Dose Calibrator Quality ControlML031080166 |
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: |
02/02/1993 |
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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-93-010, NUDOCS 9301270077 |
Download: ML031080166 (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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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 February 2, 1993 NRC INFORMATION NOTICE NO. 93-10: DOSE CALIBRATOR QUALITY CONTROL
Addressees
All Nuclear Regulatory Commission medical licensees.
Purpose
This notice is provided to alert recipients to problems concerning dose
calibrator quality control tests, identified by NRC inspectors during
inspections of medical programs, and also to emphasize the importance of
quality control procedures for equipment used to assay patient doses. It is
expected that-licensees will: review this information for applicability to
their programs; distribute this notice to those responsible for radiation
safety and medical quality assurance, including technologists; and consider
actions to preclude similar situations from occurring at their facilities.
However, the suggestions contained in this notice do not constitute any new
NRC requirements, and no written response is required.
Description of Circumstances
During recent NRC inspections of medical facilities, inspectors found
deficiencies and irregularities in the performance and recording of dose
calibrator quality control tests. The most frequently occurring deficiencies
involve the constancy checks and linearity tests. However, there have also
been citations for failure to perform accuracy tests and determine geometric
independence. In some instances, the licensee did identify a malfunctioning
dose calibrator, but no corrective action was taken even though the error or
deviation exceeded allowable limits. Other problems included: failure to
instruct supervised individuals in the proper use of the dose calibrator;
failure to perform constancy checks when emergencies required the dose
calibrator to be used during non-routine periods such as weekends and
holidays; and failure to analyze the data, as required.
Discussion
Quality control checks of dose calibrators used to assay patient dosages are
essential to ensure that the dosage administered to a patient is the same as
the prescribed dosage. Medical personnel administering dosages should be
aware of the applicable NRC regulations (10 CFR 35.50) and any specific
related license conditions. Licensees are encouraged in Regulatory Guide
10.8, Rev. 2, to develop procedures that provide an even higher level of
confidence that the correct dosage is administered. For example, Regulatory
Guide 10.8, provides a model procedure for meeting the requirement. The guide
proposes a smaller percent deviation as a trigger level, so the licensee can
9301270077 S
IN 93-10
February 2, 1993 take action before the regulatory limit is reached. However, if it committed
to the regulatory guide procedures as part of a license application, the
licensee must comply with the more restrictive requirement. Licensees are
responsible for the instruction and supervision of individuals to ensure that
they know and follow the proper procedures for dose calibrator checks.
1. Constancy Checks
Constancy means reproducibility in measuring the activity of a known source
over a long period of time. The dose calibrator is required
(10 CFR 35.50(b)(1)) to be checked for constancy with a dedicated check source
at the beginning of each day of use. This includes weekends and holidays, if
radiopharmaceuticals are administered to a patient. During recent NRC
inspections, inspectors determined that licensees had failed to perform these
required checks because part-time technologists who worked only on weekends or
staff technologists called in on weekends had not been properly instructed by
the licensee and did not know that these checks were to be performed on
weekends.
The reference source used for the constancy check must be assayed at a
frequently used setting. Regulatory Guide 10.8 suggests using two or more
sources with different photon energies and activities, although one source
meets the requirement. The rule requires that the licensee determine the
constancy of the dose calibrator under an actual condition of use. Since most
medical licensees use technetium-99m for patient-dosage administrations more
frequently than any other isotope, such licensees should check the technetium-
99m setting, on each day of use, with a dedicated check source. It is
recommended that dose calibrators having both pre-adjusted controls (i.e.,
push buttons) and variable potentiometers be tested on both the variable
potentiometer technetium-99m (or other frequently used isotope) setting and
the pre-adjusted control. Discrepancies or fluctuations between the two
controls, when tested for constancy with the same check source, may be
indicative of equipment malfunction. Licensees must plot or log (10 CFR
35.50(e)(1)) the measured activity of each source and compare it to the
calculated activity, based on decay of the dedicated check source. If the
error between the two values exceeds 10 percent, the dose calibrator must be
repaired or replaced (10 CFR 35.50(d)).
2. Accuracy Test
The accuracy test ensures that the activity is within 10 percent of a given
calibrated reference source whose activity has been determined by the
manufacturer to be within 5 percent of the activity stated by the National
Institute of Standards and Technology (NIST) or by the supplier who has
compared that source to a source that was calibrated by NIST. At least two
sealed sources with different principal photon energies, one of which has a
principal energy between 100 keY and 500 keY, must be used to determine
accuracy upon installation, and at least annually thereafter
(10 CFR 35.50(b)(2)). The regulations require that the activity is at least
10 uCi for Ra-226 and 50 ACi for any other photon-emitting radionuclide. For
best accuracy, the lower energy reference standards should be in vials of
similar thickness to those for actual samples. As with the. constancy check
IN 93-10
February 2, 1993 a trigger level of
and linearity tests, Regulatory Guide 10.8 suggests if the error exceeds
5 percent difference but the requirement states that or replaced.
10 percent then the dose calibrator must be repaired
3. Linearity Tests
can indicate the correct
The linearity test ensures that the dose calibrator dose that will be
activity over the range of use between the highest dose calibrator is to be
administered to a patient and 10 microcuries. The
thereafter
tested for linearity upon installation and at least quarterly
determined linearity over
not
(10 CFR 35.50(b)(3)). Licensees have frequently frequently used for the
the entire range of use. Technetium-99m is most
and it is
linearity test because of its availability and short half-life, 10 percent, dosage
relatively inexpensive. If the percent deviation exceeds
Regulatory Guide 10.8 suggests a
readings must be mathematically corrected. to this level in
trigger level of +5 percent but unless the licensee commits percent variation.
allows for a 10
the license application, the requirement
4. Geometry Dependence
activity does not
Testing for geometry independence ensures that the indicated
be performed, upon
change with volume or configuration. This test mustconfigurations for which it
installation, over the range of volumes and volume in Regulatory Guide 10.8, will be used (10 CFR 35.50(b)(4)) and, as suggested for injections.
should be done using a syringe that is normally used kits should also do the
Licensees who use generators and radiopharmaceutical to the
test using a vial similar in size, shape, and construction testing performed by
radiopharmaceutical kit vials normally used. Geometry manufacturer has
the manufacturer may be acceptable, provided that the the dose calibrator'
included all volumes and volume configurations for which keeps a record of
will be used at the licensee's facility and the licensee
this test.
appropriate checks
Licensees are also required (10 CFR 35.50(c)) to perform after battery
and tests following adjustment (e.g., a constancy check it is not necessary-to
replacement) or repair of the dose calibrator. Whereas relocated
check geometry dependence if the dose calibrator is physically
instrument panel, it
within the department or following minor repairs to the done that might affect
is appropriate to do the geometry check if repairs are linearity and
the response of the chamber. It is appropriate to conduct
accuracy tests following any repairs to the dose calibrator.
(RSO) and Radiation
It is the responsibility of the Radiation Safety Officerperformed. Licensees
Safety Committee (RSC) to ensure that these checks are responsible for
are reminded that 10 CFR 35.21 requires that an RSO be that radiation safety
implementing the radiation safety program and ensuring procedures and
activities are being performed in accordance with approved byproduct
regulatory requirements in the daily operation of the licensee's
that an RSC perform
material program. In addition, 10 CFR 35.22 requires
periodic reviews, to oversee the use of byproduct material.
/
IN 93-10
February 2, 1993 No written response is required by this information
questions about this matter, please contact the notice. If you have any
office or this office. appropriate NRC regional
Richard E. Cunningham, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material
Safety and Safeguards
Technical contact: Patricia K. Holahan, NMSS
(301) 504-2694 Attachments:
1. List of Recently Issued
NMSS Information Notices
2. List of Recently Issued
NRC Information Notices
g - z r
Attachment 1 IN 93-10
February 2, 1993 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
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.
ments for Radioactive
Material Shipments
92-58 Uranium Hexafluoride 08/12/92 All fuel cycle licensees.
Cylinders - Deviations
in Coupling Welds
1%J .
Attachment 2 IN 93-10
February 2, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
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
93-08 Failure of Residual 02/01/93 All holders of OLs or CPs
Heat Removal Pump for nuclear power reactors.
Bearings due to High
Thrust Loading
93-07 Classification of Trans- 02/01/93 All Licensees required to
portation Emergencies have an emergency plan.
93-06 Potential Bypass Leak- 01/22/93 All holders of OLs or CPs
age Paths Around Filters for nuclear power reactors.
Installed in Ventilation
Systems
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
93-02 Malfunction of A Pres- 01/04/93 All holders of OLs or CPs
surizer Code Safety for nuclear power reactors.
Valve
93-01 Accuracy of Motor- 01/04/93 All holders of OLs or CPs
Operated Valve Diagnostic for nuclear power reactors.
Equipment Manufactures
.by Liberty Technologies
OL = Operating License
CP = Construction Permit
IN 93-10
February 2, 1993 No written response is required by this information notice. If you have any
questions about this matter, please contact the appropriate NRC regional
office or this office.
Richard E. Cunningham, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material
Safety and Safeguards
Technical contact: Patricia K. Holahan, NMSS
(301) 504-2694 Attachments:. > v
1. List of Recently Issued
NMSS Information Notices
2. List of Recently Issued
NRC Information Notices
DOCUMENT NAME: 93-10.IN
E. Kraus
TechEd
11/23/92
'4wlm--
OFC :IMAB :IMAB* :IMAB* :IMOB* :OGC* :DD/IMNS* :D/IMNS*
NAME :PHolahan:rj:LWCamper :JEGlenn :FCombs :STreby :JTGreeves:RECunningham
DATE :01/21/93 :12/14/92 :12/17/92 :12/18/92 :01/15/93 :01/25/93 :01/25/93 OFFICIAL RECORD COPY
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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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