Increased Instrument Response Time When Pressure Dampening Devices are InstalledML031200378 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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: |
04/30/1992 |
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Revision: |
0 |
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From: |
Rossi C E Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-92-033, NUDOCS 9204240146 |
Download: ML031200378 (9) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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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Category:NRC Information Notice
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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 [[: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 [[: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 STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555April 30, 1992NRC INFORMATION NOTICE 92-33:INCREASED INSTRUMENT RESPONSE TIME WHENPRESSURE DAMPENING DEVICES ARE INSTALLED
Addressees
All holders of operating licenses or construction permits for nuclear powerreactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information noticeto alert addressees to increased response times for pressure sensing instrumentsthat occur when pressure dampening devices are installed in the instrumentsensing lines. It is expected that recipients will review the information forapplicability to their facilities and consider actions, as appropriate, toavoid similar problems. However, suggestions contained in this informationnotice are not NRC requirements; therefore, no specific action or writtenresponse is required.
Description of Circumstances
On September 25, 1991, the GPU Nuclear Corporation, licensee for the OysterCreek Nuclear Generating Station, initiated a plant shutdown after determiningthat seven of eight isolation condenser line break pressure sensors did notmeet the plant technical specification requirements for instrument responsetimes. The licensee's trouble shooting determined that pressure dampeningdevices in the sensing lines for these differential pressure sensors had causedan increase in the response times. Furthermore, the licensee found that thetime delay caused by these devices is significant at both low and high pressures.DiscussionThe pressure dampening devices (snubbers) which utilize sintered stainlesssteel elements are generally installed in instrument sensing lines to dampenpressure oscillations or to protect the instruments from particulate contami-nation.When the sensors failed to meet the required response times during surveillancetests, the licensee reviewed the pressure sensing system and found that thesnubbers were causing unacceptable time delays. The licensee later removed thesnubbers because they are not needed when using the upgraded Barton pressuresensors that were installed.9204 /X 4A= I {e0(q Q-/ /~ A3/4-//C(
IIN 92-33April 30, 1992 Snubber time delay will not be detected in response time testing conducteddirectly at the sensing instrument (see Figure 1.) The effect of a snubberwill differ from sensor to sensor because of differences in the volumetricdisplacement of fluid within the pressure sensing mechanisms. System responsetime can also be degraded by the accumulation of foreign material in sensingline snubbers.The NRC's Office of Nuclear Regulatory Research is conducting a generic studyon the performance of pressure instrumentation at nuclear power plants. Thestaff plans to publish the results in NUREG/CR 5851, "Long Term Performanceand Aging Characteristics of Nuclear Plant Pressure Transmitters." The staffhas completed a part of this effort, and the results of tests conducted onpressure sensor response time testing were published in an ISA (InstrumentSociety of America) transaction 91-720, "Response Time Testing of PressureTransmitters in Nuclear Power Plants." This publication addresses variouscauses for delays in sensor response and documents that significant timedelays can occur.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contact oneof the technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.harles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contacts: Thomas Koshy, NRR(301) 504-1176Iqbal Ahmed, NRR(301) 504-3252
Attachments:
1. Figure 1. Test Configuration that Excludes theEffect of Snubbers2. List of Recently Issued NRC Information Notices Attachment 1IN 92-33April 30, 1992 PRESSURE SENSING DEVICEUBBERSTi LOW SIDE BLOCK VALVETO PROCESSCONNECTIONFigure 1.Test Configuration That Excludes the Effect of Snubbers mz-C1>cnmZcmm0 F)-0>~03<>CA LM2aC/)cnD*o m(AnU).200'Im,,00rn ->CAAttachment 2IN 92-33April 30, 1992 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to92-32 Problems Identified with 04/29/92 All holders of OL or CPsEmergency Ventilation for nuclear power reactors.Systems for Near-Site(Within 10 Miles) Emer-gency Operations Facili-ties and Technical SupportCenters92-31 Electrical Connection 04/27/92 All holders of OLs or CPsProblem in Johnson for nuclear power reactors.Yokogawa CorporationYS-80 Programmable Indi-cating Controllers92-30 Falsification of Plant 04/23/92 All holders of OLs or CPsRecords for nuclear power reactorsand all licensed operatorsand senior operators.92-21, Spent Fuel Pool Re- 04/22/92 All holders of OLs or CPsSupp. I activity Calculations for nuclear power reactors.92-29 Potential Breaker His- 04/17/92 All holders of OLs or CPscoordination Caused by for nuclear power reactors.Instantaneous TripCircuitry92-28 -Inadequate Fire Suppres- 04/08/92 All holders of OLs or CPssian System Testing for nuclear power reactors.92-27 Thermally Induced Acceler- 04/03/92 All holders of OLs or CPsated Aging and Failure of for nuclear power reactors.ITE/GOULD A.C. Relays Usedin Safety-Related Applic-ations92-26 Pressure Locking of Motor- 04/02/92 All holders of OLs or CPsOperated Flexible Wedge for nuclear power reactors.Gate ValvesOL = Operating LicenseC? -Construction Permit((.< \
IN 92-33April 30, 1992 Snubber time delay will not be detected in response time testing conducteddirectly at the sensing instrument (see Figure 1.) The effect of a snubberwill differ from sensor to sensor because of differences in the volumetricdisplacement of fluid within the pressure sensing mechanisms. System responsetime can also be degraded by the accumulation of foreign material in sensingline snubbers.The NRC's Office of Nuclear Regulatory Research is conducting a generic studyon the performance of pressure instrumentation at nuclear power plants. Thestaff plans to publish the results in NUREG/CR 5851, "Long Term Performanceand Aging Characteristics of Nuclear Plant Pressure Transmitters." The staffhas completed a part of this effort, and the results of tests conducted onpressure sensor response time testing were published in an ISA (InstrumentSociety of America) transaction 91-720, "Response Time Testing of PressureTransmitters in Nuclear Power Plants." This publication addresses variouscauses for delays in sensor response and documents that significant timedelays can occur.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contact oneof the technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager. Orginal Signed byCharles E. RossiCharles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contacts: Thomas Koshy, NRR(301) 504-1176Iqbal Ahmed, NRR(301) 504-3252
Attachments:
1. Figure 1. Test Configuration that Excludes theEffect of Snubbers2. List of Recently Issued NRC Information NoticesReviewed by J. Main, Technical Editor, on 02/07/92*SEE PREVIOUS CONCURRENCEOFC :OEAB:DOEA :SICB:DST :SC:OEAB:DOEA:C:SICB:DST :C:OEAB:DOEA :C:OGCB:DOEA :D:DOEANAME :TKoshy* :IAhmed* :DFischer* :SNewberry* :AChaffee* :CBerlinger*_____ __ _ --------------:-- ----- --------:-- --- --: -- -----\-- -------DATE :02/12/92 :03/03/92 : 03/06/92 :03/18/92 :03/19/92 :04/20/92 :04/ v 92OFFICIAL RECORD COPYDocument Name: IN 92-33 IN 92-XXApril xx, 1992 Since the snubbers are mounted upstream of the sensors, this time delay willnot be experienced in response time testing conducted directly at the sensinginstrument (see Figure 1.) These snubbers could degrade and reduce the flowthrough the device, further increasing the time delay. The effect of a snubberwould differ between various sensors because of the differences in the volumetricdisplacement of fluid within their pressure sensing mechanism. System responsetime could be degraded by the presence and condition of snubbers in the sensingline.The NRC's Office of Nuclear Regulatory Research is conducting a generic studyon the performance of pressure instrumentation at nuclear power plants. Thestaff plans to publish this study report as NUREG/CR 5851, "Long Term Performanceand Aging Characteristics of Nuclear Plant Pressure Transmitters." The staffcompleted a part of this effort and the result of tests conducted on pressuresensor response time testing was published in an ISA (Instrument Society ofAmerica) transaction 91-720, "Response Time Testing of Pressure Transmitters inNuclear Power Plants." This publication addresses various causes for thedelays in sensor response and documents that significant time delays can occur.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contact oneof the technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contacts: Thomas Koshy, NRR(301) 504-1176Iqbal Ahmed, NRR(301) 504-3252
Attachments:
1. Figure 1. Test Configuration that Excludes theEffect of Snubbers2. List of Recently Issued NRC Information NoticesReviewed by J. Main, Technical Editor, on 02/07/92*SEE PREVIOUS CONCURRENCE,OFC :OEAB:DOEA :SICB:DST :SC:OEAB:DOEA:C:SICB:DST :C:OEAB:DOEA :C:OA D:DOEANAME :TKoshy* :IAhmed* :DFischer* :SNewberry* :AChaffee* :CB lnger :CRossi -DATE :02/12/92 :03/03/92 : 03/06/92 :03/18/92 :03/19/92 : 9/A5/92 : / /92OFFICIAL RECORD COPYDocument Name: IN/KOSHY IN 92-XXMarch xx, 1992 Since the snubbers are mounted upstream of the sensors, this time delay willnot be experienced in response time testing conducted directly at the sensinginstrument. These snubbers could degrade and reduce the flow through thedevice, further increasing the time delay. The effect of a snubber woulddiffer between various sensors because of the differences in the volumetricdisplacement of fluid within their pressure sensing mechanism. System responsetime could be degraded by the presence and condition of snubbers in the sensingline.The NRC's Office of Nuclear Regulatory Research is conducting a generic studyon the performance of pressure instrumentation at nuclear power plants. Thestaff plans to publish this study report as NUREG/CR 5851, "Long Term Performanceand Aging Characteristics of Nuclear Plant Pressure Transmitters." The staffcompleted a part of this effort and the result of tests conducted on pressuresensor response time testing was published in an ISA (Instrument Society ofAmerica) transaction 91-720, "Response Time Testing of Pressure Transmitters inNuclear Power Plants." This publication addresses various causes for thedelays in sensor response and documents that significant time delays can occur.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contact oneof the technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contacts: Thomas Koshy, NRR(301) 504-1176Iqbal Ahmed, NRR(301) 504-3252
Attachment:
List of Recently Issued NRC Information NoticesReviewed by J. Main, Technical Editor, on 02/07/92*SEE PREVIOUS CONCURRENCEOFC :OEAB:DOEA :SICB:DST :SC:OEB:DOEA SICPST :COEAB:DOEA :C:OGCB:DOEA :D:DOEANAME :TKoshy* :IAhmed* :DFsTcher :SN-- erry :ACxt :CBerlinger :CRossiDATE :02/12/92 :03/03/92 :3 /6 /92 :S,48/92 : 5It"/92 : / /92 : / /92OFFICIAL RECORD COPYDocument Name: IN/KOSHY IN 92-XXFebruary xx, 1992 The NRC's Office of Nuclear Regulatory Research is conducting a generic studyon the performance of pressure instrumentation at nuclear power plants. Thestaff plans to publish this study report as NUREG/CR 5851, "Long Term Performanceand Aging Characteristics of Nuclear Plant Pressure Transmitters." The staffcompleted a part of this effort and the result of tests conducted on pressuresensor response time testing was published in an ISA (Instrument Society ofAmerica) transaction 91-720, "Response Time Testing of Pressure Transmitters inNuclear Power Plants." This publication addresses various causes for thedelays in sensor response and documents a 3-second delay for a snubber in thesensing line.Since the snubbers are mounted upstream of the sensors, this time delay willnot be experienced in response time testing conducted directly at the sensinginstrument. These snubbers could degrade and reduce the flow through thedevice, further increasing the time delay. The effect of a snubber woulddiffer between various sensors because of the differences in the volumetricdisplacement of fluid within their pressure sensing mechanism. System responsetime could be degraded by the presence and condition of snubbers in the sensingline.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contact oneof the technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contacts: Thomas Koshy, NRR(301) 504-1176Iqbal Ahmed, NRR(301) 504-3252
Attachment:
List of Recently Issued NRC Information NoticesReviewed by J. Main, Technical Editor, on 02/07/92*SEE PREVIOUS CONCURRENCEOFC :OEAB:DOEA :SICB:DST :SC:OEAB:DOEA:C:SICB:DST :C:OEAB:DOEA :C:OGCB:DOEA :D:DOEANAME :TKoshy* :IAhmed ( :DFischer :SNewberry :AChaffee :CBerlinger :CRossiDATE :02/12/92 :3 /3/92 : / /92 : / /92 : / /92 : / /92 : / /92OFFICIAL RECORD COPYDocument Name: IN/KOSHY IN 92-XXFebruary xx, 1992 The NRC's Office of Nuclear Regulatory Research is studying the performance ofinstrumentation. The staff plans to publish this study as NUREG/CR 5851, "LongTerm Performance and Aging Characteristics of Nuclear Plant Pressure Transmitters."The staff completed a part of this effort and the result of tests conducted onpressure sensor response time testing was published in an ISA (InstrumentSociety of America) transaction 91-720, "Response Time Testing of PressureTransmitters in Nuclear Power Plants." This publication addresses variouscauses for the delays in sensor response and documents a 3-second delay for asnubber in the sensing line.Since the snubbers are mounted upstream of the sensors, this time delay willnot be experienced in response time testing conducted directly at the sensinginstrument. These snubbers could degrade and reduce the flow through thedevice, further increasing the time delay. The effect of a snubber woulddiffer between various sensors because of the differences in the volumetricdisplacement of fluid within their pressure sensing mechanism. System responsetime could be degraded by the presence and condition of snubbers in the sensingline.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contact oneof the technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contacts: Thomas Koshy, NRR(301) 504-1176Iqbal Ahmed, NRR(301) 504-3252
Attachment:
List of Recently Issued NRC Information NoticesReviewed by J. Main, Technical Editor, on 02/07/92OFC :OEAB:DOEA :SICB:DST :SC:OEAB:DOEA:C:SICB:DST :C:OEAB:DOEA :C:OGCB:DOEA :D:DOEANAME :TKoshy Tf :IAhmed :DFischer :SNewberry :AChaffee :CBerlinger :CRossiDATE :2_//2/92 :/ /92 ://92 ://92 ://92 ://92 :/ /92OFFICIAL RECORD COPYDocument Name: IN/KOSHY
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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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