Testing of Parallel Disc Gate Valves in EuropeML031130199 |
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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
11/28/1990 |
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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-90-072, NUDOCS 9011210137 |
Download: ML031130199 (7) |
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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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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>. |
I
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 November 28, 1990
NRC INFORMATION NOTICE NO. 90-72: TESTING OF PARALLEL DISC GATE VALVES
IN EUROPE
Addressees
All holders of operatinglicenses or construction permits for nuclear power
reactors.
Purpose
This information'notice is intended to alert addressees to the results of tests
of parallel disc gate valves by researchers from the United Kingdom (UK) and
theFederal Republic of Germany (FRG);. It is expected -that recipients will
review 'the information for applicability to their facilities and consider
actions, as appropriate, to avoid similar problem.;. However, suggestions
contained in this information notice do not constitute NRC requirements;
therefore, no specific action or written response Is required.
Discussion:
On October 15 to 19, 1990, members of the U.S. Nuclear Regulatory Commission
(NRC) staff met with nuclear regulatory authorities and industry representa- tives in the UK and the FRG to discuss the performance of motor-operated valves
(MOYs)4at nuclear power plants. During these discussions, researchers from
both the UK and the FRG described tests of the operation of parallel disc gate
valves under'high differential pressure and flow conditions. According to the
UK and FRG researchers, the tests resulted in internal damage to the gate
valves. This damage included-abrasion and galling of the disc-and seat sliding
surfaces. Because of this damage, significantly more thrust was required to
operate'the'valves than was predicted by the commonly-used equation. In some
instances, the increased thrust requirements could have exceeded the setting of
the MOV torque switch or the capability of the motor operator.
During the meetings, the FRG representatives reported that an improved design
for parallel disc gate valves had been developed. This improved design has
additional sliding surface area to eliminate the excessive thrust requirements
for valve operation. The FRG representatives reported that, as a result of
their valve tests, the FRG valve vendors now typically assume a valve friction
factor of 0.4 (plus or minus 0.1) in the commonly-used equation to estimate the
thrust required to operate the improved valve design. In the United States, a
valve friction factor of 0.2 is typically assumed for all parallel disc gate
9011210137
r
IN 90-72 November 28, 1990 valves even though little research has been conducted regarding the performance
of these valves under conditions of high differential pressure and flow.
A summary of the FRG parallel disc gate valve tests is provided in "Testing of
Safety-Related Valves of PWR and BWR Power Plants," by U. Simon, N. Rauffmann, and H. Schafer, which is printed in The American Society of Mechanical
Engineers, PYP - Volume 180, Pipeline Dynamics and Valves (1989).
The parallel disc gate valve tests performed by the UK and FRGresearchers
provided results similar to the results of the NRC-sponsored tests of
flexible-wedge gate valves performed by researchers at the Idaho National
Engineering Laboratory. As with the tests of parallel disc-gate valves per- formed by UK and FRG researchers, the NRC-sponsored tests revealed that inter- nal damage may occur to the flexible-wedge gate valves when operated under
conditions of high differential pressure and flow. Because of this internal
damage, the thrust required to operate the flexible-wedge gate valves exceeded
the thrust predicted from t.e commonly-used equation and typical friction
factors. The NRC-sponsored test results were discussed at public meetings on
February 1, 1989, and April 18, 1990, and are summarized in NRC Information
Notice 90-40, "Results of 1IRC-Sponsored Testing of Motor-Operated Valves."
Licensees and constructiot permit holders may wish to consider the results of
the UK and FRG tests when evaluating the capability of currently-installed
parallel disc gate valves and when considering the adequacy of replacement
vaves.i
This information notice requires no specific action or written response. If
you have any questions ribout the information in this notice, please contact the
technical contact listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Tfiomas'G. Scarbrough, NRR
(301) 492-0794 Attachment: List of Recently Issued NRC Information Notices
s . .
S
Attachment 1 IN 90-72 November-28, 1990 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
90-71 Effective Use of Radi- 11/6/90 All NRC licensees
ation Safety Committees authorized to use by- to Exercise Control Over product material for
Medical Use Programs medical purposes.
90-70 Pump Explosions Involving 11/6/90 All uranium fuel
Ammonium Nitrate fabrication and
conversion
facilities.
90-38, License and Fee Require- 11/6/90 All fuel facility and
Supp. 1 ments for Processing Fin- materials licensees.
ancial Assurance Submittals
for Decommissioning
89-30, High Temperature Environ- 11/1/90 All holders of OLs
Supp. 1 ments At Nuclear Power or CPs for nuclear
Plants power reactors.
90-69 Adequacy of Emergency and 10/31/90 All holders of OLs
Essential Lighting or CPs for nuclear
power reactors.
90-68 Stress Corrosion Cracking 10/30/90 All holders of OLs
of Reactor Coolant Pump Bolts or CPs for pres- surized water
reactors (PWRs).
90-67 Potential Security Equipment 10/29/90 All holders of OLs
Weaknesses or CPs for
nuclear power
reactors and
Category I fuel
facilities.
90-66 Incomplete Draining and 10/25/90 All holders of OLs
Drying of Shipping Casks for nuclear
power reactors
and all registered
users of NRC
approved waste
shipping packages.
OL = Operating License
CP = Construction Permit
IN 90-72 November 28, 1990 valves even though little research has been conducted regarding the performance
of these valves under conditions of high differential pressure and flow.
A summary of the FRG parallel disc gate valve tests is provided in Testing of
Safety-Related Valves of PWR and BWR Power Plants," by U. Simon, N. Rauffmann, and H. Schafer, which is printed in The American Society of Mechanical
Engineers, PVP - Volume 180, Pipeline Dynamics and Valves (1989).
The parallel disc gate valve tests performed by the UK and FRG researchers
provided results similar to the results of the NRC-sponsored tests of
flexible-wedge gate valves performed by researchers at the Idaho National
Engineering Laboratory. As with the tests of parallel disc gate valves per- formed by UK and FRG researchers, the NRC-sponsored tests revealed that inter- nal damage may occur to the flexible-wedge gate valves when operated under
conditions of high differential pressure and flow. Because of this internal
damage, the thrust required to operate the flexible-wedge gate valves exceeded
the thrust predicted from the commonly-used equation and typical friction
factors. The NRC-sponsored test results were discussed at public meetings on
February 1, 1989, and April 18, 1990, and are summarized in NRC Information
Notice 90-40, "Results of NRC-Sponsored Testing of Motor-Operated Valves.'
Licensees and construction permit holders may wish to consider the results of
the UK and FRG tests when evaluating the capability of currently-installed
parallel disc gate valves and when considering the adequacy of replacement
valves.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact the
technical contact listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Thomas G. Scarbrough, NRR
(301) 492-0794 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURJEyJC&y
DtDO ^f/ *C/OGCB:DOEA:NRR*AD/GPA:IP *RPB:ADM
CHBerlinger RHauber TechEd
11, J/90 11/19/90 11/16/90 11/06/90
- OGCB:DOEA:NRR*EMEB DET:NRR *EMEB:DET:NRR *C/EMEB:DET:NRR *D/DET:NRR
RJKiessel TGScarbrough EJSullivan LBMarsh JERichardson
11/07/90 11/09/90 11/09/90 11/09/90 11/14/90
Document Name: IN 90-72
IN 90-XX
November xx, 1990 the performance
valves even though little research has been conducted regarding and flow.
of these valves under conditions of high differential pressure
in uTesting of
A summary of the FRG parallel disc gate valve tests is provided N. Rauffmann, Safety-Related Valves of PWR and BWR Power Plants," by U. Simon, and H. Schafer, which is printed in The American Society of Mechanical
Engineers, PVP - Volume 180, Pipeline Dynamics and Valves (1989).
researchers
The parallel disc gate valve tests performed by the UK and FRG of
tests
provided results similar to the results of the NRC-sponsoredIdaho National
flexible-wedge gate valves performed by researchers at the valves per- Engineering Laboratory. As with the tests of parallel disc gate that inter- formed by UK and FRG researchers, the NRC-sponsored tests revealed under
nal damage may occur to the flexible-wedge gate valves when operated this internal
of
conditions of high differential pressure and flow. Becausegate valves exceeded
damage, the thrust required to operate the flexible-wedge
friction
the thrust predicted from the commonly-used equation and typical meetings on
factors. The NRC-sponsored test results were discussed atinpublicNRC Information
February 1, 1989, and April 18, 1990, and are summarized Valves."
Notice 90-40, "Results of NRC-Sponsored Testing of Motor-Operated
results of the
Licensees and construction permit holders should be aware of the parallel
UK and FRG tests when evaluating the capability of currently-installed valves.
disc gate valves and when considering the adequacy of replacement
response. If
This information notice requires no specific action or written contact the
please
you have any questions about the information in this notice, manager.
technical contact listed below or the appropriate NRR project
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Thomas G. Scarbrough, NRR
(301) 492-0794 Attachment: List of Recently Issued NRC Information Notices
Document Name: UK AND FRG MOV TESTING RESULTS
- SEE PREVIOUS CONCURRENCES () 3
/
D/DOEA:NRR C/OGCB:uE h:NRR*AD/GPA:IP *RPB:ADM
CERossif CHBerlinger RHauber TechEd
11/ /90 11//90 11/16/90 11/06/90
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- OGCB:DOEA:NRR*EMEB:DET:NRR
RJKlessel TGScarbrough EJSullivan LBMarsh JERichardson
11/07/90 11/09/90 11/09/90 11/09/90 11/14/90
IN 90-XX
November xx, 1990 performance
valves even though little research has been conducted regarding the flow.
and
of these valves under conditions of high differential pressure
of
A summary of the FRG parallel disc gate tests is provided in "Testing N.Rauffmann, Safety-Related Valves of PWR and BWR Power Plants," by U. Simon, and H. Schafer, which is printed in The American Society of Mechanical
Engineers, PYP - Volume 180, Pipeline Dynamics and Valves (1989).
researchers
The parallel disc gate valve tests performed by the UK and FRGtests of
provided results similar to the results of the NRC-sponsoredIdaho National
flexible-wedge gate valves performed by researchers at the valves per- Engineering Laboratory. As with the tests of parallel disc gate that inter- formed by UK and FRG researchers, the NRC-sponsored tests revealed
operated under
nal damage may occur to the flexible-wedge gate valves when internal
of this
conditions of high differential pressure and flow. Because exceeded
damage, the thrust required to operate the flexible-wedge gate valves used
typically
the thrust predicted from the commonly-used equation and the on public
friction factors. The NRC-sponsored test results were discussed in NRC
meetings on February 1, 1989, and April 18, 1990, and are summarized
of Motor-Operated
Information Notice 90-04, "Results of NRC-Sponsored Testing
Valves."
results of the
Licensees and construction permit holders should be aware of the installed parallel
UK and FRG tests when evaluating the capability of currently valves.
disc gate valves and when considering the adequacy of replacement
response. If
This information notice requires no specific action or writtenplease contact the
you have any questions about the information in this notice, technical contact listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Thomas G. Scarbrough, NRR
(301) 492-0794 Attachment: List of Recently Issued NRC Information Notices
Document Name: UK AND FRG MOV TESTING RESULTS
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEA:NRR AD/ i J:IP *RPB:ADM
CERossi CHBerlinger Ii b#r TechEd
11/ /90 11/ /90 117/4/90 11 11/06/90,
OGCB:DOEA:NRR E EP)BE:NRR £~gBDE:NRR C/E EB:DE1:AIR D/DET:NRR7¶ 6f "
RJKiessel TaGnbiough PsJFul- n LBMarsh JERic ar +n
11/X9/90 i1/go 11/i190 11/ /90 1/7/90
a ,je t 4n
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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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