Potential for Common-Mode Failure of High Pressure Safety Injection Pumps or Release of Reactor Coolant Outside Containment During a Loss-Of-Coolant AccidentML031130251 |
Person / Time |
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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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
10/04/1990 |
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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-90-064, NUDOCS 9009280049 |
Download: ML031130251 (10) |
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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, 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 [[: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 [[: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 October 4, 1990
POTENTIAL FOR COMMON-MODE FAILURE OF HIGH
NRC INFORMATION NOTICE NO. 90-64:
PRESSURE SAFETY INJECTION PUMPS OR RELEASE
OF REACTOR COOLANT OUTSIDEE CONTAINMENT DURING
A LOSS-OF-COOLANT ACCIDENI
Addressees
permits for pressurized-water
All holders of operating licenses or construction
reactors.
Purpose
addressees to the potential
This information notice is being provided to alert injection pumps (charging
for the common-mode failure of the high-head safety coolant outside of contain- pumps) due to gas binding or the release of reactordepending upon the manner in
ment during a loss of coolant accident (LOCA), installed. It is expected that
which the vent line isolation valves have been to their facilities
recipients will review the information for applicability
similar problems. However, and consider actions, as appropriate, to avoid do not constitute NRC re- suggestions contained in this information notice response is required.
quirements; therefore, no specific action or written
Description:
in preparation for refueling
On July 9, 1990, with the plant in cold shutdown
Volume Control Tank (VCT) discharge
operations, the Haddam Neck licensee had the Volume Control System (CYCS).
and vent flow paths isolated in the Chemical and
water storage tank (RWST),
The charging pumps were aligned to the refueling system in operation. The
with a train of the residual heat removal (RHR)
water was draining from the
Haddam Neck licensee subsequently discovered that (see Figure 1). The 3/4-inch
VCT through the high-point vent isolation valves isolation valves, provides for
vent line, containing two ASCO solenoid-operated of the charging pump
continuous venting of hydrogen from the high points operations. Further
suction piping to the VCT, during normal CYCS letdown valves would not isolate
investigation by the licensee revealed that the ASCO unseats with a differen- in the reverse flow direction because the valve discThe licensee indicated, as
tial pressure across the valve seat of 15-30 psid. solenoid- a result of discussions held with ASCO, that no ASCO-manufactured
in the reverse flow direction.
operated valves were designed to provide isolation
(SIAS) causes the normal
Initiation of a safety injection actuation signal closure of-the VCT dis- discharge path from the VCT to isolate by automatic pumps is then switched
charge isolation valves. The suction of the charging
( 9009280049
IN 90-64, October 4, 1990 from the VCT to the RWST. The ASCO vent line isolation valves
matically upon closure of the VCT discharge isolation valves andare shut auto- manually
de-energized. With the valves in the closed position, a differential pressure
in the reverse flow direction could allow gases in the VCT to pass
high-point vent line and. cause gas binding of the pumps. Haddam through the
to this concern by adding two check valves as shown in Figure 1. Neck responded
Discussion:
At Haddam Neck, the licensee identified a possible common-mode failure
high-point vent isolation valves in the suction vent line that connects to both
charging pumps to the YCT. The common mode failure occurs if there the
is leakage
flow through both valves after they have been shut. From their discussions
with the valve manufacturer (ASCO), the licensee learned that these
designed to provide isolation in one flow direction only. The ASCO valves are
identified as solenoid-operated, two-way, 1/2 inch isolation valves valves are
maximum pressure rating of 400 psig and are commerical grade. The with a
model
numbers of the valves are 6109R and L8211D89. The installed configuration
the ASCO valves at Haddam Neck was such that failure of these valves of
during a LOCA (i.e., during the ECCS injection phase) could drain to isolate
and allow hydrogen gas in the VCT (and any gas that had accumulateddown the VCT
line) to be transported to the suction of the charging pumps by way in the vent
high-point vent charging pump suction line. of the
A second scenario, was identified by the licensee involving the
recirculation
phase of a small-break LOCA, when the RHR pumps supply reactor coolant
sump to the suction header of the charging pumps. If the ASCO valves from the
installed in the reverse direction (i.e., to isolate venting from are
the suction of the charging pumps), then the discharge pressure the VCT to
from the RHR
pumps would be enough to increase pressure in the vent line to the
valves so as to lift the valve discs off of their seats and pressurizeASCO isolation
in excess of the 75 psig VCT relief setpoint. This would allow the VCT
reactor coolant outside containment. a release of
In addition, if the two ASCO vent line valves are installed in opposite
a single failure of a vent line isolation valve could lead to either directions, or a release of reactor coolant outside of containment. Licensees gas binding
with similar
vent lines and ECCS pump arrangements may wish to review the above
for applicability to their plants. information
The effectiveness of the Haddam Neck high point vent configuration
Figure 1) was not evaluated in conjunction with the development (as shown in
of this informa- tion notice. It is important that any plant modifications made
hydrogen buildup concerns do not introduce other ways for gas to to alleviate
into the charging pump suction or other safety concerns. be ingested
IN 90-64, October 4, 1990 Safety
Information notice 88-23, "Potential for Gas Binding of High Pressure 1 Injection Pumps During A Loss-Of-Coolant Accident" (including Supplements
of high
and 2) also describes situations that could result in gas binding
pressure safety injection pumps.
notice.
No specific action or written response is required by this information
If you have any questions about this matter, please contact the technical
NRC
contact 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 Contact:
John Thompson, NRR
(301) 492-1171 Attachments: 1. Figure 1, Haddam Neck High Point Vent Line
2. List of Recently Issued NRC Information Notices
v Detachment 1 IN 90-64 October 4, 1990 Haddam Neck High Point Vent Line
ASCO 1/2" solenoid valves
installed check valves
To
WIST
Charging Pump
Is I
Charging Pump From RHR
PuMpO
Attachment 2 IN 90-64 October 4, 1990 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
90-63 Management Attention to the 10/3/90 All fuel cycle
Establishment and Main- licensees possess- tenance of A Nuclear ing more than
Criticality Safety Program critical mass
quantities of
special nuclear
material.
90-62 Requirements for Import 9/25/90 All irradiated
and Distribution of gemstone importers
Neutron-Irradiated Gems and distributors, and all non-power
licensees.
90-61 Potential for Residual 9/20/90 All holders of
Heat Removal Pump OLs or CPs for
Pump Damage Caused By nuclear power
Parallel Pump Interaction reactors.
90-60 Availability of Failure 9/20/90 All holders of
Data In the Government- OLs or CPs for
Industry Data Exchange nuclear power
Program reactors.
90-59 Errors In the Use of 9/17/90 All medical
Radioactive Iodine-131 licensees.
90-58 Improper Handling of 9/11/90 All NRC medical
Ophthalmic Strontium-90 licensees.
Beta Radiation Applicators
90-57 Substandard, Refurbished 9/5/90 All holders of OLs
Potter & Brumfield Relays or CPs for nuclear
Misrepresented As New power reactors.
90-56 Inadvertent Shipment of A 9/4/90 All U.S. Nuclear
Radioactive Source In A Regulatory Com- Container Thought To Be mission (NRC)
Empty licensees.
OL = Operating License
CP = Construction Permit
IN 90-64, October 4, 1990 Information notice 88-23, "Potential for Gas Binding of High Pressure Safety
Injection Pumps During A Loss-Of-Coolant Accident" (including Supplements 1 and 2) also describes situations that could result in gas binding of high
pressure safety injection pumps.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate NRC
regional office.
.kLCtharles E. Rossi, Directo
( Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
John Thompson, NRR
(301) 492-1171 Attachments: 1. Figure 1, Haddam Neck High Point Vent Line
2. List of Recently Issued NRC Information Notices
- See Previous Concurrence 9 4 1 OFC :OEAB:DOEA :AC:OEAB:DO A:RPB:ADM :D:DST:NRR :C:OGCB:DOEA :D:DOE:R
X
NAME :*JWThompson :*DCFischer :*Tech Ed :*ACThandani :*CHBerlinger:ERossi
DATE :08/28/90 :08/28/90 :08/28/90 :09/04/90 :09/17/90 :09agyggo :
OFFICIAL RECORD COPY
Document Name: INFORfTO'-- //J qo90-c,
rN 90-xx, ,
vU ve r-X, 1990
,Pge 3 of 3 and 2) also describes situations that could result i gas binding of high
pressure safety injection pumps.
No specific action or written response is requi d by this information notice.
If you have any questions about this matter, ease contact the technical
contact listed below or the Regional Adminis ator of the appropriate NRC
regional office.
harles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
John Thomp on, NRR
(301) 492 171 Attachments: 1. Figure 1 Haddam Neck High Point Vent Line
2. List of Recently Issued NRC Information Notices
OFC :OEAB:DOEA :AC:OEAB:DOEA:RPB:ADM :D:DST:NRR :C:OGCB:DOEA :D:DOEA:NRR :
NAME :*JWThompson :*DCFischer :*Tech Ed :*ACThandani :*CHBerlinger:ERossi
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DATE :08/28/90 :08/28/90 :08/28/90 :09/04/90 :09/17/90 :09/ /90 :
OFFICIAL RECORD COPY
Document Name: INFORNOT
IN 88-23, SUPPLEMENT 3 September XX, 1990 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate NRC
regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
John Thompson, NRR
(301) 492-1171 Attachments: 1. Figure 1, Haddam Neck High Point Vent Line
2. List of Recently Issued NRC Information Notices
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NAME :*JWThompson :*DCFischer :*Tech Ed :*ACThandani :CHBerlinger :ERossi
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DATE :08/28/90 :08/28/90 :08/28/90 :09/04/90 :09/17/90 :09/ /90
OFFICIAL RECORD COPY
Document Name: INFORNOT
IN 88-23, SUPPLEMENT 3 August XX, 1990 valves are de-energized and shut upon closure of the VCT discharge isolation
valves. With the valves in the closed position, a differential pressure buildup
in the reverse flow direction could allow gases in the VCT to be siphoned through
the high-point vent line and gas bound the pumps. Haddam Neck responded to this
concern by adding two check valves as shown in Figure 1.
Discussion:
At Haddam Neck the licensee identified a possible common-mode failure to both
high-point vent isolation valves in the suction vent line that connects the
charging pump to the VCT. The common mode failure occurs if there is flow
through both valves after they have been shut. From their discussions with the
valve manufacturer (ASCO), the licensee learned that these valves are designed
to provide isolation in one flow direction only. The installed configuration of
the ASCO valves at Haddam Neck was such that failure of these valves to isolate
during a LOCA could allow hydrogen gas in the YCT (and any gas that had accumulated
in the vent line) to be transported to the suction of the charging pumps by way
of the high-point vent charging pump suction line. If the ASCO valves are
installed in the reverse direction (i.e., to isolate venting from the VCT to the
suction of the charging pumps), then operation of the RHR pumps in a LOCA
scenario could allow enough differential pressure to be exerted against the
valve discs to lift them off of their seats and pressurize the vent line to the
VCT in excess of the 75 psig VCT relief setpoint. This could allow a release
of reactor coolant outside containment. If the vent line valves are installed
in opposite directions, the safety concern is that a single failure could lead
to either gas binding or release of reactor coolant outside of containment.
Licensees with similar vent lines and ECCS pump arrangements may wish to review
the above information for applicability to their plants.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate NRC
regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Rdactor Regulation
Technical Contact:
John Thompson, NRR
(301) 492-1171 Attachments: 1. Figure 1, Haddam Neck ohnt Vent Line
2. List of Recentl Iss N C Information Notices
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OFFICIAL RECORD COPY
Document Name: INFONOTE 8823 SUPP 3
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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, Thermal fatigue)
- 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, Uranium Hexafluoride)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Stress corrosion cracking, Liquid penetrant)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Nondestructive Examination, Stress corrosion cracking, 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, Topic: Uranium Hexafluoride)
- 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, Topic: Exclusive Use)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- 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, Topic: Uranium Hexafluoride)
- 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: Intergranular Stress Corrosion Cracking, Dissimilar Metal Weld, Exclusive Use)
- 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, Topic: Overexposure)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990, Topic: Siren)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990, Topic: Siren)
- Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990, Topic: Siren)
- Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990, Topic: Authorized possession limits, Stress corrosion cracking)
- 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, Siren)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990, Topic: Siren)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990, Topic: Siren)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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