Inter-System Discharge of Reactor CoolantML031130342 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
01/29/1990 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-90-005, NUDOCS 9001230126 |
Download: ML031130342 (8) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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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 [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UK UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 January 29, 1990 NRC INFORMATION
NOTICE NO. 90-05: INTER-SYSTEM
DISCHARGE
OF REACTOR COOLANT
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.
Purpose
- This information
notice is intended to. alert addressees
to a potentially
significant
problem in identifying
and terminating
reactor coolant system leakage in operating
modes 4 and 5. It is expected that licensees
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 December 1, 1989, Braidwood
Unit 1 experienced
the unplanned
inter-system
discharge
of approximately
68,000 gallons of water. The discharge
was caused by the inadvertent
opening of a residual heat removal (RHR) system suction relief valve. The valve failed to reclose, allowing an open flow path from the reactor vessel, through the RHR system, into the unit's two recycle hold-up tanks (HUTs).The unit, which had been in a refueling
outage since September
2, 1989, was heating up in operational
mode 5, preparing
to enter operational
mode 4. The plant was solid and in the process of drawing a bubble in the pressurizer.
The RHR train "A" pump was in operation
and, although the "BO pump was not running, the "B" train was unisolated
and available.
The reactor coolant system (RCS)was at a pressure of 350 psig .and a temperature
of 175 0 F. Charging flow to the vessel was being provided by the "A" charging pump. Pressurizer
heaters were on. The "B" charging pump was Isolated and tagged out of service. (Technical
Specifications
governing
cold overpressure
protection
require that only one charging pump be available.
The other charging pump and the safety injection pumps are required to be tagged out of service, with power supplies removed).To protect against a pressure switch failure and the subsequent
automatic isolation
of the RHR system, the train "A" RHR suction isolation
valve was open and tagged out of service.90130126 Z #
IN 90-05 January 29, 1990 At 1:42 a.m., operators
throttled
the charging flow and maximized
the letdown flow in preparation
for drawing a bubble in the pressurizer.
The RCS pressure was 404 psig and the pressurizer
level was off scale, high. At 1:44 a.m., a rapid reduction
in the pressurizer
level occurred, with the pressurizer
level off scale, low, at 1:52 a.m. Approximately
14,000 gallons of water drained from the pressurizer
and the pressurizer
surge line; however, the reactor vessel level instrumentation
system indicated
that the vessel level remained at 100 percent. At 1:49 a.m., the charging flow was increased
and the charging pump suction was switched from the volume control tank to the refueling
water storage tank (RWST).About 30 to 50 gallons of water were observed on the floor of the auxiliary building in proximity
to the RHR train "AN suction relief valve, leading plant personnel
to believe that this valve had lifted. At 1:53 a.m., the letdown flow was reduced to minimum and charging was maximized.
The RHR trains were switched from "A" to EB", the "A" pump was stopped, and the isolation
of the"A" train was initiated.
At 1:59 a.m., one of the two running reactor coolant pumps (RCPs) was stopped because of low RCS pressure.A second charging pump, NBN, was started following
completion
of the formal pro-cedure for tagout removal. At 2:35 a.m., the "A RHR suction isolation
valve was returned to service and closed, completing
the isolation
of the "A" train of the RHR system. The pressurizer
level began to recover and the RCS pressure increased
slightly, giving operators
the impression
that the discharge
had been isolated.
The *B" charging pump was therefore
secured at 2:45 a.m. The pres-surizer level, however, did not recover. At 2:54 a.m., the ABN charging pump was restarted.
At 3:49 a.m., the inter-system
discharge
was terminated
when the RHR train WA" pump was started, the "B pump shut down, and the "8' train was isolated.
The level indication
for the HUTs stabilized
and the pressurizer
level began to recover at 3:52 a.m.By 5:06 a.m., the pressurizer
level had fully recovered
and the unit was sta-bilized at 360 psi and 1750F. Approximately
68,000 gallons of water had been discharged
from the reactor vessel to the HUTs. (The total amount of water was composed of 14,000 gallons of initial pressurizer
inventory
and 54,000 gallons of makeup water).Following
the event, it was determined
that the RHR MB" train suction relief valve had lifted at 411 psi. The lift setpoint for the valve should have been 450 psi. The valve should have reclosed on reducing pressure but failed to do so. The premature
opening of the valve was attributed
to the presence of foreign material lodged between the valve spindle and the spindle guide. This foreign material either prohibited
the correct adjustment
of the valve or affected the valve's lift setpoint.
The valve's failure to reclose was attributed
to im-proper nozzle ring adjustment.
The reset pressure is strongly influenced
by the dynamic forces created by the nozzle ring. If the ring is located too high on the nozzle, it may result in an inadequate
ventilation
area just above the nozzle. Undesirable
forces will develop which may cause a much lower reseat pressure.The water found near the RHR train "A" suction relief valve had leaked from a weep hole on a relief valve in a radwaste evaporator
line connected
to the
IN 90-05 January 29, 1990 common discharge
header of the train "A" and "B" suction relief valves. Con-trary to original assumptions, there was no evidence that the OA" train suction relief valve had lifted. The root cause of the problem with the relief valve on the evaporation
line is under investigation
but is thought to be unrelated to the failure of the 'BM suction relief valve.Hampering
operators'
efforts throughout
this event was the lack of an appro-priate emergency
operating
procedure (EOP) to detect coolant leaks while in operating
modes 4 and 5. However, the operators
were able to combine two related abnormal operating
procedures
for guidance during this event. One of the procedures
is designed to locate system leaks while in modes 3 and 4.The other provides guidance for the restoration
of the RHR system following its loss during conditions
in which the reactor vessel inventory
is at a reduced level.Discussion:
The event at Braidwood
1 is significant
because it underscores
the need to have EOPs available
for use in other than 'at power" operating
modes. The fact that over 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> were required to locate the stuck-open
valve, to terminate
the discharge, and to begin refilling
the pressurizer
highlights
the need to provide personnel
with adequate tools to perform their tasks.Relying on ad hoc procedures
during significant
events places an unnecessary
burden on operating
personnel.
The lack of adequate EOPs could handicap the most competent
operators
in their efforts to address significant
operational
problems.Also illustrated
by this event Is the need for procedures
to assure that adequate RCS makeup capability
and cooling options are available
in a timely fashion during shutdown.
The discharge
through the stuck-open
relief valve exceeded the capability
of a single charging pump. Starting a second charging pump required that formal procedures
for tag removal be conducted.
This effort necessitated
a considerable
amount of time, which may not be available
should a similar event occur while the RCS is at a higher temperature.
The severity of this event could have been increased
if greater decay heat were present in the reactor vessel or if a gross failure of the relief valve discharge header had occurred.
Greater decay heat would have increased
the potential
for voiding in the core. Also, because the header discharges
to the HUTs which are located outside containment, a piping failure could have resulted in all or a portion of the RCS water being discharged
to the building floor. This event would have necessitated
a major cleanup effort and increased
the potential
for personnel
contamination.
If this event had occurred at one of the nuclear plants that has a single suction line from the RCS to the RHR system, all shutdown cooling would have been lost as a result of isolating
the failed suction relief valve.An alternate
heat sink would likely have been required;
however, in mode 5, an alternate
heat sink may not be readily available.
IN 90-05 January 29, 1990 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
NRR project manager.arl E. ss, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts:
Nick Fields, NRR (301) 492-1173 Julian Hinds, RIII (315) 388-5575 Attachment:
List of Recently Issued NRC Information
Notices
Attachment
IN 90-05 January 29, 1990 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice-No..
Subject -Issuance Issued to-el 90-04 Cracking of the Upper Shell-to-Transition
1/26/90 All holders of OLs or CPs for Westinghouse- designed and Combustion
Engineering-designed
nuclear power reactors.90-03 90-02 90-01 89-90 89-89 89-88 89-87 89-45, Supp. 2 89-86 Malfunction
of Borg-Warner
Bolted Bonnet Check Valves Caused by Failure of the Swing Arm Potential
Degradation
of Secondary
Containment
Importance
of Proper Response to Self-Identified
Violations
by Licensees Pressurizer
Safety Valve Lift Setpoint Shift Event Notification
Worksheets
Recent NRC-Sponsored
Testing of Motor-Operated
Valves Disabling
of Emergency Diesel Generators.
by Their Neutral Ground-Fault
Protection
Circuitry Metalclad, Low-Voltage
Power Circuit Breakers Refurbished
with Substandard
Parts Type HK Circuit Breakers Missing Close Latch Anti-Shock Springs.1/23/90 1/22/90 1/12/90 12/28/89 12/26/89 12/26/89 12/19/89 12/15/89 12/15/89 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for BWRs.All holders of NRC materials
licenses.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.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.OL = Operating
License CP = Construction
Permit
IN 90-05 January 29, 1990 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
NRR project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts: Nick Fields, NRR (301) 492-1173 Julian Hinds, RIII (315) 388-5575 Attachment:
List of Recently Issued NRC Information
Notices*SEE PREVIOUS PAGE FOR CONCURRENCE
1/12/90*TECH:EDITOR
- EAB:NRR DCFischer 1/14/90 1/16/90*C:EAB:NRR
CJHaughney
1/18/90*C:OGCB:NRR
CHBerlinger
1/22 /90 Ross 11/.AY9O
.-;IN 90-January , 1990 No specific action or written response is required by this information
notice. If you have any questions
about this matter, please contact one of the technical
contacts listed below or the Regional Administrator
of the appropriate
regional office.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts: Nick Fields, NRR (301) 492-1173 Julian Hinds,RIII
(315) 388-5575 Attachment:
List of Recently Issued Information
Notices JJV I'Ins m ofi w EAB:NRR TECH:EDITOR
EAB:NRR NFields:db
DCFischer/ /,1-90 1 /*t/90 1/ i190 C: EB:NRR CJHaughney
I As/90 coY C:OGCB:NRR
CHBerlinger
I/.090 D:DOEA:NRR
CERossi/ /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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