Remote Trip Function Failures in General Electric F-Frame Molded-Case Circuit BreakersML031200762 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
---|
Issue date: |
01/06/1992 |
---|
From: |
Rossi C Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-92-003, NUDOCS 9112300071 |
Download: ML031200762 (10) |
|
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 |
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. 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.-e 7* '-923/ _ // 7#cc.
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 (3)sustained
high operating
temperatures
in the MCCBs. The high internal temper-ature in the MCCB required to produce a condition
conducive
to the malfunction
can result from continuous
high current load (greater than 50 percent of the 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 high ambient temperature
in the enclosure.
A secondary
heat source could also produce the high temperatures
required for this malfunction.
GE NE stated in its interim notification
that UYR- and ST-equipped
MCCBs produced after April 1991 (date codes J116= and 1116=) incorporated
changes that would prevent this condition.
GE NE also stated that an MCCB may or may not exhibit this malfunction, depending
on the particular
circumstances
associated
with the assembly of the breaker and the accessory
remote trip devices, in conjunction
with the high temperature
service conditions
believed to be conducive
to failure. Nevertheless, GE NE maintained
that affected MCCBs will trip under overcurrent
conditions
and will trip remotely at the 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 the multiple electrical
protection
assemblies (EPAs) used in boiling water reactor (BWR) plants to monitor power quality to the reactor protection
system (RPS).The EPAs trip the F-frame breakers for the RPS power supplies by means of the remote trip devices if the EPAs detect overvoltage, undervoltage, 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
in GE NE records. The affected MCCBs fitted with factory-installed
remote trip accessories
may also be used in numerous other applications
in all types of nuclear plants in which remote tripping of an F-frame MCCB by means of the UVR or ST may be a safety-related
function.The presence of UVRs or STs in F-frame MCCBs should be apparent when the units are installed
in the plant. However, even if accessory
designation
markings are not evident, affected MCCBs can be recognized
by the two UVR or ST lead wires protruding
through small openings in the sides of the MCCB case.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 i S 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 92-01 91-87 91-86 91-85 91-84 91-83 Relap5/Mod3 Computer Code Error Associated
with the Conservation
of Energy Equation Cable Damage Caused by Inadequate
Cable Installa-tion Procedures
and Controls Hydrogen Embrittlement
of Raychem Cryofit Couplings New Reporting
Requirements
for Contamination
Events at Medical Facilities
(10 CFR 30.50)Potential
Failures of Thermostatic
Control Valves for Diesel Generator
Jacket Cooling Water Problems with Criticality
Alarm Components/Systems
Solenoid-Operated
Valve Failures Resulted in Turbine Overspeed High-Energy
Piping Failures Caused by Wall Thinning Problems with Diaphragms
in Safety-Related
Tanks 01/03/92 01/03/92 12/27/91 12/27/91 12/26/91 12/26/91 12/20/91 12/18/91 12/18/91 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 licensees
authorized
to use byproduct
materials for human use.All holders of OLs or CPs for nuclear power reactors.All Nuclear Regulatory
Commission (NRC) fuel cycle licensees, interim spent fuel storage licens-ees, and critical mass licensees.
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.91-18, Supp. 1 91-82 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
Conti Attachment
1: Attachment
2: Ict: S. D. Alexander, NRR (301) 504-2995 Affected MCCBs and Accessories
List of Recently Issued NRC Information
Notices DISTRIBUTION:
Central Flles SAlexander
CBerlinger
PDR CVanDenburgh
ERossi DRIS R/F LNorrholm VIB R/F BGrimes* 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
- L L 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 : : DATE --- ------ :-------1/----_
___________:______________
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 SAlexander
CVanDenburgh
CBerlinger
ERossi DRIS R/F LNorrholm VIB R/F BGrimes* 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 DOEA:GCB DOEA:DD NAME CBERLINGER
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 SAlexander
CBerlinger
PDR CVanDenburgh
ERossi DRIS R/F LNorrholm VIB R/F BGrimes OFFICE DRIS:VIB DRIS:VIB DRIS:VIB TECH ED DRIS:DD NAME ACVAN GH LNORRHOLM
JMAIN 9T% BGRIMES DATE 1 2/ 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
|
---|
|
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 |
---|