Misapplication and Inadequate Testing of Molded-Case Circuit BreakersML031200137 |
Person / Time |
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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: |
07/09/1992 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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-nr IN-92-051, NUDOCS 9207020233 |
Download: ML031200137 (9) |
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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>. |
JoS / KU UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 July 9, 1992 NRC INFORMATION
NOTICE 92-51: MISAPPLICATION
AND INADEQUATE
TESTING OF MOLDED-CASE
CIRCUIT BREAKERS
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.
Purpose
TheU.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert addressees
to problems that were recently observed concerning
the application
and testing of molded-case
circuit breakers (MCCBs). It is expected that recipients
will review the information
for applicability
to their facilities
and consider actions, as appropriate, to avoid similar problems.
However, suggestions
contained
in this information
notice are not NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances
During research and inspection
activities, the NRC staff has found that licensees, when determining
the MCCB parameters
for motor loads, occasionally
underestimate
or neglect to consider the inrush transient (starting)
current (ITC) occurring
during the first few cycles after a motor is started. Often only the locked rotor current (LRC) is considered
in selecting
the appropriate- MCCB.If no special starting methodology
is used to specifically
limit the ITC, the magnitude
of the ITC can be as much as approximately
three times the LRC.Also, depending
on the electrical
characteristics
of the power supply and the impedance
of the motor when started, the ITC can increase to as much as approximately
six times the value of the LRC. A current of this magnitude
is greater than the maximum instantaneous
trip setting for circuit protection
recommended
by the National Electric Code (NEC). Therefore, the NEC recommended
level of protection
may be insufficient
to prevent an unwanted trip. Proper application
of MCCBs depends strongly upon the use of accurate design assumptions.
Another application
problem involves the use of MCCBs equipped with both thermal overload trip elements and instantaneous
magnetic trip elements.
A newly purchased
replacement
Westinghouse
Type HFB3125 ambient compensating
MCCB tripped when a hydrogen skimmer fan motor at the Catawba Nuclear Station 7 9207020233
\J 1-IN 92-51 July 9, 1992 was started during testing after installation.
Duke Power Company personnel did not expect the MCCB to trip since the peak value of the ITC for the fan motor was thought to be well below the instantaneous
trip band of that MCCB (NRC Inspection
Report 99900404/90-01).
A similar Westinghouse
MCCB used as a turbine room sump pump breaker tripped in a similar manner at the Donald C. Cook Nuclear Power Plant. (NRC Inspection
Report 99900404/90-21).
Westinghouse
determined
that most of its thermal-magnetic
MCCBs with the nonadjustable
instantaneous
magnetic trip function could trip inadvertently.
Westinghouse
attributed
this behavior to interaction
between the thermal overload trip function and the instantaneous
magnetic trip function under overload conditions.
Under nonfault conditions, these functions
may interact when the circuit current causes the thermal trip element to deflect until it presses on the MCCB's tripper bar at the same time that the instantaneous
magnetic armature is vibrating
against the tripper bar. This interaction
causes the MCCB to trip.Westinghouse
notified nuclear licensees
of this problem and recommended
that they test these MCCBs in their intended circuits before releasing
them for plant operation.
Westinghouse
also stated this recommendation
on certificates
of conformance
provided with its dedicated
MCCBs sold as safety-related
items.Potential
interactions
between thermal overload and instantaneous
trip functions
can be avoided by using a special class of MCCBs that are designed specifically
for motor loads. These MCCBs include only instantaneous
magnetic trip functions
for protecting
against faults or short circuits.
The trip setpoints
are normally adjustable
and more accurate than those in thermal-magnetic MCCBs. These MCCBs, commonly referred to by the Westinghouse
term"motor circuit protectors," are intended for use in combination
with motor contactors
or starters.
Thermal overload relays contained
in the contactors
or starters provide the coordinated
protection
against overloads
and fault currents which are below the magnitude
necessary
to actuate an instantaneous
trip of the MCCB.Instances
of premature
tripping have occurred with MCCBs manufactured
by ITE-Siemens Company. The Carolina Power and Light Company, licensee for the Shearon Harris Nuclear Power Plant, found that some of the 480 volt MCCBs manufactured
by ITE-Siemens, and purchased
as commercial-grade, tripped prematurely
when tested (NRC Inspection
Report 99901177/90-01).
The licensee had purchased
these MCCBs as replacements
for some older 600 volt ITE-Siemens
MCCBs. The ITE-Siemens
Company tested the 480 volt MCCBs and found that these trips were initiated
by the MCCBs' instantaneous
magnetic trip function, when induction
motor loads were started. The manufacturer
tested the older 600 volt MCCBs and found no premature
trips. Rather, the older 600 volt MCCBs tripped at currents significantly
above the levels at which an instantaneous
trip should have occurred.
i X -X IN 92-51 July 9, 1992 The licensee's
testing of the 480 volt MCCBs was judicious.
ITE-Siemens
stated that the instantaneous
trip setpoints
of commercial
grade MCCBs-with
nonadjustable
magnetic trips are not normally-verified
at the factory.However, ITE-Siemens
and possibly other manufacturers
of MCCBs will, upon request, verify that the instantaneous
magnetic trip points of their commercial
grade MCCBs with nonadjustable
magnetic trips supplied to nuclear utilities
fall within the appropriate
design band. Nevertheless, field testing of other MCCBs may be needed to verify that their magnetic trip points occur within the-design
band (but not below the band) because other manufacturers
may not routinely
provide this verification
for commercial
grade MCCBs. For this type of MCCB, most manufacturers
check only that the MCCB will trip instantaneously, without determining
the current level at which the trip occurs.Discussion
An MCCB can render safety-related
equipment
inoperable
if it trips prematurely.
Premature
trips can result if the incorrect
MCCB is selected (and/or incorrectly
adjusted)
as a result of inadequate
analysis of the load circuit including
dynamic analysis of expected transients
when determining
ratings, settings and coordination
requirements.
Premature
trips can also-occur with properly applied and set MCCBs that are operating
out of tolerance when incorrect
bench testing methods and/or inadequate
post-installation
testing fail to detect the out of tolerance
performance.
Acceptable
testing methods and specifications
are provided in some MCCB manufacturers'
technical
publications.
Industry and professional
organizations
also provide guidance on MCCB testing methods, including
generic acceptance
criteria, in documents
such as the National Electrical
Manufacturers
Association (NEMA) Standard AB4-1991, "Guidelines
for the Inspection
and Preventive
Maintenance
of Molded Case Circuit Breakers Used in Commercial
and Industrial
Applications." It should be noted that the application
of generic field test tolerances
to the instantaneous
trip band on manufacturers'
time-current
characteristic
curves may not always ensure that the MCCBs meet plant-specific
breaker coordination, circuit protection
or technical
specification
requirements.
Testing of properly applied and set MCCBs in accordance
with industry recommended
practices
should provide reasonable
assurance
that the MCCBs'instantaneous
trip performance
is acceptable
for safety-related
applications.
IN 92-51 July 9, 1992 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.ssi,D ide or Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contacts:
Satish K. Aggarwal, RES (301) 492-3829 Stephen D. Alexander, NRR (301) 504-2995 Nick Fields, NRR (301) 504-1173 Attachment:
List of Recently Issued NRC Information
Notices
.-1<-'Attachment
IN 92-51 July 9, 1992 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 92-50 92-49 92-48 92-47 92-46 92-45 92-44 92-43 92-42 Cracking of Valves in the Condensate
Return Lines of A BWR Emer-gency Condenser
System Recent Loss or Severe Degradation
of Service Water Systems Failure of Exide Batteries
Intent
ional
Bypassing of Automatic
Actuation of Plant Protective
Features Thermo-Lag
Fire Barrier Material Special Review Team Final Report Findings, Current Fire Endurance Tests, and Ampacity Cal-culation Errors Incorrect
Relay Used in Emergency
Diesel Generator Output Breaker Control Circuitry Problems with Westing-house DS-206 and DSL-206 Type Circuit Breakers Defective
Molded Phen-olic Armature Carriers Found on Elmwood Con-tactors Fraudulent
Bolts in Seismically
Designed Walls 07/02/92 07/02/92 07/02/92 06/29/92 06/23/92 06/22/92 06/18/92 06/09/92 06/01/92 All holders for BWRs.of OLs or CPs All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.OL = Operating
License CP = Construction
Permit
IN 92-51 July 9, 1992 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.Original Signed by Charles E. Rossi Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contacts: Satish K. Aggarwal, RES (301) 492-3829 Stephen D. Alexander, NRR (301) 504-2995 Nick Fields, NRR (301) 504-1173 Attachment:
List of Recently Issued NRC Information
Notices Brian K. Grimes, Director, Division of Reactor Inspection
and Safeguards
and Ashok C. Thadani, Director, Division of Systems Technology
concurred
in a previous version of this information
notice. Notice was significantly
revised to remove "regulatory
guide" portions of original draft after above concurrences
were obtained.
I determined
it was unnecessary
to have re-concurrence
at the Division Director level. C. E. Rossi*SEE PREVIOUS CONCURRENCE
OEAB:DOEA:NRR
NFields*05/21/92 EMEB:DE:RES
SKAggarwal*
06/08/92 SELB:NRR ASGill*06/29/92 SC/OEAB:DOEA:NRR
DFischer*05/22/92 C/EMEB:DE:RES
MVagins*06/08/92 C/OGCB:DOEA:NRR
CHBerlinger*
06/10/92 RPB:ADM TechEd*05/22/92 D/DE:RES LCShao*06/08/92 7W ssi C/OEAB:DOEA:NRR
AChaffee*06/04/92 RVIB:NRR SAlexander*
06/30/92 Document Name: 92-51.IN
IN 92-XX June xx, 1992 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.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contacts: Satish K. Aggarwal, RES (301) 492-3829 Stephen D. Alexander, NRR (301) 504-2995 Nick Fields, NRR (301) 504-1173 Attachment:
List of Recently Issued NRC Information
Notices Brian K. Grimes, Director, Division of Reactor Inspection
and Safeguards
and Ashok C. Thadani, Director, Division of Systems Technology
concurred
in a previous version of this information
notice. Notice was significantly
revised to remove "regulatory
guide" portions of original draft after above %y concurrences
were obtained.
C. E. Ros i;2r B a*SE PREVIOUS CONCURe RN-*SEE PREVIOUS CONCURRENCE
OEAB:DOEA:NRR
NFields*05/21/92 EMEB:DE:RES
SKAggarwal*
06/08/92 SC/OEAB:DOEA:NRR
DFischer*05/22/92 C/EMEB:DE:RES
MVagins*06/08/92 RPB:ADM TechEd*05/22/92 D/DE:RES LCShao*06/08/92 C/OEAB:DOEA:NRR
AChaffee*06/04/92 RVIB:NRRA SAlexander
06 / 0/92 SELB:NRR ASGill*06/29/92 C/OGCB:DOEA:NRR
CHBerlinger*
06/10/92 D/DOEA:NRR
CERossi/ /92 Document Name: C:\CIRBRK (ATB)
I I IN 92-XX May xx, 1992 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.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contacts: Satish K. Aggarwal, RES (301) 492-3829 Stephen D. Alexander, NRR (301) 504-2995--Am itpa 1 -G-i-l1 NR (301t=043-i
Nick Fields, NRR (301) 504-1173 Attachment:
List of Recently Issued NRC Information
Notices Brian K. Grimes, Director, Division of Reactor Inspection
and Safeguards
and Ashok C. Thadani, Director, Division of Systems Technology
concurred
in a previousversion
of this informa ion no t iV >4 A/ ' N. r.t*Sv i!EE P RE VIOU SC NC OCUR'RE NC W -.)4 OEAB:DOEA:NRR
NFields*05/21/92 EMEB:DE:RES
SKAggarwal
&/ g /92 C/OGBJ NRR CHBe inger G/ Io192 SC/OEAB:DOEA:NRR
DFischer*05/22)si C/4A:RES MVagins C, /of/i92 D/DOEA:NRR
CERossi/ /92 RVIB :NRR SAlexander
06/ /92 C,- A B r-t" -RPB:ADM C/OEAB:DOEA:NRR
Tech Ed* Jt);,,4*Chaffee
05/2219 /9 / C/q/92 SELB: NR- ,, ASGill 06l97/92 Document Name: C:\CIRBRK (ATB)
I r -.'K-'IN 92-XX May xx, 1992 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.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contacts: Satish K. Aggarwal, RES (301) 492-3829 Stephen D. Alexander, NRR (301) 504-2995 N raS.m l G1J4INRK Nick Fields, NRR (301) 504-1173 Attachment:
List of Recently Issued NRC Information
Notices Document Name: OEAB:DOEA:.
RR NFieldsfJ Y5/h4/92 EMEB:DE:RES
SKAggarwal
/ /92 D/DST:NRR ACThadani/ /92 C:\CIRBRK (ATB)SCREAB:DOEA:NRR
DFischer 5 /7-i/92 C/EMEB:DE:RES
MVagins/ /92 C/OGCB:DOEA:NRR
CHBerlinger
/ /92 RPB:ADM TechEd/ /92 D/DE:RES LCShao/ /92 GV fo JC C/OEAB:DOEA:NRR
AChaffee G/ 5/92 D/DRIS:NRR
BKGrimes/ /92 D/DOEA:NRR
CERossi/ /92
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list | - Information Notice 1992-01, Cable Damage Caused by Inadequate Cable Installation Procedures and Controls (3 January 1992, Topic: Overspeed trip)
- Information Notice 1992-02, Relap5/MOD3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992, Topic: Overspeed trip)
- Information Notice 1992-02, Relap5/Mod3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992)
- Information Notice 1992-03, Remote Trip Function Failures in General Electric F-Frame Molded-Case Circuit Breakers (6 January 1992, Topic: Overspeed trip)
- Information Notice 1992-04, Potter and Brumfield Model Mdr Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment, Commercial Grade, Overspeed trip)
- Information Notice 1992-04, Potter and Brumfield Model MDR Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment, Commercial Grade)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs RXMH2 Relays (8 January 1992, Topic: Commercial Grade, Overspeed trip)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs Rxmh2 Relays (8 January 1992, Topic: Commercial Grade)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in ABS RXMH2 Relays (8 January 1992, Topic: Commercial Grade)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment Not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-07, Rapid Flow-induced Erosion/Corrosion of Feedwater Piping (9 January 1992)
- Information Notice 1992-08, Revised Protective Action Guidance for Nuclear Incidents (23 January 1992)
- Information Notice 1992-09, Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions (30 January 1992)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire Used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-11, Soil and Water Contamination at Fuel Cycle Facilities (5 February 1992, Topic: Brachytherapy)
- Information Notice 1992-12, Effects of Cable Leakage Currents on Instrument Settings and Indications (10 February 1992, Topic: Brachytherapy)
- Information Notice 1992-13, Inadequate Control Over Vehicular Traffic at Nuclear Power Plant Sites (18 February 1992, Topic: Brachytherapy)
- Information Notice 1992-14, Uranium Oxide Fires at Fuel Cycle Facilities (21 February 1992, Topic: Brachytherapy)
- Information Notice 1992-15, Failure of Primary Systems Compression Fitting (24 February 1992, Topic: Unidentified leakage)
- Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown (25 February 1992, Topic: Reactor Vessel Water Level, Temporary Modification, Brachytherapy)
- Information Notice 1992-17, NRC Inspections of Programs Being Developed at Nuclear Power Plants in Response to Generic Letter 89-10 (26 February 1992, Topic: Stroke time)
- Information Notice 1992-18, Potential for Loss of Remote Shutdown Capability During a Control Room Fire (28 February 1992, Topic: Hot Short, Safe Shutdown)
- Information Notice 1992-19, Misapplication of Potter and Brumfield Mdr Rotary Relays (2 March 1992)
- Information Notice 1992-19, Misapplication of Potter and Brumfield MDR Rotary Relays (2 March 1992)
- Information Notice 1992-20, Inadequate Local Leak Rate Testing (3 March 1992, Topic: Local Leak Rate Testing)
- Information Notice 1992-21, Spent Fuel Pool Reactivity Calculations (24 March 1992)
- Information Notice 1992-23, Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment (27 March 1992)
- Information Notice 1992-24, Distributor Modification to Certain Commercial-Grade Agastat Electrical Relays (30 March 1992)
- Information Notice 1992-25, Pressure Locking of Motor-Operated Flexible Wedge Gate Valves (2 April 1992, Topic: Stroke time, Hydrostatic)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of ITE/Gould A.C. Relays used in Safety-Related Applications (3 April 1992)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of Ite/Gould A.C. Relays Used in Safety-Related Applications (3 April 1992, Topic: Commercial Grade)
- Information Notice 1992-28, Inadequate Fire Suppression System Testing (8 April 1992, Topic: Safe Shutdown)
- Information Notice 1992-29, Potential Breaker Miscoordination Caused by Instantaneous Trip Circuitry (17 April 1992)
- Information Notice 1992-30, Falsification of Plant Records (23 April 1992)
- Information Notice 1992-31, Electrical Connection Problem in Johnson Yokogawa Corporation YS-80 Programmable Indicating Controllers (27 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (Within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices Are Installed (30 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices are Installed (30 April 1992)
- Information Notice 1992-34, New Exposure Limits for Airborne Uranium and Thorium (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping Inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-36, Intersystem LOCA Outside Containment (7 May 1992)
- Information Notice 1992-37, Implementation of the Deliberate Misconduct Rule (8 May 1992)
- Information Notice 1992-38, Implementation Date for the Revision to the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (26 May 1992, Topic: Brachytherapy)
- Information Notice 1992-39, Unplanned Return to Criticality During Reactor Shutdown (13 May 1992, Topic: Fuel cladding)
- Information Notice 1992-40, Inadequate Testing of Emergency Bus Undervoltage Logic Circuitry (27 May 1992)
- Information Notice 1992-41, Consideration of Stem Rejection Load In Calculation of Required Valve Thrust (29 May 1992, Topic: Anchor Darling)
... further results |
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