Nonconservatism in Low-Temperature Overpressure Protection for Pressurized-Water ReactorsML031070245 |
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: |
07/26/1993 |
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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-93-058, NUDOCS 9307190131 |
Download: ML031070245 (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 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>. |
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 July 26, 1993 NRC INFORMATION NOTICE 93-58: NONCONSERVATISM IN LOW-TEMPERATURE OVERPRESSURE
PROTECTION FOR PRESSURIZED-WATER REACTORS
Addressees
All holders of operating licenses or construction permits for pressurized- water reactors.
,
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to a nonconservatism in the low-temperature
overpressure protection (LTOP) setpoint calculation for Westinghouse
facilities. 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 Circumstance
On October 29, 1992, the Texas Utilities Electric Company, the licensee for
Comanche Peak Steam Electric Station, reported that its existing low
temperature overpressure protection may not have provided the required margins
of safety against reactor vessel brittle fracture under certain overpressure
transients.
The same concern was later reported by the licensees for Byron, Zion, Diablo
Canyon, Kewaunee, Sequoyah and Point Beach nuclear stations.
Discussion
In reactor units designed by Westinghouse, overpressure protection of the
reactor vessel at low temperature conditions is provided by a cold
overpressure mitigation system (COMS). This system compares pressure and
temperature inputs against a preset setpoint curve and relieves the pressure
when the setpoint is reached. This protection is necessary because, while at
low temperatures during plant startup and shutdown conditions, certain
transients could cause the reactor coolant system pressure to exceed the
reactor vessel pressure-temperature (P-7) limitations established for
protection against brittle fracture. A spurious start of a safety injection
pump, reactor coolant pump, or other operational errors could activate this
system. During such events, the P-T limitations are maintained by opening the
pressurizer power-operated relief valves (PORVs) or safety relief valves in
the residual heat removal (RHR) suction lines to relieve system pressure.
9307190131 RD3 -R
IN 93-58 July 26, 1993 The transmitters that provide pressure signals to the COMS are located at the
primary system hot leg piping of the reactor vessel. During low temperature
operation of the reactor coolant pumps, dynamic pressure in the reactor vessel
would be higher (by the amount of flow loss in the core and vessel outlet)
than that sensed in the hot leg. Additionally, the static head correction for
the difference in elevation of the sensor to the core region was not
considered. The resulting pressure difference between the sensor and the
vulnerable location in the reactor vessel could be as high as 790 kPa
(100 psig), depending on the number of reactor coolant pumps in operation and
the location of the pressure-sensing taps. The LTOP setpoint curve that was
originally developed by Westinghouse did not take these factors into
consideration.
Westinghouse has sent a letter to licensees recommending one of the following
methods to compensate for this pressure increase: 1) reduce the maximum
allowable relief valve setpoint by an amount equivalent to the plant-specific
calculated difference in pressure, 2) maintain RCS pressure below the
heatup/cooldown curves by a value equal to the plant specific difference in
pressure from both flow loss and elevation difference when the reactor coolant
pumps are in operation, 3) restrict the number of reactor coolant pumps and, therefore, the flow loss error that can be operated below a defined RCS
temperature without drawing a steam bubble in the pressurizer, or 4)
demonstrate that the available margin in the LTOP calculation, taking into
account instrumentation uncertainty, is sufficient to offset the plant- specific pressure difference.
The Westinghouse letter describes interim administrative controls as well as
calculational methods to verify setpoint adequacy for addressing the LTOP
concern. The staff notes that the administrative restrictions described in
approaches (2) and (3) are intended by Westinghouse to provide interim actions
to address the concern only until LTOP setpoints are verified to be adequate
or are revised appropriately in technical specifications.
Although the information in this notice addresses the cold overpressure
mitigation system at Westinghouse designed plants, aspects of this issue may
also be applicable to other PWRs.
r *s
IN 93-58 July 26, 1993 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: Thomas Koshy
(301) 504-1176 Chu-Yu Hang
(301) 504-2878 Attachment: List of Recently Issued NRC Information Notices
. t
0
Attachment 4>
IN 93-58 July 26. IM us
Page I of I
LIST OF RECENTLY ISSUED
. 0)
NRCINFORMATION NOTICES (I)
0
Information Date of
Notice No. Subject Issuance Issued to
0.
93-57 Software Problems 07/23/93 All holders of OLs or CPs
Involving Digital for test and research
Control Console Systems reactors and nuclear power
at Non-Power Reactors reactors
93-56 Weakness in Emergency 07/22/93 All holders of OLs or CPs
Operating Procedures for pressurized water
Found as Result of reactors.
Steam generator Tube
Rupture
93-55 Potential Problem with 07/21/93 All holders of OLs or CPs
Main Steamline Break for pressurized water
Analysis for Main Steam reactors. 0 _
Vaults/Tunnels
93-54 Motor-Operated Valve 07/20/93 All holders of OLs or CPs
Actuator Thrust for nuclear power reactors.
Variations Measured
with A Torque Thrust
Cell and A Strain Gage
93-53 Effect of Hurricane 07/20/93 All holders of OLs or CPs
Andrew on Turkey Point for nuclear power reactors.
Nuclear Generating
Station and Lessons
Learned
93-52 Draft NUREG-1477, 07/14/93 All holders of OLs or CPs
'Voltage-Based Interim for pressurized water 2
.) Plugging Criteria for reactor (PWRs). 2 Steam Generator Tubes' t o
93-51 Repetitive Overspeed 07/09/93 All holders of OLs or CPs Lno
8 Tripping of Turbine- for nuclear power reactors. 0 o, Driven Auxiliary Feed- co
water Pumps W U Z UJ
93-50 Extended Storage of 07/08/93 All licensees authorized _A3>
4 Sealed Sources to possess sealed sources.
Z. i
cc
OL - Operating License
CO0
2C
-i1X
o
CP - Construction Permit
LU 0.
zw
IN 93-58 July 26, 1993 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.
Ordginal sgnei by
Brian IL. W=me
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Thomas Koshy
(301) 504-1176 Chu-Yu Liang
(301) 504-2878 Attachment: List of Recently Issued NRC Information Notices
OFC OEAB:DORS ADM:PUB SC/OEAB:DORS C/SRXB:DSSA
NAME TKoshy* Tech Editor* EGoodwin* RJones*
l DATE 06/04/93 05/10/93 05/21/93 06/04/93 I OFC
NAME
C/EMCB:DE
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C/OEAB:DORS
AChaffee*
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1 DATE 05/24/931 06/08/93 06/17/93 06/17/93
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lNAME W ames
lDATE 07/-vf/93
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IN 93-XX
June xx, 1993 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: Thomas Koshy
(301) 504-1176 Chu-Yu Liang
(301) 504-2878 Attachment: List of Recently Issued NRC Information Notices
OFC OEAB:DORS ADM:PUB l SC/OEAB:DORS C/SRXB:DSSA
l NAME TKoshy* Tech Editor* EGoodwin* RJones* l
[ DATE
OFC
NAME
l 06/04/93 l C/EMCB:DE
JStrosnider*
l 05/10/93 C/OEAB:DORS
AChaffee*
l 05/21/93 OGCB:DOR Ltj
JLBirmingam
06/04/93 C/OGCB:DORS
HMarcus L
l
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DATE 05/24/93 06/08/93 06/16/93 06/ 7/93 lOFC D/:DORS l l l _ _
NAME BKGrimes l
DATE 06/ /93 l _
[OFFICIAL RECORD COPY]
DOCUMENT NAME: S:\DO RS SEC\LTOPREV1.IN
OFC OEAB:DORS ADM:PUB SC/OEAB:DORS C/SRXB:DSSA
NAME TKoshyA- Tech Editor* EGoodwin* RJones*
DATE 6 4 /93 05/10/93 05/21/93 06/04/93
[OFC C/EMCB:DE C/OEAB:DORS C/OGCB:DORS D/DORS
NAME JStrosnider* AChaffee* GMarcus BGrlimes
DATE 05/24/93 106/08/93 / /93 / /93
[OFFICIAL RECORD COPY]
DOCUMENT NAME: S:\DORSSEC\LTOP.IN
[OFC OEAB:DORS ADM:PUB SC/OEAB:DORS C/SRXB:D S l
NAME TKoshy Tech Editor* EGoodwin* RJones/
DATE 60 /zI/93 05/10/93 05/21/93 1 y/93 OFC C/EMCB:DE C/OEAB:WDORS C/OGCB:DORS D/DORS
NAME JStrosnider* A ee GMarcus BGrimes
DATE 105/24/93 j 0 /6 /93 J
/ /93 j
[OFFICIAL RECORD COPY]
DOCUMENT NAME: G:\TXK\LTOP.IN
OFC OEAB:DORS ADM:PUB SC/OEAB:DORS C/SRXB:DSSA ,
NAME TKoshy & Tech Editor* EGoodwin RJones
DATE 05/tQ/93 05/10/93 05/ l93 e e I 193
[OFC
NAME
DATE
_ C/EMCB:DE
JStrosnide
05/24/93 IC/OEAB:DORS
AChaffee
05/ /93 C/OGCB:DORS
GMarcus
05/ /93 D/DORS
BGrimes
05/ J93
[OFFICIAL RECORD COPY]
DOCUMENT NAME: G:\TXK\LTOP.IN
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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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