Changes in Performance Characteristics of Molded-Case Circuit BreakersML031180541 |
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: |
02/27/1989 |
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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-89-021, NUDOCS 8902210564 |
Download: ML031180541 (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>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 February 27, 1989 CHANGES IN PERFORMANCE CHARACTERISTICS
NRC INFORMATION NOTICE NO. 89-21: OF MOLDED-CASE CIRCUIT BREAKERS
Addressees
power
or construction permits for nuclear
All holders of operating licenses
reactors.
Purpose
to alert addressees to an observed
This information notice is being provided to the performance characteristics
of
practice in which vendors make changes to
making any corresponding revisions
molded-case circuit breakers without that recipients will review the
the breaker part number. It is expected facilities and consider actions, as
information for applicability to their However, suggestions contained in
to avoid similar problems.
appropriate, NRC requirements; therefore, no
this information notice do not constitute is required.
specific action or written response
Description of Circumstances
manu- several inspections performed by the NRC, it was discovered that
During frequently altered the time-current
facturers of molded case circuit breakers a particular style or type of breaker.
characteristic curves pertaining to the part number of the breaker and
changes were made without changing
These
any specific notification to the customer. The changes identi- often without from very minor alterations to the
during the NRC inspections ranged
fied alterations to the magnetic instanta- thermal portion of the curves to major One change for ITE-type 100-amp breakers
neous trip portion of the curves. band from 600-1000 amps to 1200-2000
involved the movement of the instantaneous contains the appropriate curves, the
usually
amps. Although product literaturewith the breakers.
curves are not routinely provided
Discussion:
licensees who procure replacement breakers
As a result of these changes, many breakers with performance characteristics
by part number only are receiving If the
that may be different from those assumed in the original plant design.
installation
characteristics, upon
breakers are not analyzed for performance the electrical protection system
these breakers potentially could degrade the energizing of vital safety-related
and/or cause premature tripping upon failures of circuit breakers detected
systems. Additionally, many perceived
802 6
IN 89-21 February 27, 1989 during pre-installation or routine
testing may actually be the result
known changes in time-current characteristic of un- the breakers purchased conform curves. One way to ensure that
to a particular curve would be to
the specific curve (including the reference
requirements. If the breaker was applicable revision) as part of the purchase
cations of that specific curve, no longer manufactured to meet
the the specifi- its effect on the overall system. new curve would have to be analyzed
for
No specific action or written response
If you have any questions about is required by this information
this matter, notice.
contact listed below or the Regional please contact the technical
office. Administrator of the appropriate
regional
arl . si, Director
Division of Operational Events
Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
J. B. Jacobson, NRR
(301) 492-0996 Attachment: List of Recently Issued NRC Information
Notices
Attachment
IN 89-21 ;
February 27, 1989 Page 1 of I
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Informati on Date of
Subject Issuance Issued to
Notice No.
Direction-Dependent Leak 2/27/89 All holders of OLs
88-73, or CPs for nuclear
Supplement 1 Characteristics of Contain- power reactors.
ment Purge Valves
2/24/89 All holders of OLs
89-20 Weld Failures in a Pump or CPs for nuclear
of Byron-Jackson Design
power reactors.
Health Physics Network 2/23/89 All holders of OLs
89-19 or CPs for nuclear
power reactors, and
the following fuel
facilities: Nuclear
Fuel Services of Erwin, General Atomic, UNC
Montville, B&W LRC
Lynchburg, and B&W
Lynchburg.
Criminal Prosecution of 2/22/89 All holders of OLs
89-18 Wrongdoing Committed by or CPs for nuclear
Suppliers of Nuclear power reactors.
Products or Services
Contamination and Degra- 2/22/89 All holders of OLs
89-17 or CPs for nuclear
dation of Safety-Related
Battery Cells power reactors.
Excessive Voltage Drop 2/16/89 All holders of OLs
89-16 or CPs for nuclear
in dc Systems
power reactors.
Second Reactor Coolant Pump 2/16/89 All holders of OLs
89-15 or CPs for nuclear
Shaft Failure at Crystal
River power reactors.
89-14 Inadequate Dedication 2/16/89 All holders of OLs
Process for Commercial or CPs for nuclear
Grade Components Which power reactors.
Could Lead to Common Mode
Failure of a Safety System
OL = Operating License
CP = Construction Permit
IN 89-21 February 27, 1989 during pre-installation or routine testing may actually be the result of un- known changes in time-current characteristic curves. One way to ensure that
the breakers purchased conform to a particular curve would be to reference
the specific curve (including the applicable revision) as part of the the purchase
requirements. If the breaker was no longer manufactured to meet specifi- analyzed for
cations of that specific curve, the new curve would have to be
its effect on the overall system.
notice.
No specific action or written response is required by this information
If you have any questions about this matter, please contact the technical
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:
J. B. Jacobson, NRR
(301) 492-0996 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
D < *C/OGCB:DOEA:NRR *PPMB:ARM
CHBerlinger TechEd
2/89 02/09/89 02/17/89
- VIB:DRIS:NRR *SC/VIB:DRIS:NRR *BC/AB:DRIS:NRR *BC/SELB:DEST:NRR *D/DRIS:NRR
JJacobson UPotapovs EWBrach FRose BKGrimes
01/30/89 02/01/89 02/07/89 02/06/89 02/07/89
IN 89-XX
January XX, 1989 could
plant design. If unanalyzed, upon installation these breakers premature
and/or cause
potenttally degrade the electrical protection system Additionally, many
tripping upon energization of vital safety-related systems.
pre-installation or routine
perceived circuit breaker failures detected during
testing may actually be due to an unknown change in Time - Currentconform to a
Characteristic Curves. One way to ensure that received breakers revision
particular curve would be to reference the specific curve (including breaker needed is no
applicable) as part of the purchase requirements. If the
new curve would need to be
longer manufactured to that specific curve, the
analyzed for its effect on the overall system.
notice.
No specific action or written response is required by this information the technical
If you have any questions about this matter, please contact
regional
contact listed below or the Regional Administrator of the appropriate
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
J. B. Jacobson, NRR
(301) 492-0996
- See previous concurrence.
- SC:VIB:DRIS :BC:VIB:DRIS :BC:SELB:DEST :D:DRIS:NRR :BC:GCBI /w')
OFC :VIB:DRIS
- UPotapovs* :EWBrach* :FRosa* :BKGrimes* 1 CBerlinger
9 NAME :JJacobson:nrp
- 02/01/89 :02/07/89 :02/06/89 :02/07/89 :02i 1 /89 DATE :01/30/89*
OFC :D:DOEA : (To
rb,
:I--------
NAME :CERossi :f
DATE :0 - - --- -/
DATE :02/ /89 2/75
IN 89-XX
January XX, 1989 plant design. If unanalyzed, upon installation these breakers could
potentially degrade the electrical protection system and/or cause premature
trip ing upon energization of vital safety related systems. Additionally, many
perce ed circuit breaker failures detected during pre-installation or routine
testing ay actually be due to an unknown change in Time - Current
Characterstic Curves. One way to ensure that received breakers conform to a
particular urve would be to reference the specific curve (including revision
applicable) part of the purchase requirements. If the breaker need is no
longer manufac ured to that specific curve, the new curve would need o be
analyzed for it effect on the overall system. No specific actio r written
response is requi ed by this information notice. If you have a questions
about this matter, lease contact the technical contact liste below or the
Regional Administrat r of the appropriate regional office.
Charles E. i, Director
Division Operational Events Assessment
Office o Nuclear Reactor Regulation
Technical Contact:
J. B. Jacobson, RR
(301) 492-0996 DISTRIBUTION
Central Files
VIB R/F
DRIS R/F
BKGrimes
EWBrach
UPotapovs
JJacobson
IB:D I :SC: VIB- IS :BC: TORIS D- HERR : C:GCB :D:DDE
NAME :JJaco son:nrp :UPotap vs :EW')ch : i es :CBerlinger :CERo!
DATE :01 0/89* :02/ /89 :02/2 /89 :02/ /89 :02/ /89 :02/
"rrt0
IN 89-XX
January XX 1989 Page 2 of
plant design. If analyzed, upon installation these breakers cou d
potentially degrade e electrical protection system and/or caus premature
tripping upon energiza on of vital safety related systems. Ad tionally, many
perceived circuit breake failures detected during pre-install ion or routine
testing may actually be du to an unknown change in Time - Cu rent
Characteristic Curves. One y to ensure that received brea ers conform to a
particular curve would be to reference the specific curve ( ncluding Revision
applicable) as part of the purc se requirements. If the reaker needed is no
longer manufactured to that spec ic curve, the new curve ould need to be
analyzed for its effect on the ove 11 system. No speci ic action or written
response is required by this informa ion notice. If yo have any questions
about this matter, please contact the echnical contac listed below or the
Regional Administrator of the appropria regional of ice.
Charles E. or
Divisi o Op ational Events Assessment
Off' e of Nuclea Reactor Regulation
Technical Contact:
J. B. Jacobson, RR
(301) 492-0996 DISTRIBUTION
Central Files
VIB R/F
DRIS R/F
BKGrimes
EWBrach
UPotapovs
JJacobson
OFC :VIB:DRIS :9C: IB:DRIS :BC:VIB:DRIS :
______------- -- - - -- - - - - - - - ---- -----
NAME :JJacob .nrp 1 / :UPotapovs :EWBrach
:1------ --------------
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9- ::01/ -/ ---_ ---------
DATE :01/0o/8 :01/ /89 :01/ /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, Topic: Overexposure)
- 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, Topic: Overspeed)
- Information Notice 1989-08, Pump Damage Caused by Low-Flow Operation (26 January 1989, Topic: Integrated leak rate test)
- 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, Topic: Stress corrosion cracking)
- 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, Topic: Commercial Grade)
- Information Notice 1989-30, High Temperature Environments at Nuclear Power Plants (1 November 1990, Topic: Stress corrosion cracking)
- 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, Uranium Hexafluoride)
- 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, Commercial Grade)
- 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, Fatality)
- 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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