Portable Moisture-Density Gauge User Responsibilities During Field OperationsML031080084 |
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 |
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Issue date: |
03/10/1993 |
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From: |
Cunningham R NRC/NMSS/IMNS |
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To: |
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References |
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IN-93-018, NUDOCS 9303040105 |
Download: ML031080084 (7) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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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 MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 March 10, 1993 NRC INFORMATION NOTICE 93-18: PORTABLE MOISTURE-DENSITY GAUGE USER
RESPONSIBILITIES DURING FIELD OPERATIONS
Addressees
All U. S. Nuclear Regulatory Commission licensees'that possess moisture- density gauges.
PurDose
NRC is issuing this information notice to remind licensees of their
responsibility to maintain constant surveillance and security of portable
moisture-density gauges during field operations. Failure to adequately secure
gauges at construction sites has resulted in several incidents that have
caused damage to the gauges. It is'expected that recipients will review the
information for applicability to their licensed activities,' distribute'this
notice to responsible radiation safety staff and gauge users, 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.
Description of Circumstances
During the busy construction season, NRC licensees use moisture-density gauges
extensively. Consequently, mdre incidents involving gauges occur at this time
than at other times during the year. Longer working'hours, along with an
increase in the number of jobs'performeed by a licensee,'may contribute to the
increase in incidents involving gauges. 'Recent incidents show that damage by
heavy construction equipment is frequently a cause-of these incidents.
In 1991 and the first three quarters of 1992, NRC was notified about 44 incidents that involved moisture-density gauges. Sixteen of the incidents
involved gauges that were damaged at temporary job sites. Although the
devices sustained severe damage, the sources usually remained in the shielded
position within the device. In many of these cases, the authorized user had
not complied with regulatory requirements for maintaining constant
surveillance and immediate control of the device (10 CFR 20.207).
Specifically, the authorized user must be in immediate control of the gauge
(10 CFR 20.207) so that he or she'can, at all times, prevent damage to, or'
misuse of, the gauge'.
In one recent incident, a device was severely damaged by the licensee's
transport vehicle. The impact severed the source rod and dislodged the
source. The licensee did not immediately follow its own emergency procedures, and left the source unattended for several hours. The unencapsulated source
was found later, at the site, lying on the base rock. The licensee responded
93340105O
'lt
IN 93-18 March 10, 1993 by restricting the area and obtaining outside assistance to conduct radiation
surveys, recover the source, test the source for leakage of radioactive
material, and package and ship the source for disposal. The leak test showed
no leakage from the source. A survey also showed no contamination on the base
rock surface where the source was found, so decontamination operations at the
site were not necessary. However, recovery was costly and the licensee's
operations were significantly disrupted. This incident could have been
prevented by simply maintaining constant surveillance of and immediate control
of the device. In addition, NRC enforcement actions, including civil
penalties, are considered in cases such as this.
Discussion
When using moisture-density gauges at temporary job sites, the authorized user
must not leave the gauge unattended at any time (10 CFR 20.207(b)). When
personnel are finished using the device, they must properly secure the
moisture-density gauge (10 CFR 20.207(a)), to prevent damage, loss, or theft.
One method of complying with the requirements would be to lock the source rod
in the safe storage position, lock the device in its transport container, secure the transport container from theft or loss in the licensee's vehicleandor
in a storage building. The requirements for control and security of licensed
material are given in 10 CFR 20.207 or, for licensees implementing the revised
Part 20, Sections 20.1801 and 20.1802. Properly securing moisture-density
gauges will prevent damage to gauges at temporary job sites.
Many incidents involving gauges have occurred when the authorized user left
the gauge unattended for several moments to get some item (notebook, coffee, etc.), to return to the transport vehicle, or to speak with someone. It must
be emphasized that gauge users must not leave the device unattended.
Temporary lapses in control, however minor, have often resulted in damaged
gauges. NRC will take enforcement action, possibly leading to civil penalties
(i.e., monetary fines), in such cases.
In addition, it is suggested that licensees conduct periodic training, for
authorized users, to emphasize proper procedures for use and security of theall
gauges. Licensees should ensure that all personnel understand adequate
emergency response actions and relevant safety topics. An understanding of the
topics in Attachment 1 is essential to safe operations.
Related Generic Communication
The topics in Attachment 1 are covered in the license conditions, the license
application, the regulations, and in the following information notices:
IN 88-02 "Lost or Stolen Gauges"
IN 87-55 "Portable Moisture/Density Gauges: Recent
Incidents of Portable Gauges Being Stolen or
Lost'
IN 86-67 "Portable Moisture/Density Gauges: Recent
Incidents and Common Violations of Requirements
for Use, Transportation, and Storage"
IN 93-18 March 10, 1993 IN 84-26 "Recent Serious Violations of NRC Requirements by
Moisture Density Gauge Licensees"
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 regional
office.
Richard E. Cunningham, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contacts: Thomas Young, RIII
(708) 790-5182
- Scott Moore, NMSS
(301) 504-2514 Attachments:
1. Training Topics for Moisture-Density Gauge Users
2. List of Recently Issued NMSS Information Notices
3. List-of Recently Issued NRC Information Notices
Attachment 1 IN 93-18 March 10, 1993 TRAINING TOPICS FOR MOISTURE-DENSITY GAUGE USERS
- Radiological emergency response procedures for a damaged moisture- density gauge
- Loss prevention, security, surveillance, and storage
- Physical inventory, accountability
- Notification of NRC regarding damaged devices and sources
- Proper disposal of gauges to the manufacturer (to avoid inadvertent
transfer of a gauge to a scrap-metal broker and a possible foundry
contamination incident)
- Completion of NRC Form 241, 'Report of Proposed Activities in Non- Agreement States,' when applicable
- Transportation requirements for shipping papers, labels, markings, certification of packaging, and blocking and bracing
- Radiation safety instruction for gauge users
- Portable-gauge accident scenarios, to avoid incidents and accidents
with portable gauges
- Proper use of personnel-monitoring devices
- The terms and conditions of the license, and the occasions when it
is appropriate to amend the license
- Other relevant requirements of 10 CFR Parts 19, 20,
and 30
IN,. I" IN 93-18 March 10, 1993 IN 84-26 "Recent Serious Violations of NRC Requirements by
Moisture Density Gauge Licensees'
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 regional
office.
Richard E. Cunningham, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contacts: Thomas Young, RIII
(708) 790-5182 Scott Moore, NMSS
frani i Rnd-Ms1A
Attachments a z*-
Cy24
1. Training Topics for I, sture-Density Gauge Users
2. List of Recently Issued NMSS Information Notices
3. List of Recently Issued NRC Information Notices
DOCUMENT NAME: 93-18.IN
4. Cr- 4- a.. r --.
- t rrev uu4 !JUIIL.UI I__ _ _ _
OFC IMOB* NMSS* IMOB* IMOB* IMAB*
NAME SMoore:kr EKraus CJones FCombs JGlenn
DATE 2/18/93 2/17/93 2/18/93 2/19/93 2/22/93 OFC OGC(No legal RIII* IMOB* IMNS
objection) (By telephone) _
NAME STreby RCaniano KRamsey RCunnfngham
DATE 2/25/93 2/26/93 2/26/93 03/01/93 _
OFFICIAL RECORD COPY
K-'
Attachment 2 IN 93-18 March 10, 1993 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-14 Clarification of 02/18/93 All Licensees who possess
10 CFR 40.22, Small source material.
Quantities of Source
Material
93-10 Dose Calibrator Quality 02/02/93 All Nuclear Regulatory
Control Commission medical
licensees.
93-07 Classification of Trans- 02/01/93 All Licensees required to
portation Emergencies have an emergency plan.
93-05 Locking of Radiography 01/14/93 All Nuclear Regulatory
Exposure Devices Commission industrial
radiography licensees.
93-04 Investigation and Re- 01/07/93 All U.S. Nuclear Regulatory
porting of Misadministra- Commission medical
tions by the Radiation licensees.
Safety Officer
93-03 Recent Revision to 01/05/93 All byproduct, source, and
10 CFR Part 20 and special nuclear material
Change of Implementa- licensees.
tion Date to
January 1, 1994
92-84 Release of Patients 12/17/92 All Nuclear Regulatory Com- Treated with Temporary mission Medical Licensees.
Implants
92-72 Employee Training 10/18/92 All U.S. Nuclear Regulatory
and Shipper Registra- Commission Licensees.
tion Requirements for
Transporting Radioactive
Materials
92-62 Emergency Response 08/24/92 All U.S. Nuclear Regulatory
Information Require- Commission Licensees.
iments for Radioactive
Material Shipments
I
Attachment 3 IN 93-18 March 10, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-17 Safety Systems Response 03/08/93 All holders of OLs or CPs
to Loss of Coolant and for nuclear power reactors.
Loss of Offsite Power
93-16 Failures of Nut-Locking 02/19/93 All holders of OLs or CPs
Devices in Check Valves for nuclear power reactors.
93-15 Failure to Verify the 02/18/93 All holders of OLs or CPs
Continuity of Shunt Trip for nuclear power reactors.
Attachment Contacts in
Manual Safety Injection
and Reactor.Trip Switches
93-14 Clarification of 02/18/93 All licensees who possess
10 CFR 40.22, Small source material.
Quantities of Source
Material
93-13 Undetected Modification 02/16/93 All holders of OLs or CPs
of Flow Characteristics for nuclear power reactors.
in the High Pressure
Safety Injection System
93-12 Off-Gassing in Auxiliary 02/11/93 All holders of OLs or CPs
Feedwater System Raw for nuclear power reactors.
Water Sources
93-11 Single Failure Vulner- 02/04/93 All holders of OLs or CPs
ability of Engineered for nuclear power reactors.
Safety Features
Actuation Systems
93-10 Dose Calibrator Quality 02/02/93 All Nuclear Regulatory Com- Control mission medical licensees.
93-09 Failure of Undervoltage 02/02/93 All holders of OLs or CPs
Trip Attachment on for nuclear power reactors.
Westinghouse Model DB-50
Reactor Trip Breaker
OL - Operating License
CP - Construction Permit
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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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