Potential Common-Mode Failure Mechanism for Large Vertical PumpsML031070008 |
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: |
06/17/1994 |
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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-94-045, NUDOCS 9406130197 |
Download: ML031070008 (9) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. 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>. |
V
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 June 17, 1994 NRC INFORMATION NOTICE 94-45: POTENTIAL COMMON-MODE FAILURE MECHANISM FOR
LARGE VERTICAL PUMPS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to a potential common-mode failure mechanism for
large vertical pumps. 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
On March 3, 1994, while performing vibration tests on standby service water
pump B," Grand Gulf personnel noted that vibration levels at all monitored
points were higher than the reference values. Additional testing exhibited a
rapidly degrading trend in pump vibration performance. The pump was declared
inoperable and disassembled for inspection.
The pump is a two-stage vertical line shaft pump with the pump impellers
coupled to the pump motor via a segmented vertical line shaft, approximately
18 meters [60 feet] long (see Figure 1). Six couplings (see Figure 2) are
used to connect the shaft segments. The pumps are located in large cooling
towers that contain water which is chemically treated to reduce biofouling.
The pumps are run weekly for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit addition and circulation of
the chemicals.
Disassembly showed extensive corrosion of the carbon steel bolts and
lockwashers used in the pump shaft coupling assemblies. Some lockwashers were
missing and were assumed to have corroded away completely. The corrosion
allowed each retainer to move away from its contact surface on the sleeve.
This allowed the gaps between the pump shaft sections to increase. This
process increased the effective shaft length which reduced the clearance
between the pump impellers and the bottom of the bowls.
9406130197) PD1 L4 2CLfA ctE 1As- 9 if
ool4JM
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e J
IN 94-45 June 17, 1994 Inspection of pump "B" revealed that the impellers had milled into the pump
bowls, extensively damaging the impellers and the bowls. The licensee
estimated that more than 2.54 cm [1 inch] of material had been worn away from
the impellers and bowls. Subsequent disassembly and inspection of the "A"
standby service water pump also showed corrosion of the coupling fasteners, but there was only minor damage to the impellers and bowls.
The standby service water pumps are tested in accordance with the licensee's
inservice testing program. Neither pump indicated any degradation in
developed head, flow, or vibration during quarterly inservice testing
performed previously. Vibration measurements are taken near the motor bearing
housing because the pump bearings are submerged. Vibration measurements taken
at this location may not identify this type of failure mechanism until
significant damage has occurred. In addition, the motor did not indicate any
increase in running current during testing.
Discussion
This style of coupling is used by several manufacturers of vertical line shaft
pumps. The event at Grand Gulf indicates that current testing of vertical
line shaft pump hydraulic and mechanical performance may not identify, before
damage occurs, interference between the pump impellers and bowls caused by a
change in shaft length. Current manufacturer's recommendations do not require
"as-found" measurements of pump lift to be taken and evaluated whenever the
pump is uncoupled from the motor. The licensee of the Grand Gulf Station has
now added this inspection to its inservice testing program. In addition, after the pumps were rebuilt subsequent to this event, measurements of
as-found total float between the impellers and the bowls were taken by the
licensee. The measurements were taken by lifting the shaft until the upper
part of the impeller contacted the bowl, then measuring the change when the
impeller was lowered and allowed to rest on the bottom of the bowl. This
measurement was taken after the pump was installed, and is to be used to
evaluate measurements taken during the service life of the pump.
Dissimilar materials used in the coupling assembly may have contributed to
this event. The retainer bolts and lockwashers were made of carbon steel; the
pump shafts and remaining coupling components were made of stainless steel.
IN 94-45 June 17, 1994 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 (NRR) project manager.
rian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Rudolph H. Bernhard, RII
(601) 437-4620
Joseph Colaccino, NRR
(301) 504-2753 Attachments:
1. Figure 1, Grand Gulf Standby Service Water Pump
2. Figure 2, Standby Service Water Pump Coupling
3. List of Recently Issued NRC Information Notices
Attachment 1 IN 94-45 June 17, 1994 r/ PUMP MOTOR
ELEV 134' - 8"
- KEED COUPUNG
max Water Lt".
EL. 82'-V
Figure 1 Grand Gulf Standby Service Water Pump
Attachment 2 IN 94-45 June 17, 1994 Page 1 of I
PUMP SHAFT
CAPSCREW
LOCKWASHER
RETAINER
SPLIT RING
SLEEVE-
Figure 2 Standby Service Water Pump Coupling (Typical of 6)
Attachment 3 IN 94-45 June 17, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
94-44 Main Steam Isolation 06/16/94 All holders of OLs or CPs
Valve Failure to Close for nuclear power reactors.
on Demand because of
Inadequate Maintenance
and Testing
94-43 Determination of Primary- 06/10/94 All holders of OLs or CPs
to-Secondary Steam for pressurized water
Generator Leak Rate reactors.
94-42 Cracking in the Lower 06/07/94 All holders of OLs or CPs
Region of the Core for boiling-water reactors
Shroud in Boiling-Water (BWRs).
Reactors
94-41 Problems with General 06/07/94 All holders of OLs or CPs
Electric Type CR124 for nuclear power reactors.
Overload Relay Ambient
Compensation
94-40 Failure of a Rod Control 05/26/94 All holders of OLs or CPs
Cluster Assembly to Fully for pressurized-water
Insert Following a Reactor reactors (PWRs).
Trip at Braidwood Unit 2
94-39 Identified Problems in 05/31/94 All U.S. Nuclear Regulatory
Gamma Stereotactic Commission Teletherapy
Radiosurgery Medical Licensees.
94-38 Results of a Special NRC 05/27/94 All holders of OLs or CPs
Inspection at Dresden for NPRs and all fuel cycle
Nuclear Power Station and materials licensees
Unit 1 Following a Rupture authorized to possess spent
of Service Water Inside fuel.
Containment
94-37 Misadministration Caused 05/27/94 All U.S. Nuclear Regulatory
by a Bent Interstitial Commission Medical Licensees
Needle during Brachy- authorized to us brachy- therapy Procedure therapy sources in high-,
medium-, and pulsed-dose- rate remote afterloaders.
OL = Operating License
CP = Construction Permit
IN 94-45 June 17, 1994 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 (NRR) project manager.
orig /s/'d by BKGrimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Rudolph H. Bernhard, RII
(601) 437-4620
Joseph Colaccino, NRR
(301) 504-2753 Attachments:
1. Figure 1, Grand Gulf Standby Service Water Pump
2. Figure 2, Standby Service Water Pump Coupling
3. List of Recently Issued NRC Information Notices
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OFFICE DRP/RII* EMEB/DE* OGCB/DORS* TECH ED* SC:DRP/RII*
NAME RHBernhard JColaccino PCWen RSanders FCantrell
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05/25/94
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05/25/94 05/25/94 05/26/94 05/26/94 06/01/94 06//3'/94 DOCUMENT NAME: 94-45.IN
'-' IN 94-xx
June xx, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this hotice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Rudolph H. Bernhard, RII
(601) 437-4620
Joseph Colaccino, NRR
(301) 504-2753 Attachments:
1. Figure 1, Grand Gulf Standby Service Water Pump
2. Figure 2, Standby Service Water Pump Coupling
3. List of Recently Issued NRC Information Notices
OFFICE DRP/RII* EMEB/DE* OGCB/DORS* TECH ED* SC:DRP/RII*
NAME RHBernhard JColaccino PCWen RSanders FCantrell
nATF ng/99/94 05/25/94 05/25/94 05/25/94 05/25/94
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IN 94-xx
June xx, 1994 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 (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Rudolph H. Bernhard, RII
(601) 437-4620
Joseph Colaccino, NRR
(301) 504-2753 Attachments:
1. Figure 1, Grand Gulf Standby Service Water Pump
2. Figure 2, Pump Coupling
3. List of Recently Issued NRC Information Notices
OFFICE DRP/RIICW EMEB/DE I OGCB/DOR > TECH ED I _SC:DRP/
NAME A fRHBernhard JColaccino I PCWen Lj' rFaCantrell
DATE 05/aS/94 05/2-5/94_
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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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