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| ==Description of Circumstances== | | ==Description of Circumstances== |
| During a steam generator tube rupture event at Palo Verde Unit 2 on March 14,1993 (NRC Inspection Report 50-279/93-14), a charging pump tripped off on lowsuction pressure when the operators switched the charging pump suction sourcefrom the volume control tank to the refueling water tank. During thesubsequent evaluation of the event, the licensee determined that four pumps,three charging pumps and a boric acid makeup pump, were all taking suctionthrough the same 7.6-cm [3-in.] diameter pipe. The licensee also determinedthat the high rate of flow through the suction pipe that resulted from thesimultaneous operation of all four pumps caused a sufficient pressurereduction at the suction of the pumps to lower this pressure below the lowsuction trip setpoints of the charging pumps.Two charging pumps were already running when the tube rupture occurred. Inaddition, the operators were running a boric acid pump to circulate therefueling water through filters to purify it for an upcoming outage; Theboric acid pump flow was being recirculated back to the refueling water tankand did not contribute to the makeup water going into the reactor coolantsystem. The operators started the third charging pump early in the event inan effort to restore the pressurizer level, which was decreasing because ofthe tube rupture. At that time all of the charging pumps were taking suctionfrom the volume control tank, which is the normal source of makeup water forthe reactor coolant system. Approximately 30 minutes later, in accordancewith emergency procedures, the operators opened the suction valve from the9404060036 po-rXE qq-D29 qqoqIn TkId9L III IN 94-29-V April 11, 1994 refueling water tank and then closed the suction valve from the volume controltank.At this point one of the charging pumps tripped off. The operators were ableto restore the tripped charging pump to operation by realigning the suction ofthe charging pumps to other suction paths from the refueling water tank.DiscussionFollowing this event the licensee calculated that, with the boric acid pumprunning, the remaining flow capacity of the refueling water tank suctionsource that was in use was Just sufficient for two charging pumps. With allfour pumps running the suction pressure was below the low suction trip setpoints (81.0 kPa to 87.2 kPa [11.75 psia to 12.65 psia]) for the chargingpumps. Because the trip set points are set at slightly different pressures,only one pump tripped. Once this first pump tripped, the resulting rise insuction pressure allowed the remaining pumps to keep running.The licensee concluded that, if recirculation by the boric acid pump is not inprogress, sufficient suction pressure exists for all three charging-pumps.Consequently, the licensee revised the emergency procedures that involve thecharging pumps to specify that any ongoing recirculation of the refuelingwater by the boric acid pump is to be terminated when refueling water isneeded for emergency makeup.Licensees of pressurized-water reactors use the charging systems in a numberof ways for accident mitigation, such as including the charging system as apart of the automatic safety injection system. Charging systems are also usedas a source of pressurizer spray to depressurize the reactor when the reactorcoolant pumps are shut down. Emergency operating procedures often refer tothe charging systems for other uses as well.Some licensees do not isolate the volume control tank (or its equivalent) whenthe charging system source is switched to the refueling water tank (or itsequivalent), but depend on the static pressure in the refueling water tank tokeep the volume control tank from draining. Should the volume control tankempty in response to lower-than-expected suction pressure, hydrogen cover gasnormally contained in this tank could enter the charging system suction andcause the pumps to malfunctio IN 94-29April 11, 1994 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 project manager.Brian K. Gr es, Director ter-Division of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Warren C. Lyon, NRR(301) 504-3892 | | During a steam generator tube rupture event at Palo Verde Unit 2 on March 14,1993 (NRC Inspection Report 50-279/93-14), a charging pump tripped off on lowsuction pressure when the operators switched the charging pump suction sourcefrom the volume control tank to the refueling water tank. During thesubsequent evaluation of the event, the licensee determined that four pumps,three charging pumps and a boric acid makeup pump, were all taking suctionthrough the same 7.6-cm [3-in.] diameter pipe. The licensee also determinedthat the high rate of flow through the suction pipe that resulted from thesimultaneous operation of all four pumps caused a sufficient pressurereduction at the suction of the pumps to lower this pressure below the lowsuction trip setpoints of the charging pumps.Two charging pumps were already running when the tube rupture occurred. Inaddition, the operators were running a boric acid pump to circulate therefueling water through filters to purify it for an upcoming outage; Theboric acid pump flow was being recirculated back to the refueling water tankand did not contribute to the makeup water going into the reactor coolantsystem. The operators started the third charging pump early in the event inan effort to restore the pressurizer level, which was decreasing because ofthe tube rupture. At that time all of the charging pumps were taking suctionfrom the volume control tank, which is the normal source of makeup water forthe reactor coolant system. Approximately 30 minutes later, in accordancewith emergency procedures, the operators opened the suction valve from the9404060036 po-rXE qq-D29 qqoqIn TkId9L III |
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| | IN 94-29-V April 11, 1994 refueling water tank and then closed the suction valve from the volume controltank.At this point one of the charging pumps tripped off. The operators were ableto restore the tripped charging pump to operation by realigning the suction ofthe charging pumps to other suction paths from the refueling water tank.DiscussionFollowing this event the licensee calculated that, with the boric acid pumprunning, the remaining flow capacity of the refueling water tank suctionsource that was in use was Just sufficient for two charging pumps. With allfour pumps running the suction pressure was below the low suction trip setpoints (81.0 kPa to 87.2 kPa [11.75 psia to 12.65 psia]) for the chargingpumps. Because the trip set points are set at slightly different pressures,only one pump tripped. Once this first pump tripped, the resulting rise insuction pressure allowed the remaining pumps to keep running.The licensee concluded that, if recirculation by the boric acid pump is not inprogress, sufficient suction pressure exists for all three charging-pumps.Consequently, the licensee revised the emergency procedures that involve thecharging pumps to specify that any ongoing recirculation of the refuelingwater by the boric acid pump is to be terminated when refueling water isneeded for emergency makeup.Licensees of pressurized-water reactors use the charging systems in a numberof ways for accident mitigation, such as including the charging system as apart of the automatic safety injection system. Charging systems are also usedas a source of pressurizer spray to depressurize the reactor when the reactorcoolant pumps are shut down. Emergency operating procedures often refer tothe charging systems for other uses as well.Some licensees do not isolate the volume control tank (or its equivalent) whenthe charging system source is switched to the refueling water tank (or itsequivalent), but depend on the static pressure in the refueling water tank tokeep the volume control tank from draining. Should the volume control tankempty in response to lower-than-expected suction pressure, hydrogen cover gasnormally contained in this tank could enter the charging system suction andcause the pumps to malfunction. |
| List of Recently Issued NRC Information Notices Ak-1achmentIN 94-29April 12, 1994 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to92-51,Supp. 194-2894-2794-26Misapplication andInadequate Testing ofMolded-Case CircuitBreakersPotential Problems withFire-Barrier PenetrationSealsFacility OperatingConcerns Resulting fromLocal Area FloodingPersonnel Hazards andOther Problems fromSmoldering Fire-Retard-ant Material in theDrywell of a Boiling-Water ReactorSafety Systems Responseto Loss of Coolant andLoss of Offsite PowerFailure of ContainmentSpray Header Valve toOpen due to ExcessivePressure from InertialEffects of WaterInadequate Maintenanceof Uninterruptible PowerSupplies and InvertersGuidance to Hazardous,Radioactive and MixedWaste Generators on theElements of a WasteMinimization Program04/12/9404/05/9403/31/9403/28/9403/25/9403/25/9403/24/9403/25/94All 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.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All NRC Licensees.93-17,Rev. 194-2594-2494-23OL -Operating LicenseCP -Construction Permit
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| .I IfIN 94-29April 11, 1994 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 project manager.orig /s/'d by CIGrimesBrian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Warren C. Lyon, NRR(301) 504-3892
| | IN 94-29April 11, 1994 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 project manager.Brian K. Gr es, Director ter-Division of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Warren C. Lyon, NRR(301) 504-3892Attachment:List of Recently Issued NRC Information Notices |
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| | Ak-1achmentIN 94-29April 12, 1994 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to92-51,Supp. 194-2894-2794-26Misapplication andInadequate Testing ofMolded-Case CircuitBreakersPotential Problems withFire-Barrier PenetrationSealsFacility OperatingConcerns Resulting fromLocal Area FloodingPersonnel Hazards andOther Problems fromSmoldering Fire-Retard-ant Material in theDrywell of a Boiling-Water ReactorSafety Systems Responseto Loss of Coolant andLoss of Offsite PowerFailure of ContainmentSpray Header Valve toOpen due to ExcessivePressure from InertialEffects of WaterInadequate Maintenanceof Uninterruptible PowerSupplies and InvertersGuidance to Hazardous,Radioactive and MixedWaste Generators on theElements of a WasteMinimization Program04/12/9404/05/9403/31/9403/28/9403/25/9403/25/9403/24/9403/25/94All 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.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All NRC Licensees.93-17,Rev. 194-2594-2494-23OL -Operating LicenseCP -Construction Permit |
| List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFICE *OGCB *TECH ED *SRXB/DSSA *C:SRXB/DSSANAME DCKirkpatrick RSanders WCLyon RJonesDATE 111/30/93 111/30/93 , 12/20/93 12/22/93*D:DSSA*C:OGCB/DORSD:DORS/NRRAThadani GHMarcus BKGrimes601/04/94 01/11/94 04/L /94VULUMMN NAME: 4-M. IN IN 94-xxMarch xx, 1994 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 project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact:Warren C. Lyon, NRR(301) 504-3892*SFF PREVOUS CONCURRENCEOFFICE *OGCB *TECH ED *SRXB/DSSA *C:SRXB/DSSANAME DCKirkpatrick RSanders WCLyon RJonesDATE 11/30/93 11/30/93 12/20/93 1 12/22/93.-- .1*D: DSSA*C:OGCB/DORSD:DORS/NRRAThadani GHMarcus BKGrimes01/04/94 01/11/94 03/ /94I=01twDOCUMENT NAME: CHARGING.DCK IN 94-xxJanuary xx, 1994 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 project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor Regulation | | |
| | .I IfIN 94-29April 11, 1994 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 project manager.orig /s/'d by CIGrimesBrian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Warren C. Lyon, NRR(301) 504-3892Attachment:List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFICE *OGCB *TECH ED *SRXB/DSSA *C:SRXB/DSSANAME DCKirkpatrick RSanders WCLyon RJonesDATE 111/30/93 111/30/93 , 12/20/93 12/22/93*D:DSSA*C:OGCB/DORSD:DORS/NRRAThadani GHMarcus BKGrimes601/04/94 01/11/94 04/L /94VULUMMN NAME: 4-M. IN |
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| | IN 94-xxMarch xx, 1994 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 project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact:Warren C. Lyon, NRR(301) 504-3892*SFF PREVOUS CONCURRENCEOFFICE *OGCB *TECH ED *SRXB/DSSA *C:SRXB/DSSANAME DCKirkpatrick RSanders WCLyon RJonesDATE 11/30/93 11/30/93 12/20/93 1 12/22/93.-- .1*D: DSSA*C:OGCB/DORSD:DORS/NRRAThadani GHMarcus BKGrimes01/04/94 01/11/94 03/ /94I=01twDOCUMENT NAME: CHARGING.DCK |
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| | IN 94-xxJanuary xx, 1994 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 project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor Regulation |
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| Warren C. Lyon, NRR(301) 504-3892t OFFICE OGCB TECH ED SRXBA 54 l C:OGCB/DORS D:DORS/NRRNAME fDCKirkpatrick RPoUlm'us WCLyon GHMarcus BKGrimesDATE /(1g9/93PZ-@ Iit/3093 j/93 / /93 / /93 1DOCUMENT NAME: CHARGING .CK l"05-- 1}} | | Warren C. Lyon, NRR(301) 504-3892t OFFICE OGCB TECH ED SRXBA 54 l C:OGCB/DORS D:DORS/NRRNAME fDCKirkpatrick RPoUlm'us WCLyon GHMarcus BKGrimesDATE /(1g9/93PZ-@ Iit/3093 j/93 / /93 / /93 1DOCUMENT NAME: CHARGING .CK l"05-- 1 |
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Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction PressureML031060474 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, 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, 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: |
04/11/1994 |
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From: |
Grimes B K Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-94-029, NUDOCS 9404060036 |
Download: ML031060474 (9) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, 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, 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
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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 [[:Mcguire]] 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 [[: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 [[:Mcguire]] 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 [[: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>. |
I.' 4 AUNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555April 11, 1994NRC INFORMATION NOTICE 94-29: CHARGING PUMP TRIP DURING A LOSS-OF-COOLANTEVENT CAUSED BY LOW SUCTION PRESSURE
Addressees
All holders of operating licenses or construction permits for pressurized-water reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to the possibility of a charging pump trip causedby inadequate suction pressure because too many pumps may be aligned to asingle suction path during accident mitigation. It is expected thatrecipients will review the information for applicability to their facilitiesand 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
During a steam generator tube rupture event at Palo Verde Unit 2 on March 14,1993 (NRC Inspection Report 50-279/93-14), a charging pump tripped off on lowsuction pressure when the operators switched the charging pump suction sourcefrom the volume control tank to the refueling water tank. During thesubsequent evaluation of the event, the licensee determined that four pumps,three charging pumps and a boric acid makeup pump, were all taking suctionthrough the same 7.6-cm [3-in.] diameter pipe. The licensee also determinedthat the high rate of flow through the suction pipe that resulted from thesimultaneous operation of all four pumps caused a sufficient pressurereduction at the suction of the pumps to lower this pressure below the lowsuction trip setpoints of the charging pumps.Two charging pumps were already running when the tube rupture occurred. Inaddition, the operators were running a boric acid pump to circulate therefueling water through filters to purify it for an upcoming outage; Theboric acid pump flow was being recirculated back to the refueling water tankand did not contribute to the makeup water going into the reactor coolantsystem. The operators started the third charging pump early in the event inan effort to restore the pressurizer level, which was decreasing because ofthe tube rupture. At that time all of the charging pumps were taking suctionfrom the volume control tank, which is the normal source of makeup water forthe reactor coolant system. Approximately 30 minutes later, in accordancewith emergency procedures, the operators opened the suction valve from the9404060036 po-rXE qq-D29 qqoqIn TkId9L III
IN 94-29-V April 11, 1994 refueling water tank and then closed the suction valve from the volume controltank.At this point one of the charging pumps tripped off. The operators were ableto restore the tripped charging pump to operation by realigning the suction ofthe charging pumps to other suction paths from the refueling water tank.DiscussionFollowing this event the licensee calculated that, with the boric acid pumprunning, the remaining flow capacity of the refueling water tank suctionsource that was in use was Just sufficient for two charging pumps. With allfour pumps running the suction pressure was below the low suction trip setpoints (81.0 kPa to 87.2 kPa [11.75 psia to 12.65 psia]) for the chargingpumps. Because the trip set points are set at slightly different pressures,only one pump tripped. Once this first pump tripped, the resulting rise insuction pressure allowed the remaining pumps to keep running.The licensee concluded that, if recirculation by the boric acid pump is not inprogress, sufficient suction pressure exists for all three charging-pumps.Consequently, the licensee revised the emergency procedures that involve thecharging pumps to specify that any ongoing recirculation of the refuelingwater by the boric acid pump is to be terminated when refueling water isneeded for emergency makeup.Licensees of pressurized-water reactors use the charging systems in a numberof ways for accident mitigation, such as including the charging system as apart of the automatic safety injection system. Charging systems are also usedas a source of pressurizer spray to depressurize the reactor when the reactorcoolant pumps are shut down. Emergency operating procedures often refer tothe charging systems for other uses as well.Some licensees do not isolate the volume control tank (or its equivalent) whenthe charging system source is switched to the refueling water tank (or itsequivalent), but depend on the static pressure in the refueling water tank tokeep the volume control tank from draining. Should the volume control tankempty in response to lower-than-expected suction pressure, hydrogen cover gasnormally contained in this tank could enter the charging system suction andcause the pumps to malfunction.
IN 94-29April 11, 1994 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 project manager.Brian K. Gr es, Director ter-Division of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Warren C. Lyon, NRR(301) 504-3892Attachment:List of Recently Issued NRC Information Notices
Ak-1achmentIN 94-29April 12, 1994 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to92-51,Supp. 194-2894-2794-26Misapplication andInadequate Testing ofMolded-Case CircuitBreakersPotential Problems withFire-Barrier PenetrationSealsFacility OperatingConcerns Resulting fromLocal Area FloodingPersonnel Hazards andOther Problems fromSmoldering Fire-Retard-ant Material in theDrywell of a Boiling-Water ReactorSafety Systems Responseto Loss of Coolant andLoss of Offsite PowerFailure of ContainmentSpray Header Valve toOpen due to ExcessivePressure from InertialEffects of WaterInadequate Maintenanceof Uninterruptible PowerSupplies and InvertersGuidance to Hazardous,Radioactive and MixedWaste Generators on theElements of a WasteMinimization Program04/12/9404/05/9403/31/9403/28/9403/25/9403/25/9403/24/9403/25/94All 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.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All NRC Licensees.93-17,Rev. 194-2594-2494-23OL -Operating LicenseCP -Construction Permit
.I IfIN 94-29April 11, 1994 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 project manager.orig /s/'d by CIGrimesBrian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact: Warren C. Lyon, NRR(301) 504-3892Attachment:List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFICE *OGCB *TECH ED *SRXB/DSSA *C:SRXB/DSSANAME DCKirkpatrick RSanders WCLyon RJonesDATE 111/30/93 111/30/93 , 12/20/93 12/22/93*D:DSSA*C:OGCB/DORSD:DORS/NRRAThadani GHMarcus BKGrimes601/04/94 01/11/94 04/L /94VULUMMN NAME: 4-M. IN
IN 94-xxMarch xx, 1994 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 project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contact:Warren C. Lyon, NRR(301) 504-3892*SFF PREVOUS CONCURRENCEOFFICE *OGCB *TECH ED *SRXB/DSSA *C:SRXB/DSSANAME DCKirkpatrick RSanders WCLyon RJonesDATE 11/30/93 11/30/93 12/20/93 1 12/22/93.-- .1*D: DSSA*C:OGCB/DORSD:DORS/NRRAThadani GHMarcus BKGrimes01/04/94 01/11/94 03/ /94I=01twDOCUMENT NAME: CHARGING.DCK
IN 94-xxJanuary xx, 1994 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 project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor Regulation
Technical Contact:
Warren C. Lyon,(301) 504-3892NRR*SEE PREVIOUS CONCURRENCEOFFICE *OGCB *TECH ED *SRXB/DSSA *C:SRXB/DSSANAME DCKirkpatrick I RSanders WCLyon RJonesDATE I1/30/93 J >/BY 11/30/93 112/20/93 12/22/93D:DSSA Okl C:OGCB/DORSD:DORS/NRR c llAThadani GHMarcus MYA1 BKGrimes01/04/94 01/ti/94 01/ /94DOCUMENT NAME: CHARGING.DCK
-* IIN 93-xxDecember xx, 993This 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 project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor Regulation
Technical Contact:
Warren C. Lyon, NRR(301) 504-3892Af. -.-/*SEF PREVIOUS CONCURRENCE,____1 ____ _ _____' /sOFFICE *OGCB *TECH ED ' XifDSSA SU C:SRXB/DSSAI INAME DCKirkpatrick RSanders WCLyon TC K ns RJones VDATE 11/30/93 1 11/30/93 2 /£ ./z/'?L I3L , ..aD:DSSAMC:OGCB/DORSD:DORS/NRRATha n GHMarcus I BKGrimesF 1k/ & _ /91 _ 1 /93r4DOCUMENT NAME: CHARGING.DCK3a9 IN 93-xxDecember xx, 993This 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 project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor Regulation
Technical Contact:
Warren C. Lyon, NRR(301) 504-3892t OFFICE OGCB TECH ED SRXBA 54 l C:OGCB/DORS D:DORS/NRRNAME fDCKirkpatrick RPoUlm'us WCLyon GHMarcus BKGrimesDATE /(1g9/93PZ-@ Iit/3093 j/93 / /93 / /93 1DOCUMENT NAME: CHARGING .CK l"05-- 1
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list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994)
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