Failure of Borg-Warner Gate Valves to Close Against Differential PressureML031180726 |
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
08/30/1989 |
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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-89-061, NUDOCS 8908240164 |
Download: ML031180726 (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, 05000000, Zimmer, 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 [[:05000000]] OR [[:Zimmer]] 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 [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
A
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 August 30, 1989 NRC INFORMATION NOTICE NO. 89-61: FAILURE OF BORG-WARNER GATE VALVES TO
CLOSE AGAINST DIFFERENTIAL PRESSURE
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice is intended to alert addressees to potential problems
resulting from Borg-Warner gate valves with air or motor actuators failing to
close against differential pressures. It is expected that recipients will
review the information for applicability to their facilities and consider
actions, as appropriate, to avoid similar problems. However, suggestions
contained in this information notice do not constitute NRC requirements;
therefore, no specific action or written response is required.
Description of Circumstances
On March 14, 1988, a motor-driven auxiliary feedwater (AFW) pump discharge
isolation motor-operated valve (MOV) failed to fully close against a differen- tial pressure of 1800 psi at Catawba Nuclear Power Plant, Unit 2. The valve
failed while an AFW piping flush was being performed. At the time of the*
failure, the reactor was shut down and the steam generators were in hot standby.
The failure of the MOY to fully close was a contributing factor that led to
overfilling steam generator 2A and resulted in an automatic feedwater isola- tion. The licensee, Duke Power Company, investigated the failure and reported
(Licensee Event Report No. 414/89-10) the cause to be a higher valve factor
than originally specified by the valve manufacturer, Borg-Warner, for sizing
valve actuators. The valve factor is the term which is multiplied by the valve
seat area and the differential pressure across the valve to calculate one of
the parameters used in the standard valve thrust formula. If a low valve
factor is used when sizing the valve air or motor actuator, the calculated
required valve thrust will also be low. This results in low torque switch
settings being specified and, in some cases, can result in undersized air or
motor actuators.
Discussion:
The AFW MOV that failed to close against 1800 psi, 2CA62A, was a Borg-Warner
4-inch, 1500-psi, flexible wedge, carbon steel gate valve with a pinned body
8908240164
IN 89-61 August 30, 1989 guide insert ring disk guide. Actuation of the torque switch stops the motor
when the valve is closed and fully seated. The torque switch was not bypassed
in the closing direction. Following the March 14, 1988, failure to close, the
valve was diagnostically tested and the switch settings were found to be within
specified tolerances. Since no problems were found with the torque switch
settings, the valve was retested at 1800 psi differential pressure and again
failed to fully close. In order to get the valve to fully close at 1800 psi
differential pressure, the closed torque switch setting had to be increased to
the maximum allowed by the manufacturer's design calculations. During the
subsequent refueling outage, the valve was disassembled and inspected by the
licensee in order to determine what was creating the excessive friction between
the disk and seat rings. The inspection did not reveal any damage or condi- tions that would have caused excessive friction.
In November 1988, Duke Power Company performed differential pressure testing
on an MOV identical in design to 2CA62A. This testing was performed on a test
loop at the Riverbend Steam Station. During the testing, valve signature
analysis was obtained. This testing resulted in higher than anticipated seating
loads at high differential pressure conditions, and the valve failed to close
on two of the tests completed with differential pressures greater than 1500
psi.
In November 1988, four Catawba Nuclear Power Plant Unit 1 AFW MOVs, identical in
design and size to 2CA62A, were differential pressure tested at l800 psi.ATll
four valves indicated intermediate position after being closed during the test
and were 1/8 inch to 1/2 inch from the fully closed position. The test results
identified that all four valves failed to wedge completely shut. One valve did
not close enough to shut off flow.
In March 1989, valve 2CA62A and three identical Unit 2 AFW MOVs were differen- tial pressure tested at 1800 psi. During the test, the three Unit 2 identical
valves'failed to completely close and isolate flow. All four valves failed to
wedge completely shut. Valve signature analysis test data obtained during this
testing yielded closing valve factors ranging from 0.38 to 0.74 and were
different for each valve tested. These were higher than the 0.3 valve factor
utilized by the valve manufacturer to size the actuators.
Testing performed by Duke Power Company on carbon steel valves similar in
design to 2CA62A has yielded opening valve factors ranging from 0.48 to 0.67.
Testing performed by Duke Power Company on stainless steel valves similar to
2CA62A has yielded valve factors ranging from slightly higher than 0.3 to 0.5.
Based on Duke Power Company testing, the valve factor of 0.3 originally uti- lized for Borg-Warner flexible wedge carbon steel or stainless steel gate
valves with pinned body guide insert rings when sizing air or motor actuators
was not correct. The actual valve factors, as measured by Duke Power Company, vary from valve to valve but are consistently above 0.3. This results in the
potential that air- or motor-actuated valves will not operate against a differ- ential pressure when called upon to do so because of inadequate torque switch
settings or undersized actuators.
IN 89-61 August 30, 1989 Related Generic Communications:
The general concern of the ability of motor-operated valves to function properly
when subjected to the design basis loadings has been previously addressed in
NRC Bulletins 81-02, "Failure of Gate Type Valves to Close Against Differential
Pressure," and 85-03, "Motor-Operated Valve Common Mode Failures During Plant
Transients Due to Improper Switch Settings;" Circular 77-01, "Malfunctions of
Limitorque Valve Operators;" Information Notices 81-31, "Failure of Safety In- jection Valves to Operate Against Differential Pressure," and 85-50, "Complete
Loss of Main and Auxiliary Feedwater at a PWR Designed by Babcock & Wilcox;"
and Generic Letter 89-10, "Safety-Related Motor-Operated Valve Testing and
Surveillance."
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:
S. Tingen, RII
(404) 331-2603 Attachment: List of Recently Issued NRC Information Notices
Attachment
IN 89-61 August 30, 1989 Page I of I
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
88-48, Licensee Report of Defective 8/22/89 All holders of OLs
Supp. 2 Refurbished Valves or CPs for nuclear
power reactors.
89-60 Maintenance of Teletherapy 8/18/89 All NRCMedical.
Units Teletherapy Licensees.
89-59 Suppliers of Potentially 8/16/89 All holders of OLs
Misrepresented Fasteners or CPs for nuclear
power reactors.
89-58 Disablement of Turbine-Driven 8/3/89 All holders of OLs
Auxiliary Feedwater Pump Due or CPs for PURs.
to Closure of One of the
Parallel Steam Supply Valves
89-57 Unqualified Electrical 7/26/89 All holders of OLs
Splices in Vendor-Supplied or CPs for nuclear
Environmentally Qualified power reactors.
Equipment
89-56 Questionable Certification 7/20/89 All holders of OLs
of Material Supplied to the or CPs for nuclear
Defense Department by Nuclear power reactors
Suppliers
89-45, Metalclad, Low-Voltage 7/6/89 All holders of OLs
Supp. I Power Circuit Breakers or CPs for nuclear
Refurbished With Substandard power reactors.
Parts
89-5S Degradation of Containment 6/30/89 All holders of OLs
Isolation Capability by a or CPs for nuclear
High-Energy Line Break power reactors.
89-54 Potential Overpressurization 6/23/89 All holders of OLs
-of theC~~.~4eowo-Hng--- - ii-o CF~, Fr rueltr =
Water System power reactors.
89-53 Rupture of Extraction 6/13/89 All holders of OLs
Steam Line on High or CPs for nuclear
Pressure Turbine power reactors.
OL
CP* Construction Permit
UNITED STATES
NUCLEAR REGULATORY COMMISSION FIRST CLASS MAIL
POSTAGE b FEES PAID
WASHINGTON, D.C. 20555 USNRC
PERMIT No- 0-67 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE, $300
IN 89-61 August 30, 1989 Related Generic Communications:
The general concern of the ability of motor-operated valves to function properly
when subjected to the design basis loadings has been previously addressed in
NRC Bulletins 81-02, "Failure of Gate Type Valves to Close Against Differential
Pressure," and 85-03, "Motor-Operated Valve Common Mode Failures During Plant
Transients Due to Improper Switch Settings;" Circular 77-01, "Malfunctions of
Limitorque Valve Operators;" Information Notices 81-31, "Failure of Safety In- jection Valves to Operate Against Differential Pressure," and 85-50, "Complete
Loss of Main and Auxiliary Feedwater at a PWR Designed by Babcock & Wilcox;"
and Generic Letter 89-10, "Safety-Related Motor-Operated Valve Testing and
Surveillance."
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:
S. Tingen, RII
(404) 331-2603 Attachment: List of Recently Issued NRC Information Notices
This information was received from Region II as an attachment to AFGibson's
memorandum to CERossi dated July 12, 1989.
- SEE PREVIOUS PAGE FOR CONCURRENCE
CX;HR~~isV \CHBerlinger TechEd
08/1-.89 '08/23/89 08/8/89
- OGCB:DOEA:NRR *RII *RrlI *C/EMEB:DEST:NRR *EAD/DEST:NRR
RJKiessel STingen AFGibson LBMarsh JERichardson
08/8/89 07/12/89 07/12/89 08/10/89 08/11/89
4- *
IN 89-XX
August xx, 1989 Related Generic Communications:
The general concern of the ability of motor-operated valves to function properly
when subjected to the design basis loadings has been previously addressed in
NRC Bulletins 81-02, "Failure of Gate Type Valves to Close Against Differential
Pressure," and 85-03, "Motor-Operated Valve Common Mode Failures During Plant
Transients Due to Improper Switch Settings," Circular 77-01, "Malfunction of
Limitorque Valve Operators," Information Notices 81-31, "Failure of Safety In- jection Valves to Operate Against Differential Pressure," and 85-50, "Complete
Loss of Main and Auxiliary Feedwater at a PWR Designed by Babcock & Wilcox,"
and Generic Letter 89-10, "Safety-Related Motor-Operated Valve Testing and
Surveillance."
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:
S. Tingen, RII
(404) 331-2603 Attachment: List of Recently Issued NRC Information Notices
This information was received from Region II as an attachment to AFGibson's
memorandum to CERossi dated July 12, 1989.
- SEE PREVIOUS PAGE FOR CONCURRENCE
D/DOEA:NRR C/bU\.D EA:NRR *RPB:ARM
CERossi CHBerlinger TechEd
08/ /89 08//e/89 08/8/89
- OGCB:DOEA:NRR *RII *RII *C/EMEB:DEST:NRR *EAD/DEST:NRR
RJKiessel STingen AFGibson LBMarsh JERichardson
08/8/89 07/12/89 07/12/89 08/10/89 08/11/89
4 V
IN 89-XX
August xx, 1989 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:
S. Tingen, RII
(404) 331-2603 Attachment: List of Recently Issued NRC Information Notices
This information was received from Region II as an attachment to AFGibson's
memorandum to CERossi dated July 12, 1989.
D/DOEA:NRR C/OGCB:DOEA:NRR RPB:ARM
CERossi CHBerlinger TechEd 8
08/ /89 08/ /89 08/ 8/8 Q
R11 RII C .:NRR END n N"RR
OGCB:DOEA:NRR
RJKiessel STingen AFGibson ER a dson
08/2 /89 0F/IZ/89 07/12/89 08/1 /89
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list | - Information Notice 1989-01, Valve Body Erosion (4 January 1989)
- Information Notice 1989-02, Criminal Prosecution of Licensee'S Former President for Intentional Safety Violations (9 January 1989)
- Information Notice 1989-03, Potential Electrical Equipment Problems (11 January 1989)
- Information Notice 1989-04, Potential Problems from the Use of Space Heaters (17 January 1989)
- Information Notice 1989-05, Use of Deadly Force by Guards Protecting Nuclear Power Reactors Against Radiological Sabotage (19 January 1989)
- Information Notice 1989-06, Bent Anchor Bolts in Boiling Water Reactor Torus Supports (24 January 1989)
- Information Notice 1989-07, Failures of Small-Diameter Tubing in Control Air, Fuel Oil & Lube Oil Systems Render Emergency Diesel Generators Inoperable (25 January 1989)
- Information Notice 1989-08, Pump Damage Caused by Low-Flow Operation (26 January 1989)
- Information Notice 1989-09, Credit for Control Rods Without Scram Capability in the Calculation of Shutdown Margin (26 January 1989, Topic: Shutdown Margin)
- Information Notice 1989-10, Undetected Installation Errors in Main Steam Line Pipe Tunnel Differential Temperature-Sensing Elements at Boiling Water Reactors (27 January 1989)
- Information Notice 1989-11, Failure of DC Motor-Operated Valves to Develop Rated Torque Because of Improper Cable Sizing (2 February 1989, Topic: Shutdown Margin)
- Information Notice 1989-12, Dose Calibrator Quality Control (9 February 1989)
- Information Notice 1989-13, Alternative Waste Management Procedures in Case of Denial of Access to Low-Level Waste Disposal Sites (8 February 1989, Topic: Shutdown Margin, Authorized possession limits)
- Information Notice 1989-15, Second Reactor Coolant Pump Shaft Failure at Crystal River (16 February 1989, Topic: Shutdown Margin)
- Information Notice 1989-16, Excessive Voltage Drop in DC Systems (16 February 1989, Topic: Shutdown Margin, Battery sizing)
- Information Notice 1989-17, Contamination and Degradation of Safety-Related Battery Cells (22 February 1989)
- Information Notice 1989-18, Criminal Prosecution of Wrongdoing Committed by Suppliers of Nuclear Products or Services (24 August 1990)
- Information Notice 1989-20, Weld Failures in a Pump of Byron-Jackson Design (24 February 1989, Topic: Health Physics Network)
- Information Notice 1989-21, Changes in Performance Characteristics of Molded-Case Circuit Breakers (27 February 1989, Topic: Health Physics Network)
- Information Notice 1989-23, Environmental Qualification of Litton-Veam Cir Series Electrical Connectors (3 March 1989, Topic: Health Physics Network)
- Information Notice 1989-24, Nuclear Criticality Safety (6 March 1989, Topic: Health Physics Network)
- Information Notice 1989-25, Unauthorized Transfer of Ownership or Control of Licensed Activities (7 March 1989, Topic: Health Physics Network)
- Information Notice 1989-26, Instrument Air Supply to Safety-Related Equipment (7 March 1989, Topic: Health Physics Network)
- Information Notice 1989-27, Limitations on the Use of Waste Forms and High Integrity Containers for the Disposal of Low-Level Radioactive Waste (8 March 1989, Topic: Process Control Program)
- Information Notice 1989-28, Weight and Center of Gravity Discrepancies for Copes-Vulcan Air-Operated Valves (14 March 1989)
- Information Notice 1989-29, Potential Failure of Asea Brown Boveri Circuit Breakers During Seismic Event (15 March 1989)
- Information Notice 1989-30, High Temperature Environments at Nuclear Power Plants (1 November 1990)
- Information Notice 1989-31, Swelling and Cracking of Hafnium Control Rods (22 March 1989)
- Information Notice 1989-32, Surveillance Testing of Low-Temperature Overpressure-Protection Systems (23 March 1989, Topic: Stroke time)
- Information Notice 1989-33, Potential Failure of Westinghouse Steam Generator Tube Mechanical Plugs (23 March 1989)
- Information Notice 1989-34, Disposal of Americium Well-Logging Sources (30 March 1989)
- Information Notice 1989-35, Loss & Theft of Unsecured Licensed Material, Attachment 1 to NRC Information Notice 1990-014: Accidental Disposal of Radioactive Materials. (Also includes Attachments 2 & 3) (30 March 1989)
- Information Notice 1989-35, Loss & Theft of Unsecured Licensed Material, Attachment 1 to NRC Information Notice 1990-014: Accidental Disposal of Radioactive Materials. (Also Includes Attachments 2 & 3) (30 March 1989, Topic: Moisture-Density Gauge)
- Information Notice 1989-36, Excessive Temperatures in Emergency Core Cooling System Piping Located Outside Containment (4 April 1989)
- Information Notice 1989-37, Proposed Amendments to 40 CFR Part 61, Air Emission Standards for Radionuclides (4 April 1989)
- Information Notice 1989-38, Atmospheric Dump Valve Failures at Palo Verde Units 1, 2, and 3 (5 April 1989, Topic: Emergency Lighting)
- Information Notice 1989-39, List of Parties Excluded from Federal Procurement or Non-Procurement Programs (5 April 1989)
- Information Notice 1989-40, Unsatisfactory Operator Test Results and Their Effect on the Requalification Program (14 April 1989)
- Information Notice 1989-41, Operator Response to Pressurization of Low-Pressure Interfacing Systems (20 April 1989)
- Information Notice 1989-42, Failure of Rosemount Models 1153 and 1154 Transmitters (21 April 1989)
- Information Notice 1989-43, Permanent Deformation of Torque Switch Helical Springs in Limitorque SMA-Type Motor Operators (1 May 1989)
- Information Notice 1989-44, Hydrogen Storage on the Roof of the Control Room (27 April 1989, Topic: Coatings)
- Information Notice 1989-45, Metalclad, Low-Voltage Power Circuit Breakers Refurbished with Substandard Parts (8 May 1989, Topic: Commercial Grade Dedication, Coatings)
- Information Notice 1989-46, Confidentiality of Exercise Scenarios (11 May 1989, Topic: Coatings)
- Information Notice 1989-47, Potential Problems with Worn or Distorted Hose Clamps on Self-Contained Breathing Apparatus (18 May 1989, Topic: Coatings)
- Information Notice 1989-48, Design Deficiency in the Turbine-Driven Auxiliary Feedwater Pump Cooling Water Systems (22 May 1989, Topic: Coatings, Temporary Modification)
- Information Notice 1989-49, Failure to Close Service Water Cross-Connect Isolation Valves (22 May 1989, Topic: Coatings)
- Information Notice 1989-50, Inadequate Emergency Diesel Generator Fuel Supply (30 May 1989)
- Information Notice 1989-51, Potential Loss of Required Shutdown Margin During Refueling Operations (31 May 1989, Topic: Shutdown Margin, Coatings)
- Information Notice 1989-52, Potential Fire Damper Operational Problems (8 June 1989, Topic: Safe Shutdown, Shutdown Margin, Fire Barrier, Fire Protection Program)
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