Deficiency in Design Modifications to Address Failures of Hiller Actuators Upon a Gradual Loss of Air PressureML031210653 |
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: |
09/10/1992 |
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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-92-067, NUDOCS 9209030017 |
Download: ML031210653 (8) |
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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>. |
i-./
i
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 September 10, 1992 NRC INFORMATION NOTICE 92-67: DEFICIENCY IN DESIGN MODIFICATIONS TO ADDRESS
FAILURES OF HILLER ACTUATORS UPON A GRADUAL
LOSS OF AIR PRESSURE
Addressees
for nuclear power
All holders of operating licenses or construction permits
reactors.
Purpose
issuing this information
The U.S. Nuclear Regulatory Commission (NRC) is problem pertaining to
notice to alert addressees to a potentially significantvalve actuators upon a
modifications made to address failures of Hiller Information Notice (IN)
gradual loss of air pressure, as discussed in NRC Loss of Air Pressure." It
82-25, "Failures of Hiller Actuators upon Gradual for applicability to
is expected that recipients will review the information to avoid similar
their facilities and consider actions, as appropriate, information notice are not
problems. However, suggestions contained in thisor written response is
NRC requirements; therefore, no specific action
required.
Description of Circumstances
preheater bypass
Valve assemblies for three Shearon Harris main feedwater for Q Class
isolation valves were specified, procured, and installed
the valves and the
application. The Anchor Darling Valve Company supplied
associated Hiller actuators.
discovered several
On January 7, 1992, Carolina Power and Light Company of the three main
to the actuators
components associated with the air supply qualified for a Q Class
feedwater preheater bypass isolation valves were notpump in the non-Q Class, application. Specifically, the failure of the air accumulator could
non-seismic instrument air supply to the valve actuator from detecting slow leakage
prevent pressure switches upstream of the air pump
lines. The pressure
in the Q Class, seismic portion of the actuator air sending an automatic close
switches were installed to ensure valve closure by
of the actuator air
signal if the instrument air system pressure (upstream
pump) dropped to 66 psig as discussed in IN 82-25.
function as containment
The main feedwater preheater bypass isolation valves signal. The function
isolation valves upon receipt of a feedwater isolation
air supply pressure from
of the air pump is to raise the normal instrument pressure drops from
70 toJlO-.ps4s to approximately 150 psig. If accumulator
I
_r003017/X
J
IN 92-67 September 10, 1992 150 psig to 122 psig, the main feedwater
not close within 10 seconds. If pressure preheater bypass isolation valve may
it may not be sufficient to close the main drops to a value as low as 20 psig, isolation valve and keep it closed against feedwater preheater bypass
across the valve seat. the maximum differential pressure
Upon discovery of this condition, Shearon
interval for verifying that the actuators' Harris established a surveillance
properly and that the accumulators were fully components were functioning
1992, non-Q components were replaced with pressurized. On January 12, completed satisfactorily. suitable components and testing was
On January 15, 1992, the Shearon Harris
deficiency in the Hiller actuator for theSafety Committee determined that the
isolation valves was reportable under 10 main feedwater preheater bypass
of the possibility that these valves mightCFR Part 21 (Attachment 1), because
related function to close within 10 seconds not be able to meet their safety- for containment isolation. of a feedwater isolation signal
Other air-operated valves may be susceptible
to similar failure mechanisms.
This information notice requires no specific
you have any questions about the information action or written response. If
the technical contact listed below or the in this notice, please contact
Reactor Regulation (NRR) project manager. appropriate Office of Nuclear
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: Patricia Campbell, NRR
(301) 504-1311 Attachments:
1. Carolina Power and Light Company
Shearon Harris Nuclear Power Plant Part
2. List of Recently Issued NRC Information 21 Notices
'-I
Attachment 2 IN 92-67 September 10, 1992 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
92-66 Access Denied to NRC 09/01/92 All holders of OLs or CPs
Inspectors at Five Star for nuclear power reactors
Products, Inc. and and all reci pients of
Construction Products NUREG-0040, "Licensee, Con- Research, Fairfield, tractor and Vendor Inspec- Connecticut tion Status Report" (White
Book).
92-65 Safety System Problems 09/03/92 All holders of OLs or CPs
Caused by Modifications for nuclear power reactors.
That Were Not Adequately
Reviewed and Tested
92-64 Nozzle Ring Settings 08/28/92 All holders of OLs or CPs
on Low Pressure Water- for nuclear power reactors.
Relief Valves
92-63 Cracked Insulators in 08/26/92 All holders of OLs or CPs
ASL Dry Type Transformers for nuclear power reactors.
Manufactured by Westing- house Electric Corporation
92-62 Emergency Response 08/24/92 All U.S. Nuclear Regulatory
Information Require- Commission licensees.
ments for Radioactive
Material Shipments
92-61 Loss of High Head 08/20/92 All holders of OLs or CPs
Safety Injection for nuclear power reactors.
92-60 Valve Stem Failure 08/20/92 All holders of OLs or CPs
Caused by Embrittlement for pressurized water
reactors (PWRs).
92-59 Horizontally-Installed 08/18/92 All holders of OLs or CPs
Motor-Operated Gate for nuclear power reactors.
Valves
92-58 Uranium Hexafluoride 08/12/92 All Fuel Cycle Licensees.
Cylinders - Deviations
in Coupling Welds
OL = Operating License
CP = Construction Permit
IN 92-67 September 10, 1992 150 psig to 122 psig, the main feedwater preheater bypass isolation valve may
not close within 10 seconds. If pressure drops to a value as low as 20 psig, it may not be sufficient to close the main feedwater preheater bypass
isolation valve and keep it closed against the maximum differential pressure
across the valve seat.
Upon discovery of this condition, Shearon Harris established a surveillance
interval for verifying that the actuators' components were functioning
properly and that the accumulators were fully pressurized. On January 12,
1992, non-Q components were replaced with suitable components and testing was
completed satisfactorily.
On January 15, 1992, the Shearon Harris Safety Committee determined that the
deficiency in the Hiller actuator for the main feedwater preheater bypass
isolation valves was reportable under 10 CFR Part 21 (Attachment 1), because
of the possibility that these valves might not be able to meet their safety- related function to close within 10 seconds of a feedwater isolation signal
for containment isolation.
Other air-operated valves may be susceptible to similar failure mechanisms.
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: Patricia Campbell, NRR
(301) 504-1311 Attachments:
1. Carolina Power and Light Company
Shearon Harris Nuclear Power Plant Part 21
2. List of Recently Issued NRC Information Notices
Document Name: 92-67.IN
- SEE PREVIOUS CONCURRENCES
GHMarcus
0("/7/ \08/31/92 OGCB:DOEA:NRR *EMEB:DET:NRR *C/EMEB:DET:NRR *D/DET:NRR *RPB:ADM
NCampbell PCampbell JNorberg JRichardson TechEd
08/ /92 08/17/92 08/17/92 08/28/92 08/11/92
IN 92-XX
August xx, 1992 150 psig to 122 psig, the main feedwater preheater bypass isolation valve may
not close within 10 seconds. If pressure drops to a value as low as 20 psig, it may not be sufficient to close the main feedwater preheater bypass
isolation valve and keep it closed against the maximum differential pressure
across the valve seat.
Upon discovery of this condition, Shearon Harris initiated a surveillance
interval to verify that the actuators' components were functioning properly
and that the accumulators were fully pressurized. On January 12, 1992, non-Q components were replaced with suitable components and testing completed
satisfactorily.
On January 15, 1992, the Shearon Harris Safety Committee determined that the
deficiency in the Hiller actuator for the main feedwater preheater bypass
isolation valves reportable under 10 CFR Part 21 (Attachment 1), because of
the possibility that these valves might not be able to meet their safety- related function to close within 10 seconds of a feedwater isolation signal
for containment isolation.
Other air-operated valves may be susceptible to similar failure mechanisms.
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: Patricia Campbell, NRR
(301) 504-1311 Attachments:
1. Carolina Power and Light Company
Shearon Harris Nuclear Power Plant Part 21
2. List of Recently Issued NRC Information Notices
Document Name: LOSSAIR.IN
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEA:NRR
CERossi GHMarcus
08/ /92, A// 8/ /92 OGCB:DOEA:NRR *EMEB:DET:NRR *C/EMEB:DET:NRR D/DET:NR~b QRPB:ADM
NCampbell PCampbell JNorberg JRicIrd n TechEd
08/ /92 08/17/92 08/17/92 08/1)X/92 08/11/92
6,1
IN 92-XX
August xx, 1992 150 psig to 122 psig, the main feedwater preheater bypass isolation valve may
not close within 10 seconds. If pressure drops to a value as low as 20 psig, it may not be sufficient to close the main feedwater preheater bypass
isolation valve and keep it closed against the maximum differential pressure
across the valve seat.
Upon discovery of this condition, Shearon Harris initiated a surveillance
interval to verify that the actuators' components were functioning properly
and that the accumulators were fully pressurized. On January 12, 1992, non-Q components were replaced with suitable components and testing completed
satisfactorily.
On January 15, 1992, the Shearon Harris Safety Committee determined that the
deficiency in the Hiller actuator for the main feedwater preheater bypass
isolation valves was reportable under 10 CFR Part 21 (Attachment 1), because
of the possibility that these valves might not be able to meet their safety- related function to close within 10 seconds of a feedwater isolation signal
for containment isolation.
Other air-operated valves may be susceptible to similar failure mechanisms.
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: Patricia Campbell, NRR
(301) 504-1311 Attachments:
1. Carolina Power and Light Company
Shearon Harris Nuclear Power Plant Part 21
2. List of Recently Issued NRC Information Notices
Document Name: LOSSAIR.IN
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEA:NRR
CERossi GHMarcusff
08/ /92 08/.31/926M
OGCB:DOEA:NRR *EMEB:DET:NRR *C/EMEB:DET:NRR *D/DET:NRR *RPB:ADM
NCampbell PCampbell JNorberg JRichardson TechEd
08/al/92 08/17/92 08/17/92 08/28/92 08/11/92
_wF,-tr
The air pump raises the normal instrument air supply pressure from 70 to 100
psig to approximately 150 psig. If accumulator pressure drops from 150 psig
to 122 psig, the valve may not close within 10 seconds. If pressure drops to
a value as low as 20 psig, it may not be sufficient to close the valve and
keep it closed against the maximum differential pressure across the valve
seat.
Upon discovery of the condition on January 7, 1992, Shearon Harris initiated a
surveillance interval to verify that the actuators' components were
functioning properly and that the accumulators were fully pressurized. On
January 12, 1992, non- components were replaced with suitable components and
testing completed sati c torily.
Other air-operated valves m sbe susceptible to similar failure mechanisms
addressed herein.
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 NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Technical Contact:
Patricia Campbell, NRR
(301) 504-ES3&
Attachments:
1. Carolina Power and Light Company
Shearon Harris Nuclear Power Plant Part 21
2. List of Recently Issued NRC Information Notices
DISTRIBUTION:
Central Files
DOEA R/F
OGCB R/F
N. Campbell R/F
OFFICE: OGCB:DOEA *RPB:ADM EMEB:DET 4B S ET
NAME: NCampbell:db TechEd PCampbell J ere
DATE: 08/ /92 08/11/92 08//f/92 08//7/92 OFFICE: BC:OGCB:DOEA D:DOEA
NAME: GMarcus CRossi
DATE: 08/ /92 08/ /92
,qaq42 i.1_ tt
isoVen1 2 Upon-dlsewery-1/te condition on January 7, 1992, Shearor-Hrr4 initiated a1 surveillance to verify that the actuators' components were
ote,'e&V
functioning properly and that the accumulators were fully pressurized. On
January 12,'-H002J non-Q components were replaced with suitable components and
testing completed satisfactorily.
,--t n~ wes-iwUth er air-operated valves may be susceptible to similar failure
mechanisms addressed herein.
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 NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Technical Contact:
Patricia Campbell, NRR
(301) 504-2836 Attachments:
1. Carolina Power and Light Company
Shearon Harris Nuclear Power Plant Part 21
2. List of Recently Issued NRC Information Notices
DISTRIBUTION:
Central Files
DOEA R/F
OGCB R/F
OFFICE: OGCB:DOEA RPB:ADM EMEB:DET BC:EMEB:DET
NAME: NCampbell:db TechEdJM?,' PCampbell JNorberg
DATE: 08/ /92 08/u /927 08/ /92 08/ /92 OFFICE: BC:OGCB:DOEA D:DOEA
NAME: GMarcus CRossi
DATE: 08/ /92 08/ /92 FILENAME: LOSSAIR.WP
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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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