Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-UpML031130253 |
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 |
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Issue date: |
04/16/1990 |
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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-90-025, NUDOCS 9004120133 |
Download: ML031130253 (8) |
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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 Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[: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 16, 1990NRC INFORMATION NOTICE NO. 90-25: LOSS OF VITAL AC POWER WITH SUBSEQUENTREACTOR COOLANT SYSTEM HEAT-UP
Addressees
- All holders of operating licenses or construction permits for nuclear powerreactors.
Purpose
- This information notice is being provided to inform addressees of a significantoperating event which occurred at the Georgia Power Company's Vogtle NuclearPlant on March 20, 1990. The event took place while Unit 1 was in mid-loopin operational mde 6 and demonstrates the need for operating personnel to beprudent in removing equipment from service or establishing atypical equipmentalignments during shutdown. It is expected that recipients will review theinformation for applicability to their facilities and consider actions, asappropriate,.to avoid similar problems. However, suggestions contained inthis information notice do not constitute NRC requirements; therefore, nospecific action or written response is required.
Description of Circumstances
- On March 20, 1990, a loss of vital ac power occurred while Vogtle Unit 2 wasoperating at 100 percent power and Unit 1 had been in a refueling outage forabout 4 weeks. Unit 1 was in mid-loop in operational mode 6 with plant equip-ment conditions as follows:o The Unit 1 B reserve auxiliary transformer (RAT) was tagged out ofservice for maintenanceo The Unit 1 B emergency diesel generator (EDG) was tagged out ofservice and disassembled for maintenanceo The Unit 1 A RAT was supplying offsite power to the crosstied Unit 1A and B vital buseso The reactor coolant system (RCS) temperature was being maintained ataround 90 degrees Fahrenheit (F) via the train A residual heat removal(RHR) pump, the-train B pump was in standbyo The vessel head was in place with the bolts not fully tensionedo The pressurizer manway cover was removed_ __ A l e ,
IN 90-25April 16, 1990 o The manways for steam generators 2 and 3 were partially bolted in placeand the manways for steam generators 1 and 4 were in place with boltsfully tensionedo The inboard charging line check valve and an accumulator isolationvalve were open for inspectiono The containment equipment hatch and the containment personnel hatchwere openAt about 9:20 a.m., a truck carrying fuel and lubricants in the plant lowvoltage switchyard backed into a support column for the feeder line supplyingpower to the Unit 1 A RAT and the Unit 2 B RAT. The insulator for the C phaseof the feeder line fractured and initiated a phase-to-ground electrical fault.The fault resulted in a loss of power to the Unit 1 A RAT and the Unit 2 B RAT.The Unit 2 B EDG started and loaded to the deenergized Unit 2 B vital bus. How-ever, a Unit 2 turbine trip and reactor trip occurred because of an improperlyconnected (wrong tap) differential current transformer (DCT). The DCT initiatedthe trip when the current surge associated with the phase-to-ground fault wassensed. The Unit 2 trip was uncomplicated.Because both of the Unit 1 vital buses were crosstied and being supplied bythe Unit 1 A RAT, the loss of the transformer deenergized both vital buses.Deenergizing these buses resulted in the loss of power to the operating RHRpump. Since the Unit 1 B EDG was tagged out of service and disassembled formaintenance, the emergency power supply for the B vital bus was unavailableand the standby B RHR pump could not be started.The available Unit 1 A EDG started on bus undervoltage, but for unknown reasons,it shut down automatically after 1 minute and 20 seconds. At 9:40 a.m., plantoperators declared a site area emergency. A loss of all onsite and offsite acpower at Vogtle for more than 15 minutes is classified as a site area emergency.The licensee made their declaration because all vital ac power was lost forgreater than 15 minutes. Approximately 18 minutes after the first start ofthe A EDG, the operators locally reset the load sequencer which automaticallyrestarted the A EDG on undervoltage. However, after 1 minute and 10 seconds,the diesel again shut down automatically. At 9:56 a.m., plant operators per-formed an "emergency" manual start of the diesel, which bypassed most of thediesel's protective trips. The diesel started and loaded to the bus, the ARHR pump was restarted, and core cooling was reestablished to Unit 1. Withthe start of the diesel, the site area emergency was downgraded to an "alert"at 10:15 a.m. Containment integrity was established at 11:03 a.m.Plant personnel returned the Unit 1 B RAT to service after completing formaltagout removal procedures. However, attempts to energize the transformer weredelayed for several minutes because of a sticking mechanical interlock in thecontrol circuitry for a motor-operated disconnect switch on the high side ofthe B RAT. Power was restored to the B vital bus via the B RAT at 11:40 a.m.At 12:38 a.m., core cooling was shifted to the B RHR train to facilitate sub-sequent electrical alignment changes.
e. v -%IN 90-25April 16, 1990 According to control roon indication, RCS temperature increased from 90 to136 degrees F during the 36 minutes required to reenergize the A bus (1.3degrees F/min).Throughout the event, non-vital power was continuously provided to Unit 1 fromoffsite sources, via backfeed through the main generator transformer. Also,the Unit 2 electrical distribution system remained energized (aside from themomentary loss of power before the reactor trip). However, the Vogtle electricalsystem was not designed to permit easy interconnection of the Unit 1 vital busesto nonvital power or to the Unit 2 electrical buses. Therefore, there were noprocedures in place to provide guidance on interconnecting the Unit 1 vital andnonvital buses or for interconnecting the Unit 1 electrical distribution systemwith the distribution system at Unit 2. (There are no regulatory requirementsthat direct the licensee to develop Interconnection procedures.)Discussion:The NRC has previously identified concerns with the operability of necessaryequipment in shutdown modes. In Information Notice (IN) 80-2O, "Loss of DecayHeat Removal Capability at Davis-Besse Unit 1 While in a Refueling Mode" anextended loss of decay heat removal capability was attributed to a number offactors, including inadequate procedures, inadequate administrative controls,and the conduct of extensive maintenance activities.Information Notice 84-42, "Equipment Availability for Conditions During OutagesNot Covered by Technical Specifications," describes an event at the PalisadesNuclear Plant involving the total loss of all ac power. The Palisades eventwas precipitated by personnel performing actions during a refueling outagewithout an appreciation for the effect of those actions on the plant as itwas configured. Many pieces of equipment were tagged out of service formaintenance. Personnel intentionally interrupted offsite power. This actioncaused the loss of the only available service water pump. As a result, coolingwater was interrupted to the only available (and operating) diesel generator.The diesel overheated and was manually tripped. As a result, all station acpower was interrupted, causing the loss of fuel pool cooling. (The reactorhad been defueled, and its fuel was being stored in the spent fuel pool).The recent Vogtle event reemphasizes the need for careful planning of equipmentoutages during shutdown. Licensees, in general, have considerable latitude inremoving equipment from service and altering normal system lineups while inshutdown modes if only the minimum technical specification requirements areconsidered. The desire to return nuclear units to service as quickly aspossible can result in maintenance being conducted on redundant, safety-related systems, concurrently. The appropriateness of conducting parallelmaintenance activities should be considered in light of the availability ofalternate equipment and procedures to mitigate the consequences of potentialoperational problems. It is important that plant outage plans assure thatan adequate complement of equipment capable of responding to potential eventsremains available throughout the outage. Particular care is needed when thereactor pressure boundary is not intact or the reactor coolant system is atmid-loop.
IN 90-25April 16, 1990 A special investigation of the Vogtle event is being conducted by an NRCIncident Investigation Team (1IT). The information contained in this noticeis preliminary and is subject to change, pending the findings made by the IIT.This Information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate NRR projectmanager.~6hfares Eossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical Contacts: N. Fields, NRR(301) 492-1173E. Trager, AEOD(301) 492-4496Attachment: List ofRecently Issued NRC Information Notices
, 0 --uAttachmentIN 90-25April 16, 1990 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESIntormation Date otNotice No. Subject Issuance Issued to90-2490-2390-2290-2190-2090-1990-1890-17Transportation of ModelSpec 2-T RadiographicExposure DeviceImproper Installation ofPatel Conduit SealsUnanticipated EquipmentActuations FollowingRestoration of Powerto Rosemount TransmitterTrip UnitsPotential Failure of Motor-Operated Butterfly Valvesto Operate Because ValveSeat Friction was Under-estimatedPersonnel Injuries Resultingfrom Improper Operation ofRadwaste IncineratorsPotential Loss of EffectiveVolume for ContainmentRecirculation Spray atPWR FacilitiesPotential Problems withCrosby Safety Relief ValvesUsed on Diesel GeneratorAir Start Receiver TanksWeight and Center ofGravity Discrepanciesfor Copes-Vulcan Valves4/10/904/4/903/23/903/22/903/22/903/14/903/9/903/8/90All NRC licenseesauthorized to use,transport, or operateradiographic exposuredevices and sourcechangers.All holders of OLsor CPs for nuclearpower reactors.All holders of OLsor CPs for nuclearpower reactors.All holders of OLsor CPs for nuclearpower reactors.All NRC licenseeswho process orincinerate radio-active waste.All holders of OLsor CPs for PWRs.All holders of OLsor CPs for nuclearpower reactors.All holders of OLsor CPs for nuclearpower reactors.OL = Operating LicenseCP = Construction Permit
tNOW,IN 90-25--April 16, 1990
OFFICIAL RECORD COPYDocument Name: VOGTLEOFC O .DOEA pNAME NFleldsDATE yv"1/90OFC O X -DOEANAME DFISCHERDATE f /11/90
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list | - Information Notice 1990-01, Importance of Proper Response to Self-Identified Violations by Licensees (12 January 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-02, Potential Degradation of Secondary Containment (22 January 1990)
- Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm (23 January 1990, Topic: Liquid penetrant)
- Information Notice 1990-04, Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, (26 January 1990, Topic: Nondestructive Examination)
- Information Notice 1990-05, Inter-System Discharge of Reactor Coolant (29 January 1990)
- Information Notice 1990-06, Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels (29 January 1990)
- Information Notice 1990-07, New Information Regarding Insulation Material Performance and Debris Blockage of PWR Containment Sumps (30 January 1990)
- Information Notice 1990-08, KR-85 Hazards from Decayed Fuel (1 February 1990)
- Information Notice 1990-08, KR-85 Hazards From Decayed Fuel (1 February 1990)
- Information Notice 1990-09, Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees (5 February 1990, Topic: Decommissioning Funding Plan)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Liquid penetrant)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-11, Maintenance Deficiency Associated with Solenoid-Operated Valves (28 February 1990)
- Information Notice 1990-12, Monitoring or Interruption of Plant Communications (28 February 1990)
- Information Notice 1990-13, Importance of Review and Analysis of Safeguards Event Logs (5 March 1990)
- Information Notice 1990-14, Accidental Disposal of Radioactive Materials (6 March 1990, Topic: Brachytherapy)
- Information Notice 1990-15, Reciprocity Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States (17 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-16, Compliance with New Decommissioning Rule (7 March 1990)
- Information Notice 1990-17, Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves (8 March 1990, Topic: Earthquake)
- Information Notice 1990-18, Potential Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-18, Potential Problems With Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-19, Potential Loss of Effective Volume for Containment Recirculation Spray at PWR Facilities (14 March 1990)
- Information Notice 1990-20, Personnel Injuries Resulting from Improper Operation of Radwaste Incinerators (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction was Underestimated (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction Was Underestimated (22 March 1990)
- Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units (23 March 1990, Topic: Reactor Vessel Water Level)
- Information Notice 1990-23, Improper Installation of Patel Conduit Seals (4 April 1990)
- Information Notice 1990-24, Transportation of Model Spec 2-T Radiographic Exposure Device (10 April 1990)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power With Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-26, Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems (24 April 1990)
- Information Notice 1990-27, Clarification of the Recent Revisions to the Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for Transportation (30 April 1990)
- Information Notice 1990-28, Potential Error In High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-28, Potential Error in High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head (30 April 1990, Topic: Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-30, Ultrasonic Inspection Techniques for Dissimilar Metal Welds (1 May 1999, Topic: Dissimilar Metal Weld)
- Information Notice 1990-31, Update on Waste Form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-31, Update on Waste form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head (3 May 1990)
- Information Notice 1990-33, Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools (9 May 1990)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990)
- Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990)
- Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990, Topic: Authorized possession limits)
- Information Notice 1990-39, Recent Problems with Service Water Systems (1 June 1990)
- Information Notice 1990-40, Results of NRC-Sponsored Testing of Motor-Operated Valves (5 June 1990, Topic: Weak link)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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