicular Traffic at Nuclear Power Plant Sites (18 February 1992, Topic: Brachytherapy)
- Information Notice 1992-14, Uranium Oxide Fires at Fuel Cycle Facilities (21 February 1992, Topic: Brachytherapy)
- Information Notice 1992-15, Failure of Primary Systems Compression Fitting (24 February 1992)
- Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown (25 February 1992, Topic: Reactor Vessel Water Level, Temporary Modification, Brachytherapy)
- Information Notice 1992-17, NRC Inspections of Programs Being Developed at Nuclear Power Plants in Response to Generic Letter 89-10 (26 February 1992, Topic: Stroke time)
- Information Notice 1992-18, Potential for Loss of Remote Shutdown Capability During a Control Room Fire (28 February 1992, Topic: Hot Short, Safe Shutdown)
- Information Notice 1992-19, Misapplication of Potter and Brumfield Mdr Rotary Relays (2 March 1992)
- Information Notice 1992-19, Misapplication of Potter and Brumfield MDR Rotary Relays (2 March 1992)
- Information Notice 1992-20, Inadequate Local Leak Rate Testing (3 March 1992)
- Information Notice 1992-21, Spent Fuel Pool Reactivity Calculations (24 March 1992)
- Information Notice 1992-23, Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment (27 March 1992)
- Information Notice 1992-24, Distributor Modification to Certain Commercial-Grade Agastat Electrical Relays (30 March 1992)
- Information Notice 1992-25, Pressure Locking of Motor-Operated Flexible Wedge Gate Valves (2 April 1992, Topic: Stroke time, Hydrostatic)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of ITE/Gould A.C. Relays used in Safety-Related Applications (3 April 1992)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of Ite/Gould A.C. Relays Used in Safety-Related Applications (3 April 1992)
- Information Notice 1992-28, Inadequate Fire Suppression System Testing (8 April 1992, Topic: Safe Shutdown)
- Information Notice 1992-29, Potential Breaker Miscoordination Caused by Instantaneous Trip Circuitry (17 April 1992)
- Information Notice 1992-30, Falsification of Plant Records (23 April 1992)
- Information Notice 1992-31, Electrical Connection Problem in Johnson Yokogawa Corporation YS-80 Programmable Indicating Controllers (27 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (Within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices Are Installed (30 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices are Installed (30 April 1992)
- Information Notice 1992-34, New Exposure Limits for Airborne Uranium and Thorium (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping Inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-36, Intersystem LOCA Outside Containment (7 May 1992)
- Information Notice 1992-37, Implementation of the Deliberate Misconduct Rule (8 May 1992)
- Information Notice 1992-38, Implementation Date for the Revision to the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (26 May 1992, Topic: Brachytherapy)
- Information Notice 1992-39, Unplanned Return to Criticality During Reactor Shutdown (13 May 1992, Topic: Fuel cladding)
- Information Notice 1992-40, Inadequate Testing of Emergency Bus Undervoltage Logic Circuitry (27 May 1992)
- Information Notice 1992-41, Consideration of Stem Rejection Load In Calculation of Required Valve Thrust (29 May 1992, Topic: Anchor Darling)
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