Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip BreakerML031080169 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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: |
02/02/1993 |
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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-93-009, NUDOCS 9301260286 |
Download: ML031080169 (8) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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 [[: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 [[: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 February 2, 1993 NRC INFORMATION NOTICE 93-09: FAILURE OF UNDERVOLTAGE TRIP ATTACHMENT ON
WESTINGHOUSE MODEL DB-50 REACTOR TRIP BREAKER
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 the failure of an undervoltage trip attachment
on a reactor trip breaker at the Salem Nuclear Generating Station, Unit 1.
The failure occurred during surveillance testing. 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 July 25, 1991, Public Service Electric and Gas Company, the licensee for
Salem, Unit 1, was conducting the monthly surveillance tests of the
undervoltage trip attachment and the shunt trip attachment associated with
reactor trip circuit breakers. Licensee personnel successfully completed the
shunt trip attachment surveillance tests. However, when the undervoltage trip
attachment trip test was attempted on the "A" reactor trip breaker
(Westinghouse model DB-50), the circuit breaker required approximately
16 cycles (0.267 seconds) to open. For the function to be considered
operable, technical specifications require that the breaker open in 10 cycles
(0.167 seconds) or less. A second attempt to open the breaker using the
undervoltage attachment was unsuccessful; the breaker remained closed.
Discussion
On July 26, 1991, a Westinghouse representative and licensee personnel
performed various bench tests on the "A" reactor trip breaker. The tests
indicated that the breaker had been properly maintained and that the breaker
trip bar was functioning normally. However, when the undervoltage trip
attachment was tested, it again failed to open the breaker. The undervoltage
trip attachment was not striking the circuit breaker trip bar with sufficient
force to lift the bar. When the undervoltage trip attachment was lubricated
and retested, the undervoltage trip attachment armature successfully lifted
the circuit breaker trip bar, opening the breaker within the required
10 cycles. The licensee re-lubricated and tested the undervoltage trip
9301260286 PatI If past 9l3-0
4 EC
IN 93-09 February 2, 1993 attachment with 300 grams of weight added to the trip bar as required
monthly surveillance test procedure. The test was again performed by the
satisfactorily. The trip attachment also lifted the trip bar with an
460 grams, the amount of additional weight required by the licensee semi-added
annual surveillance test procedure.
Initially, the cause of the failure appeared to have been inadequate
lubrication; however, the undervoltage trip attachment was returned
Westinghouse for further evaluation. Westinghouse later concluded to
that the
root cause of the failure'of the device was abnormal frictional forces
resulted primarily from the unpolished outside latch contact surfaces which
undervoltage trip attachment. Westinghouse representatives stated thatof the
areas had not been properly finished during the manufacturing process. these
outside contact surface of the latch was "bright" on only one edge ratherThe
on the entire surface. The "bright" edge also appeared to be burred than
serrated. or
Westinghouse representatives also found excessive wear and grooving
on
undervoltage trip attachment latch spring at a location where the latch the
latch spring were making'contact. Contact between the latch and the and
spring occurred because the latch spring was somewhat deformed and did latch
flat as designed. The latch spring deformation, grooving, and wear not lie
in
combination with the improperly finished latch contact surfaces created
additional internal frictional forces such that the undervoltage trip
attachment armature-was unable to apply sufficient-force-to lift the-breaker
trip bar.
During the evaluation, Westinghouse personnel reassembled and cycled
the
undervoltage trip attachment 250 times. The undervoltage trip attachment
then tested, lubricated, and retested. Each time the undervoltage trip was
attachment was tested, it provided sufficient force to operate the breaker
trip bar. However, the force applied by the device appeared to decrease
250 cycles but increase at 500 cycles. 'The force then appeared to decrease at
somewhat after 750 cycles, although this may be attributed to testing
inaccuracies. While the testing was not considered conclusive, the
performance of the undervoltage trip attachment apparently degrades
improves to some plateau. Westinghouse concluded that this change and then
from, first, increasing friction as the latch cuts into the latch results
spring; and
later, decreasing friction as the parts wear and as pressure from the
spring decreases as it permanently deforms. latch
The undervoltage trip attachments equipped with improperly finished
latches
were provided to various utilities by the Replacement Component Services
Department of the Westinghouse Nuclear Services Division (NSD). These (RCS)
undervoltage trip attachments were supplied either individually or as
remanufactured or overhauled Westinghouse Model DB-50 circuit breakers part of
installed undervoltage trip attachments. Westinghouse determined that with
improperly finished undervoltage trip attachment parts were from one all the
parts that was made exclusively for RCS by a subcontractor. The same lot of
subcontractor made a second lot of undervoltage trip attachment parts;
second lot contained no improperly finished parts. Westinghouse this
IN 93-09 February 2, 1993 representatives stated that none of the defective parts have been used in
undervoltage trip attachments or DB-50 circuit breakers available on the open
market as commercial 'grade items. Westinghouse informed the NRC that it has
notified all customers of record who have purchased undervoltage trip
attachments or Model DB-50 circuit-breakers with parts from the affected lot.
Westinghouse personnel recommended that the Salem licensee visually inspect, for proper finish, the undervoltage trip attachment latches on all other Model
DB-50 circuit breakers at the Salem facility. They also recommended that the
licensee develop criteria for replacing the undervoltage trip attachment when
the difference in the force generated before and after lubrication exceeds a
predetermined value.
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: N. Fields, NRR
(301) 504-1173 S. Alexander, NRR
(301) 504-2995 Attachment: List of Recently Issued NRC Information Notices
Attachment
IN 93-09 February 2, 1993 Page I of i
Q0 e?
LIST OF RECENTLY ISSUED 4 NRC INFORNATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-08 Failure of Residual 02/01/93 All holders of OLs or CPs Sa.
Neat Removal Pump for nuclear power reactors. 0
Bearings due to High 0. N
Thrust Loading
93-07 Classification of Trans- 02/01/93 All Licensees required to
portation Emergencies have an emergency plan.
93-06 Potential Bypass Leak- 01/22/93 All holders of OLs or CPs
age Paths Around Filters for nuclear power reactors.
Installed in Ventilation
Systems
93-05 Locking of Radiography 01/14/93 All Nuclear Regulatory
Exposure Devices Commission industrial
radiography licensees.
93-04 Investigation and Re- 01/07/93 All U.S. Nuclear Regulatory '0'
porting of Misadministra- Commission medical
tions by the Radiation licensees.
Safety Officer
93-03 Recent Revision to 01/05/93 All byproduct, source, and
10 CFR Part 20 and special nuclear material
Change of Implementa- licensees.
tion Date to
January 1, 1994
93-02 Nalfunction of A Pres- 01/04/93 All holders of OLs or CPs
surizer Code Safety for nuclear power reactors.
Valve
93-01 Accuracy of Notor- 01/04/93 All holders of OLs or CPs
Operated Valve Diagnostic for nuclear power reactors.
Equipment Nanufactures
l by Liberty Technologies
92-86 Unexpected Restriction 12/24/92 All holders of OLs or CPs W Uj
to Thermal Growth of for nuclear power reactors.
Reactor Coolant Piping
2.
IL-
co
m_J
2 OL - Operating License 2ZL g
CP
0t
z
ot
I
IN 93-09 February 2, 1993 representatives stated that none of the defective parts have been used in
undervoltage trip attachments or DB-50 circuit breakers available on the open
market as commercial grade items. Westinghouse informed the NRC that it has
notified all customers of record who have purchased undervoltage trip
attachments or Model DB-50 circuit breakers with parts from the affected lot.
Westinghouse personnel recommended that the Salem licensee visually inspect, for proper finish, the undervoltage trip attachment latches on all other Model
DB-50 circuit breakers at the Salem facility. They also recommended that the
licensee develop criteria for replacing the undervoltage trip attachment when
the difference in the force generated before and after lubrication exceeds a
predetermined value.
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: N. Fields, NRR
(301) 504-1173 S. Alexander, NRR
(301) 504-2995 Attachment: List of Recently Issued N C Information Notices
OEAB:DORS ADM:RPB EELB:DE ASC/OEAB:DORS
NFields* JMain* SAlexander* EGoodwin *
01/25/93 09/06/92 10/22/92 01/13/93 F C/EELB:DE
CBerlinger*
01/15/93 C/OEAB:DORS
AChaffee*
01/19/93 C/OGCB:DORS
GMarcus*
01/25/93 e
1/2a/93 OFFICIAL RECORD COPY
DOCUMENT NAME: 93-09.IN
IN 93-XX
January xx, 1993 representatives stated that none of the defective parts have been used in
undervoltage trip attachments or DB-50 circuit breakers available on the open
market as commercial grade items. Westinghouse informed the NRC that it has
notified all customers of record who have purchased undervoltage trip
attachments or Model DB-50 circuit breakers with parts from the affected lot.
Westinghouse personnel recommended that the Salem licensee visually inspect, for proper finish, the undervoltage trip attachment latches on all other Model
DB-50 circuit breakers at the Salem facility. They also recommended that the
licensee develop criteria for replacing the undervoltage trip attachment when
the difference in the force generated before and after lubrication exceeds a
predetermined value.
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: N. Fields, NRR
(301) 504-1173 S. Alexander, NRR
(301) 504-2995 Attachment: List of Recently Issued NRC Information Notices
OEAB:DORS ADM:RPB EELB:DE ASC/OEAB:DORS
NFields JMain* SAlexander* EGoodwin l *
i /2593 09/06/92 10/22/92 01/13/93 C/EELB:DE C/OEAB:DORS C/OGCB:DORS
CBerlinger* AChaffee* GMarcus* IV~1imes
01/15/93 01/19/93 01/25/93 93/4/93
OFFICIAL RECORD COPY
DOCUMENT NAME: G:\INSALEM.ENF
- j
IN 93-XX
January xx, 1993 representatives stated that none of the defective parts have been used in
undervoltage trip attachments or DB-50 circuit breakers available on the open
market as commercial grade items. Westinghouse informed the NRC that it has
notified all customers of record who have purchased undervoltage trip
attachments or Model DB-50 circuit breakers with parts from the affected lot.
Westinghouse personnel recommended that the Salem licensee visually inspect, for proper finish, the undervoltage trip attachment latches on all other Model
DB-50 circuit breakers at the Salem facility. They also recommended that the
licensee develop criteria for replacing the undervoltage trip attachment when
the difference in the force generated before and after lubrication exceeds a
predetermined value.
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: N. Fields, NRR
(301) 504-1173 S. Alexander, NRR
(301) 504-2995 Attachment: List of Recently Issued NRC Information Notices
OEAB:DORS ADM:RPB EELB:DE ASC/OEAB:DORS
NFields x JMain* SAlexander* EGoodwin *
I /+ /93 09/06/92 10/22/92 01/13/93 OFFICIAL RECORD COPY
DOCUMENT NAME: G:\INSALEM.ENF
IN 93-XX
January xx, 1993 representatives stated that none of the defective parts have been used in
undervoltage trip attachments or DB-50 circuit breakers available on the open
market as commercial grade items. Westinghouse informed the NRC that it has
notified all customers of record who have purchased undervoltage trip
attachments or Model DB-50 circuit breakers with parts from the affected lot.
Westinghouse personnel recommended that the Salem licensee visually inspect, for proper finish, the undervoltage trip attachment latches on all other Model
DB-50 circuit breakers at the Salem facility. They also recommended that the
licensee develop criteria for replacing the undervoltage trip attachment when
the difference in the force generated before and after lubrication exceeds a
predetermined value.
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: N. Fields, NRR
(301) 504-1173 S. Alexander, NRR
(301) 504-2995 Attachment: List of Recently Issued NRC Information Notices
OEAB:DORS ADM:RPB EELB:DE ASC/OEAB:DORS
NFields* JMain* SAlexander* EGoodwin
09/11/92 09/06/92 10/22/92 11/3/93 '
C/EELB:DE C/OEAB:DORS C/OGCB:DORS D/DORS
CBerlinger AChaffee GMarcus BGrimes
/ /93 / /93 / /93 / /93
OFFICIAL RECORD COPY
DOCUMENT NAME: G:\INSALEM.ENF
|
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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)
... further results |
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