Inadequate Testing of Engineered Safety Features Actuation SystemsML031080046 |
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: |
05/24/1993 |
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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-93-038, NUDOCS 9305180426 |
Download: ML031080046 (7) |
|
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 May 24, 1993 NRC INFORMATION NOTICE 93-38: INADEQUATE TESTING OF ENGINEERED
SAFETY FEATURES ACTUATION SYSTEMS
Addressees
for nuclear power
All holders of operating licenses or construction permits
reactors.
Purpose
this information
The U.S. Nuclear Regulatory Commission (NRC) is issuing testing of
in which inadequate
notice to alert addressees to situations It is expected
engineered safety features actuation systems was performed. to their
that recipients will review the information for applicability
avoid similar problems.
facilities and consider actions, as appropriate, to notice are not NRC
However, suggestions contained in this information response is required.
requirements; therefore, no specific action or written
Description of Circumstances
South Texas Units 1 and 2
Nuclear Plant
On September 15, 1992, personnel at the South Texas spray channels
(South Texas) determined that a portion of the containment and logic circuitry was
between the process instrumentation and the actuation engineered safety
not being tested. The containment spray system is an
to be verified
feature (ESF) and is required by technical specifications
operable for plant operation.
is part of the
The controlling logic for the containment spray systemThe purpose of the ESFAS
engineered safety features actuation system (ESFAS). signals to actuate ESF
is to sense plant conditions and, if required, transmit During plant
accidents.
equipment to mitigate the consequences of postulated the ESFAS circuitry is
operation, a set of overlapping tests verifies that
at which process
operable. These tests are performed from the point
of the logic relays. When the
conditions are sensed through the signal output the contacts for the logic
containment spray portion of the system is tested, of the containment spray
relays are opened to prevent inadvertent actuation complete, the
logic is
system. After testing of the containment spray closed position.
contacts for the logic relays are returned to the normal
to verify that
However, the test procedure does not require the test personnel The licensee
the contacts are closed and that the circuits are continuous.
could render the
has determined that a failure of these contacts to close
circuitry inoperable.
9305180426 I: tE NotI CR_ q3-°23
IN 93-38 May 24, 1993 discrepancy. Later, this condition was also found in the same test circuits
at the Braidwood Nuclear Power Station (Braidwood) and at McGuire.
Discussion
In three of the events described above, the testing of normally energized
ESFAS circuits was found to be inadequate because the licensee did not
that the contacts which were opened for the test were closed and the verify
circuits
continuous after completing the test. Failure to close these contacts
result in the failure of ESF equipment to actuate as required. Because could
indication of continuity for this type of circuit may not be available
same manner as for normally energized circuits, other methods may be in the
used
verify that the contacts are closed and that the circuits are continuous. to
Although these three events occurred at pressurized water reactors, potential exists for similar conditions at boiling water reactors. the
The wiring discrepancy found in the test circuitry at Byron, Braidwood
McGuire may also exist in test circuits supplied by Westinghouse at and
sites. At these three facilities, the discrepancy resulted in a failureother
the licensee to perform a required technical specification surveillance by
of the containment isolation phase B logic. test
This information notice requires no specific action or written response.
you have any questions about the information in this notice, please If
the technical contact listed below or the appropriate Office of Nuclearcontact
Reactor-Regulation-(NRR}-projecttmanagei%.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: P. Kim VanDoorn, RII
(704) 875-1681 Attachment:
List of Recently Issued NRC Information Notices
IN 93-38 May 24, 1993 For most of the circuits in the ESFAS, the bistables are normally energized.
The status of these circuits can readily be monitored and displayed on a
bistable status monitoring panel. However, to prevent spurious actuation of
containment spray, the bistables for the containment spray circuits are
normally deenergized and the status of the circuits cannot be monitored in the
same manner as the normally energized circuits. At South Texas, a test
circuit was provided in the containment spray circuitry to allow verification
of circuit continuity between the process instrumentation and the ESF
actuation and logic circuitry without actuating the containment spray system.
The test personnel were not aware that it was necessary to use this test
circuit to verify circuit continuity after closing the contacts.
After making the above discovery, the licensee tested the containment spray
circuitry and found the circuits acceptable. The licensee revised the
applicable procedures to ensure that these circuits would be tested during
future surveillances.
McGuire Units 1 and 2 On February 16, 1993, personnel at the William B. McGuire Nuclear Station
(McGuire) Units 1 and 2, determined that, similar to the event at South Texas, continuity checks were not performed for the containment spray logic relay
contacts and for a contact in the reactor protection circuitry that was also
opened during testing. The contact in the reactor protection circuitry was
the channel test relay contact at the bistable output to the solid-state
protection system for containment spray. The licensee revised the applicable
procedures to ensure that these contacts would be tested during future tests.
Catawba Units 1 and 2 On February 16, 1993, personnel at the Catawba Nuclear Station Units 1 and 2, determined that, similar to the condition at McGuire, continuity checks were
not performed for certain normally deenergized contacts. The licensee
verified the continuity of the circuits and revised procedures to ensure that
the contacts would be tested during future tests. In addition, the licensee
found that, for three channels in Unit I and two channels in Unit 2, the test
points on the printed circuit cards were mislabeled.
Byron Units I and 2
On February 22, 1993, personnel at the Byron Nuclear Power Station (Byron)
Unit 1, found a wiring discrepancy in a cabinet of the solid-state protection
system. The licensee determined that a test connection for containment
isolation phase B (set to actuate at 50 percent of the design pressure of the
containment) was wired to pin 5 of a terminal board instead of pin 6. Because
of this error, surveillance tests performed to verify that the containment
isolation phase B logic cicuitry was acceptable were actually performed on the
containment spray logic circuitry. As a consequence, surveillance tests of
the containment isolation phase B logic had not been performed as required.
This condition was later found to exist also in Unit 2. The licensee
consulted with the supplier, Westinghouse Electric Company, and corrected the
Attachment
IN 93-38 0
.I . May 24, 1993 Page I of I
4 y) I0
0)LU
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Date of
Information
Notice No. Subject Issuance Issued to <U) ~
93-37 Eyebolts with Indeter- 05/19/93 All holders of OLs or CPs 0
minate Properties In- for nuclear power reactors. IL
stalled in Limitorque
Valve Operator Housing
Covers
93-36 Notifications, Reports, 05/07/93 All U.S. Nuclear Regulatory
and Records of Misadmin- *Comission medical
istrations licensees.
93-35 Insights from Common- 05/12/93 All holders of OLs or CPs
Cause Failure Events for nuclear power plants
(NPPs).
93-34, Potential for Loss of 05/06/93 All holders of OLs or CPs
Supp. 1 Emergency Cooling for nuclear power reactors.
Function Due to A
Combination of
Operational and Post- Loca Debris in Contain- ment
93-34 Potential for Loss of 04/26/93 All holders of OLs or CPs
Emergency Cooling for nuclear power reactors.
Function Due to A
Combination of
Operational and Post- Loca Debris in Contain- ment
93-33 Potential Deficiency 04/28/93 All holders of OLs or CPs
of Certain Class IE for nuclear power reactors.
2 Instrumentation and
Control Cables
0
0
) 93-32 Nonconservative Inputs 04/21/93 All holders of OLs or CPs 'no
for Boron Dilution for pressurized water coo0L 0.
Event Analysis reactors (PWRs). td
wUO0
DL
CP - Construction Permit
o'o (A U.
U-
UJ
Z4u
rA
D<
wU )
0 0
25
-1-1
'- IN 93-38 May 24, 1993 AI - .. ________..
. 4... E--44^f
_ .me
% nl m
fmindi tha cnamp tptt circuits
IN 93-xx
'-' May xx, 1993 Discussion
In three of the events described above, the testing of normally energized
ESFAS circuits was found to be inadequate because the licensee did not verify
that the contacts which were opened for the test were closed and the circuits
continuous after completing the test. Failure of these contacts to close
could result in the failure of ESF equipment to actuate as required. Because
indication of continuity for this type of circuit may not be available in the
same manner as for normally energized circuits, other methods may be used to
verify that the contacts are closed and that the circuits are continuous.
Although these three events occurred at pressurized water reactors, the
potential exists for a similar condition at boiling water reactors.
The wiring discrepancy found in the test circuitry at Byron, Braidwood and
McGuire may also exist in test circuits supplied by Westinghouse at other
sites. At these three facilities, the discrepancy resulted in a failure by
the licensee to perform a required technical specification surveillance test
of the containment isolation phase B logic.
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 Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: P. Kim VanDoorn, Region II
(704) 875-1681 Attachment: List of Recently Issued NRC Information Notices
- RPB:ADM *OGCB:DORS:NRR *C/OGCB:DORS:NRR D/DORS/NRR
RSanders JBirmingham GHMarcus BKGrimes
03/29/93 05/14/93 05/14/93 05/ /93
PKVanDoorn WMiller
05/12/93 05/12/93 DOCUMENT NAME: ESFAS.IN2
IN 93-xx
v<-' May xx, 1993 Discussion
In three of the events described above, the testing of normally energized
ESFAS circuits was found to be inadequate because the licensee did not verify
that the contacts which were opened for the test were closed and the circuits
continuous after completing the test. Failure of these contacts to close
could result in the failure of ESF equipment to actuate as required. Because
indication of continuity for this type of circuit may not be available in the
same manner as for normally energized circuits, other methods may be used to
verify that the contacts are closed and that the circuits are continuous.
Although these three events occurred at pressurized water reactors, the
potential exists for a similar condition at boiling water reactors.
The wiring discrepancy found in the test circuitry at Byron, Braidwood and
McGuire may also exist in test circuits supplied by Westinghouse at other
sites. At these three facilities, the discrepancy resulted in a failure by
the licensee to perform a required technical specification surveillance test
of the containment isolation phase B logic.
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 Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: P. Kim VanDoorn, Region II
(704) 875-1681 Attachment: List of Recently Issued NRC Information Notices
RPB:ADM / %' OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS/NRR
RSanders 4 JBirmingham GHMarcus/9 f BKGrimes
03/29/93 05//-/93 05/14/93 05/ /93 R1 1 / 6 RII:DRP p 4 PKVanDoorn
05//2./93 A WMiller°
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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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