Motor Brakes on Valve Actuator MotorsML031060590 |
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: |
12/20/1993 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-93-098, NUDOCS 9312150064 |
Download: ML031060590 (8) |
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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>. |
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K-
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 December 20, 1993 NRC INFORMATION NOTICE 93-98: MOTOR BRAKES ON VALVE ACTUATOR MOTORS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to potential problems with the performance of
motor-operated valves (MOVs) resulting from improper operation of motor brakes
used on valve actuator motors. 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 are not NRC requirements; therefore, no specific
action or written response is required.
Background
Some MOVs have motor brakes installed to help minimize the inertial loads
during valve closure after the control switch has tripped. Motor brakes also
help prevent MOVs with non-locking gear mechanisms from inadvertently opening.
One type of motor brake is designed to be electromagnetically released and has
friction pads to slow the motor shaft following control switch trip. Improper
operation of motor brakes can result in problems with the performance of MOVs.
Description of Circumstances
In Maintenance Update 92-2, Limitorque Corporation informed the nuclear
industry that it had discovered, through operating experience and testing, that motor brakes do not substantially minimize the thrust load caused by
inertia when closing MOYs. Limitorque also stated that it did not qualify
motor brakes through its nuclear qualification testing. Limitorque warned
that voltage variation into the motor brake may render the brake inoperable.
Limitorque noted that disconnection of the brake leads does not render the
brakes inoperable and specified that the friction pads be removed. Each of
the following reports involve valves with Limitorque motor operators.
On August 4, 1993, the licensee of Crystal River Nuclear Plant, Unit 3, reported (Licensee Event Report 93-008) that seven MOVs with motor brakes
installed might receive insufficient voltage to allow the motor brakes to be
released under degraded voltage conditions. Of these seven MOVs, the licensee
9312150064 I o v't 3-o1S
PD9 Ie 19 3c) 0
IN 93-98 I-'December 20, 1993 declared a normally closed high-pressure injection suction NOV to be
inoperable on July 6, 1993. The licensee removed the friction disks and
electrical power connections from this NOV as well as from normally open
borated water storage tank suction NOV. The licensee tested another of the
seven MOVs to ensure that its motor brake would release under degraded voltage
conditions. The remaining four MOVs are locked in their safety function
position during plant operation.
On September 14, 1993, the licensee of Millstone Nuclear Power Station, Unit 2, notified NRC that it had declared four feedwater supply MOVs with
motor brakes installed inoperable when it determined that the MOVs might
receive insufficient voltage during degraded voltage conditions to allow the
motor brakes to release. The licensee relies on these MOVs as a backup for
feedwater isolation in the event of a main steam line break. The licensee
shut down Millstone Unit 2 in accordance with its plant technical
specification requirements. The licensee subsequently removed the motor
brakes.
On September 28, 1993, the licensee of James A. FitzPatrick Nuclear Power
Plant notified NRC of problems with the operation of motor brakes on two low- pressure coolant injection MOVs. The licensee determined that the motor
brakes were undersized to prevent the actuator spring pack from relaxing and
causing the torque switch to restart the actuator motor on a repeated basis.
Continuous restarting of the actuator motor can cause (1)damage to the motor
from overheating, and (2)excessive stress to the NOV by driving the valve
disk into its seat (sometimes referred to as a 'hammering" effect).
Discussiosn
In Generic Letter (GL) 89-10, 'Safety-Related Motor-Operated Valve Testing and
Surveillance," the NRC staff requested nuclear power plant licensees to
confirm the capability of safety-related MOVs to perform their intended
functions by reviewing NOV design bases, verifying NOV switch settings
initially and periodically, testing MOVs under design-basis conditions where
practicable, improving evaluations of NOV failures and necessary corrective
action, and trending NOV problems. In response to GL 89-10, licensees are
implementing programs to evaluate the design-basis capability of MOVs within
the scope of tbe generic letter.
As indicated by the discovery of NOV operability problems at Crystal River and
Millstone, some licensees may not be evaluating the minimum voltage required
to ensure the proper operation of motor brakes when determining the design- basis capability of MOVs with motor brakes installed. Improper operation of
motor brakes on MOVs could allow the motor to restart repeatedly as found at
FitzPatrick.
. I
K2IN 93-98 December 20 1993 Related Generic Communications
NRC has issued other information notices pertaining to MOVs. During the past
year, these have included NRC Information Notices 93-74, wHigh Temperatures
Reduce Limitorque AC Motor Operator Torque;" 93-54, "Motor-Operated Valve
Actuator Thrust Variations Measured With a Torque Thrust Cell and a Strain
Gage;" 93-01, 'Accuracy of Motor-Operated Valve Diagnostic Equipment
Manufactured by Liberty Technologies;" 92-83, 'Thrust Limits for Limitorque
Actuators and Potential Overstressing of Motor-Operated Valves;" and 92-70,
"Westinghouse Motor-Operated Valve Performance Data Supplied to Nuclear Power
Plant Licensees."
In addition, the hammering effect was specifically addressed in NRC
Information Notice 85-20, "Motor-Operated Valve Failures Due to Hammering
Effect," and its supplement.
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 orrthe appropriate Office of
Nuclear Reactor Regulation project manager.
Z24_-_O_ _
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: P. K. Eapen, RI
(215) 337-5150
Thomas G. Scarbrough, NRR
(301) 504-2794 Attachment:
List of Recently Issued NRC Information Notices
At&.dchment
IN 93-98 December 20, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
Failures of Yokes 12/17/93 All holders of OLs or CPs
Installed on Walworth for nuclear power reactors.
Gate and Globe Valves
93-96 Improper Reset Causes 12/14/93 All holders of OLs or CPs
Emergency Diesel for nuclear power reactors.
Generator Failures
93-95 Storm-Related Loss of 12/13/93 All holders of OLs or CPs
Offsite Power Events for nuclear power reactors
due to Salt Buildup located close to a large
on Switchyard Insulators body of salt water.
93-94 Unauthorized Forced 12/09/93 All holders of OLs or CPs
Entry into the Pro- for nuclear power reactors.
tected Area at Three
Mile Is-land Unit 1 on
February 7, 1993
93-93 Inadequate Control of 12/08/93 All holders of OLs or CPs
Reactor Coolant System for nuclear power reactors.
Conditions During Shutdown
Plant Improvements to 12/07/93 Al I holders of OLs or CPs
Mitigate Common Depend- for nuclear power reactors.
encies in Component
Cooling Water Systems
91-21, Inadequate Quality 12/07/93 All holders of OLs or CPs
Supp. 1 Assurance Program of for nuclear power reactors
Vendor Supplying and all recipients of
Safety-Related Equipment NUREG-0040, License Con- tractor and Vendor Inspec- tion Status Report" (White
Book).
89-77, Debris in Containment 12/03/93 All holders of OLs or CPs
Supp. 1 Emergency Sumps and for nuclear power reactors.
Incorrect Screen
Configurations
OL = Operating License
CP - Construction Permit
-
KJ~
IN 93-98 December 20, 1993 Related Generic Communications
NRC has issued other information notices pertaining to MO s. During the past
year, these have included NRC Information Notices 93-74, "High Temperatures
Reduce Limitorque AC Motor Operator Torque;" 93-54, "Motor-Operated Valve
Actuator Thrust Variations Measured With a Torque Thrust Cell and a Strain
Gage;" 93-01, "Accuracy of Motor-Operated Valve Diagnostic Equipment
Manufactured by Liberty Technologies;" 92-83, "Thrust Limits for Limitorque
Actuators and Potential Overstressing of Motor-Operated Valves;" and 92-70,
"Westinghouse Motor-Operated Valve Performance Data Supplied to Nuclear Power
Plant Licensees."
In addition, the hammering effect was specifically addressed in NRC
Information Notice 85-20, "Motor-Operated Valve Failures Due to Hammering
Effect," and its supplement.
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 Office of
Nuclear Reactor Regulation project manager. Original signed by
Brian K.Grimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: P. K. Eapen, RI
(215) 337-5150
Thomas G. Scarbrough, NRR
(301) 504-2794 Attachment:
List of Recently Issued NRC Information Notices
- See nravinui concurrence naae
OFFICE *EMEB/DE/NRR *C:EMEB/DE/NRR *D:DE/NRR *OGCB/DORS/NRR
NAME TGScarbrough JANorberg JTWiggins RJKiessel/vsb
DATE 9/20/93 9/27/93 12/01/93 10/21/93 OFFICE *Tech Ed *EB/DRS/RI l*C:EB/DRS/RI *D:DRS/RI
NAME DGable PKEapen JPDurr WDHodges
DATE 10/22/93 1 i 11/29/93 11/29/93 OFFICE *C:OGCB/DORS/NRR
NAME GHMarcus I/
DATE 12/03/93 12(
Document Name: Y3-9U.IN
-
K>1 IN 93-xx
December xx, 1993 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 Office of
Nuclear Reactor Regulation project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: P. K. Eapen, Region I
(215) 337-5150
Thomas G. Scarbrough, NRR
(301) 504-2794 Attachment: List of Recently Issued NRC Information Notices
C t4
- See nrevious concurrence naae 'd'0
OFFICE *EMEB/DE/NRR *C:EMEB/DE/NRR N *OGCB/DORS/NRR
NAME TGScarbrough JANorberg ~ T~igginsk RJKiessel/vsb
DATE 1 9/20/93 1 9/27/93 1tI!\ 93 10/21/93 OFFICE *Tech Ed *EB/DRS/RI *C:EB/DRS/RI *D:DRS/RI
NAME DGable PKEapen JPDurr WDHodges
DATE 10/22/93 111/29/93 , 1/29/93 11/29/93 OFFICE C:OGCB/DORS/NRR D: DORS/NRR
NAME GHMarcusmW BKGrines
I
DATE 1 f1/3 /93 _1_/ _/93 __ _p
Document Name: nrcin.3al
V
Effect," and its supplement.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
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U11ne orIei ILecMicUa conMACU I ILsu D0OW or fne dppropridite urTice Ot
Nuclear Rea4:tor Regulatibn project manager.
Brian K. Grimes, Director
Division of Operating Reactor Supp t
Office of Nuclear Reactor Regula on
Technical ccontacts: P. K. Eapan, Region I
(215) 337-5150
Thomas G. Scarbrough, NRR
(301) 504-2794 Attachment: List of Recently Issued NRC Info ation Notices
Transmitted by JANorberg memorandum date September 27. 1993
- SPP nrpvioniis concurrence page
OFFICE *EMEB/DE/NRR *C:EMEBDE/NRR D:DE/NRR *OGCB/DORS/NRR
NAME TGScarbrough JAN berg JTWiggins RJKiessel/vsb
DATE 9/20/93 9//7/93 1i/ /93 10/21/93i
OFFICE *Tech Ed /EB/DRS/RI A C:EB/DRS/RI D:DRS/RI
NAME
DATE
OFFICE
T DGable
10/22/93 C:OGCB/MfRS/NRR
PKEapan
11 93
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D: DORS/NRR
'
JPDurr
IIg 93V
I Modge
11 V 93 NAME GHMarII BKGrimes
DATE II///93 11/ /93 Document Name: nrcln.3al
F
(215) 337-5240
Thomas G. Scarbrough, NRR
(301) 504-2794 Attachment: List of Recently Issued NRC Information Notices
Transmitted by JANorbera memorandum dated Sentomhbr 27. l 4 OB/DRS/RI C:OB/DRS/RI D:DRS/RI *EMEBID NRR *C:EMEB/DE/NRR
JSStewart LHBettenhausen M4WHodges TGS brough JANorberg
1O/ /93 IO/ /93 10/ /93 120/93 a 9/27/93 OGCB/DORS/NRR Tech Ed D:DE/NRR /C:OGCB/DORS/NRR D:DORS/NRR
RJKiesselftk , k JTW~ggins / GHMarcus BKGrimes
10 /93 10.ZZ/93 10/ /93 10/ /93 10/ /93 uoPcumenr name: nrcin.al /
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list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
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