Investigation and Reporting of Misadministrations by the Radiation Safety OfficerML031080049 |
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: |
01/07/1993 |
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From: |
Cunningham R Office of Nuclear Material Safety and Safeguards |
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To: |
|
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References |
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IN-93-004, NUDOCS 9212300319 |
Download: ML031080049 (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 January 7, 1993 NRC INFORMATION NOTICE NO. 93-04: INVESTIGATION AND REPORTING OF
MISADMINISTRATIONS BY THE RADIATION
SAFETY OFFICER
Addressees
All U.S. Nuclear Regulatory Commission medical licensees.
Purpose
. 4.
The NRC is issuing this information notice to provide guidance to licensees on
the investigation of events surrounding a misadministration. On January 27,
1992, the "Quality Management Program and Misadministrations" rule became
effective. The current (1992) 10 CFR 35.33(a)(2) requires that a report of a
misadministration must be submitted to NRC and must include, in part, why the
event occurred. This superseded the previous requirement in 10 CFR 35.33(c)
that the Radiation Safety Officer (RSO) should promptly investigate the cause
of a diagnostic misadministration and make a record for NRC review.
Furthermore, in 10 CFR 35.21(b)(1), the RSO is required, in part, to
investigate overexposures and misadministrations, and implement corrective
action, as necessary. Information contained in this notice does not
constitute a new requirement, and no written response is required.
Description of Circumstances
The following case of a diagnostic misadministration reported to the NRC
involved inaccurate information provided by the licensee and a failure of the
RSO to adequately investigate the incident.
A diagnostic misadministration report (DMR), submitted by the licensee, stated
that a nuclear medicine technologist, called in from vacation to administer a
dose of I-131 sodium iodide for a thyroid uptake study, inadvertently
administered 112 microcuries instead of the intended dose of 10 microcuries.
The DMR indicated that the error occurred because the technologist incorrectly
read the dose calibrator as 11.2 microcuries instead of 112 microcuries.
This implies that the technologist assayed a single iodine capsule, which she
subsequently administered to the patient. The DMR also stated that, instead
of five capsules for a total of 100 microcuries, an order was placed for five
capsules of 100 microcuries each. No explanation was provided for the order
of five 20 microcurie capsules for a diagnostic procedure utilizing
10 microcuries. During the inspection, the technologist indicated that she
had assayed five capsules at the same time and then mathematically determined
the activity of a single capsule. Thus the measured activity expressed on the
dose calibrator would have read 560 microcuries instead of 112 microcuries as
reported in the licensee's report. This inaccuracy of the DMR obscured a
9212300319 lase t% 93-OOy 9i°Pro
yet;~C
OWC-A -3 11 c '
CZcT
IN 93-04 January 7, 1992 violation of 10 CFR 35.53 involving a failure to assay each dosage
administration, which very likely contributed to the misadministration.before
RSO was also on vacation at the time of the incident and was not The
made aware of
it until his return. There were inconsistencies between the DMR
explanations of the misadministration event given by the licensee'sand verbal
technologists during an NRC inspection. The RSO indicated that
he performed
an investigation, but he did not personally make a report or maintain
records of the investigation, and his efforts did not uncover the any
fact
the DMR, which was prepared by the Chief Technologist, was inaccurate that
inconsistent. Thus, the violation of 10 CFR 35.53 remained uncorrected, and
could have resulted in future misadministrations. and
Discussion:
Although this event occurred before January 27, 1992, and therefore
defined as a misadministration under the old rule, it would continue was
the definition of a misadministration under the "Quality Management to meet
and Misadministrations' rule. Of greater importance, however, is Program
complete and accurate information in the misadministration report the lack of
failure of the RSO to identify and investigate the cause of the and the
misadministration and implement the necessary corrective action.
10 CFR 30.9(a) requires, in part, that information provided to the
by a licensee or information required by the Commission's regulations Commission
maintained by the licensee must be complete and accurate in all to be
respects. material
Currently, 10 CFR 35.33(a)(2) requires, in part, that the licensee
submit a
written report within 15 days after the discovery of a misadministration
include a brief description of the event, why the event occurred, to
effect
the patient, necessary improvements to prevent recurrence, and actions on
to prevent recurrence as well as other information. 10 CFR 35.21(a) taken
in part, that the licensee, through the RSO, shall ensure that radiation states, safety activities are being performed in accordance with approved
and regulatory requirements in the daily operation of th? licensee'sprocedures
material program. Furthermore, 10 CFR 35.21(b)(1) requires, in byproduct
RSO shall investigate misadministrations, and implement correctivepart, that the
necessary. An investigation may include: 1) talking to all persons action, as
in the misadministration, to include the technologists, authorized involved
patient (if acceptable to the referring physician and necessary user, and
to the
investigation), in order to determine the correct details and
events; 2) reviewing the records associated with the procedure sequence of
requesting physician's order(s) and/or the written directive; 3) including the
independent assessment of the dose delivered to the patient; and performing a,
4) reviewing
any other circumstances associated with the incident. This information
be used to identify the best course of corrective action. If there would
be any discrepancies, the RSO should reexamine all the available appear to
to resolve these discrepancies and make the best determination of information
cause of the misadministration. the root
Licensees should ensure that the RSO at their facility is aware
of and
understands the requirements to: 1) conduct a thorough investigation
IN 93-04 January 7, 1992 following a misadministration; 2) determine improvements needed to prevent
recurrence; 3) implement any necessary corrective action; 4) submit a written
report of the investigation as stated above; and 5) retain a record for five
years of the written report and any other records required by 10 CFR 35.33.
Furthermore, it is essential that the RSO provide sufficient time and
attention to fulfill properly his/her radiation safety program
responsibilities, including all of the requirements in 10 CFR 35.21.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below, or the appropriate NRC regional 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:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
5s-~ 1 / MLsA(
Attachment 2 IN 93-04 January 7, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
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
92-86 Unexpected Restriction 12/24/92 All holders of OLs or CPs
to Thermal Growth of for nuclear power reactors.
Reactor Coolant Piping
92-85 Potential Failures of 12/23/92 All holders of OLs or CPs
Emergency Core Cooling for nuclear power reactors.
Systems Caused by
Foreign Material Blockage
92-84 Release of Patients 12/17/92 All Nuclear Regulatory
Treated with Temporary Commission Medical Licensees
Implants
88-23, Potential for Gas 12/18/92 All holders of OLs or CPs
Supp. 4 Binding of High-Pres- for nuclear power reactors.
sure Safety Injection
Pumps during A Design
Basis Accident
92-83 Thrust Limits for 12/17/92 All holders of OLs or OPs
Limitorque Actuators for nuclear power reactors.
and Potential Over- stressing of Motor- Operated Valves
OL = Operating License
CP = Construction Permit
Attachment 1 IN 93-04 January 7, 1993 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
I_ z __ _._
InTormation Date of
Notice No. Subject Issuance Issued to
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
92-38 Implementation Date for 05/12/92 All holders of OLs or CPs
the Revision to the EPA for-nuclear power reactors.
Manual of Protective non-power reactors and
Action Guides and Pro- materials licensees author- tective Actions for ized to possess large
Nuclear Incidents quantities of radioactive
material.
9.-37 Implementation of the 05/08/92 All Nuclear Regulatory
Deliberate Misconduct Rule Commission Licensees.
92-34 New Exposure Limits for 05/06/92 All licensees whose opera- Airborne Uranium and tions can cause airborne
Thorium concentrations of uranium
and thorium.
IN 93-04 January 7, 1992 following a misadministration; 2) determine improvements needed to prevent
recurrence; 3) implement any necessary corrective action; 4) submit a written
report of the investigation as stated above; and 5) retain a record for five
years of the written report and any other records required by 10 CFR 35.33.
Furthermore, it is essential that the RSO provide sufficient time and
attention to fulfill properly his/her radiation safety program
responsibilities, including all of the requirements in 10 CFR 35.21.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below, or the appropriate NRC regional 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:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
See previous concurrence*
OFC IMAB* l - IMAB *Tl IMAB * l IMOB *
NAME PKHolahan LWCamper JEGlenn FCombs
DATE 12/16/92 12/17/92 12/18/92 12/22/92 OFCOGC l l DD/IMNS N TechEd
NAME STreby JTGreeves RECunningham EKraus
DATE 12/29/92 12/29/92 12/30/92 08/04/92
I
Tick et
DATE RECEIVED: 10/22/92 ORIGINAL DUE DT: 01/05/93 CONTROL NO: 9200608 DIVISION DATE: 12/30/92 DOC DT: 10/19/92 FROM: TIME: COMP DT:
Taylor/Holahan
EDO / NMSS
TO:
Commission
FOR SIGNATURE OF: t* SPEC ** SECY NO:
ASSIGNED TO:
CONTACT
IMNS Camper/Holahan
DESC: ROUTING:
STAFF ACTIONS TO DEVELOP GUIDANCE ON WHAT Bernero
CONSITITUTES A SUFFICIENT INVESTIGATION BY A RSO Arlotto
AFTER A MISADM - STAFF IS PREPARING AN INFO NOTICE Knapp
TO INFORM LICENSEES OF THE ESSENTIAL COMPONENTS OF Jacobs-Baynard
AN ADEQUATE INVESTIGATION OF A MISADMINISTRATION Poland
SPECIAL INSTRUCTIONS OR REMARKS:
SAME AS EDO WITS NUMBER 9200164
DUe to NMSS - 12/30/92 Due to EDO - 01/05/93
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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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