Incorrect Relay Used in Emergency Diesel Generator Output Breaker Control CircuitryML031200213 |
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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
06/22/1992 |
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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-92-045, NUDOCS 9206160071 |
Download: ML031200213 (9) |
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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>. |
K)
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 June 22, 1992 NRC INFORMATION NOTICE 92-45: INCORRECT RELAY USED IN EMERGENCY DIESEL
GENERATOR OUTPUT BREAKER CONTROL 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 a potential problem that may exist at their
facilities resulting from the failure of a relay in the control circuitry for
an emergency diesel generator (EDG) output breaker to perform its intended
design function. It is expected that recipients will review the information
for applicability to their facilities and consider actions, as appropriate, to
avoid similar problems. However, suggestions contained in this information
notice are not NRC requirements; therefore, no specific action or written
response is required.
Description of Circumstances
On April 3, 1992, during the weekly idle start test of an EDG at the St. Lucie
Plant, Unit 1, of the Florida Power and Light Company (the licensee), the
control room operator was unable to close the output circuit breaker after the
EDG had started, warmed up, and achieved rated speed. The licensee analyzed
the control circuitry and found that a relay was not functioning properly for
an unknown reason. The licensee sent the relay to Westinghouse for failure
analysis. This relay is intended to prevent the output circuit breaker from
closing when the generator is operating at a frequency below 54 Hz. However, the licensee found independent of the specific cause of the failure which
occurred on April 3, 1992, that the relay had not been properly selected and
was not able to perform its intended function. When operating as actually
designed, the relay would permit the circuit breaker to close at all frequen- cies up to 62.5Hz. The licensee had not noticed this discrepancy during
previous testing because the EDG usually achieves 90 percent of full voltage
(the circuitry also includes an under-voltage permissive relay function) at
almost the same time as it achieves 90 percent of full frequency. The
licensee determined that the relay had been incorrectly selected because of an
ambiguity in the Westinghouse catalog description for this particular relay
(Style 177C717G03, 60 Hz/120 V). Westinghouse has since corrected the catalog
description. The licensee corrected the error in relay selection by replacing
the relay with another relay that properly performs the under-frequency
permissive function.
-
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IN 92-45 June 22, 1992 Discussion
The EDG control circuitry is designed to prevent the output circuit breaker
from closing prematurely. This circuitry includes under-frequency and under- voltage permissive relays to ensure that the EDG attains both 90 percent of
rated frequency and 90 percent of rated voltage before the output circuit
breaker closes. Under emergency conditions (e.g., accident conditions with
loss of offsite power), use of the incorrect relay could allow the output
circuit breaker to close before the EDG reaches the necessary operating
conditions possibly resulting in shutdown of the diesel engine and/or damage
to the safety-related loads.
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, Dire r
___Di-vision-of OperationalEvents Assessment
Office of Nuclear Reactor Regulation
Technical contacts: Walter P. Haass, NRR
(301) 504-3219 E. Nick Fields, NRR
(301) 504-1173 Attachment: List of Recently Issued NRC Information Notices
K>J
Attachment
IN 92-45 June 22, 1992 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
92-44 Problems with Westing- 06/18/92 All holders of OLs or CPs
house DS-206 and DSL-206 for nuclear power reactors.
Type Circuit Breakers
92-43 Defective Molded Phen- 06/09/92 Al 1 holders of OLs or CPs
olic Armature Carriers for nuclear power reactors.
Found on Elmwood Con- tactors
92-42 Fraudulent Bolts in 06/01/92 All holders of OLs or CPs
Seismically Designed for nuclear power reactors.
Walls
92-41 Consideration of the 05/29/92 All holders of OLs or CPs
Stem Rejection Load in for nuclear power reactors.
Calculation of Required
Valve Thrust
92-40 Inadequate Testing of 05/27/92 All holders of OLs or CPs
Emergency Bus Under- for nuclear power reactors.
voltage Logic Circuitry
92-39 Unplanned Return to 05/13/92 All holders of OLs or CPs
Criticality during for nuclear power reactors.
Reactor Shutdown
92-38 Implementation Date for 05/12/92 All holders of OLs or CPs
the Revision to the EPA for nuclear power reactors, Manual of Protective non-power reactors and
Action Guides and Pro- materials licensees auth- tective Actions for orized to possess large
Nuclear Incidents quantities of radioactive
material.
92-37 Implementation of the 05/08/92 All Nuclear Regulatory
Deliberate Misconduct Rule Commission Materials
Licensees.
OL = Operating License
CP = Construction Permit
IN 92-45 June 22, 1992 Discussion
The EDG control circuitry is designed to prevent the output circuit breaker
from closing prematurely. This circuitry includes under-frequency and under- voltage permissive relays to ensure that the EDG attains both 90 percent of
rated frequency and 90 percent of rated voltage before the output circuit
breaker closes. Under emergency conditions (e.g., accident conditions with
loss of offsite power), use of the incorrect relay could allow the output
circuit breaker to close before the EDG reaches the necessary operating
conditions possibly resulting in shutdown of the diesel engine and/or damage
to the safety-related loads.
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: Walter P. Haass, NRR
(301) 504-3219 E. Nick Fields, NRR
(301) 504-1173 Attachment: List of Recently Issued NRC Information Notices
VIB/DRIS OEAB/NRR RIII VIB/DRIS VIB/DRIS VIB/DRIS
WPHaass* ENFields* KLandis** GCwalina* LNorrholm* BKGrimes
04/15/92 04/15/92 04/13/92 04/15/92 04/21/92 04/23/92 OEAB/NRR OGCB/NRR DO "Y
AChaffee* CBerlinger**CRossi Tch. Edtr.*
04/29/92 05/20/92 06//1/92 04/15/92 DOCUMENT NAME: 92-45.in
- Telephone concurrence received on 4/13/92
- See previous concurrence.
IN 92-XX
K> June XX, 1992 ambiguity in the Westinghouse catalog description for this particular relay
(Style 177C717G03, 60 Hz/120 V). Westinghouse has since corrected the catalog
description. The licensee corrected the error in relay selection by replacing
the relay with another relay that properly performs the under-frequency
permissive function.
Discussion
The EDG control circuitry is designed to prevent the output circuit breaker
from closing prematurely. This circuitry includes under-frequency and under- voltage permissive relays to ensure that the EDG attains both 90 percent of
rated frequency and 90 percent of rated voltage before the output circuit
breaker closes. Under emergency conditions (e.g., accident conditions with
loss of offsite power), use of the incorrect relay could allow the output
circuit breaker to close before the EDG reaches the necessary operating
conditions within the 10-second required period possibly resulting in shutdown
of the diesel engine and/or damage to the safety related loads.
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 contacts listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Sincerely, Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: Walter P. Haass, NRR
301-504-3219 E. Nick Fields, NRR
301-504-1173 Attachment: List of Recently Issued NRC Information Notices
OFF VIB/DRIS OEAB/NRR R III VIB/DRIS VIB/DRIS VIB/DRIS
NAME WPHaass* ENFields* Iqandis** GCwalina* f lNorrholm* BKGrimes*
DATE 04/15/92 04/15/92 04/13/92 04/15/92 04/21/92 04/23/92 OFF 0EAB/NRR OGCB/NMR DOEA/NRR
NAME AChaffee* CBerlinqfer CRossi CO Tch. Edtr.*
DATE 04/29/92 05/ /92 05/ /92 04/15/92 OFFICIAL RECORD COPY DOCUMENT NAME: INF0N0TE.WH
- Telephone Concurrence received on 4/13/92
DISTRIBUTION:
VIB R/F DRIS R/F INorrholm WPHaass
AChaffee BKGrimes ENFields CBerlinger
KLandis CRossi GCwalina
K)> IN 92-XX
K> May -, 1992 Discussion
The EDG control circuitry is designed to prevent the output circuit breaker
from closing prematurely. This circuitry includes under-frequency and under- voltage permissive relays to ensure that the EDG attains both 90 percent of
rated frequency and 90 percent of rated voltage before the circuit breaker
closes. Under emergency conditions (e.g., accident conditions with loss of
offsite power), use of the incorrect relay could allow the output circuit
breaker to close before the EDG reaches the necessary operating conditions
within the 10-second required period.
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.
Sincerely, Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: Walter P. Haass, NRR
301-504-3219 E. Nick Fields, NRR
301-504-1173 Attachment: List of Recently Issued NRC Information Notices
Distribution:
VIB R/F WNorrholm
DRIS R/F BKGrimes
WPHaass AChaffee
ENFields CBerlinger
KLandis CRossi
GCwalina
Concurrence:
OFF VIB/DRIS OEAB/NRR R III VIB/DRIS VIB/DRIS VIB/DRIS
NAME WPHaass* ENFields* KLandis** GCwalina* T-Norrholn* BKGrines*
DATE 04/15/92 04/15/92 04/13/92 I 04/15/92 04/21/92 04/23/92 OFF OEAB/NRR OGCB/}m DOEA/NRR
NAME AChaffee* CBer& CRossirjV jTch. Edtr.*
DATE 04/29/92 05i9V/92 05/ /92 04/15/92 I
OFFICIAL RECORD COPY DOCUMENT NAME: INFONOTE.WH
- Telephone Concurrence received on 4/13/92
IN 92-XX
April XX, 1992 DRISTRIBUTION
VIB R/F
DRIS R/F
WHaass
ENFields
KLandis
GCwalina
LNorrholm
AChaffee
CBerlinger
CRossi
[OFC
NAME
OEAB/NRR
AChafee
OGCB/NRR
CBerlinger
DOEA/NRR
CRossi TechEditor*
D 04L21/92 04/ /92 04/ /92 04/15/92 OFFICIAL RECORD COPY DOCUMENT NAME: A:\INFONOTE.2
- Telephone concurrence received on 4/13/92
K>
IN 92-XX
Apri LXX, 1992 Page{-of 2 DRISTRIBUTION
VIB R/F
DRIS R/F
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KLandis
GCwalina
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AChaffee
CBerlinger
CRossi
concurrence:
/
OFC VIB/DRIS OEAB/NRR RIII VIB/DRIS VIB/RIS VIB/DRIS
NAME WHaass* ENF, ields* KLandis** GCwalina* L BGrimes
DATE 04/15/92 O/15/92 04/13/92 04/15/92 04/-Z,(/92 04/ /92 OFC OEAB/NRR /OGCB/NRR DOEA/NRR
NAME AChaffee / CBerlinger CRossi TechEditor*
DATE 04/ /92/ 04/ /92 04/ /92 04/15/92 OFFI IAL RECORD COPY DOCUMENT NAME: A:\INFONOTE.2
- Telephope concurrence received on 4/13/92
IN 92-XX
April 15, 1992 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.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: Walter P. Haass, NRR
301-504-3219 E. Nick Fields, NRR
301-504-1173 Attachment: List of Recently Issued NRC Information Notices
Concurrence:
EOFC
NAME " rX ENFields ad LNorrholm BGrimes
DAE 0 592 04112 4//92 04//~9 04/ /9
04/ /92 IA _ _ _ _ _ _ _ _ _ _ _
NAME AChaffee CBerlinger CRossi
DATE 04/ /92 04/ /92 04/ /92
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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)
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