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| | issue date = 01/29/1990 | | | issue date = 01/29/1990 |
| | title = Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels | | | title = Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels |
| | 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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| | page count = 7 | | | page count = 7 |
| }} | | }} |
| {{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555January 29, 1990NRC INFORMATION NOTICE NO. 90-06: POTENTIAL FOR LOSS OF SHUTDOWN COOLINGWHILE AT LOW REACTOR COOLANT LEVELS | | {{#Wiki_filter:UNITED STATES |
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| | NUCLEAR REGULATORY COMMISSION |
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| | OFFICE OF NUCLEAR REACTOR REGULATION |
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| | WASHINGTON, D.C. 20555 January 29, 1990 |
| | SHUTDOWN COOLING |
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| | NRC INFORMATION NOTICE NO. 90-06: POTENTIAL FOR LOSS OF COOLANT LEVELS |
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| | WHILE AT LOW REACTOR |
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| ==Addressees== | | ==Addressees== |
| :All holders of operating licenses or construction permits for nuclear powerreactors. | | : |
| | nuclear power |
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| | All holders of operating licenses or construction permits for |
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| | reactors. |
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| ==Purpose== | | ==Purpose== |
| :This information notice is intended to alert addressees to a potential problemaffecting the operability of the residual heat removal (RHR) system duringoperating conditions involving mid-loop operation. It is expected that re--cipients will review the information for applicability to their facilitiesand consider actions, as appropriate, to avoid similar problems. However,suggestions contained in this information notice do not constitute NRCrequirements; therefore, no specific action or written response is required. | | : |
| | to a potential problem |
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| | This information notice is intended to alert addressees (RHR) system during |
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| | affecting the operability of the residual heat removal |
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| | is expected that re- operating conditions involving mid-loop operation. It to their facilities |
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| | -cipients will review the information for applicability problems. However, and consider actions, as appropriate, to avoid similar constitute NRC |
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| | suggestions contained in this information notice do not |
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| | response is required. |
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| | requirements; therefore, no specific action or written |
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| ==Description of Circumstances== | | ==Description of Circumstances== |
| :On July 18, 1989, at Comanche Peak Unit 1, train 'Al of the residual heatremoval system was in operation prior to initial fuel loading. The airoperated RHR heat exchanger flow control valve (FCV) was being used tomaintain system flow below 2000 gpm. The reactor vessel water level wasbeing maintained slightly abpve the center line of the hot legs.The inverter supplying power to the controller for the FCV failed. The lossof power to the controller resulted in the FCV failing to its emergency corecooling system (ECCS) position of being fully open. The open valve causedan increase in system flow to 4400 gpm. This sudden, increased flow causedconditions where vortexing was expected at the suction of the RHR pipe con-nection to the RCS.The power supply for the controllers was manually transferred to an alternatesource and the FCV was throttled, thus terminating the event.Discussion:The FCV is manually throttled to maintain a desired rate of flow through theRHR heat exchanger. The heat exchanger flow rate is adjusted to control thetemperature of the water being returned to the vessel. Total system flow isregulated by throttling the heat exchanger bypass valve coincident with theadjustment of the FCV.001230175 Z ( (' D*1 IC,eo uachr | | : |
| | the residual heat |
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| | On July 18, 1989, at Comanche Peak Unit 1, train 'Al ofloading. The air |
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| | removal system was in operation prior to initial fuel |
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| | being used to |
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| | operated RHR heat exchanger flow control valve (FCV) was water level was |
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| | maintain system flow below 2000 gpm. The reactor vessel |
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| | legs. |
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| | being maintained slightly abpve the center line of the hot |
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| | FCV failed. The loss |
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| | The inverter supplying power to the controller for the to its emergency core |
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| | of power to the controller resulted in the FCV failing open valve caused |
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| | cooling system (ECCS) position of being fully open. The flow caused |
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| | an increase in system flow to 4400 gpm. This sudden, increased |
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| | the RHR pipe con- conditions where vortexing was expected at the suction of |
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| | nection to the RCS. |
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| | to an alternate |
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| | The power supply for the controllers was manually transferred |
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| | terminating the event. |
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| | source and the FCV was throttled, thus |
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| | Discussion: |
| | flow through the |
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| | The FCV is manually throttled to maintain a desired rate of to control the |
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| | RHR heat exchanger. The heat exchanger flow rate is adjusted |
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| | to the vessel. Total system flow is |
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| | temperature of the water being returned with the |
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| | regulated by throttling the heat exchanger bypass valve coincident |
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| | adjustment of the FCV. |
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| | 001230175 Z (( |
| | ' D*1 IC, |
| | eo uachr |
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| | IN 90-06 January 29, 1990 During this event, there were no indications of pump air ingestion. However, the increased system flow corresponded to the rate at which vortexing had |
| | |
| | been calculated to occur based on the existing RCS level. The licensee had |
| | |
| | previously determined maximum permitted flow rates for various reduced levels |
| | |
| | of the RCS to prevent the possibility of vortexing and air entrainment into |
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| | the RHR pump. |
| | |
| | Although RHR pump operation was never actually impaired, the potential existed |
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| | for air to be introduced to the pump's suction. This concern is exacerbated by |
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| | * the fact that the heat exchanger FCVs for both trains of RHR are powered from |
| | |
| | the same inverter. Since the FCVs open fully on a loss of power, both trains |
| | |
| | of RHR could become inoperable on a loss of power during mid-loop operation. |
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| | (A loss of instrument air would also cause the FCVs to fail to the full open |
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| | position and could also result in the loss of both trains of the RHR system). |
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| | During most modes of operation, having the FCVs go -fully open on loss of |
| | |
| | power or instrument air is not a safety concern because having the valves |
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| | fully open does not normally prevent the system from performing its safety |
| | |
| | function. However, having the valves go fully open while at mid-loop could |
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| | result in the loss of decay heat removal capability. This loss could persist |
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| | until electrical power or instrument air is restored and air is vented from |
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| | the RHR system. |
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| | The licensee has revised procedures for mid-loop operation to require manually |
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| | positioning the cold leg injection isolation valves to limit the maximum flow |
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| | through the system, even with the FCVs fully open. This lineup will be used |
| | |
| | whenever the unit is at mid-loop and protects against the consequences of |
| | |
| | failure of either electrical power or instrument air. |
| | |
| | Several generic communications have been issued informing licensees of the |
| | |
| | consequences of the loss of residual (decay) heat removal and the operating |
| | |
| | conditions under which the probability of a loss increases; i.e., reduced |
| | |
| | inventory conditions. The most recent publications include Generic Letter |
| | |
| | (GL) No. 87-12, "Loss of Decay Heat Removal While the Reactor Coolant System |
| | |
| | is Partially Filled;" GL No. 88-17, *Loss of Decay Heat Removal;" NRC In- formation Notice (IN)87-23, "Loss of Decay Heat Removal During Low Reactor |
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| | Coolant Level Operation;" IN 88-36, 'Possible Sudden Loss of RCS Inventory |
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| | During Low Coolant Level Operation;" and IN 89-67, "Loss of Residual Heat |
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| | Removal Caused by Accumulator Nitrogen Injection." The event described |
| | |
| | above introduces a subtle failure scenario which licensees may not have |
| | |
| | considered. |
| | |
| | IN 90-06 January 29, 1990 This information notice requires no specific action or written response. If |
| | |
| | you have any questions about the information in this notice, please contact |
| | |
| | one of the technical contacts listed below or the appropriate NRR project manager. |
| | |
| | Charles E. Rossi, irector |
| | |
| | Division of Operational Events Assessment |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: Nick Fields, NRR |
| | |
| | (301) 492-1173 Steve Bitter, RIV |
| | |
| | (817) 897-1500 |
| | Attachment: List of Recently Issued NRC Information Notices |
| | |
| | I |
| | |
| | IN 90-06 January 29, 1990 During this event, there were no indications of pump air ingestion However |
| | |
| | the increased system flow enrraenan~nA n~ -~ neto. Hwvr |
| | |
| | Attachment ~ |
| | q ) sx 90-06 Jasmary 2§ 1990 |
| | Page I of I |
| | |
| | LIST OF RECEITLT ISSUED |
| | |
| | NIR INFORtAT1011 OTICES |
| | |
| | JCW -- |
| | lnfonation Issuance Issued te |
| | |
| | Notice No. SubJect |
| | |
| | 90-05 Inter-System Discharge of 1/26/9O All holders of ULs |
| | |
| | Reactor Coelant or Ch for nuclear |
| | |
| | power reactors. |
| | |
| | 90-04 Cracking of the Upper Shall- 1/26/90 All holders of OLs |
| | |
| | to-Transition Cone Girth or CPs.for Westinghouse. |
| | |
| | Melds Is Steam Generators designed and Combustion |
| | |
| | Engineering-disigned |
| | |
| | nuclear power reactors. |
| | |
| | 90-03 malfunction of Borg-Varner 1/23/90 All holders of OLs |
| | |
| | SBlted Sonnet Check Valves or CPs for uclewr |
| | |
| | Causd by Failure of the power reactors. |
| | |
| | Swing Arm |
| | |
| | 90-02 Potential Degradation of 1/29D All holders of OLs |
| | |
| | Secondary Contaient or CPs for Slis. |
| | |
| | 90-01 lIportace of Proper 1/12/90 All holders of NRC |
| | |
| | Response to Self-Identifted materials licenses. |
| | |
| | Violations by Licensees |
| | |
| | 89-90 Pressurizer Safety Valv 12/28/84 All holder of OMs |
| | |
| | Lift Setpoint Shift or Ch for Pilb. |
| | |
| | 89-8 Event Notificatton 12/26/89 All holders of CLs |
| | |
| | Workshents or en for nuclear |
| | |
| | powerreactors. |
| | |
| | 89-88 Recent XRC-Sponsored 12/26189 All holders of Ots |
| | |
| | Testing of motor-Operated or CPsfor nutlear |
| | |
| | Valves poer reactors. |
| | |
| | 8647 Disablilg of Emergency 12/19189 All helders of OLs |
| | |
| | Diesel Generators by or CVs for nuclear |
| | |
| | Their Neutral Ground-Fault power reactors. |
| | |
| | Protection Circuitry |
| | |
| | 8945. etalclad. Lou-Voltage 12/IS/19 All holders of OLs |
| | |
| | Supp. 2 Power Circuit Dreakars or CPsfor nuclear |
| | |
| | Refurbished with power reactors. |
| | |
| | Substandard Parts |
| | |
| | OL*OpitunceS - _ |
| | CV s Construction Permit |
| | |
| | UNITED STATES |
| | |
| | IPOSTAGE & FEES PAOID |
| | |
| | NUCLEAR REGULATORY COMMISSION ISNiRC 1 WASHINGTON, D.C. 20555 OFFICIAL BUSINESS |
| | |
| | PENALTY FOR PRIVATE USE. 8300 |
| | |
| | IN 90-06 January 29, 1990 This information notice requires no specific action or written response. If |
| | |
| | you have any questions about the information in this notice, please contact |
| | |
| | one of the technical contacts listed below or the appropriate NRR project manager. |
| | |
| | Charles E. Rossi, Director |
| | |
| | Division of Operational Events Assessment |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: Nick Fields, NRR |
| | |
| | (301) 492-1173 Steve Bitter, RIV |
| | |
| | (817) 897-1500 |
| | Attachment: List of Recently Issued NRC Information Notices |
| | |
| | *SEE PREVIOUS CONCURRENCE |
| | |
| | EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR NRR:SRXB |
| | |
| | *NFields: db *BCalure *DCFischer *CJHaughney *CHBerlinger *RJones |
| | |
| | 1/12/90 1/13/90 1/16/90 1/16/90 1/17/90 1/23/90 |
| | 1/Z3'90 |
| | |
| | K)j V%2IN 90- |
| | January , 1990 No specific action or written response is required by this information notice. |
| | |
| | If you have any questions about this matter, please contact one of the technical |
| | |
| | contacts listed below or the Regional Administrator of the appropriate regional |
| | |
| | office. |
| | |
| | Charles E. Rossi, Director |
| | |
| | Division of Operational Events Assessment |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: Nick Fields (301) 492-1173 Steve Bitter (817) 897-1500 |
| | Attachment: List of Recently Issued NRC Information Notices |
|
| |
|
| IN 90-06January 29, 1990 During this event, there were no indications of pump air ingestion. However,the increased system flow corresponded to the rate at which vortexing hadbeen calculated to occur based on the existing RCS level. The licensee hadpreviously determined maximum permitted flow rates for various reduced levelsof the RCS to prevent the possibility of vortexing and air entrainment intothe RHR pump.Although RHR pump operation was never actually impaired, the potential existedfor air to be introduced to the pump's suction. This concern is exacerbated by* the fact that the heat exchanger FCVs for both trains of RHR are powered fromthe same inverter. Since the FCVs open fully on a loss of power, both trainsof RHR could become inoperable on a loss of power during mid-loop operation.(A loss of instrument air would also cause the FCVs to fail to the full openposition and could also result in the loss of both trains of the RHR system).During most modes of operation, having the FCVs go -fully open on loss ofpower or instrument air is not a safety concern because having the valvesfully open does not normally prevent the system from performing its safetyfunction. However, having the valves go fully open while at mid-loop couldresult in the loss of decay heat removal capability. This loss could persistuntil electrical power or instrument air is restored and air is vented fromthe RHR system.The licensee has revised procedures for mid-loop operation to require manuallypositioning the cold leg injection isolation valves to limit the maximum flowthrough the system, even with the FCVs fully open. This lineup will be usedwhenever the unit is at mid-loop and protects against the consequences offailure of either electrical power or instrument air.Several generic communications have been issued informing licensees of theconsequences of the loss of residual (decay) heat removal and the operatingconditions under which the probability of a loss increases; i.e., reducedinventory conditions. The most recent publications include Generic Letter(GL) No. 87-12, "Loss of Decay Heat Removal While the Reactor Coolant Systemis Partially Filled;" GL No. 88-17, *Loss of Decay Heat Removal;" NRC In-formation Notice (IN) 87-23, "Loss of Decay Heat Removal During Low ReactorCoolant Level Operation;" IN 88-36, 'Possible Sudden Loss of RCS InventoryDuring Low Coolant Level Operation;" and IN 89-67, "Loss of Residual HeatRemoval Caused by Accumulator Nitrogen Injection." The event describedabove introduces a subtle failure scenario which licensees may not haveconsidered.
| | *SEE PREVIOUS CONCURRENCE |
|
| |
|
| IN 90-06January 29, 1990 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate NRR project manager.Charles E. Rossi, irectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical Contacts: Nick Fields, NRR(301) 492-1173Steve Bitter, RIV(817) 897-1500Attachment:List of Recently Issued NRC Information Notices
| | EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR N R B |
|
| |
|
| IIN 90-06January 29, 1990 During this event, there were no indications of pump air ingestion Howeverthe increased system flow enrraenan~nA n~ -~ neto. HwvrAttachment ~q ) sx 90-06Jasmary 2§ 1990Page I of ILIST OF RECEITLT ISSUEDNIR INFORtAT1011 OTICESJCW --lnfonationNotice No.90-0590-04SubJectInter-System Discharge ofReactor CoelantIssuance1/26/9OCracking of the Upper Shall- 1/26/90to-Transition Cone GirthMelds Is Steam GeneratorsIssued teAll holders of ULsor Ch for nuclearpower reactors.All holders of OLsor CPs.for Westinghouse.designed and CombustionEngineering-disignednuclear power reactors.All holders of OLsor CPs for uclewrpower reactors.All holders of OLsor CPs for Slis.All holders of NRCmaterials licenses.90-03 malfunction of Borg-VarnerSBlted Sonnet Check ValvesCausd by Failure of theSwing Arm90-02 Potential Degradation ofSecondary Contaient90-01 lIportace of ProperResponse to Self-IdentiftedViolations by Licensees89-90 Pressurizer Safety ValvLift Setpoint Shift89-8 Event NotificattonWorkshents89-88 Recent XRC-SponsoredTesting of motor-OperatedValves8647 Disablilg of EmergencyDiesel Generators byTheir Neutral Ground-FaultProtection Circuitry8945. etalclad. Lou-VoltageSupp. 2 Power Circuit DreakarsRefurbished withSubstandard Parts1/23/901/29D1/12/9012/28/84 All holder of OMsor Ch for Pilb.12/26/89 All holders of CLsor en for nuclearpower reactors.12/26189 All holders of Otsor CPs for nutlearpoer reactors.12/19189 All helders of OLsor CVs for nuclearpower reactors.12/IS/1 9 All holders of OLsor CPs for nuclearpower reactors.OL*OpitunceS -_CV s Construction PermitUNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D.C. 20555OFFICIAL BUSINESSPENALTY FOR PRIVATE USE. 8300IPOSTAGE & FEES PAOIDISNiRC1 IN 90-06January 29, 1990 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate NRR project manager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical Contacts:Nick Fields, NRR(301) 492-1173Steve Bitter, RIV(817) 897-1500Attachment:List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEEAB:NRR*NFields: db1/12/90TECH:EDITOR*BCalure1/13/90EAB:NRR C:EAB:NRR*DCFischer *CJHaughney1/16/90 1/16/90C:OGCB:NRR*CHBerlinger1/17/90NRR:SRXB*RJones1/23/901 /Z3'90
| | *DCFischer *CJHaughney* *CHBerlinger RJV es |
| K)jV%2IN 90-January , 1990 No specific action or written response is required by this informationIf you have any questions about this matter, please contact one of thecontacts listed below or the Regional Administrator of the appropriateoffice.notice.technicalregionalCharles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical Contacts:Nick Fields (301) 492-1173Steve Bitter (817) 897-1500Attachment: List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEEAB:NRR*NFields:db/ /90D:DOEA:NRRCERossi/ /90TECH:EDITOR*BCalure/ /90EAB:NRR*DCFischer/ /90C:EAB:NRR*CJHaughney*/ /90C:OGCB:NRR*CHBerlinger/ /90N R BRJV esI j:/90
| | |
| IN 90-January , 1990%...Z'age 3 of 3No specific action or written response is required by thisinfornation notice. If you have any questions about this matter,please contact the technical contact listed below or the RegionalAdministrator of the appropriate regional office.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical Contacts:Nick Fields (301) 492-1173Steve Bitter (817) 897-1500List of Recently Issued NRC Information NoticesAttachment:AJFEAB:NRRNFields:dbJr //,/90C0Wvtn Au tVIU46x1 4fhire0rAtU rAITECH:EDITOR EAB:NRRDCFischerI /11/SQ , /14/90C:EAB:NRRCJHaughneyI /14/90CVC:OGCB:NRRCHBerlinger/ 117/90D:DOEA:NRRCERossi/ /90 | | *NFields:db *BCalure |
| }} | | |
| | / /90 / /90 / /90 / /90 / /90 I j:/90 |
| | D:DOEA:NRR |
| | |
| | CERossi |
| | |
| | / /90 |
| | |
| | IN 90- |
| | January , 1990 |
| | %...Z'age 3 of 3 No specific action or written response is required by this |
| | |
| | infornation notice. If you have any questions about this matter, please contact the technical contact listed below or the Regional |
| | |
| | Administrator of the appropriate regional office. |
| | |
| | Charles E. Rossi, Director |
| | |
| | Division of Operational Events Assessment |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: Nick Fields (301) 492-1173 Steve Bitter (817) 897-1500 |
| | Attachment: List of Recently Issued NRC Information Notices |
| | |
| | C0Wvtn Au t |
| | |
| | AJF VIU46x1 4fhire0rAtU rAI CV |
| | |
| | EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR D:DOEA:NRR |
| | |
| | NFields:db DCFischer CJHaughney CHBerlinger CERossi |
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| | Jr //,/90 I /11/SQ , /14/90 I /14/90 / 117/90 / /90}} |
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| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Potential for Loss of Shutdown Cooling While at Low Reactor Coolant LevelsML031130325 |
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, 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, 05000000, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
01/29/1990 |
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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-90-006, NUDOCS 9001230175 |
Download: ML031130325 (7) |
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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 [[: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 [[: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 [[:05000000]] 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 [[: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 [[:05000000]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 January 29, 1990
SHUTDOWN COOLING
NRC INFORMATION NOTICE NO. 90-06: POTENTIAL FOR LOSS OF COOLANT LEVELS
WHILE AT LOW REACTOR
Addressees
nuclear power
All holders of operating licenses or construction permits for
reactors.
Purpose
to a potential problem
This information notice is intended to alert addressees (RHR) system during
affecting the operability of the residual heat removal
is expected that re- operating conditions involving mid-loop operation. It to their facilities
-cipients will review the information for applicability problems. However, and consider actions, as appropriate, to avoid similar constitute NRC
suggestions contained in this information notice do not
response is required.
requirements; therefore, no specific action or written
Description of Circumstances
the residual heat
On July 18, 1989, at Comanche Peak Unit 1, train 'Al ofloading. The air
removal system was in operation prior to initial fuel
being used to
operated RHR heat exchanger flow control valve (FCV) was water level was
maintain system flow below 2000 gpm. The reactor vessel
legs.
being maintained slightly abpve the center line of the hot
FCV failed. The loss
The inverter supplying power to the controller for the to its emergency core
of power to the controller resulted in the FCV failing open valve caused
cooling system (ECCS) position of being fully open. The flow caused
an increase in system flow to 4400 gpm. This sudden, increased
the RHR pipe con- conditions where vortexing was expected at the suction of
nection to the RCS.
to an alternate
The power supply for the controllers was manually transferred
terminating the event.
source and the FCV was throttled, thus
Discussion:
flow through the
The FCV is manually throttled to maintain a desired rate of to control the
RHR heat exchanger. The heat exchanger flow rate is adjusted
to the vessel. Total system flow is
temperature of the water being returned with the
regulated by throttling the heat exchanger bypass valve coincident
adjustment of the FCV.
001230175 Z ((
' D*1 IC,
eo uachr
IN 90-06 January 29, 1990 During this event, there were no indications of pump air ingestion. However, the increased system flow corresponded to the rate at which vortexing had
been calculated to occur based on the existing RCS level. The licensee had
previously determined maximum permitted flow rates for various reduced levels
of the RCS to prevent the possibility of vortexing and air entrainment into
the RHR pump.
Although RHR pump operation was never actually impaired, the potential existed
for air to be introduced to the pump's suction. This concern is exacerbated by
- the fact that the heat exchanger FCVs for both trains of RHR are powered from
the same inverter. Since the FCVs open fully on a loss of power, both trains
of RHR could become inoperable on a loss of power during mid-loop operation.
(A loss of instrument air would also cause the FCVs to fail to the full open
position and could also result in the loss of both trains of the RHR system).
During most modes of operation, having the FCVs go -fully open on loss of
power or instrument air is not a safety concern because having the valves
fully open does not normally prevent the system from performing its safety
function. However, having the valves go fully open while at mid-loop could
result in the loss of decay heat removal capability. This loss could persist
until electrical power or instrument air is restored and air is vented from
the RHR system.
The licensee has revised procedures for mid-loop operation to require manually
positioning the cold leg injection isolation valves to limit the maximum flow
through the system, even with the FCVs fully open. This lineup will be used
whenever the unit is at mid-loop and protects against the consequences of
failure of either electrical power or instrument air.
Several generic communications have been issued informing licensees of the
consequences of the loss of residual (decay) heat removal and the operating
conditions under which the probability of a loss increases; i.e., reduced
inventory conditions. The most recent publications include Generic Letter
(GL) No. 87-12, "Loss of Decay Heat Removal While the Reactor Coolant System
is Partially Filled;" GL No. 88-17, *Loss of Decay Heat Removal;" NRC In- formation Notice (IN)87-23, "Loss of Decay Heat Removal During Low Reactor
Coolant Level Operation;" IN 88-36, 'Possible Sudden Loss of RCS Inventory
During Low Coolant Level Operation;" and IN 89-67, "Loss of Residual Heat
Removal Caused by Accumulator Nitrogen Injection." The event described
above introduces a subtle failure scenario which licensees may not have
considered.
IN 90-06 January 29, 1990 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate NRR project manager.
Charles E. Rossi, irector
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Nick Fields, NRR
(301) 492-1173 Steve Bitter, RIV
(817) 897-1500
Attachment: List of Recently Issued NRC Information Notices
I
IN 90-06 January 29, 1990 During this event, there were no indications of pump air ingestion However
the increased system flow enrraenan~nA n~ -~ neto. Hwvr
Attachment ~
q ) sx 90-06 Jasmary 2§ 1990
Page I of I
LIST OF RECEITLT ISSUED
NIR INFORtAT1011 OTICES
JCW --
lnfonation Issuance Issued te
Notice No. SubJect
90-05 Inter-System Discharge of 1/26/9O All holders of ULs
Reactor Coelant or Ch for nuclear
power reactors.
90-04 Cracking of the Upper Shall- 1/26/90 All holders of OLs
to-Transition Cone Girth or CPs.for Westinghouse.
Melds Is Steam Generators designed and Combustion
Engineering-disigned
nuclear power reactors.
90-03 malfunction of Borg-Varner 1/23/90 All holders of OLs
SBlted Sonnet Check Valves or CPs for uclewr
Causd by Failure of the power reactors.
Swing Arm
90-02 Potential Degradation of 1/29D All holders of OLs
Secondary Contaient or CPs for Slis.
90-01 lIportace of Proper 1/12/90 All holders of NRC
Response to Self-Identifted materials licenses.
Violations by Licensees
89-90 Pressurizer Safety Valv 12/28/84 All holder of OMs
Lift Setpoint Shift or Ch for Pilb.
89-8 Event Notificatton 12/26/89 All holders of CLs
Workshents or en for nuclear
powerreactors.
89-88 Recent XRC-Sponsored 12/26189 All holders of Ots
Testing of motor-Operated or CPsfor nutlear
Valves poer reactors.
8647 Disablilg of Emergency 12/19189 All helders of OLs
Diesel Generators by or CVs for nuclear
Their Neutral Ground-Fault power reactors.
Protection Circuitry
8945. etalclad. Lou-Voltage 12/IS/19 All holders of OLs
Supp. 2 Power Circuit Dreakars or CPsfor nuclear
Refurbished with power reactors.
Substandard Parts
OL*OpitunceS - _
CV s Construction Permit
UNITED STATES
IPOSTAGE & FEES PAOID
NUCLEAR REGULATORY COMMISSION ISNiRC 1 WASHINGTON, D.C. 20555 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE. 8300
IN 90-06 January 29, 1990 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Nick Fields, NRR
(301) 492-1173 Steve Bitter, RIV
(817) 897-1500
Attachment: List of Recently Issued NRC Information Notices
EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR NRR:SRXB
- NFields: db *BCalure *DCFischer *CJHaughney *CHBerlinger *RJones
1/12/90 1/13/90 1/16/90 1/16/90 1/17/90 1/23/90
1/Z3'90
K)j V%2IN 90-
January , 1990 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact one of the technical
contacts listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Nick Fields (301) 492-1173 Steve Bitter (817) 897-1500
Attachment: List of Recently Issued NRC Information Notices
EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR N R B
- DCFischer *CJHaughney* *CHBerlinger RJV es
/ /90 / /90 / /90 / /90 / /90 I j:/90
D:DOEA:NRR
CERossi
/ /90
IN 90-
January , 1990
%...Z'age 3 of 3 No specific action or written response is required by this
infornation notice. If you have any questions about this matter, please contact the technical contact listed below or the Regional
Administrator of the appropriate regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Nick Fields (301) 492-1173 Steve Bitter (817) 897-1500
Attachment: List of Recently Issued NRC Information Notices
C0Wvtn Au t
AJF VIU46x1 4fhire0rAtU rAI CV
EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR D:DOEA:NRR
NFields:db DCFischer CJHaughney CHBerlinger CERossi
Jr //,/90 I /11/SQ , /14/90 I /14/90 / 117/90 / /90
|
---|
|
list | - Information Notice 1990-01, Importance of Proper Response to Self-Identified Violations by Licensees (12 January 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-02, Potential Degradation of Secondary Containment (22 January 1990)
- Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm (23 January 1990, Topic: Liquid penetrant)
- Information Notice 1990-04, Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, (26 January 1990, Topic: Nondestructive Examination, Thermal fatigue)
- Information Notice 1990-05, Inter-System Discharge of Reactor Coolant (29 January 1990)
- Information Notice 1990-06, Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels (29 January 1990)
- Information Notice 1990-07, New Information Regarding Insulation Material Performance and Debris Blockage of PWR Containment Sumps (30 January 1990)
- Information Notice 1990-08, KR-85 Hazards from Decayed Fuel (1 February 1990)
- Information Notice 1990-08, KR-85 Hazards From Decayed Fuel (1 February 1990)
- Information Notice 1990-09, Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees (5 February 1990, Topic: Decommissioning Funding Plan, Uranium Hexafluoride)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Liquid penetrant)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-11, Maintenance Deficiency Associated with Solenoid-Operated Valves (28 February 1990)
- Information Notice 1990-12, Monitoring or Interruption of Plant Communications (28 February 1990)
- Information Notice 1990-13, Importance of Review and Analysis of Safeguards Event Logs (5 March 1990)
- Information Notice 1990-14, Accidental Disposal of Radioactive Materials (6 March 1990, Topic: Brachytherapy)
- Information Notice 1990-15, Reciprocity Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States (17 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-16, Compliance with New Decommissioning Rule (7 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-17, Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves (8 March 1990, Topic: Earthquake)
- Information Notice 1990-18, Potential Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-18, Potential Problems With Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-19, Potential Loss of Effective Volume for Containment Recirculation Spray at PWR Facilities (14 March 1990)
- Information Notice 1990-20, Personnel Injuries Resulting from Improper Operation of Radwaste Incinerators (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction was Underestimated (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction Was Underestimated (22 March 1990)
- Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units (23 March 1990, Topic: Reactor Vessel Water Level)
- Information Notice 1990-23, Improper Installation of Patel Conduit Seals (4 April 1990)
- Information Notice 1990-24, Transportation of Model Spec 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-25, Loss of Vital AC Power With Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-26, Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems (24 April 1990)
- Information Notice 1990-27, Clarification of the Recent Revisions to the Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for Transportation (30 April 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-28, Potential Error In High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-28, Potential Error in High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head (30 April 1990, Topic: Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-30, Ultrasonic Inspection Techniques for Dissimilar Metal Welds (1 May 1999, Topic: Dissimilar Metal Weld)
- Information Notice 1990-31, Update on Waste Form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-31, Update on Waste form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head (3 May 1990)
- Information Notice 1990-33, Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools (9 May 1990, Topic: Overexposure)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990, Topic: Siren)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990, Topic: Siren)
- Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990)
- Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990, Topic: Authorized possession limits)
- Information Notice 1990-39, Recent Problems with Service Water Systems (1 June 1990)
- Information Notice 1990-40, Results of NRC-Sponsored Testing of Motor-Operated Valves (5 June 1990, Topic: Weak link)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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