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) |
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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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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) C-FW 0f bla .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 on Self-Shielded
Irradia-tors Because of Inadequate
Maintenance
and Training Hydrogen Gas Ignition during Closure Welding of a VSC-24 Multi-Assembly
Sealed Basket 06/11/96 05/31/96 All U.S. Nuclear Regulatory
Commission
irradiator
licensees
and vendors All holders of OLs or CPs for nuclear power reactors 96-34 96-33 Erroneous Defective Results ii Data From Thermocouple
i a Fire 05/24/96 All material and fuel cycle licensees
that monitor tem-perature with thermocouples
96-32 96-31 96-30 Implementation
of 10 CFR 50.55a(g)(6)(ii)(A),"Augmented
Examination
of Reactor Vessel" Cross-Tied
Safety Injec-tion Accumulators
Inaccuracy
of Diagnostic
Equipment
for Motor-Operated Butterfly
Valves Requirements
in 10 CFR Part 21 for Reporting
and Evaluating
Software Errors Suggested
Guidance Relating to Development
and Imple-mentation
of Corrective
Action Potential
Clogging of High Pressure Safety Injection Throttle Valves During Recirculation
06/05/96 05/22/96 05/21/96 05/20/96 05/01/96 05/01/96 All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for pressurized
water reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All material and fuel cycle licensees All holders of OLs or CPs for pressurized
water reactors 96-29 96-28 96-27 OL -Operating
License CP = Construction
Permit
.I 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.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 attachment/enclosure
- s this document, indicate in the box: "C""EN -Copy with attachment/enclosure
ee Drevious concurrences
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CONTACT
S IC C/SRXB:DSSA
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D/JT(S, i NAME JTappert
BKf1Tntee'
l BJorgensen
- lDATE 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 (301) 415-1167 Internet:Jrt@nrc.gov
Bruce Jorgensen, RIII (708) 829-9615 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 attachment/enclosure
'El -Copy with attachment/enclosure
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CONTACT
S C C/SRXB:DSSA
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I D/DRPM NAME JTappert
- 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 (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:G:\JRT\WOLFICE.IN
Tech Editor reviewed 5/1/96 To receive a copy of this document, indicate in the box: "C" attachment/enclosure "E" = Copy with attachment/enclosure
= Copy without"N" = No copy OFFICE
CONTACT
S IC C/SRXB:DSSAl
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- 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 (301) 415-1167 Internet:jrt~nrc.gov
Bruce Jorgensen, RIII (708) 829-9615 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'attachment/enclosure
HEN -Copy with attachment/enclosure
- see nrevinus concurrences
-Copy without ON" -No copy--r-V. ---*OFFICE
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S IC C/SRXB:DSSA
[_ C/PECB:DRPM
I D/DRPM NAME JTappert
- AChaffee BGrimes BJorgensen
- DATE 5 12/96 5/14/96 5 / /96 5 / /96.- -----------. b OFFICIAL KLLRCD COPY so§S
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 one of the technical
contacts listed below or the appropriate
0 Nuclear Reactor Regulation
project manager..act of Technical
Contacts: John R. Tappert, (301) 415-1167 Internet :Jrt~nrc Brian K. Grimes Acting Director Division of Resctor Program Management
Office of Nu ear Reactor Regulation
NRR uce Jorgensen, RGN III (708) 829-9615:.gov Internet:blj@nrc.gov
NRC I iormation
Notices Attachment:
List of Recently Issued DOCUMENT NAME:G:\JRT\WO
4ICE.IN Tech Editor reviewed /1/96 To receive a copy p this documi attachment/enclosyre "E -Coi seep nrpvinu!ent, indicate in the box: IC'py with attachment/enclosure
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- DATE /2/96 5/14/96 5 / /96 5 / /96 7 ArTTA I £'LFIL rIILvrv -'WI 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
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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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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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