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| | issue date = 06/12/1996 | | | issue date = 06/12/1996 |
| | title = Degradation of Cooling Water Systems Due to Icing | | | title = Degradation of Cooling Water Systems Due to Icing |
| | author name = Grimes B K | | | author name = Grimes B |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = | | | addressee name = |
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| | page count = 11 | | | page count = 11 |
| }} | | }} |
| {{#Wiki_filter:"J June 12, 1996NRC INFORMATION NOTICE 96-36: DEGRADATION OF COOLING WATER SYSTEMS DUE TOICING | | {{#Wiki_filter:"J |
| | |
| | UNITED STATES |
| | |
| | NUCLEAR REGULATORY COMMISSION |
| | |
| | OFYFICE OF NUCLEAR REACTOR REGULATION |
| | |
| | - WASHINGTON, DC 20555-0001 June 12, 1996 NRC INFORMATION NOTICE 96-36: DEGRADATION OF COOLING WATER SYSTEMS DUE TO |
| | |
| | ICING |
|
| |
|
| ==Addressees== | | ==Addressees== |
| All holders of operating licenses or construction permits for nuclear powerreactors. | | All holders of operating licenses or construction permits for nuclear power |
| | |
| | reactors. |
|
| |
|
| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to potential degradation of facility water intakesystems (circulating, service, and fire water) due to icing conditions.It is expected that recipients will review the information for applicabilityto their facilities and consider actions, as appropriate, to avoid similarproblems. However, suggestions contained in this information notice are notNRC requirements; therefore, no specific action or written response isrequired. | | The U.S. Nuclear Regulatory Commission (NRC) is issuing this information |
| | |
| | notice to alert addressees to potential degradation of facility water intake |
| | |
| | systems (circulating, service, and fire water) due to icing conditions. |
| | |
| | It is expected that recipients will review the information for applicability |
| | |
| | to their facilities and consider actions, as appropriate, to avoid similar |
| | |
| | problems. However, suggestions contained in this information notice are not |
| | |
| | NRC requirements; therefore, no specific action or written response is |
| | |
| | required. |
|
| |
|
| ==Description of Circumstances== | | ==Description of Circumstances== |
| Wolf CreekBetween 1:45 a.m. and 2:45 a.m. (all times central standard time) onJanuary 30, 1996, operators at Wolf Creek received alarms indicating that thecirculating water system traveling screens were becoming blocked. A visualinspection showed that the traveling screens for bays 1 and 3 were frozen andthat water levels in these bays were approximately 2.5 m [8 ft] below normal.The emergency service water system was started with the intent to separatethis system from the service water system. However, the emergency servicewater system was incorrectly aligned; flow was directed to the service watersystem and warming flow to the emergency service water system suction bays wasrestricted. Operators also shifted to circulating water pump B. At approxi-mately 3:30 a.m., operators received a service water pressure alarm and anelectric fire pump started on low service water pressure. The shift super-visor then directed a manual reactor/turbine trip. Circulating water systembays were subsequently determined to be at 3.5 m [12 feet] below normal. Thelevel loss was caused by water from the spray wash system freezing and block-ing the traveling screens.The Train A emergency service water system pump was tripped and declaredinoperable at 7:47 a.m. because of low discharge pressure and high strainerdifferential pressure. At about 8:00 a.m., the supervising operator coming onshift noted the incorrect alignment of the emergency service water system andtook action to correct it. At about 5:45 p.m., the operators declared Train A'~P) C-FW 0f bla .pDR :t:-E moric6 6'sVOU 160612 ' | | Wolf Creek |
| 1.'K)IN 96-36June 12, 1996 operable on the basis of an engineering evaluation and placed it in service.However, the pump was again stopped 1-1/2 hours later at approximately7:30 p.m. when the pump exhibited further oscillations in flow and pressure.At approximately 8:00 p.m., operators noted that emergency service watersystem Train B suction bay level was 4.5 m [15 ft] below normal and decreasingslowly. Operators placed additional heat loads on Train B and the suction baylevels subsequently recovered. At 10:14 p.m., the operators again startedTrain A emergency service water system and secured it at 10:27 p.m. due todecreasing flow and pressure.At about 10:00 a.m. on January 31, divers inspected the suction bay of Train Aand noted complete blockage of the trash racks by frazil ice. Train B was notinspected because the pump was running. The ice blockage was cleared by4:00 p.m. by sparging the trash racks with air. The emergency service watersystem was designed to have warming flow injected in front of trash racks toincrease bulk water temperature and prevent the formation of frazil ice. Dueto calculational errors by the architect-engineer and the as-built systemconfiguration, the emergency service water system warming flow wasinsufficient to prevent frazil ice from forming at the Train A trash racks.FitzPatrickOn February 25, 1993, at 1:25 a.m., the electric fire pump started on low fireheader pressure. After verifying normal fire header pressure, operatorssecured the electric fire pump, and the diesel fire pumps subsequently startedon low header pressure. It was later determined that the fire jockey pump hadlost suction because of the decreasing screenwell level.Over the next several minutes, operators noted an increase in circulatingwater system motor amperage (which is consistent with decreased suctionpressure). Reactor power was also reduced and one circulating water pump wassecured. At 1:40 a.m., an operator reported that the screenwell level wasapproximately 3 m [10 ft] below normal and the reactor was manually scrammed.After a second circulating water pump was subsequently secured, the screenwellwater level quickly recovered. The licensee concluded that the reducedscreenwell level had been caused by ice partially blocking the lake intakestructure. Either frazil ice formed around or in front of the heated intakebar racks, or slush ice was present in front of the bar racks.FermiOn February 5, 1996, at approximately 2:30 p.m., diesel generator servicewater pump C failed to develop normal discharge pressure, flow, and motorcurrent during a surveillance. This made Division I emergency dieselgenerator (EDG) 12 inoperable. After several unsuccessful attempts to startthe pump, an air purge of the pump column on the discharge of the pump wasinitiated in an attempt to clear any obstruction in the column or the pumpinlet. The licensee detected blockage when it tried to blow air through thepipe. At 8:21 p.m., the pump was started and after 3 to 5 seconds an erraticdischarge pressure was noted. In a short time, pump flow, discharge pressure,and motor amps were normal. The following day, on February 6, dieselgenerator service water pump B was started. The pump, which cools Division II K> < IN 96-36June 12, 1996 EDG 13, showed no flow, no pressure, and low amperage for the first30 seconds. After approximately 90 seconds, normal flow discharge pressureand motor current were achieved. The remaining safety-related pumps weretested satisfactorily.The diesel generator service water pumps are all deep-draft pumps and takesuction from the ultimate heat sink reservoir which is a segregated pool. Thelicensee evaluation concluded that although the reservoir temperatures aremaintained above 5 eC [41 OF], part of the pump column and two of the linearguide bearings are located above the water level and are exposed to ambientair temperature conditions. The failure of the diesel generator service waterpump C was attributed to ice buildup around the shaft and spider bearing fromleakage past the discharge check valve and the cold weather. The licenseealso concluded that under some credible meteorological conditions, thefunctions of both divisions could have been affected.DiscussionFrazil icing is a phenomenon that affects the operation of intake structuresin regions that experience cold weather. The accumulation of frazil ice onintake trash racks can completely block the flow of water into the intake.The process starts when the water flowing into the intake is supercooled (acondition where the water is below the freezing point). The supercooling maybe very small, on the order of a few hundredths of a degree.The supercooling occurs with a loss of heat from a large surface area such asa lake with open water and clear nights. High winds contribute to the problemby providing mixing of the supercooled water to depths as great as 6 to 9 m[20 to 30 ft]. The frazil ice, which is composed of very small crystals(1-15 mm) with little buoyancy because of their size, is carried along in thewater and mixed all through the supercooled water.The suction of the supercooled water and the suspended frazil ice crystalsthrough an intake structure brings the frazil ice crystals in contact with thetrash rack bars. Frazil ice crystals easily adhere to any object with whichthey collide. The ice collects first on the upstream side of the trash racks,then steadily grows until the space between the trash racks is bridged. Thisbridging rapidly blocks the trash racks. The accumulation of ice can with-stand high differential pressures; effectively damming the intake suction.Facility vulnerability to icing events is a function of plant design. Fraziland other ice formation is dependent on specific environmental conditions andrepresents a potential common-mode failure that can cause the loss or degrada-tion of multiple cooling water systems, including the potential loss of theultimate heat sin IN 96-36June 12, 1996 Related InformationNUREG/CR-0548, "Ice Blockage of Water Intakes."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 Office ofNuclear Reactor Regulation project manager.Ii -..--.....-.Brian K. Grimes, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical Contacts:John R. Tappert, NRR(301) 415-1167Internet:jrtlnrc.govBruce Jorgensen, RIII(708) 829-9615Internet:blj@nrc.gov | | |
| | Between 1:45 a.m. and 2:45 a.m. (all times central standard time) on |
| | |
| | January 30, 1996, operators at Wolf Creek received alarms indicating that the |
| | |
| | circulating water system traveling screens were becoming blocked. A visual |
| | |
| | inspection showed that the traveling screens for bays 1 and 3 were frozen and |
| | |
| | that water levels in these bays were approximately 2.5 m [8 ft] below normal. |
| | |
| | The emergency service water system was started with the intent to separate |
| | |
| | this system from the service water system. However, the emergency service |
| | |
| | water system was incorrectly aligned; flow was directed to the service water |
| | |
| | system and warming flow to the emergency service water system suction bays was |
| | |
| | restricted. Operators also shifted to circulating water pump B. At approxi- mately 3:30 a.m., operators received a service water pressure alarm and an |
| | |
| | electric fire pump started on low service water pressure. The shift super- visor then directed a manual reactor/turbine trip. Circulating water system |
| | |
| | bays were subsequently determined to be at 3.5 m [12 feet] below normal. The |
| | |
| | level loss was caused by water from the spray wash system freezing and block- ing the traveling screens. |
| | |
| | The Train A emergency service water system pump was tripped and declared |
| | |
| | inoperable at 7:47 a.m. because of low discharge pressure and high strainer |
| | |
| | differential pressure. At about 8:00 a.m., the supervising operator coming on |
| | |
| | shift noted the incorrect alignment of the emergency service water system and |
| | |
| | took action to correct it. At about 5:45 p.m., the operators declared Train A |
| | |
| | '~P) bla 0f . |
| | |
| | C-FW |
| | |
| | pDR :t:-E moric6 6'sVOU 160612 ' |
| | |
| | 1.' K) |
| | IN 96-36 June 12, 1996 operable on the basis of an engineering evaluation and placed it in service. |
| | |
| | However, the pump was again stopped 1-1/2 hours later at approximately |
| | |
| | 7:30 p.m. when the pump exhibited further oscillations in flow and pressure. |
| | |
| | At approximately 8:00 p.m., operators noted that emergency service water |
| | |
| | system Train B suction bay level was 4.5 m [15 ft] below normal and decreasing |
| | |
| | slowly. Operators placed additional heat loads on Train B and the suction bay |
| | |
| | levels subsequently recovered. At 10:14 p.m., the operators again started |
| | |
| | Train A emergency service water system and secured it at 10:27 p.m. due to |
| | |
| | decreasing flow and pressure. |
| | |
| | At about 10:00 a.m. on January 31, divers inspected the suction bay of Train A |
| | |
| | and noted complete blockage of the trash racks by frazil ice. Train B was not |
| | |
| | inspected because the pump was running. The ice blockage was cleared by |
| | |
| | 4:00 p.m. by sparging the trash racks with air. The emergency service water |
| | |
| | system was designed to have warming flow injected in front of trash racks to |
| | |
| | increase bulk water temperature and prevent the formation of frazil ice. Due |
| | |
| | to calculational errors by the architect-engineer and the as-built system |
| | |
| | configuration, the emergency service water system warming flow was |
| | |
| | insufficient to prevent frazil ice from forming at the Train A trash racks. |
| | |
| | FitzPatrick |
| | |
| | On February 25, 1993, at 1:25 a.m., the electric fire pump started on low fire |
| | |
| | header pressure. After verifying normal fire header pressure, operators |
| | |
| | secured the electric fire pump, and the diesel fire pumps subsequently started |
| | |
| | on low header pressure. It was later determined that the fire jockey pump had |
| | |
| | lost suction because of the decreasing screenwell level. |
| | |
| | Over the next several minutes, operators noted an increase in circulating |
| | |
| | water system motor amperage (which is consistent with decreased suction |
| | |
| | pressure). Reactor power was also reduced and one circulating water pump was |
| | |
| | secured. At 1:40 a.m., an operator reported that the screenwell level was |
| | |
| | approximately 3 m [10 ft] below normal and the reactor was manually scrammed. |
| | |
| | After a second circulating water pump was subsequently secured, the screenwell |
| | |
| | water level quickly recovered. The licensee concluded that the reduced |
| | |
| | screenwell level had been caused by ice partially blocking the lake intake |
| | |
| | structure. Either frazil ice formed around or in front of the heated intake |
| | |
| | bar racks, or slush ice was present in front of the bar racks. |
| | |
| | Fermi |
| | |
| | On February 5, 1996, at approximately 2:30 p.m., diesel generator service |
| | |
| | water pump C failed to develop normal discharge pressure, flow, and motor |
| | |
| | current during a surveillance. This made Division I emergency diesel |
| | |
| | generator (EDG) 12 inoperable. After several unsuccessful attempts to start |
| | |
| | the pump, an air purge of the pump column on the discharge of the pump was |
| | |
| | initiated in an attempt to clear any obstruction in the column or the pump |
| | |
| | inlet. The licensee detected blockage when it tried to blow air through the |
| | |
| | pipe. At 8:21 p.m., the pump was started and after 3 to 5 seconds an erratic |
| | |
| | discharge pressure was noted. In a short time, pump flow, discharge pressure, and motor amps were normal. The following day, on February 6, diesel |
| | |
| | generator service water pump B was started. The pump, which cools Division II |
| | |
| | K> |
| | < IN 96-36 June 12, 1996 EDG 13, showed no flow, no pressure, and low amperage for the first |
| | |
| | 30 seconds. After approximately 90 seconds, normal flow discharge pressure |
| | |
| | and motor current were achieved. The remaining safety-related pumps were |
| | |
| | tested satisfactorily. |
| | |
| | The diesel generator service water pumps are all deep-draft pumps and take |
| | |
| | suction from the ultimate heat sink reservoir which is a segregated pool. The |
| | |
| | licensee evaluation concluded that although the reservoir temperatures are |
| | |
| | maintained above 5 eC [41 OF], part of the pump column and two of the linear |
| | |
| | guide bearings are located above the water level and are exposed to ambient |
| | |
| | air temperature conditions. The failure of the diesel generator service water |
| | |
| | pump C was attributed to ice buildup around the shaft and spider bearing from |
| | |
| | leakage past the discharge check valve and the cold weather. The licensee |
| | |
| | also concluded that under some credible meteorological conditions, the |
| | |
| | functions of both divisions could have been affected. |
| | |
| | Discussion |
| | |
| | Frazil icing is a phenomenon that affects the operation of intake structures |
| | |
| | in regions that experience cold weather. The accumulation of frazil ice on |
| | |
| | intake trash racks can completely block the flow of water into the intake. |
| | |
| | The process starts when the water flowing into the intake is supercooled (a |
| | |
| | condition where the water is below the freezing point). The supercooling may |
| | |
| | be very small, on the order of a few hundredths of a degree. |
| | |
| | The supercooling occurs with a loss of heat from a large surface area such as |
| | |
| | a lake with open water and clear nights. High winds contribute to the problem |
| | |
| | by providing mixing of the supercooled water to depths as great as 6 to 9 m |
| | |
| | [20 to 30 ft]. The frazil ice, which is composed of very small crystals |
| | |
| | (1-15 mm) with little buoyancy because of their size, is carried along in the |
| | |
| | water and mixed all through the supercooled water. |
| | |
| | The suction of the supercooled water and the suspended frazil ice crystals |
| | |
| | through an intake structure brings the frazil ice crystals in contact with the |
| | |
| | trash rack bars. Frazil ice crystals easily adhere to any object with which |
| | |
| | they collide. The ice collects first on the upstream side of the trash racks, then steadily grows until the space between the trash racks is bridged. This |
| | |
| | bridging rapidly blocks the trash racks. The accumulation of ice can with- stand high differential pressures; effectively damming the intake suction. |
| | |
| | Facility vulnerability to icing events is a function of plant design. Frazil |
| | |
| | and other ice formation is dependent on specific environmental conditions and |
| | |
| | represents a potential common-mode failure that can cause the loss or degrada- tion of multiple cooling water systems, including the potential loss of the |
| | |
| | ultimate heat sink. |
| | |
| | IN 96-36 June 12, 1996 Related Information |
| | |
| | NUREG/CR-0548, "Ice Blockage of Water Intakes." |
| | 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 Office of |
| | |
| | Nuclear Reactor Regulation project manager. |
| | |
| | I |
| | |
| | i - . .- - . . . . . - . |
| | |
| | Brian K. Grimes, Acting Director |
| | |
| | Division of Reactor Program Management |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: John R. Tappert, NRR |
| | |
| | (301) 415-1167 Internet:jrtlnrc.gov |
| | |
| | Bruce Jorgensen, RIII |
| | |
| | (708) 829-9615 Internet:blj@nrc.gov |
| | |
| | Attachment: List of Recently Issued NRC Information Notices |
| | |
| | I |
| | |
| | k W (0%0% J4-c- -d I |
| | |
| | K> |
| | Attachment |
| | |
| | IN 96-36 June 12, 1996 LIST OF RECENTLY ISSUED |
| | |
| | NRC INFORMATION NOTICES |
| | |
| | Information Date of |
| | |
| | Notice No. Subject Issuance Issued to |
| | |
| | 96-35 Failure of Safety Systems 06/11/96 All U.S. Nuclear Regulatory |
| | |
| | on Self-Shielded Irradia- Commission irradiator |
| | |
| | tors Because of Inadequate licensees and vendors |
| | |
| | Maintenance and Training |
| | |
| | 96-34 Hydrogen Gas Ignition 05/31/96 All holders of OLs or CPs |
| | |
| | during Closure Welding for nuclear power reactors |
| | |
| | of a VSC-24 Multi-Assembly |
| | |
| | Sealed Basket |
| | |
| | 96-33 Erroneous Data From 05/24/96 All material and fuel cycle |
| | |
| | Defective Thermocouple licensees that monitor tem- Results ii i a Fire perature with thermocouples |
| | |
| | 96-32 Implementation of 10 CFR 06/05/96 All holders of OLs or CPs |
| | |
| | 50.55a(g)(6)(ii)(A), for nuclear power reactors |
| | |
| | "Augmented Examination |
| | |
| | of Reactor Vessel" |
| | 96-31 Cross-Tied Safety Injec- 05/22/96 All holders of OLs or CPs |
| | |
| | tion Accumulators for pressurized water |
| | |
| | reactors |
| | |
| | 96-30 Inaccuracy of Diagnostic 05/21/96 All holders of OLs or CPs |
| | |
| | Equipment for Motor- for nuclear power reactors |
| | |
| | Operated Butterfly Valves |
| | |
| | 96-29 Requirements in 10 CFR 05/20/96 All holders of OLs or CPs |
| | |
| | Part 21 for Reporting and for nuclear power reactors |
| | |
| | Evaluating Software Errors |
| | |
| | 96-28 Suggested Guidance Relating 05/01/96 All material and fuel cycle |
| | |
| | to Development and Imple- licensees |
| | |
| | mentation of Corrective |
| | |
| | Action |
| | |
| | 96-27 Potential Clogging of High 05/01/96 All holders of OLs or CPs |
| | |
| | Pressure Safety Injection for pressurized water |
| | |
| | Throttle Valves During reactors |
| | |
| | Recirculation |
| | |
| | OL - Operating License |
| | |
| | CP = Construction Permit |
| | |
| | IN 96-36 |
| | . I June 12, 1996 Related Information |
| | |
| | NUREG/CR-0548, "Ice Blockage of Water Intakes." |
| | This information notice requires no specific action or written response. If |
|
| |
|
| ===Attachment:===
| | you have any questions about the information in this notice, please contact |
| List of Recently Issued NRC Information NoticesIk W (0%0%J4-c- -dI K>AttachmentIN 96-36June 12, 1996 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to96-35Failure of Safety Systemson Self-Shielded Irradia-tors Because of InadequateMaintenance and TrainingHydrogen Gas Ignitionduring Closure Weldingof a VSC-24 Multi-AssemblySealed Basket06/11/9605/31/96All U.S. Nuclear RegulatoryCommission irradiatorlicensees and vendorsAll holders of OLs or CPsfor nuclear power reactors96-3496-33ErroneousDefectiveResults iiData FromThermocouplei a Fire05/24/96All material and fuel cyclelicensees that monitor tem-perature with thermocouples96-3296-3196-30Implementation of 10 CFR50.55a(g)(6)(ii)(A),"Augmented Examinationof Reactor Vessel"Cross-Tied Safety Injec-tion AccumulatorsInaccuracy of DiagnosticEquipment for Motor-Operated Butterfly ValvesRequirements in 10 CFRPart 21 for Reporting andEvaluating Software ErrorsSuggested Guidance Relatingto Development and Imple-mentation of CorrectiveActionPotential Clogging of HighPressure Safety InjectionThrottle Valves DuringRecirculation06/05/9605/22/9605/21/9605/20/9605/01/9605/01/96All holders of OLs or CPsfor nuclear power reactorsAll holders of OLs or CPsfor pressurized waterreactorsAll holders of OLs or CPsfor nuclear power reactorsAll holders of OLs or CPsfor nuclear power reactorsAll material and fuel cyclelicenseesAll holders of OLs or CPsfor pressurized waterreactors96-2996-2896-27OL -Operating LicenseCP = Construction Permit
| |
|
| |
|
| .IIN 96-36June 12, 1996 Related InformationNUREG/CR-0548, "Ice Blockage of Water Intakes."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 Office ofNuclear Reactor Regulation project manager.Original signed by Brian K. GrimesBrian K. Grimes, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical Contacts:John R. Tappert, NRR(301) 415-1167Internet:jrt@nrc.govBruce Jorgensen, RIII(708) 829-9615Internet:blj@nrc.gov
| | one of the technical contacts listed below or the appropriate Office of |
|
| |
|
| ===Attachment:===
| | Nuclear Reactor Regulation project manager. |
| List of Recently Issued NRC Information NoticesDOCUMENT NAME: 96-36.INTech Editor reviewed 5/1/96To receive a copy ofattachment/enclosure* sthis document, indicate in the box: "C""EN -Copy with attachment/enclosureee Drevious concurrences-Copy without"N" -No coOFFICE | | |
| | Original signed by Brian K.Grimes |
| | |
| | Brian K. Grimes, Acting Director |
| | |
| | Division of Reactor Program Management |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: John R. Tappert, NRR |
| | |
| | (301) 415-1167 Internet:jrt@nrc.gov |
| | |
| | Bruce Jorgensen, RIII |
| | |
| | (708) 829-9615 Internet:blj@nrc.gov |
| | |
| | Attachment: List of Recently Issued NRC Information Notices |
| | |
| | DOCUMENT NAME: 96-36.IN |
| | |
| | Tech Editor reviewed 5/1/96 To receive a copy of this document, indicate in the box: "C"- Copy without |
| | |
| | attachment/enclosure "EN - Copy with attachment/enclosure "N"- No co |
| | |
| | * s ee Drevious concurrences |
| | |
| | OFFICE |
|
| |
|
| ==CONTACT== | | ==CONTACT== |
| S IC C/SRXB:DSSA I C/PECB:DRPM D/JT(S, iNAME JTappert | | S IC C/SRXB:DSSA I C/PECB:DRPM D/JT(S, i |
| | |
| | NAME JTappert * LMarsh * AChaffee* BKf1Tntee' l |
| | |
| | BJorgensen * l |
| | |
| | DATE 5 /2/96 5/14/96 6/5/96 6//(/96 OFFICIAL RECORD COPY |
|
| |
|
| * LMarsh
| | IN 96-XX |
|
| |
|
| * AChaffee* BKf1Tntee' lBJorgensen
| | June XX, 1996 Related information |
|
| |
|
| * lDATE 5 /2/96 5/14/96 6/5/96 6//(/96OFFICIAL RECORD COPY IN 96-XXJune XX, 1996 Related informationNUREG/CR-0548, *Ice Blockage of Water Intakes"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 Office ofNuclear Reactor Regulation project manager.Brian K. Grimes, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical Contacts:John R. Tappert, NRR(301) 415-1167Internet:Jrt@nrc.govBruce Jorgensen, RIII(708) 829-9615Internet:bl Jnrc.gov
| | NUREG/CR-0548, *Ice Blockage of Water Intakes" |
| | This information notice requires no specific action or written response. If |
|
| |
|
| ===Attachment:===
| | you have any questions about the information in this notice, please contact |
| List of Recently Issued NRC Information NoticesDOCUMENT NAME:G:\JRT\WOLFICE.INTech Editor reviewed 5/1/96To receive a copy of this document, indicate in the box: ACTattachment/enclosure 'El -Copy with attachment/enclosure* see orevious concurrences-Copy withoutON" -No copyOFFICE | | |
| | one of the technical contacts listed below or the appropriate Office of |
| | |
| | Nuclear Reactor Regulation project manager. |
| | |
| | Brian K. Grimes, Acting Director |
| | |
| | Division of Reactor Program Management |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: John R. Tappert, NRR Bruce Jorgensen, RIII |
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| | (301) 415-1167 (708) 829-9615 Internet:Jrt@nrc.gov Internet:bl Jnrc.gov |
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| | Attachment: List of Recently Issued NRC Information Notices |
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| | DOCUMENT NAME:G:\JRT\WOLFICE.IN |
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| | Tech Editor reviewed 5/1/96 To receive a copy of this document, indicate in the box: ACT - Copy without |
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| | attachment/enclosure 'El - Copy with attachment/enclosure ON" - No copy |
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| | * see orevious concurrences |
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| | OFFICE |
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| ==CONTACT== | | ==CONTACT== |
| S C C/SRXB:DSSA I C/PECB:DRPM I D/DRPMNAME JTappert | | S C C/SRXB:DSSA I C/PECB:DRPM I D/DRPM |
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| | NAME JTappert * LMarsh * AChaffeer,(, IBGrimes |
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| | BJorgensen * |
| | DATE 5 /2/96 5/14/96 _ _ 6 _6/_/96 UrIU-lAL KLLUKU WO |
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| | IN 96 d |
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| * AChaffeer,(, IBGrimesBJorgensen *DATE 5 /2/96 5/14/96 6 _ _ _6/ _/96UrIU-lAL KLLUKU WO/WY-,*-)
| | NUREG/CR-0548, "Ice Blockage of Water Intakes" |
| -IN 96 dMay XX, 1995 Related-InformationNUREG/CR-0548, "Ice Blockage of Water Intakes"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 Office ofNuclear Reactor Regulation project manager.Brian K. Grimes, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical Contacts:John R. Tappert, NRR(301) 415-1167Internet:jrt@nrc.govBruce Jorgensen, RIII(708) 829-9615Internet:blj@nrc.gov
| | This information notice requires no specific action or written response. If |
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| ===Attachment:===
| | you have any questions about the information in this notice, please contact |
| List of Recently Issued NRC Information NoticesDOCUMENT NAME:G:\JRT\WOLFICE.INTech Editor reviewed 5/1/96To receive a copy of this document, indicate in the box: "C"attachment/enclosure "E" = Copy with attachment/enclosure* _ nrvin_ , concurrences= Copy without"N" = No copyOFFICE | | |
| | one of the technical contacts listed below or the appropriate Office of |
| | |
| | Nuclear Reactor Regulation project manager. |
| | |
| | Brian K. Grimes, Acting Director |
| | |
| | Division of Reactor Program Management |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: John R. Tappert, NRR Bruce Jorgensen, RIII |
| | |
| | (301) 415-1167 (708) 829-9615 Internet:jrt@nrc.gov Internet:blj@nrc.gov |
| | |
| | Attachment: List of Recently Issued NRC Information Notices |
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| | DOCUMENT NAME:G:\JRT\WOLFICE.IN |
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| | Tech Editor reviewed 5/1/96 To receive a copy of this document, indicate in the box: "C" = Copy without |
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| | attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy |
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| | , |
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| | * _ nrvin_ concurrences |
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| | OFFICE |
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| ==CONTACT== | | ==CONTACT== |
| S IC C/SRXB:DSSAl C/PECB:DRPM l D/DRPM HNAME JTappert | | S IC C/SRXB:DSSAl C/PECB:DRPM l D/DRPM H |
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| | NAME JTappert * LMarsh * AChaffee BGrimes |
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| | BJorgensen * |
| | DATE 5 /2/96 5/14/96 5 / /96 5 / /96 OFFICIAL RECORD COPY |
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| | IN 96-XX |
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| * LMarsh
| | May XX, 1995 This information notice requires no specific action or written response. If |
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| * AChaffee BGrimesBJorgensen *DATE 5 /2/96 5/14/96 5 / /96 5 / /96OFFICIAL RECORD COPY IN 96-XXMay XX, 1995 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 Office ofNuclear Reactor Regulation project manager.Brian K. Grimes, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical Contacts:John R. Tappert, NRR(301) 415-1167Internet:jrt~nrc.govBruce Jorgensen, RIII(708) 829-9615Internet:bl Jnrc.gov
| | you have any questions about the information in this notice, please contact |
|
| |
|
| ===Attachment:===
| | one of the technical contacts listed below or the appropriate Office of |
| List of Recently Issued NRC Information NoticesDOCUMENT NAME:G:\JRT\WOLFICE.INTech Editor reviewed 5/1/96To receive a copy of this document, Indicate in the box: "C'attachment/enclosure HEN -Copy with attachment/enclosure* see nrevinus concurrences-Copy withoutON" -No copy--r-V. ---*OFFICE | | |
| | Nuclear Reactor Regulation project manager. |
| | |
| | Brian K. Grimes, Acting Director |
| | |
| | Division of Reactor Program Management |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical Contacts: John R. Tappert, NRR Bruce Jorgensen, RIII |
| | |
| | (301) 415-1167 (708) 829-9615 Internet:jrt~nrc.gov Internet:bl Jnrc.gov |
| | |
| | Attachment: List of Recently Issued NRC Information Notices |
| | |
| | DOCUMENT NAME:G:\JRT\WOLFICE.IN |
| | |
| | Tech Editor reviewed 5/1/96 To receive a copy of this document, Indicate in the box: "C'- Copy without |
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| | attachment/enclosure HEN - Copy with attachment/enclosure ON" - No copy |
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| | * see nrevinus |
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| | --- * |
| | - - r-V. |
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| | concurrences |
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| | OFFICE |
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| ==CONTACT== | | ==CONTACT== |
| S IC C/SRXB:DSSA [_ C/PECB:DRPM I D/DRPMNAME JTappert | | S IC C/SRXB:DSSA [_ C/PECB:DRPM I D/DRPM |
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| | NAME JTappert * LMarsh * AChaffee BGrimes |
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| | BJorgensen * |
| | DATE 5 12/96 5/14/96 5 / /96 5 / /96 |
| | .- - - - - -- - - ---.b |
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| | OFFICIAL KLLRCD COPY so |
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| | IN 96-XX |
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| | May XX, 1995 This information notice requires no specific action or written |
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| | you have any questions about the information In this notice, pl .act |
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| | one of the technical contacts listed below or the appropriate 0 of |
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| | Nuclear Reactor Regulation project manager. |
| | |
| | Brian K. Grimes Acting Director |
| | |
| | Division of Resctor Program Management |
| | |
| | Office of Nu ear Reactor Regulation |
| | |
| | Technical Contacts: John R. Tappert, NRR uce Jorgensen, RGN III |
| | |
| | (301) 415-1167 (708) 829-9615 Internet :Jrt~nrc :.gov Internet:blj@nrc.gov |
| | |
| | Attachment: List of Recently Issued NRC I Notices |
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| | iormation |
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| | DOCUMENT NAME:G:\JRT\WO 4ICE.IN |
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| | Tech Editor reviewed /1/96 To receive a copy p this documient, indicate in the box: IC'= Copy without |
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| | attachment/enclosyre "E - Coi py with attachment/enclosure ON, - No copy |
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| | seep nrpvinu! I concurrences |
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| * LMarsh
| | OFFICE CONTSCTS IC C/SRXB:DSSA _ C/PECB:DRPM l/DRPM |
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| * AChaffee BGrimesBJorgensen *DATE 5 12/96 5/14/96 5 / /96 5 / /96.- -----------. bOFFICIAL KLLRCD COPY so§S IN 96-XXMay XX, 1995 This information notice requires no specific action or writtenyou have any questions about the information In this notice, plone of the technical contacts listed below or the appropriate 0Nuclear Reactor Regulation project manager..actofTechnical Contacts:John R. Tappert,(301) 415-1167Internet :Jrt~nrcBrian K. Grimes Acting DirectorDivision of Resctor Program ManagementOffice of Nu ear Reactor RegulationNRR uce Jorgensen, RGN III(708) 829-9615:.gov Internet:blj@nrc.govNRC I iormation Notices | | NAME JT pert * LMarsh * AChaffee BGrimes |
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| ===Attachment:===
| | AB4rgensen * |
| List of Recently IssuedDOCUMENT NAME:G:\JRT\WO 4ICE.INTech Editor reviewed /1/96To receive a copy p this documiattachment/enclosyre "E -Coiseep nrpvinu!ent, indicate in the box: IC'py with attachment/enclosureI concurrences= Copy withoutON, -No copyOFFICE CONTSCTS IC C/SRXB:DSSA _ C/PECB:DRPM l/DRPMNAME JT pert
| | DATE /2/96 5/14/96 5 / /96 5 / /96 |
| | 7 I I £'LFIL rIILvrv |
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| | 'WArTTA I - |
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| * AChaffee BGrimesAB4rgensen *DATE /2/96 5/14/96 5 / /96 5 / /967 ArTTA I £'LFIL rIILvrv -'WI I AULOISI.WWI 5 JP4\
| | WWI 5 JP4\ |
| IN 96-XXMay XX, 1995 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 Office ofNuclear Reactor Regulation project manager.Brian K. Grimes, Acting Direc rDivision of Reactor Program anagementOffice of Nuclear Reactor egulationTechnical Contacts: John R. Tappert, NRR Bruc Jorgensen, RGN III(301) 415-1167 (7 ) 829-9615Internet:jrt~nrc.gov I ernet:blJ~nrc.gov
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| ===Attachment:===
| | IN 96-XX |
| List of Recently Issued NRC Informat1o oticesDOCUMENT NAME:G:\JRT\WOLFICE.1ITech Editor reviewed 5/1/96To receive a copy of this ocument, indicate in the box: OCR -Copy withoutattachment/enclosure -C y with ttachment/enclosure N" -No copyOFFICE | | |
| | May XX, 1995 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 Office of |
| | |
| | Nuclear Reactor Regulation project manager. |
| | |
| | Brian K. Grimes, Acting Direc r |
| | |
| | Division of Reactor Program anagement |
| | |
| | Office of Nuclear Reactor egulation |
| | |
| | Technical Contacts: John R. Tappert, NRR Bruc Jorgensen, RGN III |
| | |
| | (301) 415-1167 (7 ) 829-9615 Internet:jrt~nrc.gov I ernet:blJ~nrc.gov |
| | |
| | Attachment: List of Recently Issued NRC Informat1o otices |
| | |
| | DOCUMENT NAME:G:\JRT\WOLFICE.1I |
| | |
| | Tech Editor reviewed 5/1/96 To receive a copy of this ocument, indicate in the box: OCR - Copy without |
| | |
| | attachment/enclosure - C y with ttachment/enclosure N" - No copy |
| | |
| | OFFICE |
|
| |
|
| ==CONTACT== | | ==CONTACT== |
| S IC C SRXB:DSSA I ?lC/PECB:DRPM D/DRPMNAME JTappert [7LMarsh ftv AChaffee BGrimes.~BJorgensel ;V 8DATE 5 /2/96/ 5 /0t/96 5 / /96 5 //96OFFICIAL RECORD COPY}} | | S IC C SRXB:DSSA I ?lC/PECB:DRPM D/DRPM |
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| | NAME JTappert [7LMarsh ftv AChaffee BGrimes |
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| | . ~BJorgensel;V 8 DATE 5 /2/96/ 5/0t/96 5 / /96 5 //96 OFFICIAL RECORD COPY}} |
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| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Degradation of Cooling Water Systems Due to IcingML031060039 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
06/12/1996 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-96-036, NUDOCS 9606070097 |
Download: ML031060039 (11) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
"J
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFYFICE OF NUCLEAR REACTOR REGULATION
- WASHINGTON, DC 20555-0001 June 12, 1996 NRC INFORMATION NOTICE 96-36: DEGRADATION OF COOLING WATER SYSTEMS DUE TO
ICING
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to potential degradation of facility water intake
systems (circulating, service, and fire water) due to icing conditions.
It is expected that recipients will review the information for applicability
to their facilities and consider actions, as appropriate, to avoid similar
problems. However, suggestions contained in this information notice are not
NRC requirements; therefore, no specific action or written response is
required.
Description of Circumstances
Wolf Creek
Between 1:45 a.m. and 2:45 a.m. (all times central standard time) on
January 30, 1996, operators at Wolf Creek received alarms indicating that the
circulating water system traveling screens were becoming blocked. A visual
inspection showed that the traveling screens for bays 1 and 3 were frozen and
that water levels in these bays were approximately 2.5 m [8 ft] below normal.
The emergency service water system was started with the intent to separate
this system from the service water system. However, the emergency service
water system was incorrectly aligned; flow was directed to the service water
system and warming flow to the emergency service water system suction bays was
restricted. Operators also shifted to circulating water pump B. At approxi- mately 3:30 a.m., operators received a service water pressure alarm and an
electric fire pump started on low service water pressure. The shift super- visor then directed a manual reactor/turbine trip. Circulating water system
bays were subsequently determined to be at 3.5 m [12 feet] below normal. The
level loss was caused by water from the spray wash system freezing and block- ing the traveling screens.
The Train A emergency service water system pump was tripped and declared
inoperable at 7:47 a.m. because of low discharge pressure and high strainer
differential pressure. At about 8:00 a.m., the supervising operator coming on
shift noted the incorrect alignment of the emergency service water system and
took action to correct it. At about 5:45 p.m., the operators declared Train A
'~P) bla 0f .
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IN 96-36 June 12, 1996 operable on the basis of an engineering evaluation and placed it in service.
However, the pump was again stopped 1-1/2 hours later at approximately
7:30 p.m. when the pump exhibited further oscillations in flow and pressure.
At approximately 8:00 p.m., operators noted that emergency service water
system Train B suction bay level was 4.5 m [15 ft] below normal and decreasing
slowly. Operators placed additional heat loads on Train B and the suction bay
levels subsequently recovered. At 10:14 p.m., the operators again started
Train A emergency service water system and secured it at 10:27 p.m. due to
decreasing flow and pressure.
At about 10:00 a.m. on January 31, divers inspected the suction bay of Train A
and noted complete blockage of the trash racks by frazil ice. Train B was not
inspected because the pump was running. The ice blockage was cleared by
4:00 p.m. by sparging the trash racks with air. The emergency service water
system was designed to have warming flow injected in front of trash racks to
increase bulk water temperature and prevent the formation of frazil ice. Due
to calculational errors by the architect-engineer and the as-built system
configuration, the emergency service water system warming flow was
insufficient to prevent frazil ice from forming at the Train A trash racks.
FitzPatrick
On February 25, 1993, at 1:25 a.m., the electric fire pump started on low fire
header pressure. After verifying normal fire header pressure, operators
secured the electric fire pump, and the diesel fire pumps subsequently started
on low header pressure. It was later determined that the fire jockey pump had
lost suction because of the decreasing screenwell level.
Over the next several minutes, operators noted an increase in circulating
water system motor amperage (which is consistent with decreased suction
pressure). Reactor power was also reduced and one circulating water pump was
secured. At 1:40 a.m., an operator reported that the screenwell level was
approximately 3 m [10 ft] below normal and the reactor was manually scrammed.
After a second circulating water pump was subsequently secured, the screenwell
water level quickly recovered. The licensee concluded that the reduced
screenwell level had been caused by ice partially blocking the lake intake
structure. Either frazil ice formed around or in front of the heated intake
bar racks, or slush ice was present in front of the bar racks.
Fermi
On February 5, 1996, at approximately 2:30 p.m., diesel generator service
water pump C failed to develop normal discharge pressure, flow, and motor
current during a surveillance. This made Division I emergency diesel
generator (EDG) 12 inoperable. After several unsuccessful attempts to start
the pump, an air purge of the pump column on the discharge of the pump was
initiated in an attempt to clear any obstruction in the column or the pump
inlet. The licensee detected blockage when it tried to blow air through the
pipe. At 8:21 p.m., the pump was started and after 3 to 5 seconds an erratic
discharge pressure was noted. In a short time, pump flow, discharge pressure, and motor amps were normal. The following day, on February 6, diesel
generator service water pump B was started. The pump, which cools Division II
K>
< IN 96-36 June 12, 1996 EDG 13, showed no flow, no pressure, and low amperage for the first
30 seconds. After approximately 90 seconds, normal flow discharge pressure
and motor current were achieved. The remaining safety-related pumps were
tested satisfactorily.
The diesel generator service water pumps are all deep-draft pumps and take
suction from the ultimate heat sink reservoir which is a segregated pool. The
licensee evaluation concluded that although the reservoir temperatures are
maintained above 5 eC [41 OF], part of the pump column and two of the linear
guide bearings are located above the water level and are exposed to ambient
air temperature conditions. The failure of the diesel generator service water
pump C was attributed to ice buildup around the shaft and spider bearing from
leakage past the discharge check valve and the cold weather. The licensee
also concluded that under some credible meteorological conditions, the
functions of both divisions could have been affected.
Discussion
Frazil icing is a phenomenon that affects the operation of intake structures
in regions that experience cold weather. The accumulation of frazil ice on
intake trash racks can completely block the flow of water into the intake.
The process starts when the water flowing into the intake is supercooled (a
condition where the water is below the freezing point). The supercooling may
be very small, on the order of a few hundredths of a degree.
The supercooling occurs with a loss of heat from a large surface area such as
a lake with open water and clear nights. High winds contribute to the problem
by providing mixing of the supercooled water to depths as great as 6 to 9 m
[20 to 30 ft]. The frazil ice, which is composed of very small crystals
(1-15 mm) with little buoyancy because of their size, is carried along in the
water and mixed all through the supercooled water.
The suction of the supercooled water and the suspended frazil ice crystals
through an intake structure brings the frazil ice crystals in contact with the
trash rack bars. Frazil ice crystals easily adhere to any object with which
they collide. The ice collects first on the upstream side of the trash racks, then steadily grows until the space between the trash racks is bridged. This
bridging rapidly blocks the trash racks. The accumulation of ice can with- stand high differential pressures; effectively damming the intake suction.
Facility vulnerability to icing events is a function of plant design. Frazil
and other ice formation is dependent on specific environmental conditions and
represents a potential common-mode failure that can cause the loss or degrada- tion of multiple cooling water systems, including the potential loss of the
ultimate heat sink.
IN 96-36 June 12, 1996 Related Information
NUREG/CR-0548, "Ice Blockage of Water Intakes."
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 Office of
Nuclear Reactor Regulation project manager.
I
i - . .- - . . . . . - .
Brian K. Grimes, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: John R. Tappert, NRR
(301) 415-1167 Internet:jrtlnrc.gov
Bruce Jorgensen, RIII
(708) 829-9615 Internet:blj@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
I
k W (0%0% J4-c- -d I
K>
Attachment
IN 96-36 June 12, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-35 Failure of Safety Systems 06/11/96 All U.S. Nuclear Regulatory
on Self-Shielded Irradia- Commission irradiator
tors Because of Inadequate licensees and vendors
Maintenance and Training
96-34 Hydrogen Gas Ignition 05/31/96 All holders of OLs or CPs
during Closure Welding for nuclear power reactors
of a VSC-24 Multi-Assembly
Sealed Basket
96-33 Erroneous Data From 05/24/96 All material and fuel cycle
Defective Thermocouple licensees that monitor tem- Results ii i a Fire perature with thermocouples
96-32 Implementation of 10 CFR 06/05/96 All holders of OLs or CPs
50.55a(g)(6)(ii)(A), for nuclear power reactors
"Augmented Examination
of Reactor Vessel"
96-31 Cross-Tied Safety Injec- 05/22/96 All holders of OLs or CPs
tion Accumulators for pressurized water
reactors
96-30 Inaccuracy of Diagnostic 05/21/96 All holders of OLs or CPs
Equipment for Motor- for nuclear power reactors
Operated Butterfly Valves
96-29 Requirements in 10 CFR 05/20/96 All holders of OLs or CPs
Part 21 for Reporting and for nuclear power reactors
Evaluating Software Errors
96-28 Suggested Guidance Relating 05/01/96 All material and fuel cycle
to Development and Imple- licensees
mentation of Corrective
Action
96-27 Potential Clogging of High 05/01/96 All holders of OLs or CPs
Pressure Safety Injection for pressurized water
Throttle Valves During reactors
Recirculation
OL - Operating License
CP = Construction Permit
IN 96-36
. I June 12, 1996 Related Information
NUREG/CR-0548, "Ice Blockage of Water Intakes."
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 Office of
Nuclear Reactor Regulation project manager.
Original signed by Brian K.Grimes
Brian K. Grimes, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: John R. Tappert, NRR
(301) 415-1167 Internet:jrt@nrc.gov
Bruce Jorgensen, RIII
(708) 829-9615 Internet:blj@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: 96-36.IN
Tech Editor reviewed 5/1/96 To receive a copy of this document, indicate in the box: "C"- Copy without
attachment/enclosure "EN - Copy with attachment/enclosure "N"- No co
- s ee Drevious concurrences
OFFICE
CONTACT
S IC C/SRXB:DSSA I C/PECB:DRPM D/JT(S, i
NAME JTappert * LMarsh * AChaffee* BKf1Tntee' l
BJorgensen * l
DATE 5 /2/96 5/14/96 6/5/96 6//(/96 OFFICIAL RECORD COPY
IN 96-XX
June XX, 1996 Related information
NUREG/CR-0548, *Ice Blockage of Water Intakes"
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 Office of
Nuclear Reactor Regulation project manager.
Brian K. Grimes, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: John R. Tappert, NRR Bruce Jorgensen, RIII
(301) 415-1167 (708) 829-9615 Internet:Jrt@nrc.gov Internet:bl Jnrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME:G:\JRT\WOLFICE.IN
Tech Editor reviewed 5/1/96 To receive a copy of this document, indicate in the box: ACT - Copy without
attachment/enclosure 'El - Copy with attachment/enclosure ON" - No copy
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OFFICE
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S C C/SRXB:DSSA I C/PECB:DRPM I D/DRPM
NAME JTappert * LMarsh * AChaffeer,(, IBGrimes
BJorgensen *
DATE 5 /2/96 5/14/96 _ _ 6 _6/_/96 UrIU-lAL KLLUKU WO
/WY-,*-)
-
IN 96 d
May XX, 1995 Related-Information
NUREG/CR-0548, "Ice Blockage of Water Intakes"
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 Office of
Nuclear Reactor Regulation project manager.
Brian K. Grimes, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: John R. Tappert, NRR Bruce Jorgensen, RIII
(301) 415-1167 (708) 829-9615 Internet:jrt@nrc.gov Internet:blj@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME:G:\JRT\WOLFICE.IN
Tech Editor reviewed 5/1/96 To receive a copy of this document, indicate in the box: "C" = Copy without
attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy
,
OFFICE
CONTACT
S IC C/SRXB:DSSAl C/PECB:DRPM l D/DRPM H
NAME JTappert * LMarsh * AChaffee BGrimes
BJorgensen *
DATE 5 /2/96 5/14/96 5 / /96 5 / /96 OFFICIAL RECORD COPY
IN 96-XX
May XX, 1995 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 Office of
Nuclear Reactor Regulation project manager.
Brian K. Grimes, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: John R. Tappert, NRR Bruce Jorgensen, RIII
(301) 415-1167 (708) 829-9615 Internet:jrt~nrc.gov Internet:bl Jnrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME:G:\JRT\WOLFICE.IN
Tech Editor reviewed 5/1/96 To receive a copy of this document, Indicate in the box: "C'- Copy without
attachment/enclosure HEN - Copy with attachment/enclosure ON" - No copy
--- *
- - r-V.
concurrences
OFFICE
CONTACT
S IC C/SRXB:DSSA [_ C/PECB:DRPM I D/DRPM
NAME JTappert * LMarsh * AChaffee BGrimes
BJorgensen *
DATE 5 12/96 5/14/96 5 / /96 5 / /96
.- - - - - -- - - ---.b
§S
OFFICIAL KLLRCD COPY so
IN 96-XX
May XX, 1995 This information notice requires no specific action or written
you have any questions about the information In this notice, pl .act
one of the technical contacts listed below or the appropriate 0 of
Nuclear Reactor Regulation project manager.
Brian K. Grimes Acting Director
Division of Resctor Program Management
Office of Nu ear Reactor Regulation
Technical Contacts: John R. Tappert, NRR uce Jorgensen, RGN III
(301) 415-1167 (708) 829-9615 Internet :Jrt~nrc :.gov Internet:blj@nrc.gov
Attachment: List of Recently Issued NRC I Notices
iormation
DOCUMENT NAME:G:\JRT\WO 4ICE.IN
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attachment/enclosyre "E - Coi py with attachment/enclosure ON, - No copy
seep nrpvinu! I concurrences
OFFICE CONTSCTS IC C/SRXB:DSSA _ C/PECB:DRPM l/DRPM
NAME JT pert * LMarsh * AChaffee BGrimes
AB4rgensen *
DATE /2/96 5/14/96 5 / /96 5 / /96
7 I I £'LFIL rIILvrv
'WArTTA I -
AULOISI.
WWI 5 JP4\
IN 96-XX
May XX, 1995 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 Office of
Nuclear Reactor Regulation project manager.
Brian K. Grimes, Acting Direc r
Division of Reactor Program anagement
Office of Nuclear Reactor egulation
Technical Contacts: John R. Tappert, NRR Bruc Jorgensen, RGN III
(301) 415-1167 (7 ) 829-9615 Internet:jrt~nrc.gov I ernet:blJ~nrc.gov
Attachment: List of Recently Issued NRC Informat1o otices
DOCUMENT NAME:G:\JRT\WOLFICE.1I
Tech Editor reviewed 5/1/96 To receive a copy of this ocument, indicate in the box: OCR - Copy without
attachment/enclosure - C y with ttachment/enclosure N" - No copy
OFFICE
CONTACT
S IC C SRXB:DSSA I ?lC/PECB:DRPM D/DRPM
NAME JTappert [7LMarsh ftv AChaffee BGrimes
. ~BJorgensel;V 8 DATE 5 /2/96/ 5/0t/96 5 / /96 5 //96 OFFICIAL RECORD COPY
|
---|
|
list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy, Overexposure, Depleted uranium)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996, Topic: Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Stress corrosion cracking, Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996, Topic: Tone Alert Radio, Siren)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy, Overspeed trip)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996, Topic: Feedwater Heater)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996)
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