Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-UpML031130253 |
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: |
04/16/1990 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-90-025, NUDOCS 9004120133 |
Download: ML031130253 (8) |
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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>. |
.* -*UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 April 16, 1990 NRC INFORMATION
NOTICE NO. 90-25: LOSS OF VITAL AC POWER WITH SUBSEQUENT
REACTOR COOLANT SYSTEM HEAT-UP
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.
Purpose
- This information
notice is being provided to inform addressees
of a significant
operating
event which occurred at the Georgia Power Company's
Vogtle Nuclear Plant on March 20, 1990. The event took place while Unit 1 was in mid-loop in operational
mde 6 and demonstrates
the need for operating
personnel
to be prudent in removing equipment
from service or establishing
atypical equipment alignments
during shutdown.
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 do not constitute
NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances:
On March 20, 1990, a loss of vital ac power occurred while Vogtle Unit 2 was operating
at 100 percent power and Unit 1 had been in a refueling
outage for about 4 weeks. Unit 1 was in mid-loop in operational
mode 6 with plant equip-ment conditions
as follows: o The Unit 1 B reserve auxiliary
transformer (RAT) was tagged out of service for maintenance
o The Unit 1 B emergency
diesel generator (EDG) was tagged out of service and disassembled
for maintenance
o The Unit 1 A RAT was supplying
offsite power to the crosstied
Unit 1 A and B vital buses o The reactor coolant system (RCS) temperature
was being maintained
at around 90 degrees Fahrenheit (F) via the train A residual heat removal (RHR) pump, the-train
B pump was in standby o The vessel head was in place with the bolts not fully tensioned o The pressurizer
manway cover was removed_ __ A l e ,
IN 90-25 April 16, 1990 o The manways for steam generators
2 and 3 were partially
bolted in place and the manways for steam generators
1 and 4 were in place with bolts fully tensioned o The inboard charging line check valve and an accumulator
isolation valve were open for inspection
o The containment
equipment
hatch and the containment
personnel
hatch were open At about 9:20 a.m., a truck carrying fuel and lubricants
in the plant low voltage switchyard
backed into a support column for the feeder line supplying power to the Unit 1 A RAT and the Unit 2 B RAT. The insulator
for the C phase of the feeder line fractured
and initiated
a phase-to-ground
electrical
fault.The fault resulted in a loss of power to the Unit 1 A RAT and the Unit 2 B RAT.The Unit 2 B EDG started and loaded to the deenergized
Unit 2 B vital bus. How-ever, a Unit 2 turbine trip and reactor trip occurred because of an improperly
connected (wrong tap) differential
current transformer (DCT). The DCT initiated the trip when the current surge associated
with the phase-to-ground
fault was sensed. The Unit 2 trip was uncomplicated.
Because both of the Unit 1 vital buses were crosstied
and being supplied by the Unit 1 A RAT, the loss of the transformer
deenergized
both vital buses.Deenergizing
these buses resulted in the loss of power to the operating
RHR pump. Since the Unit 1 B EDG was tagged out of service and disassembled
for maintenance, the emergency
power supply for the B vital bus was unavailable
and the standby B RHR pump could not be started.The available
Unit 1 A EDG started on bus undervoltage, but for unknown reasons, it shut down automatically
after 1 minute and 20 seconds. At 9:40 a.m., plant operators
declared a site area emergency.
A loss of all onsite and offsite ac power at Vogtle for more than 15 minutes is classified
as a site area emergency.
The licensee made their declaration
because all vital ac power was lost for greater than 15 minutes. Approximately
18 minutes after the first start of the A EDG, the operators
locally reset the load sequencer
which automatically
restarted
the A EDG on undervoltage.
However, after 1 minute and 10 seconds, the diesel again shut down automatically.
At 9:56 a.m., plant operators
per-formed an "emergency" manual start of the diesel, which bypassed most of the diesel's protective
trips. The diesel started and loaded to the bus, the A RHR pump was restarted, and core cooling was reestablished
to Unit 1. With the start of the diesel, the site area emergency
was downgraded
to an "alert" at 10:15 a.m. Containment
integrity
was established
at 11:03 a.m.Plant personnel
returned the Unit 1 B RAT to service after completing
formal tagout removal procedures.
However, attempts to energize the transformer
were delayed for several minutes because of a sticking mechanical
interlock
in the control circuitry
for a motor-operated
disconnect
switch on the high side of the B RAT. Power was restored to the B vital bus via the B RAT at 11:40 a.m.At 12:38 a.m., core cooling was shifted to the B RHR train to facilitate
sub-sequent electrical
alignment
changes.
e. v -%IN 90-25 April 16, 1990 According
to control roon indication, RCS temperature
increased
from 90 to 136 degrees F during the 36 minutes required to reenergize
the A bus (1.3 degrees F/min).Throughout
the event, non-vital
power was continuously
provided to Unit 1 from offsite sources, via backfeed through the main generator
transformer.
Also, the Unit 2 electrical
distribution
system remained energized (aside from the momentary
loss of power before the reactor trip). However, the Vogtle electrical
system was not designed to permit easy interconnection
of the Unit 1 vital buses to nonvital power or to the Unit 2 electrical
buses. Therefore, there were no procedures
in place to provide guidance on interconnecting
the Unit 1 vital and nonvital buses or for interconnecting
the Unit 1 electrical
distribution
system with the distribution
system at Unit 2. (There are no regulatory
requirements
that direct the licensee to develop Interconnection
procedures.)
Discussion:
The NRC has previously
identified
concerns with the operability
of necessary equipment
in shutdown modes. In Information
Notice (IN) 80-2O, "Loss of Decay Heat Removal Capability
at Davis-Besse
Unit 1 While in a Refueling
Mode" an extended loss of decay heat removal capability
was attributed
to a number of factors, including
inadequate
procedures, inadequate
administrative
controls, and the conduct of extensive
maintenance
activities.
Information
Notice 84-42, "Equipment
Availability
for Conditions
During Outages Not Covered by Technical
Specifications," describes
an event at the Palisades Nuclear Plant involving
the total loss of all ac power. The Palisades
event was precipitated
by personnel
performing
actions during a refueling
outage without an appreciation
for the effect of those actions on the plant as it was configured.
Many pieces of equipment
were tagged out of service for maintenance.
Personnel
intentionally
interrupted
offsite power. This action caused the loss of the only available
service water pump. As a result, cooling water was interrupted
to the only available (and operating)
diesel generator.
The diesel overheated
and was manually tripped. As a result, all station ac power was interrupted, causing the loss of fuel pool cooling. (The reactor had been defueled, and its fuel was being stored in the spent fuel pool).The recent Vogtle event reemphasizes
the need for careful planning of equipment outages during shutdown.
Licensees, in general, have considerable
latitude in removing equipment
from service and altering normal system lineups while in shutdown modes if only the minimum technical
specification
requirements
are considered.
The desire to return nuclear units to service as quickly as possible can result in maintenance
being conducted
on redundant, safety-related systems, concurrently.
The appropriateness
of conducting
parallel maintenance
activities
should be considered
in light of the availability
of alternate
equipment
and procedures
to mitigate the consequences
of potential operational
problems.
It is important
that plant outage plans assure that an adequate complement
of equipment
capable of responding
to potential
events remains available
throughout
the outage. Particular
care is needed when the reactor pressure boundary is not intact or the reactor coolant system is at mid-loop.
IN 90-25 April 16, 1990 A special investigation
of the Vogtle event is being conducted
by an NRC Incident Investigation
Team (1IT). The information
contained
in this notice is preliminary
and is subject to change, pending the findings made by the IIT.This Information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
NRR project manager.~6hfares Eossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts:
N. Fields, NRR (301) 492-1173 E. Trager, AEOD (301) 492-4496 Attachment:
List of Recently Issued NRC Information
Notices
, 0 --u Attachment
IN 90-25 April 16, 1990 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Intormation
Date ot Notice No. Subject Issuance Issued to 90-24 90-23 90-22 90-21 90-20 90-19 90-18 90-17 Transportation
of Model Spec 2-T Radiographic
Exposure Device Improper Installation
of Patel Conduit Seals Unanticipated
Equipment Actuations
Following Restoration
of Power to Rosemount
Transmitter
Trip Units Potential
Failure of Motor-Operated Butterfly
Valves to Operate Because Valve Seat Friction was Under-estimated Personnel
Injuries Resulting from Improper Operation
of Radwaste Incinerators
Potential
Loss of Effective Volume for Containment
Recirculation
Spray at PWR Facilities
Potential
Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks Weight and Center of Gravity Discrepancies
for Copes-Vulcan
Valves 4/10/90 4/4/90 3/23/90 3/22/90 3/22/90 3/14/90 3/9/90 3/8/90 All NRC licensees authorized
to use, transport, or operate radiographic
exposure devices and source changers.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All NRC licensees who process or incinerate
radio-active waste.All holders of OLs or CPs for PWRs.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.OL = Operating
License CP = Construction
Permit
tNOW, IN 90-25--April 16, 1990 A special investigation
of the Vogtle event is being conducted
by an NRC Incident Investigation
Team (IIT). The information
contained
in this notice is preliminary
and is subject to change, pending the findings made by the IIT.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
NRR project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts: N. Fields, NRR (301) 492-1173 E. Trager, AEOD (301) 492-4496 Attachment:
List of Recently Issued NRC Information
Notices*SEE PREVIOUS PAGE FOR CONCURRENCE
OFC NAME DATE OFC NAME DATE*OEAB:DOEA
NFields 4/11/90*OEAB:DOEA
DFISCHER 4/11/90*TECH ED 4/11/90*C:OEAB:DOEA
PSwetland 4/11/90*REGION I (IIT)WLazarus 4/11/90*C:GCB:DOEA
CBERLINGER
4/11/90*PD23 TReed 4/11/90 4/1 3/90 OFFICIAL RECORD COPY
OFFICIAL RECORD COPY Document Name: VOGTLE OFC O .DOEA p NAME NFlelds DATE yv"1/90 OFC O X -DOEA NAME DFISCHER DATE f /11/90
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list | - Information Notice 1990-01, Importance of Proper Response to Self-Identified Violations by Licensees (12 January 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-02, Potential Degradation of Secondary Containment (22 January 1990)
- Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm (23 January 1990, Topic: Liquid penetrant)
- Information Notice 1990-04, Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, (26 January 1990, Topic: Nondestructive Examination)
- Information Notice 1990-05, Inter-System Discharge of Reactor Coolant (29 January 1990)
- Information Notice 1990-06, Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels (29 January 1990)
- Information Notice 1990-07, New Information Regarding Insulation Material Performance and Debris Blockage of PWR Containment Sumps (30 January 1990)
- Information Notice 1990-08, KR-85 Hazards from Decayed Fuel (1 February 1990)
- Information Notice 1990-08, KR-85 Hazards From Decayed Fuel (1 February 1990)
- Information Notice 1990-09, Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees (5 February 1990, Topic: Decommissioning Funding Plan)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Liquid penetrant)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-11, Maintenance Deficiency Associated with Solenoid-Operated Valves (28 February 1990)
- Information Notice 1990-12, Monitoring or Interruption of Plant Communications (28 February 1990)
- Information Notice 1990-13, Importance of Review and Analysis of Safeguards Event Logs (5 March 1990)
- Information Notice 1990-14, Accidental Disposal of Radioactive Materials (6 March 1990, Topic: Brachytherapy)
- Information Notice 1990-15, Reciprocity Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States (17 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-16, Compliance with New Decommissioning Rule (7 March 1990)
- Information Notice 1990-17, Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves (8 March 1990, Topic: Earthquake)
- Information Notice 1990-18, Potential Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-18, Potential Problems With Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-19, Potential Loss of Effective Volume for Containment Recirculation Spray at PWR Facilities (14 March 1990)
- Information Notice 1990-20, Personnel Injuries Resulting from Improper Operation of Radwaste Incinerators (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction was Underestimated (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction Was Underestimated (22 March 1990)
- Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units (23 March 1990, Topic: Reactor Vessel Water Level)
- Information Notice 1990-23, Improper Installation of Patel Conduit Seals (4 April 1990)
- Information Notice 1990-24, Transportation of Model Spec 2-T Radiographic Exposure Device (10 April 1990)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power With Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-26, Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems (24 April 1990)
- Information Notice 1990-27, Clarification of the Recent Revisions to the Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for Transportation (30 April 1990)
- Information Notice 1990-28, Potential Error In High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-28, Potential Error in High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head (30 April 1990, Topic: Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-30, Ultrasonic Inspection Techniques for Dissimilar Metal Welds (1 May 1999, Topic: Dissimilar Metal Weld)
- Information Notice 1990-31, Update on Waste Form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-31, Update on Waste form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head (3 May 1990)
- Information Notice 1990-33, Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools (9 May 1990)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990)
- Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990)
- Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990, Topic: Authorized possession limits)
- Information Notice 1990-39, Recent Problems with Service Water Systems (1 June 1990)
- Information Notice 1990-40, Results of NRC-Sponsored Testing of Motor-Operated Valves (5 June 1990, Topic: Weak link)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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