Potential Breaker Miscoordination Caused by Instantaneous Trip CircuitryML031200401 |
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: |
04/17/1992 |
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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-92-029, NUDOCS 9204100124 |
Download: ML031200401 (3) |
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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 April 17, 1992 NRC INFORMATION NOTICE 92-29: POTENTIAL BREAKER MISCOORDINATION CAUSED BY
INSTANTANEOUS TRIP CIRCUITRY
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 potential breaker miscoordination involving instantane- ous trip circuitry installed by the manufacturer in certain solid state trip
units. It is expected that recipients will review the information for applica- bility to their facilities and consider actions, as appropriate, to avoid
similar problems. However, suggestions contained in this information notice
are not NRC requirements; therefore, no specific action or written response is
required.
Description of Circumstances
On November 6, 1991, personnel at the Sequoyah Nuclear Plant (Sequoyah) cali- brated a solid state trip unit in a 480 Volt power circuit breaker. The
licensee had recently revised the procedure used for the calibration and had
increased the test current required for measuring the response time of the
short time delay trip element from 10 to 13.5 times the rating of the current
sensor. When plant personnel applied the test current, the current caused the
breaker to trip instantly rather than after the expected short time delay. The
instantaneous trip indicated that breaker miscoordination existed between the
480 Volt power circuit breaker and any downstream load breaker.
Discussion
The trip unit was an "Amptector Solid State Trip Device" (Amptector) which was
installed in a type DS power circuit breaker. Both the circuit breaker and the
trip unit were manufactured by the Westinghouse Electric Corporation (Westing- house). The licensee knew that the trip unit was equipped with a long and a
short time delay element. However, the licensee did not know that the Amptector
trip unit included a circuit which provided an instantaneous trip feature.
After the unexpected instantaneous trip, the licensee reviewed the vendor's
manual, "Westinghouse Instructions for Low-Voltage Power Circuit Breakers Types
DS and DSL." In Section 8.3 of the manual the licensee found that Westinghouse
had included a "making current release" feature in certain models of Amptector
trip units not equipped with an instantaneous trip element. The manual
9204100124 D X B 9oq7 L~r V( M Y,. Y.
IN 92-Z-9 April 17, 1992 referred to this feature as a "Discriminator." The Discriminator is a circuit
in the trip unit which determines at the time of a fault whether or not there
was any current flow in the primary circuit previous to the fault. The trip
unit would trip instantaneously if (1) there was "no measurable current" flow
previous to the fault, indicating that the circuit is just being closed or that
another switching device upstream of the breaker has been closed, and (2) the
current in the primary circuit exceeded approximately 12 times the sensor's
rating. Otherwise, the short time delay element would function to delay the
breaker tripping. Westinghouse stated that, in the event of a fault, this
feature allowed the breaker to provide selectivity and continuity in unfaulted
sections of a system so that service to those sections could be maintained but
if there was no previously operating load in the faulted circuit the trip unit
would function instantaneously to limit damage.
Based on the information found in Section 8.3, the licensee determined that the
instantaneous trip that occurred during calibration of the above circuit
breaker resulted from the Discriminator circuit sensing that there was no
measurable current flow previous to the test and that the test current was
greater than 12 times the sensor's rating. Previous calibrations of similar
circuit breakers had not resulted in instantaneous trips because the test
current was less than 12 times the sensor's rating. The licensee noted that, for the Discriminator feature, "no measurable current" is current flow that is
less than approximately 10 percent of the sensor's rating.
The licensee determined that the Discriminator feature could cause breaker
miscoordination in other electrical systems. This problem could occur in those
systems in which a motor control center (MCC) serves both safety-related and
nonsafety-related loads and current flow in the nonsafety-related portion of
the circuit could be less than 10 percent of the sensor's rating. In these
circuits, a fault on a nonsafety-related portion of the circuit could cause the
safety-related MCC to become deenergized and result in the loss of the
safety-related loads.
After consulting with Westinghouse, the licensee issued a design change to
disable the Discriminator feature on 41 circuit breakers. Westinghouse stated
that its DS type circuit breakers receive interrupting tests with the short and
long time delay elements only (i.e. no instantaneous element) and disabling the
Discriminator feature would not affect the interrupting ratings of the
breakers. However, Westinghouse also indicated that disabling the Discrimina- tor feature could increase the potential for equipment damage and personnel
injury in downstream portions of the circuit.
Westinghouse informed the licensee that the Discriminator circuit had been a
part of the Amptector trip unit since its first installation in DS type circuit
breakers. However, Westinghouse did not address the Discriminator feature in
the vendor's manual from the time of the manual's original issue in
January 1971 until Revision C was issued in August 1976.
Licensees may have designed circuits without considering the effect of the
Discriminator feature on breaker coordination because-this feature was not
IN 92-29
- April17, 1992 Page 3 of3 addressed in early revisions of the vendor's manual and because testing of the
time delay elements with current less than approximately 12 times the sensor's
rating may not reveal the presence of the Discriminator circuit.
The staff previously discussed the importance of proper breaker coordination in
NRC Information Notice 88-45, "Problems In Protective Relay and Circuit Breaker
Coordination," July 7, 1988.
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: Paul J. Fillion, RII
(404) 331-7288 Joseph Birmingham, NRR
(301) 504-2829 v s---
S-u4 Attachment: List of Recently Issued NRC Information Notices
Attachment
IN 92-29 LIST OF RECENTLY ISSUED April 17, 1992 NRC INFORMATIONNOTICES PageI of I
Information Date of
Notice No. Subject Issuance Issued to
92-28 Inadequate Fire Suppres- 04/08/92 All holders of OLs or CPs
slon System Testing for nuclear power reactors.
92-27 Thermally Induced Acceler- 04/03/92 All holders of OLs or CPs
ated Aging and Failure of for nuclear power reactors.
ITE/GOULDA.C. Relays Used
in Safety-Related Applic-
92-26 Pressure Locking of Motor- 04/02/92 All holders of OLs or CPs
Operated Flexible Wedge for nuclear power reactors.
Gate Valves
92-25 Potential Weaknessin 03/31/92 All holders of OLs or CPs
Licensee Procedures for A for nuclear power reactors.
Loss of the Refueling
CavityWater
92-24 Distributor Modification to 03/30/92 All holders of OLs or CPs
Certain Comnercial-Grade for nuclear power reactors.
Agastat Electrical Relays
92-23 Results of Validation Test- 03/27/92 All holders of OLs or CPs
ing of Motor-Operated Valve for nuclear power reactors
DiagnosticEquipment and all vendors of notor- operated valve (NOV) diag- nostic equipment.
92-22 CriminalProsecution and 03/24/92 All holders of OLs or CPs
Conviction of Wrongdoing for nuclear power reactors.
Committed by A Commercial- GradeValve Supplier
92-21 Spent Fuel Pool Reactivity 03/24/92 All holders of OLs or CPs
Calculations for nuclear power reactors.
92-20 Inadequate Local Leak Rate 03/03/92 All holders of OLs or CPs
Testing for nuclear power reactors.
OL
CP - Construction Permit
|
---|
|
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- 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, Topic: Commercial Grade)
- 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)
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