Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor ActuatorsML031140125 |
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
---|
Issue date: |
05/24/1990 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
---|
IN-90-037, NUDOCS 9005180095 |
Download: ML031140125 (5) |
|
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>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 May 24, 1990
NRC INFORMATION NOTICE NO. 90-37: SHEARED PINION GEAR-TO-SHAFT KEYS IN
LIMITORQUE MOTOR ACTUATORS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice alerts addressees to potential problems related to
sheared pinion gear-to-shaft keys in Limitorque motor actuators. It is ex- pected 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 April 27, 1990, the Public Service Electric & Gas Company (PSE&G) submitted
a 10 CFR Part 21 report to the NRC regarding a materials misapplication in valve
motor actuators supplied by the Limitorque Corporation at its Salem Nuclear Power
Generating Station, Units 1 and 2. PSE&G reported that it had discovered that
the pinion gear-to-shaft keys in the motor actuators of six service water valves
(three per unit) were sheared or severely deformed. These keys had failed under
conditions of normal operation, and one of them showed significant deformation
after only 15 valve cycles. The valve units use high-speed (3600 rpm) Limitorque
SMB-O actuators with 25 ft-lb of torque that operate 30-inch Jamesbury butterfly
valves. At Salem this type of valve is only used for the fast isolation (closing
within 10 secondsl of non-safety thermal loads in the turbine building from the
safety-related service water system load during accident conditions. These keys
failed after the licensee had replaced the original valves with the subject
Jamesbury valves in a recent upgrade program during the last fuel cycle. The
original valves manufactured by the Henry Pratt Company had Limitorque SMB-1 actuators.
The failure identified by PSE&G indicated that the failed keys had wedged
between the motor shafts and the pinion gears at the key-slots. These wedged
keys had allowed the valves to operate under low-flow conditions. However, during normal flow conditions, the failure of these keys could prevent the
valve units from operating reliably. PSE&G realized the magnitude of the
49t'180095
IN 90-37 May 24, 1990 problem after performing a thorough inspection following a second valve failure
during service water valve testing. The licensee did not initially realize the
magnitude of the problem because even during normal flow conditions, the valve
appeared to operate adequately, masking the potential for valve failure.
Discussion:
In the past, the NRC issued Information Notices 88-84, Defective Motor Shaft
Keys in Limitorque Motor Actuators;" 85-67, "Valve-Shaft-to-Actuator Key May
Fall Out of Place When Mounted Below Horizontal Axis;" and 81-08, "Repetitive
Failures of Limitorque Operator SMB-4 Motor-to-Shaft Key," regarding the failure
of keys in the actuators of motor-operated valves. These earlier failures
resulted either from use of improper materials or incorrect installations, whereas, the failure reported by PSE&G resulted from an apparent misappli- cation of material.
Although the licensee is continuing its investigation, the preliminary results
indicate that the failures resulted from the impact loading on the soft keyway
assemblies during fast valve closures. The licensee performed a hardness check
of a failed key and of 38 other keys in stock supplied by Limitorque. The
inspection confirmed that the material was within the ASTM-1018 range for
material hardness that was specified by Limitorque. The licensee also in- spected all 14 actuators supplied by Limitorque under the same purchase order
and found the remaining 8 actuators had no similar problems.-These-& actuators
are used for valves that are not required to close within 10 seconds and are
not subject to the same impact loading experienced in the failed service water
system valves.
PSE&G decided to replace the failed keys in the 6 valve actuators with keys
made from a harder material, such as ASTM-4140 stainless steel. The licensee
tested one valve with a key made from this new material with a hardness of 290
(Brinell) and found no apparent wear after it was operated for 60 valve cycles.
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. ossD rector
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Peter C. Wen, NRR
(301) 492-1172 Paul D. Swetland, RI
(215) 337-5114 Attachment: List of Recently Issued NRC Information Notices
Attachment
IN 90-37 May 24, 1990 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
.. . .. . ..... .... ...... .. ............. ..... ........... ........
Information Date of
Notice No. - Subject__ ---- -- -Issuance . --Issued-to.- . -.-
90-36 Apparent Falsification of 5/24/90 All holders of OLs
State of Connecticut or CPs for nuclear
Weight Certificates power reactors, and
10 CFR 70 licensees.
90-35 Transportation of Type A 5/24/90 All U.S. NRC licensees.
Quantities of Non-Fissile
Radioactive Materials
90-34 Response to False Siren 5/10/90 All holders of OLs
Activations or CPs for nuclear
power reactors.
90-33 Sources of Unexpected 5/9/90 All holders of OLs
Occupational Radiation or CPs for nuclear
Exposures at Spent Fuel power reactors.
Pools
.. .. I .; .. .... .
~~. ~ ~ :. . :- .
90-32 Surface Crack and Subsurface 5/3/90 All holders of OLs
Indications in the Weld of or CPs for nuclear
A Reactor Vessel Head power reactors.
90-31 Update on Waste Form and 5/4/90 All holders of OLs
High Integrity Container or CPs for nuclear
Topical Report Review power reactors, fuel
Status, Identification cycle licenses, and
of Problems with Cement certain by-product
Solidification, and materials licenses.
Reporting of Waste Mishaps
90-30 Ultrasonic Inspection 5/1/90 All holders of OLs
Techniques for Dissimilar or CPs for nuclear
Metal Welds power reactors.
90-29 Cracking of Cladding and 4/30/90 All holders of OLs
Its Heat-Affected Zone in or CPs for nuclear
the Base Metal of a Reactor power reactors.
Vessel Head
-__ ___
OL = Operating License
CP = Construction Permit
IN 90-37 May 24, 1990 problem after performing a thorough inspection following a second valve failure
during service water valve testing. The licensee did not initially realize the
magnitude of the problem because even during normal flow conditions, the valve
appeared to operate adequately, masking the potential for valve failure.
Discussion:
In the past, the NRC issued Information Notices 88-84, "Defective Motor Shaft
Keys in Limitorque Motor Actuators;" 85-67, "Valve-Shaft-to-Actuator Key May
Fall Out of Place When Mounted Below Horizontal Axis;" and 81-08, Repetitive
Failures of Limitorque Operator SMB-4 Motor-to-Shaft Key," regarding the failure
of keys in the actuators of motor-operated valves. These earlier failures
resulted either from use of improper materials or incorrect installations, whereas, the failure reported by PSE&G resulted from an apparent misappli- cation of material.
Although the licensee is continuing its investigation, the preliminary results
indicate that the failures resulted from the impact loading on the soft keyway
assemblies during fast valve closures. The licensee performed a hardness check
of a failed key and of 38 other keys in stock supplied by Limitorque. The
inspection confirmed that the material was within the ASTM-1018 range for
material hardness that was specified by Limitorque. The licensee also in- spected all 14 actuators supplied by Limitorque under the same purchase order
and found the remaining 8 actuators had no similar problems. These 8 actuators
are used for valves that are not required to close within 10 seconds and are
not subject to the same impact loading experienced in the failed service water
system valves.
PSE&G decided to replace the failed keys in the 6 valve actuators with keys
made from a harder material, such as ASTM-4140 stainless steel. The licensee
tested one valve with a key made from this new material with a hardness of 290
(Brinell) and found no apparent wear after it was operated for 60 valve cycles.
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: Peter C. Wen, NRR
(301) 492-1172 Paul D. Swetland, RI
(215) 337-5114 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS PAGE FOR CONCURRENCE
Document Name: IN LIMITORQUE KEY FAILURE
- OGCB:DOEA:NRR *RI *RPB:ADM *C/OGCB:DOEA:NRR
PCWen PSwetland TechEd CHBerlinger
05/15/90 05/15/90 05/16/90 05/17/90 05//90
IN 90-XX
- ¶V ~ May xx, 1990 of the problem after it performed a thorough inspection following a second
valve failure during service water valve testing. The licensee did not ini- tially realize the magnitude of the problem because, even during normal flow
conditions, the valve appeared to operate adequately, masking the potential for
valve failure.
Discussion:
In the past, the NRC issued Information Notices 88-84, "Defective Motor Shaft
Keys in Limitorque Motor Actuators," 85-67, "Valve-Shaft-to Actuator Key May
Fall Out of Place When Mounted Below Horizontal Axis," and 81-08, "Repetitive
Failures to Limitorque Operator SMB-4 Motor-to-Shaft Key," regarding the
failure of keys in the actuators of motor-operated valves. These earlier
failures resulted either from use of improper materials or incorrect installa- tions, whereas, the failure reported by PSE&G resulted from an apparent misap- plication of material.
Although the licensee is continuing its investigation, the preliminary results
indicated that the failure resulted from the impact loading on the soft keyway
assemblies during the fast valve closure. The licensee performed a hardness
check of a failed key and of 38 other keys in stock supplied by Limitorque.
The inspection confirmed that the material was within the ASTM-1018 range for
material hardness that was specified by Limitorque. The licensee also in- spected all 14 actuators supplied by Limitorque under the same purchase order
and found the remaining 8 actuators had no similar problems. These 8 actuators
are used for valves that are not required to close within 10 seconds and are
not subject to the same impact loading experienced in the failed service water
system valves.
PSE&G decided to replace the failed keys in the 6 valve actuators with keys
made from a harder material, such as ASTM-4140 stainless steel. The licensee
tested one valve with a key made from this new material with a hardness of 290
(Brinell), and found no apparent wear after it was operated for 60 valve
cycles.
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: Peter C. Wen, NRR
(301) 492-1172 Paul D. Swetland, RI
(215) 337-5114 Attachment: List of Recently Issued NRC Information Notices
X ciJ Document Name: IN LIMITORQUE KEY FAILURE ( -
GCB:DOEA:NRd RI RPB:ADM C/OGIX:OEAANRR D/DOEA:NRR
PCWen W S e~laWind TechEd :7i9lli CHBerlinger CERossi
05//5/90 1 05/157/90 05/IC/90 ' 0541(/90 05/ /90
PKtML.Cow.
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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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