Remote Trip Function Failures in General Electric F-Frame Molded-Case Circuit BreakersML031200762 |
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 |
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Issue date: |
01/06/1992 |
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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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IN-92-003, NUDOCS 9112300071 |
Download: ML031200762 (10) |
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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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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 January 6, 1992 NRC INFORMATION NOTICE 92-03: REMOTE TRIP FUNCTION FAILURES IN GENERAL
ELECTRIC F-FRAME MOLDED-CASE CIRCUIT
BREAKERS
Addressees
All holders of operating licenses or construction permits for nuclear
power reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice
to alert addressees to a potentially safety-significant problem resulting from
the possible failure of the remote trip functions of General Electric (GE)
F-frame (225-ampere frame size) 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 require- ments; therefore, no specific action or written response is required.
Description of Circumstances
On November 5, 1991, GE Nuclear Energy (GE NE), San Jose, California, issued an
interim notification of its evaluation of a deviation in accordance with the
latest revision (effective October 29, 1991) of Part 21, "Reporting of Defects
and Noncompliance," of Title 10 of the Code of Federal Regulations
(10 CFR Part 21). The notification described the deviation as a "tolerance
buildup" in certain GE F-frame MCCBs with undervoltage releases (UVRs) and
shunt trip devices (STs) that may inhibit these internal accessory remote trip
devices from functioning properly under conditions that produce sustained high
internal temperatures in the MCCBs.
The attachment to the GE NE notification was taken from a draft Service Advice
Letter (SAL) on this subject being prepared by the MCCB manufacturer, GE
Electrical Distribution and Control (ED&C), in Plainville, Connecticut.
GE NE plans to send the 10 CFR Part 21 interim notification to all of its
customers who have purchased F-frame MCCBs for safety-related applications
and to all GE NE Material Services field representatives. GE ED&C plans to
send the SAL (issued November 25, 1991 as SAL 91-2F) to all of its customers of
record, many of whom are distributors. However, both the F-frame MCCBs and
their accessory trip devices are available on the open market as commercial
grade items through various distribution paths. Therefore, the licensees for
some nuclear plants who use these MCCBs may not receive the GE notifications.
cc.
-e 7* '-923/
7# _ //
IN 92-03 January 6, 1992 Discussion
Although still evaluating the problem, the MCCB manufacturer has determined
that assembly and operational variations caused the reported failures.
The
variations reportedly resulted from (1) tolerances in mounting the accessory
trip devices in the MCCBs, (2) tolerances on the adjustment of the ambient
compensating bimetal (part of the thermal overload trip mechanism), and
sustained high operating temperatures in the MCCBs. The high internal (3)
ature in the MCCB required to produce a condition conducive to the temper- malfunction
can result from continuous high current load (greater than 50 percent
overcurrent trip unit rating for more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) together with a of the
ambient temperature in the enclosure. A secondary heat source could high
produce the high temperatures required for this malfunction. also
GE NE stated in its interim notification that UYR- and ST-equipped
produced after April 1991 (date codes J116= and 1116=) incorporatedMCCBs
changes
that would prevent this condition. GE NE also stated that an MCCB may
not exhibit this malfunction, depending on the particular circumstances or may
associated with the assembly of the breaker and the accessory remote
devices, in conjunction with the high temperature service conditions trip
be conducive to failure. Nevertheless, GE NE maintained that affectedbelieved to
will trip under overcurrent conditions and will trip remotely at the MCCBs
lower MCCB
internal temperatures usually present with lower load currents and enclosure
ambient temperatures or without secondary heat sources.
GE NE initially reported that it had identified a.specific safety-related
application for the affected F-frame MCCBs equipped with internal accessory
remote trip devices. The identified application is associated with
multiple electrical protection assemblies (EPAs) used in boiling water the
(BWR) plants to monitor power quality to the reactor protection system reactor
The EPAs trip the F-frame breakers for the RPS power supplies by means (RPS).
remote trip devices if the EPAs detect overvoltage, undervoltage, of the
or underfre- quency conditions in RPS power. In addition, GE NE informed the NRC
in a
subsequent communication that it may also have supplied some of the affected
MCCBs as part of subassembly-level applications not separately identified
GE NE records. The affected MCCBs fitted with factory-installed remote in
accessories may also be used in numerous other applications in all types trip
nuclear plants in which remote tripping of an F-frame MCCB by means of
or ST may be a safety-related function. of the UVR
The presence of UVRs or STs in F-frame MCCBs should be apparent when
are installed in the plant. However, even if accessory designation the units
are not evident, affected MCCBs can be recognized by the two UVR or markings
ST
wires protruding through small openings in the sides of the MCCB case. lead
Additionally, UVRs set up for monitoring 240, 480, or 600 volts-AC
or 250
volts-DC should have an external dropping resistor connected in series
with one
of their lead wires. Attachment 1 lists the breaker frame type designations
of
IN 92-03 January 6, 1992 the potentially affected MCCBs and the catalog numbers of the affected
internal accessory remote trip devices and also gives the date codes of the
units believed by the manufacturer to be affected.
In view of the potentially wide scope of application of the affected
MCCBs, addressees may find the affected types of UVR- and ST-equipped MCCBs
both installed and in the warehouse.
Addressees
who find any affected MCCBs
may consult the manufacturer on this subject to determine the appropriate
corrective action, including testing for the existence of the malfunction, analyzing the potential high temperature producing conditions, or replacing
the affected components.
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.
I.1os Si Doirector
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: S. D. Alexander, NRR
(301) 504-2995 Attachments:
1. Affected MCCBs and Accessories
2. List of Recently Issued NRC Information Notices
Attachment 1 IN 92-03 January 6, 1992 AFFECTED MCCBs and ACCESSORIES
The affected GE F-frame ("F-225 Line") MCCBs include the breaker types or
frames listed below which can be fitted with any of the accessory remote trip
devices with the listed catalog numbers:
BREAKER FRAMES SHUNT TRIPS UNDERVOLTAGE RELEASES
TFK, THFK TFKSTA12 TFKUVA1 TFJ TFKSTA13 TFKUVA2 THLC2 TFKSTA7 TFKUVA4 THLB2 TFKSTA8 TFKUVA6 THLC4 TFKSTA9 TFKUVA7 TLB4 TFKSTA11 TFKUYA8 TFKUVA9 TFKUVA10
TFKUVA11 According to GE NE and GE ED&C, the tolerance buildup affects F-frame MCCBs and
UYRs and STs assembled between August 1979 and April 1991 (accessory date codes
N927* through N116=). The potentially affected MCCBs could have manufacturing
date codes J927* through J116= (1116= for current limiting frames), but ED&C
reported no identifiable volume of field returns for this condition among MCCBs
built before the fourth quarter of 1987 (breaker date codes J736+ and I736+).
The accessory date code is its manufacturing date code and only appears on the
accessory itself. However, the date code from the accessory installation
facility may appear on the MCCB case in addition to the manufacturing date code
of the MCCB.
Attachment 2 IN 92-03 January 6, 1992 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
92-02 Relap5/Mod3 Computer Code 01/03/92 All holders of OLs or CPs
Error Associated with the for nuclear power reactors.
Conservation of Energy
Equation
92-01 Cable Damage Caused by 01/03/92 All holders of OLs or CPs
Inadequate Cable Installa- for nuclear power reactors.
tion Procedures and Controls
91-87 Hydrogen Embrittlement of 12/27/91 All holders of OLs or CPs
Raychem Cryofit Couplings for nuclear power reactors.
91-86 New Reporting Requirements 12/27/91 All licensees authorized
for Contamination Events at to use byproduct materials
Medical Facilities for human use.
(10 CFR 30.50)
91-85 Potential Failures of 12/26/91 All holders of OLs or CPs
Thermostatic Control Valves for nuclear power reactors.
for Diesel Generator Jacket
Cooling Water
91-84 Problems with Criticality 12/26/91 All Nuclear Regulatory
Alarm Components/Systems Commission (NRC) fuel
cycle licensees, interim
spent fuel storage licens- ees, and critical mass
licensees.
91-83 Solenoid-Operated Valve 12/20/91 All holders of OLs or CPs
Failures Resulted in for nuclear power reactors.
Turbine Overspeed
91-18, High-Energy Piping Failures 12/18/91 All holders of OLs or CPs
Supp. 1 Caused by Wall Thinning for nuclear power reactors.
91-82 Problems with Diaphragms 12/18/91 All holders of OLs or CPs
in Safety-Related Tanks for nuclear power reactors.
OL = Operating License
CP = Construction Permit
IN 91-XX
December XX, 1991 the potentially affected MCCBs and the catalog numbers of the affected internal
accessory remote trip devices and also gives the date codes of the units
believed by the manufacturer to be affected.
In view of the potentially wider scope of the application of the affected
MCCBs, addressees may find the affected types of UVR- and ST-equipped MCCBs
both installed and in the warehouse.
Addressees
who find any affected MCCBs
may consult the manufacturer on this subject to determine the appropriate
corrective action, including testing to confirm the existence of the malfunc- tion, analyzing the potential high temperature producing conditions, or
replacing the affected components.
No specific action or written response is required by this notice. If you
have any questions regarding this notice, please call the technical contact
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 ContiIct: S. D. Alexander, NRR
(301) 504-2995 Attachment 1: Affected MCCBs and Accessories
Attachment 2: List of Recently Issued NRC Information Notices
DISTRIBUTION:
Central Flles PDR DRIS R/F VIB R/F
SAlexander CVanDenburgh LNorrholm BGrimes
CBerlinger ERossi
- see previous concurrences
OFC :VIB/DRIS :VIB/DRIS :VIB/DRIS :TECH ED :D:DRIS
NAME :SAlexander:sda :CVanDenburgh :LNorrholm :JMain :BKGrimes
DATE :12/19/91* :12/4/91* :12/19/91* :12/4/91* :12/19/91*
OFC :B'9C:
~8L9A :DD:DOEA:
NAM CBe :CERossi:
DATE :12/tO/91 :12/ /91 : :
OFFICIAL RECORD COPY Document Name: GE FFRAME MCCB INFO NOTICE
IN 92-03 January 6, 1992 the potentially affected MCCBs and the catalog numbers of the affected
internal accessory remote trip devices and also gives the date codes of the
units believed by the manufacturer to be affected.
In view of the potentially wide scope of application of the affected
MCCBs, addressees may find the affected types of UVR- and ST-equipped MCCBs
both installed and in the warehouse.
Addressees
who find any affected MCCBs
may consult the manufacturer on this subject to determine the appropriate
corrective action, including testing for the existence of the malfunction, analyzing the potential high temperature producing conditions, or replacing
the affected components.
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.
original Signed by
Charles E. Rossi
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: S. D. Alexander, NRR
(301) 504-2995 Attachments:
1. Affected MCCBs and Accessories
2. List of Recently Issued NRC Information Notices
- see previous concurrences
OFC :VIB/DRIS :YIB/DRIS :VIB/DRIS :TECH ED :D:DRIS
NAME :SAlexander:sda :CVanDenburgh :LNorrholm :JMain :BKGrimes
DATE :12/19/91* :12/4/91* :12/19/91* :12/4/91* :12/19/91*
OFC :BC:GCB:DOEA :DD:D0EA
NAME :CBerlinger : oRJ O : : :
DATE :12/20/91* :12/tW91 : : :
OFFICIAL RECORD COPY Document Name: IN 92-03
IN 91-XX
December XX, 1991 Pace 3 of 3 the potentially affected MCCBs and the catalog numbers of the affected internal
accessory remote trip devices and also gives the date codes of the units
believed by the manufacturer to be affected.
In view of the potentially wider scope of the application of the affected
MCCBs, addressees may find the affected types of UVR- and ST-equipped MCCBs
both installed and in the warehouse.
Addressees
who find any affected MCCBs
may consult the manufacturer on this subject to determine the appropriate
corrective action, including testing to confirm the existence of the malfunc- tion, analyzing the potential high temperature producing conditions, or
replacing the affected components.
No specific action or written response is required by this notice. If you
have any questions regarding this notice, please call the technical contact
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 Contact:
S. D. Alexander, NRR
(301) vq-0995 Attachment 1: Affected MCCBs and Accessories
Attachment 2: List of Recently Issued NRC Information Notices
DISTRIBUTION:
Central Files PDR DRIS R/F VIB R/F
SAlexander CVanDenburgh LNorrholm BGrimes
CBerlinger ERossi
- see previous concurrences
OFC :VIB/DRIS VIB/DRIS :VIB IS :TECH ED
___-_--_---_-_- l----- ---------.--- f-- ------- -------------- -- iv-------- --------------
NAME :5Alexander:sda: CVanDenburgh :LL Wm :JMain s
DATE :1 2 4J9 1 :12/4/91* :12A9/91 :12/4/91* :12/11 /91 CA"
OFC :BC:.BDOEA :DD:DOEA : ' :
NAME C erlinger :CERossi : :
-------------
--- ------ :-------1/----_ ___________:______________
DATE
DATE :12/,vO/91 :121 /9-1 ::
OFFICIAL RECORD COPY Document Name: DRAFT GE INFO MCCB NOTICE
IN 91-XX
December XX, 1991 No specific action or written response is required by this
notice. If you have any questions regarding this notice, please
call the technical contact 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 Contact:
S. D. Alexander, NRR
(301) 492-0995 Attachment 1: Affected MCCBs and Accessories
Attachment 2: List of Recently Issued NRC Information Notices
DISTRIBUTION:
Central Files PDR DRIS R/F VIB R/F
SAlexander CVanDenburgh LNorrholm BGrimes
CBerlinger ERossi
- see previous concurrences
OFFICE DRIS:VIB DRIS:VIB DRIST B TECH ED 0
NAME SALEXANDER CVANDENBURGH JIAIN
DATE *12/ 4/91 *12/ 4/91 12/../91 *12/ 4/91 12/;, /91
[OFFICE
NAME
DOEA:GCB
CBERLINGER
DOEA:DD
EROSSI
DATE 12/ /91 12/ /91 OFFICIAL RECORD COPY Document Name: GER2.IN
IN 91-XX
December XX, 1991 No specific action or written response is required by this
notice. If you have any questions regarding this notice, please
call the technical contact listed below, or the appropriate
Office of Nuclear Reactor Regulation project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
S. D. Alexander, NRR
(301) 492-0995 Attachment 1: Frame Types and Date Codes of Affected MCCBs and
Catalog Numbers and Date Codes of Affected Acces- sories
Attachment 2: List of Recently Issued NRC Information Notices
DISTRIBUTION:
Central Files PDR DRIS R/F VIB R/F
SAlexander CVanDenburgh LNorrholm BGrimes
CBerlinger ERossi
OFFICE DRIS:VIB DRIS:VIB DRIS:VIB TECH ED DRIS:DD
NAME ACVAN GH LNORRHOLM JMAIN 9T% BGRIMES
DATE 12 / LJ/91 12/1 /91 12/ /91 12/ Y/91 12/ /91 OFFICE DOEA:GCB DOEA:DD
NAME CBERLINGER EROSSI
DATE 12/ /91 12/ /91
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list | - Information Notice 1992-01, Cable Damage Caused by Inadequate Cable Installation Procedures and Controls (3 January 1992)
- Information Notice 1992-02, Relap5/MOD3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992)
- 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)
- Information Notice 1992-04, Potter and Brumfield Model Mdr Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment)
- Information Notice 1992-04, Potter and Brumfield Model MDR Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs RXMH2 Relays (8 January 1992)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs Rxmh2 Relays (8 January 1992)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in ABS RXMH2 Relays (8 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 1992-06, 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)
- 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)
- 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)
- 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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