Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing: Difference between revisions

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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
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{{#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
 
(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
 
* see orevious concurrences
 
OFFICE


==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
 
NAME    JTappert *            LMarsh *      AChaffeer,(,        IBGrimes
 
BJorgensen *
  DATE      5 /2/96              5/14/96        _    _  6  _6/_/96 UrIU-lAL KLLUKU WO
 
/WY-,*-)
 
-
                                                    IN 96 d


* LMarsh
May XX, 1995 Related-Information


* 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


===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
 
DOCUMENT NAME:G:\JRT\WOLFICE.IN
 
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==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
 
NAME    JTappert *            LMarsh *        AChaffee          BGrimes
 
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IN 96-XX


* LMarsh
May XX, 1995 This information notice requires no specific action or written response. If


* 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
 
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OFFICE


==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
 
NAME    JTappert *              LMarsh *        AChaffee            BGrimes
 
BJorgensen *
  DATE      5 12/96                5/14/96            5 / /96            5 / /96
                                    .- - - - - --  - - ---.b
 
&sect;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
 
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* AChaffee BGrimesBJorgensen *DATE 5 12/96 5/14/96 5 / /96 5 / /96.- -----------. bOFFICIAL KLLRCD COPY so&sect;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


===Attachment:===
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* LMarsh
'WArTTA  I                      -
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* AChaffee BGrimesAB4rgensen *DATE /2/96 5/14/96 5 / /96 5 / /967 ArTTA I &#xa3;'LFIL rIILvrv -'WI I AULOISI.WWI 5 JP4\
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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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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
 
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S         IC C SRXB:DSSA I ?lC/PECB:DRPM       D/DRPM
 
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{{Information notice-Nav}}
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Latest revision as of 04:38, 24 November 2019

Degradation of Cooling Water Systems Due to Icing
ML031060039
Person / Time
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
Issue date: 06/12/1996
From: Grimes B
Office of Nuclear Reactor Regulation
To:
References
IN-96-036, NUDOCS 9606070097
Download: ML031060039 (11)
v • d • e


"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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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

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

  • see orevious concurrences

OFFICE

CONTACT

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

,

  • _ nrvin_ concurrences

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

  • see nrevinus

--- *

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CONTACT

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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

Tech Editor reviewed /1/96 To receive a copy p this documient, indicate in the box: IC'= Copy without

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


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