Digital Integrated Circuit Sockets with Intermittent ContactML031070058 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
01/14/1994 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-94-004, NUDOCS 9401100143 |
Download: ML031070058 (6) |
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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 REACTOR REGULATION
WASHINGTON, D.C. 20555 January 14, 1994 NRC INFORMATION NOTICE 94-04: DIGITAL INTEGRATED CIRCUIT SOCKETS WITH
INTERMITTENT
CONTACT
Addressees
All NRC licensees except licensed operators.
PurDose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to a potential problem involving socket connectors
used for digital integrated circuits manufactured by Augat, Inc. It is
expected that recipients will review the information for applicability to
their facilities and consider actions, as appropriate, to avoid similar
problems. However, suggestions contained in this information notice are not
NRC requirements; therefore, no specific action or written response is
required.
Description of Circumstances
During April 1993, at the D. C. Cook Nuclear Plant, the licensee observed
intermittent failures of various process control units during testing. The
internal monitoring system for a control unit would detect a problem and
the instrument down (i.e., cause its outputs to reduce to zero and remain shutin
an audible alarm state). The NRC learned about this recurrent problem during
an analog-to-digital process instrumentation inspection at this site (NRC
Inspection Report 50-315/93-18; 50-316/93-18). Subsequent to a July
meeting between the licensee and the control unit manufacturer, Asea 1, 1993, Brown
Boveri-Kent-Taylor (ABB-Kent-Taylor), the problem was isolated to the sockets
for the integrated circuits. Deficiencies in the sockets resulted in
intermittent contacts between the integrated circuits and the sockets, thus
interrupting signal processing. These sockets, which are manufactured by
Augat, Inc., are made in various grades and one of the lower grade sockets was
being used. Augat, Inc. is an international supplier of interconnection
systems for the computer, automotive, and telecommunications industries.
These sockets were produced in large numbers and some may be in use in nuclear
as well as non-nuclear applications where their failure could either initiate
a transient or interfere with response to a transient.
The process control units (Taylor MOD 30) were built as commercial-grade
equipment in 1989 but were not delivered to the licensee until 1992, and were
not shipped to the site until the Spring of 1993. The original purchase order
included both safety-related units and nonsafety-related units. Asea Brown
Boveri-Combustion Engineering (ABB-CE) was supposed to qualify the equipment
9401100143'
P1tE M oist cv-, 94 oOL4 c q6ll
Ill
\_JIN 94-04 January 14, 1994 designated for safety-related use before the safety-related equipment was
released and shipped to the D.C. Cook plant. For reasons unrelated to the
socket deficiencies, the contract was amended to exclude safety-related
equipment. However, the nonsafety-related equipment will be used in the AMSAC
[ATWS (anticipated transients without scram) Mitigation System Actuation
Circuitry].
The licensee informed ABB-CE of this potential generic product deficiency in
an August 20, 1993, letter. Followup in September 1993 revealed that the
manufacturer believes it has not sold any Taylor MOD 30 instruments to nuclear
power plants for use in safety-related applications.
Discussion
In the D. C. Cook application, the sockets are located on an internal
component identified as a 'digital board." There are 7 sockets per digital
board; 5 of the sockets are 28-pin sockets and are being used for programmed
PROMs (Programmable Read Only Memories), one 20-pin socket is being used for a
programmed logic array integrated circuit, and one 40-pin socket is being used
for a single-chip microprocessor unit. The 520 instruments contain a total of
more than 3500 sockets.
Subsequent discussions with the licensee concerning the generic nature of the
deficiency produced additional information. The 20-, 28-, and 40-pin sockets
had the following respective Augat part numbers: 520-AG12D-ES, 528-AG12D-ES,
540-AG12D-ES. The 'ES' suffix indicates that a socket is an Economy Series
socket. Augat, Inc. introduced this series in 1985 to provide a less
expensive version of its traditional machined contact. The contact portion of
the ES socket is produced by a stamping process rather than by a machining
process. The stamped ES sockets were first used in Taylor MOD 30 equipment in
1988. In February 1991, the control unit manufacturer, ABB-Kent-Taylor, changed back to the machined version after producing approximately 7,000-
10,000 instruments with the ES sockets. Tests performed in July 1993 confirmed that the withdrawal force for the ES stamped contact sockets was
considerably less than for the machined contact sockets. Both of these
sockets had a tin-lead inner contact. The ES sockets are being replaced with
machined contact 520-AG12D, 528-AG12D, and 540-AG12D sockets.
Some Augat, Inc. ES sockets have exhibited a relatively high incidence of
intermittent failure. The failure rate among the 256 Taylor MOD 30
instruments tested was determined to be approximately 15 percent through
July 1993. It appears that the use of a tin-lead inner contact, the stamping
method of manufacture, and the length of time an instrument sits de-energized
may serve in combination to permit or create oxidation on the contacts.
However, the root cause of the intermittent contact between the integrated
circuit and its socket has not been determined. ABB-Kent-Taylor believes that
the delay between shipment and construction, while the units sat de-energized, may have been a contributing factor in the failure. If this is the case, instruments stored as spare parts (which would also be de-energized) could be
similarly affected.
IN 94-04 January 14, 1994 A recent design review of an analog-to-digital upgrade for the reactor
protection system at a foreign plant revealed that the integrated circuit
socket specified was the type discussed above; i.e., it was
Augat, Inc. and was the ES type. The contact design is beingmanufactured by
reevaluated.
This information notice requires no specific action or written response.
you have any questions about the information in this notice, please If
contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation project manage
n K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Edward R. Schweibinz, RIII
(708) 829-9712 Vern Hodge, NRR
(301) 504-1861 Attachment:
List of Recently Issued NRC Information Notices
.A- h-Atchment
IN 94-04 January 14, 1994 Page 1 of I
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information ate of
Notice No. Subject Issuance
IssuaceIssued
Isued to
t
94-03 Deficiencies Identified 01/11/94 during Service Water System All holders of OLs or CPs
Operational Performance for nuclear power reactors.
Inspections
94-02 Inoperability of General 01/07/94 Electric Magne-Blast All holders of OLs or CPs
Breaker Because of Mis- for nuclear power reactors.
Alignment of Close-Latch
Spring
94-01 Turbine Blade Failures 01/07/94 All holders of OLs or CPs
Caused by Torsional for nuclear power reactors.
Excitation from Electrical
System Disturbance
93-101 Jet Pump Hold-Down Beam 12/17/93 Failure All holders of OLs or CPs
for boiling-water reactors.93-100 Reporting Requirements 12/22/93 for Bankruptcy All U.S. Nuclear Regulatory
Commission licensees.
91-29, Potential Deficiencies 12/22/93 Supp. 2 Found During Electrical All holders of OLs or CPs
Distribution System for nuclear power reactors.
Functional Inspections
93-99 Undervoltage Relay and 12/21/93 Thermal Overload Setpoint All holders of OLs and CPs
Problems for nuclear power reactors.
93-98 Motor Brakes on Valve 12/20/93 Actuator Motors All holders of OLs and CPs
for nuclear power reactors.
93-97 Failures of Yokes 12/17/93 Installed on Walworth All holders of OLs or CPs
Gate and Globe Valves for nuclear power reactors.
93-96 Improper Reset Causes 12/14/93 Emergency Diesel All holders of OLs or CPs
Generator Failures for nuclear power reactors.
OL
0 Operating License
CP = Construction Permit
<F~IN 94-04 il I . .
January 14, 1994 A recent design review of an analog-to-digital upgrade for the reactor
protection system at a foreign plant revealed that the integrated circuit
socket specified was the type discussed above; i.e., it was manufactured by
Augat, Inc. and was the ES type. The contact design is being reevaluated.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation project manager.
°rfml agned '
Bnaln K.Grimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Edward R. Schweibinz, RIII
(708) 829-9712 Vern Hodge, NRR
(301) 504-1861 Attachments:
1. List of Recently Issued NRC Information Notices
This information notice was coordinated with MBCongdon, OIP/PDD, on about
11/22/93.
This information notice was coordinated with EWBrach, NMSS/LLWM, on 12/22/93.
OFFICE *OGCB *TECH ED. *C:HICB/DSSA *REGION III
NAME CVHodge RSanders JSWermiel ERSchweibinz
DATE 11/18/93 11/16/93 1/18/93 Ž2101/93
_I II
I _ .
- D:DRP/REGION III *C:OGCB/NRR D: DM/lRX
EGGreenman GHMarcus A60Vs
12/01/93 12/02/93 101//0/94 DOCUMENT NAME: 94-04.IN
IN 93-xx
November xx, 1993 During a September 13-14, 1993, Digital System Reliability and Nuclear Safety
Workshop sponsored by the NRC in cooperation with the National Institute of
Standards and Technology, this subject was discussed with a foreign
participant. The following week that participant contacted the NRC for more
details, because a design review of an analog-to-digital upgrade for the
reactor protection system at the foreign plant revealed that the IC socket
specified was the type discussed above; i.e., it was manufactured by Augat, Inc. and was the ES type. Subsequently, the design has been reevaluated to
consider specification of a machined contact.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Edward R. Schweibinz, Region III
(708) 829-9712 Vern Hodge, NRR
(301) 504-1861 Attachments:
1. List of Recently Issued NRC Information Notices
OFFICE *OGCB *TECH ED. *REGION III *Region *C:HICB/DSSA
III
NAME CVHodge RSanders ERSchweibinz EGGreenman JSWermiel
DATE 11/18/93. . 11/16/93
. 12/01/93
. . 12/01/93
. 11/18/93
. l
I D:DORS/NRR
C:OGCB/NRR
GHMarcus&
1a/2. /93 I BKGrimes
11/ /93 DOCUMENT NAME: ICSOCKET.INF
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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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