Misadministration Caused by a Bent Interstitial Needle During Brachytherapy ProcedureML031060537 |
Person / Time |
---|
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: |
05/27/1994 |
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From: |
Paperiello C NRC/NMSS/IMNS |
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To: |
|
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References |
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-nr IN-94-037, NUDOCS 9405230065 |
Download: ML031060537 (5) |
|
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 May 27, 1994 NRC INFORMATION NOTICE 94-37: MISADMINISTRATION CAUSED BY A BENT INTERSTITIAL
NEEDLE DURING BRACHYTHERAPY PROCEDURE
Addressees
All U.S. Nuclear Regulatory Commission Medical Licensees authorized to use
brachytherapy sources in high-, medium-, and pulsed-dose-rate remote
afterloaders.
Purpose
NRC is issuing this information notice to alert NRC licensees of an incident
involving an interstitial needle bent inside the patient's body during a high- dose-rate procedure with an Omnitron 2000 brachytherapy system. The bend in
the Omnitron interstitial needle, through which the radioactive source
travels, prevented the source from retracting beyond the point of the bend.
This resulted in the actual radiation dose received by the patient exceeding
the prescribed dose by approximately 75 percent. It is expected that
recipients will review this information for applicability to their facilities
and consider actions, as appropriate. However, suggestions contained in this
information notice are not new NRC requirements; therefore, no specific
actions nor written response is required.
Description of Circumstances
On January 13, 1994, at the end of an interstitial lung treatment, the source
wire containing a 144.3 gigabecquerel (3.9 curie) iridium-192 source failed to
retract to the shielded storage position. Members of the medical staff
followed appropriate emergency procedures and removed the needle from the
patient. Licensee personnel noted a kink in the interstitial needle after
removal. Once outside the patient's body, the source retracted into the
shielded position. As a result of the stuck source, the dose to the last
treatment position was 17.32 gray (Gy) (1732 rads) versus the prescribed dose
of 10 Gy (1000 rads). In addition, an area just below the last treatment
location received a dose of approximately 14 Gy (1400 rads) versus the 8 Gy
(800 rads) intended in the prescribed treatment plan.
The kink in the needle occurred at a location where the interstitial needle
extended beyond a biopsy needle to facilitate the insertion. Under this
configuration, the biopsy needle acted as a sleeve covering approximately 75 percent of the interstitial needle. The licensee's preliminary conclusion was
that the kink at the interface between the interstitial and biopsy needles was
caused by a sudden movement of the patient near the end of the treatment. The
licensee reached this conclusion on the basis that X-rays taken just before
the treatment revealed no unusual conditions and the treatment was uneventful
9405230065 PD tE NcWC)lC 9&- 03 Qf 9 ji 5bA
lV
~Abotm II
IN 94-37 May 27, 1994 until the patient's sudden movement. When the biopsy and interstitial needles
were withdrawn from the patient, the kink in the interstitial needle was
relieved somewhat, allowing the source to return to the storage position.
Early during the needle insertion process, it had been difficult to insert a
different Omnitron needle through the patient's rib cage to the treatment
site. As a result, licensee physicians opted to use a biopsy needle, through
which the interstitial needle was placed in the desired location. Believing
that the shielding provided by the biopsy needle would interfere with the
delivery of the radiation dose, a physician retracted the biopsy needle to
just outside the treatment site.
Discussion
Needles and other accessories to high-dose-rate remote afterloading therapy
may be subjected to unusual mechanical stresses during patient treatment.
Each patient setup should be carefully evaluated to avoid or minimize the
potential for deformation of needles and other guides. In particular, reducing thickness or withdrawing another device in order to preserve dose
rate may not be in the best interests of safety. In most instances, any
reduction in dose rate may be compensated by a modest increase in treatment
time. If the use of extremely thin materials cannot be avoided, licensees
should ensure that their operating and emergency procedures are adequate to
prevent and mitigate the consequences of mechanical deformations in the path
of the source wire. In such circumstances, surgical intervention may be
required and should be included in emergency plans as required in NRC
Bulletin 93-01.
This information notice requires no specific action nor written response. If
you have questions about the information in this notice, please contact the
technical contact listed below or the appropriate regional office.
I^,Carl J. Paperiello, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contacts: Hector Bermudez, RII
(404) 331-7880
James Smith, NMSS
(301) 415-7904 Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
Attachment 1 IN 94-37 May 27, 1994 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
94-35 NIOSH Respirator User 05/16/94 All holders of OLs or CPs
Notices, "Inadvertent for nuclear power reactors, Separation of the Mask- and all licensed fuel
Mounted Regulator (MMR) facilities.
from the Facepiece on the
Mine Safety Appliances (MSA)
Company MMR Self-Contained
Breathing Apparatus (SCBA)
and Status Update"
94-23 Guidance to Hazardous, 03/25/94 All NRC licensees.
Radioactive and Mixed
Waste Generators on the
Elements of A Waste
Minimization Program
94-21 Regulatory Requirements 03/18/94 All fuel cycle and materials
when No Operations are licensees.
being Performed
94-17 Strontium-90 Eye Appli- 03/11/94 All U.S. Nuclear Regulatory
cators: Submission of Commission Medical Use
Quality Management Plan Licensees.
(QMP), Calibration, and
Use
94-16 Recent Incidents Resulting 03/03/94 All U.S. Nuclear Regulatory
in Offsite Contamination Commission material and fuel
cycle licensees.
94-15 Radiation Exposures during 03/02/94 All U.S. Nuclear Regulatory
an Event Involving a Fixed Commission licensees author- Nuclear Gauge ized to possess, use, manu- facture, or distribute
industrial nuclear gauges.
Attachment 2 IN 94-37 May 27, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
94-36 Undetected Accumulation 05/24/94 All holders of OLs or CPs
of Gas in Reactor for nuclear power reactors.
Coolant System
91-81, Switchyard Problems that 05/19/94 All holders of OLs or CPs
Supp. 1 Contribute to Loss of for nuclear power reactors.
Offsite Power
94-35 NIOSH Respirator User 05/16/94 All holders of OLs or CPs
Notices, "Inadvertent for nuclear power reactors, Separation of the Mask- and all licensed fuel
Mounted Regulator (MMR) facilities.
from the Facepiece on the
Mine Safety Appliances (MSA)
Company MMR Self-Contained
Breathing Apparatus (SCBA)
and Status Update"
94-Z4 Thermo-Lag 330-660 05/13/94 All holders of OLs or CPs
Flexi-Blanket Ampacity for nuclear power reactors.
Derating Concerns
94-33 Capacitor Failures in 05/09/94 All holders of OLs or CPs
Westinghouse Eagle 21 for nuclear power reactors.
Plant Protection Systems
93-53, Effect of Hurricane 04/29/94 All holders of OLs or CPs
Supp. 1 Andrew on Turkey Point for nuclear power reactors.
Nuclear Generating
Station and Lessons Learned
94-32 Revised Seismic Hazard 04/29/94 All holders of OLs or CPs
Estimates for nuclear power reactors.
94-31 Potential Failure of 04/14/94 All holders of OLs or CPs
Wilco, Lexan-Type HN-4-L for nuclear power reactors.
Fire Hose Nozzles
90-68, Stress Corrosion Cracking 04/14/94 All holders of 01 or CPs
Supp. 1 of Reactor Coolant Pump for pressurized water
Bolts reactors.
OL = Operating License
CP = Construction Permit
___ IN 94-37
_ May 27, 1994 until the patient's sudden movement. When the biopsy and interstitial needles
were withdrawn from the patient, the kink in the interstitial needle was
relieved somewhat, allowing the source to return to the storage position.
Early during the needle insertion process, it had been difficult to insert a
different Omnitron needle through the patient's rib cage to the treatment
site. As a result, licensee physicians opted to use a biopsy needle, through
which the interstitial needle was placed in the desired location. Believing
that the shielding provided by the biopsy needle would interfere with the
delivery of the radiation dose, a physician retracted the biopsy needle to
just outside the treatment site.
Discussion
Needles and other accessories to high-dose-rate remote afterloading therapy
may be subjected to unusual mechanical stresses during patient treatment.
Each patient setup should be carefully evaluated to avoid or minimize the
potential for deformation of needles and other guides. In particular, reducing thickness or withdrawing another device in order to preserve dose
rate may not be in the best interests of safety. In most instances, any
reduction in dose rate may be compensated by a modest increase in treatment
time. If the use of extremely thin materials cannot be avoided, licensees
should ensure that their operating and emergency procedures are adequate to
- prevent and mitigate the consequences of mechanical deformations in the path
of the source wire. In such circumstances, surgical intervention may be
required and should be included in emergency plans as required in NRC
Bulletin 93-01.
This information notice requires no specific action nor written response. If
you have questions about the information in this notice, please contact the
technical contact listed below or the appropriate regional office.
Carl J. Paperiello, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contacts: Hector Bermudez, R11
(404) 331-7880
James Smith, NMSS
(301) 415-7904 Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
lOFC IMAB I IMAB IMAB I Tech Ed ll IMO
NAME JASmith LWCamper* JEGlenn* EKraus* FCCombs*
DATE 05/12/94 04/25/94 04/26/94 04/22/94 05/02/94 OFC OGC I E DD/IMNS L D/IMNS III
NAME STreby* WBrach CPaperiello
DATE 05/10/94 05/17/94 05/16/94 _
DOC NAME: 94-37.IN
Official Record Copy
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list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994)
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