U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement
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U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement
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The organization U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement represents an institution, an association, or corporate body that is associated with resources found in University of Missouri-Kansas City Libraries.
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- Obtaining approval for disposing of very-low-level radioactive waste - 10 CFR Section 20.302
- 10 CFR 50.7, Employee Protection
- 8X8R water rod lower end plug wear
- Accidental actuation of prompt public notification system
- Actuation of ECCS in the recirculation mode while in hot shutdown
- Actuation of fire suppression system causing inoperability of safety-related equipment
- Actuation of fire suppression system causing inoperability of safety-related ventilation equipment
- Age/environment induced electrical cable failures
- Air/gas entrainment events resulting in system failures
- Alleged use of stand-ins for welder qualification tests
- Alternate rod Insertion for BWR scram represents a potential path for loss of primary coolant
- Anchorage and support of safety-related electrical equipment
- Apparent improper modification of a component affecting plant safety
- Apparently improper use of commercial grade components in safety-related systems
- Applicability of 10 CFR 21 to consulting firms providing training
- Assessment of intakes of radioactive material by workers
- Attempted damage to new fuel assemblies
- Auditability of electrical equipment qualification records at licensees' facilities
- Auxiliary feed pump turbine bearing failures
- Auxiliary feedwater pump lockout resulting from Westinghouse W-2 switch circuit modification
- Auxiliary feedwater sparger and pipe hanger damage
- Axial (longitudinal) oriented cracking in piping
- BBC Brown Boveri low-voltage K-line circuit breakers, with deficient overcurrent trip devices models OD-4 and 5
- BWR fuel exposure in excess of limits
- BWR high-pressure coolant injection (HPCI) initiation seal-in and indication
- BWR post-scram drywell pressurization
- Backup telephone numbers to the NRC Operations Center
- Boiling water reactor safety/relief valve failures
- Boron dilution of reactor coolant during steam generator decontamination
- Breach of containment integrity
- Breakdowns in contamination control programs
- Broken inner-external closure springs on Atwood & Morrill main steam isolation valves
- Broken studs on terry turbine steam inlet flange
- Buildup of enriched uranium in effluent treatment tanks
- Buildup of enriched uranium in ventilation ducts and associated effluent treatment systems
- Calibration of liquid level instruments
- Calibration problems - Eberline Instrument model 6112b analog teletectors
- Change in NRC practice regarding issuance of confirming letters to principal contractors
- Change in format and distribution system for Ie Bulletins, Circulars, and Information Notices
- Check valve failures
- Check valve failures on diesel generator engine cooling system
- Check valve problems
- Checklist for licensees making notifications of significant events in accordance with 10 CFR 50.72
- Chemical cleaning of steam generators at Millstone 2
- Chloride contamination of safety related piping and components
- Circuit breaker position verification
- Clarification of certain requirements for exclusive-use shipments of radioactive materials
- Clarification of conditions for waste shipments subject to hydrogen gas generation
- Clarification of emergency plan exercise requirements
- Clarification of requirements for fabrication and export of certain previously approved Type B packages
- Clarification of scope of quality assurance programs for transport packages pursuant to 10 CFR 50, Appendix B
- Clarification of several aspects of removable radioactive surface
- Clarification of several aspects relating to use of NRC-certified transport
- Common mode failure of main steam isolation nonreturn check valves
- Common-mode valve failures degrade Surry's recirculation spray subsystem
- Compilation of health physics related information Items
- Complete loss of main and auxiliary feedwater at a PWR designed by Babcock & Wilcox
- Compliance with conditions of license and notification of disability by licensed operators
- Compliance with the posting requirements of Subsection 223B of the Atomic Energy Act of 1954, as amended
- Component failures caused by elevated DC control voltage
- Computer code defect in stress analysis of piping elbow
- Computer program error report handling
- Conductor insulation degradation on Foxboro Model E controllers
- Containment cooler leaks and reactor cavity flooding at Indian Point Unit 2
- Containment integrated leak rate tests
- Contamination of reactor coolant system by organic cleaning solvents
- Contamination of the Auburn Steel Company property with cobalt-60
- Continuous supervision of irradiators
- Control of maintenance and essential equipment
- Control of radiation levels in unrestricted areas adjacent to brachytherapy patients
- Control rod drive (CRD) guide tube support pin failures at Westinghouse PWRS
- Control rod drive system malfunctions
- Correction for sample conditions for air and gas monitoring
- Crack growth in steam generator girth welds
- Cracked and broken piston rods in Brown Bovery electric type 5HK breakers
- Cracking in boiling-water-reactor Mark I and Mark II containments caused by failure of the inerting system
- Cracking in charging pump casing cladding
- Cracking in low pressure turbine discs
- Cracking in main steam lines
- Cracking in piping of makeup coolant lines at B&W plants
- Cracking in the upper shell to transition cone girth weld of a steam generator at an operating pressurized water reactor
- Cracking of flywheels on Cummins fire pump diesel engines
- Criminal prosecution of a former radiation safety officer who willfully directed an unqualified individual to perform radiography
- Criteria for protective action recommendations for general emergencies
- Defective RHR replacement piping
- Defective and obsolete combination padlocks
- Defective emergency-use respirator
- Defective heat sink adhesive and seismically induced chatter in relays within printed circuit cards
- Defective negative-pressure, air-purifying, full facepiece respirators
- Defects in load-bearing welds on lifting devices for vessel head and internals
- Defects observed in Panasonic model 801 and model 802 thermoluminescent dosimeters
- Deficiencies in LWR air filtration/ventilation systems
- Deficiencies in design base documentation and calculations supporting nuclear power plant design
- Deficiencies in equipment qualification testing and certification process
- Deficiencies in ferro-resonant transformers
- Deficiencies in primary containment electrical penetration assemblies
- Deficiencies in upgrade programs for plant emergency operating procedures
- Deficiency in Comsip, Inc. standard bed catalyst
- Deficient operator actions following dual function valve failures
- Deficient procedures
- Degradation of automatic ECCS actuation capability by isolation of instrument lines
- Degradation of engineered safety features
- Degradation of reactor coolant pump studs
- Degradation of residual heat removal (RHR) system
- Degradation of static "O" ring pressure switches
- Degradation of station batteries
- Degradation or loss of charging systems at PWR nuclear power plants using swing-pump designs
- Degraded DC system at Palisades
- Degraded ability to isolate the reactor coolant system from low-pressure coolant systems in BWRS
- Degraded motor leads in Limitorque DC motor operators
- Delayed access to safety-related areas and equipment during plant emergencies
- Deliberate circumventing of station health physics procedures
- Design limitations of gaseous effluent monitoring systems
- Design misapplication of Bergen-Paterson standard strut restraint clamp
- Design-basis threat and review of vehicular access controls
- Determination of teletherapy timer accuracy
- Dewatered spent ion exchange resin susceptibility to exothermic chemical reaction
- Diesel generator differential protection relay not seismically qualified
- Diesel generator events
- Diesel generator fails test because of degraded fuel
- Diesel generator failure at Calvert Cliffs Nuclear Station Unit 1
- Discrepancies between as-built construction drawings and equipment installations
- Discrepancies in record keeping and material defects in Bahnson heating, ventilation, and air conditioning units
- Dose assignment for workers in non-uniform radiation fields
- Downrating of self-aligning ball bushings used in snubbers
- Dropped fuel assembly
- EPA crosscheck program - low level radioiodine in water intercomparison
- Effect of radiation on hydraulic snubber fluid
- Effects of changing valve motor-operator switch settings
- Electrical control logic problem resulting in inoperable auto-start of emergency diesel generator units
- Emergency communication system monthly test
- Emergency diesel generator control circuit logic design error
- Emergency diesel generator lube oil coolers
- Emergency diesel generator room cooling design deficiency
- Emergency worker doses
- Emergency-use respirator material defect causes production of noxious gases
- Enclosure of vital equipment within designated vital areas
- Enforcement actions against medical licensees for willfull failure to report misadministrations
- Entry into high radiation areas from areas which are not under direct surveillance
- Environmental qualification test of General Electric Company "CR-2940" position selector control switch
- Environmental qualification testing experience
- Environmental qualification testing of Rockbestos cables
- Environmental qualification tests of electrical terminal blocks
- Environmental tests of electrical terminal blocks
- Equipment availability for conditions during outages not covered by technical specifications
- Equipment environmental qualification testing experience - updating of test summaries previously published in 81-29
- Equipment qualification testing experience
- Erratic behavior of static "O" ring differential pressure switches
- Error in the Adlpipe computer program
- Errors in dose assessment computer codes and reporting requirements under 10 CFR Part 21
- Evaluation of contractor QA programs
- Evaluation of questionable exposure readings of licensee personnel dosimeters
- Event notication
- Event notification information worksheet
- Excess lubricant in electric cable sheaths
- Excessive nitrogen supply pressure actuates safety-relief valve operation to cause reactor depressurization
- Excessive pneumatic leakage in the automatic depressurization system
- Excessive radiation exposures to the fingers of three individuals incurred during cleaning and wipe testing of radioactive sealed sources at a sealed-source manufacturing facility
- Excessive skin exposures due to contamination with hot particles
- Exercise frequency
- Failure 17-7 PH stainless steel springs in Valcor valves due to hydrogen embrittlement
- Failure of ELMA power supply units 1
- Failure of ITE model K-600 circuit breaker
- Failure of Rockwell-Edward main steam isolation valves
- Failure of a General Electric type AK-2-25 reactor trip breaker
- Failure of air check valves to seat
- Failure of air-purifying respirator filter to meet efficiency requirement
- Failure of automatic sprinkler system valves to operate
- Failure of auxiliary feedwater manual isolation valve
- Failure of check and stop check valves subjected to low flow conditions
- Failure of elastomer seated butterfly valves used only during cold shutdowns
- Failure of hydraulic snubbers as a result of contaminated hydraulic fluid
- Failure of lifting rig attachment while lifting the upper guide structure at St Lucie Unit 1
- Failure of main feedwater check valves causes loss of feedwater system integrity and water-hammer damage
- Failure of redundant toxic gas detectors positioned at control room ventilation air intakes
- Failure of safety injection valves to operate against differential pressure
- Failure of safety/relief valve discharge line vacuum breakers
- Failure of safety/relief valves to open at BWR--final report
- Failure of safety/relief valves to open at BWR--interim report
- Failure of safety/relief valves to open at a BWR
- Failure of soft seat valve seals
- Failure of steam generator primary side manway closure studs
- Failure of steam generator support bolting
- Failure of swing check valve in the decay heat removal system at Davis-Besse Unit No. 1
- Failure of three check valves on high pressure injection lines to pass flow
- Failure to follow procedures when working in high radiation areas
- Failure to properly install steam separator at Vermont Yankee
- Failures in turbine exhaust lines
- Failures of AGASTAT CR 0095 relay sockets
- Failures of Class 1E safety-related switchgear circuit breakers to close on demand
- Failures of General Electric type HFA relays
- Failures of Hiller actuators upon gradual loss of air pressure
- Failures of RHR pump motors and pump internals
- Failures of Rockwell International globe valves
- Failures of scram discharge volume vent and drain valves
- Failures of the continuous water level monitor for the scram discharge volume at Dresden Unit No. 2
- Failures of the undervoltage, trip function of reactor trip system breakers
- Failures to identify containment leakage due to inadequate local testing of BWR vacuum relief system valves
- Falsification of test results for protective coatings
- Falsified pre-employment screening records
- Fatality at Argentine critical facility
- Fire in compressible material at Dresden Unit 3
- Flammable gas mixtures in the waste gas decay tanks in PWR plants
- Following up symptomatic repairs to assure resolution of the problem
- Fuel assembly damaged due to improper positioning of handling equipment
- Fuel binding caused by fuel rack deformation
- Fuel handling events
- Fuel movement with control rods withdrawn at BWRS
- Fuel rod degradation resulting from baffle water-jet impingement
- Gaseous effluent releases of radioactive Iodine-125 and Iodine-131 in excess of Nuclear Regulatory Commission limits
- General Electric Magne-Blast circuit breaker problems
- General Electric type HFA relay contact gap and wipe setting adjustments
- General Electric type SBM control switches defective cam followers
- Generic problems with ASCO valves in nuclear applications including fire protection systems
- Graphitic corrosion of cast iron in salt water
- Guidance for posting radiation areas
- Guidance on order issued January 9, 1981 regarding automatic control rod insertion on low control air pressure
- HPCI/RCIC high steam flow setpoints
- Hazards of inerting atmospheres
- Heat tracing contributes to corrosion failure of stainless steel piping
- Highlights of recent transport regulatory revisions by DOT and NRC
- Hydrogen explosion while grinding in the vicinity of drained and open reactor coolant system
- IGSCC in BWR plants
- ITT Grinnell figure 306/307 mechanical snubber attachment interference
- Impact of security practices on safe operations
- Improper assembly, material selection, and test of valves and their actuators
- Improper cleaning and decontamination of respiratory protection equipment
- Improper closure of primary containment access hatches
- Improper control rod manipulation
- Improper installation and testing of differential pressure transmitters
- Improper installation of heat shrinkable tubing
- Improper maintenance of radiation monitoring systems
- Improper settings of intermediate range (IR) high flux trip setpoints
- Improperly installed fire dampers at nuclear power plants
- Improperly installed instrumentation, inadequate quality control and inadequate postmodification testing
- Inadequate communications between maintenance, operations, and security personnel
- Inadequate design of safety-related heat exchangers
- Inadequate environment control for components and systems in extended storage or layup
- Inadequate inservice testing of main steam isolation valves
- Inadequate material procurement controls on the part of licensees and vendors
- Inadequate security screening programs
- Inadequate seismic qualification of diaphragm valves by mathematical modeling and analysis
- Inadequate service water protection against core melt frequency
- Inadequate shutdown margins
- Inadequate testing of boron solution concentration in the standby liquid control system
- Inadequate testing to detect failures of safety-related pneumatic components or systems
- Inadvertent containment spray due to personnel error
- Inadvertent defeat of safety function caused by human error involving wrong unit, wrong train, or wrong system
- Inadvertent isolation of containment spray systems
- Inadvertent loss or improper actuation of safety-related equipment
- Inadvertent reduction in primary coolant inventory in boiling water reactors during shutdown and startup
- Incident involving teletherapy unit (AECL Eldorado-78)
- Incorrect boron standards
- Incorrect maintenance procedure on traversing incore probe lines
- Increased monitoring of certain patients with implanted Coratomic, Inc, model C-100 and C-101 nuclear-powered cardiac pacemakers
- Increased stroking time of Bettis actuators because of swollen ethylene-propylene rubber seals and seal set
- Increasing frequency of drug-related incidents
- Independent verification
- Indication of low water level in the Oyster Creek reactor
- Information concerning the use of Loctite 242 and other anaerobic adhesive/sealants
- Information for licensee regarding the Chernobyl Nuclear Plant Accident
- Inoperable containment atmosphere sensing systems
- Instrument failure causes opening of PORV and block valve
- Interconnection of contaminated systems with service air systems used as the source of breathing air
- Intergranular stress corrosion cracking leading to steam generator tube failure
- Isolation between signals of the protection system and non-safety-related equipment
- Isolation of reactor coolant system from low-pressure systems outside containment
- Jail term for former contractor employee who intentionally falsified welding inspection records
- Jammed source rack in a gamma irradiator
- Lack of detailed instruction and inadequate observance of precautions during maintenance and testing of diesel generator Woodward governors
- Lead shielding attached to safety-related systems without 10 CFR 50.59 evaluations
- Leak of reactor water to reactor building caused by scram solenoid valve problem
- Leaking and dislodged iodine-125 implant seeds
- Lessons learned from NRC inspections of fire protection SafeShutdown systems (10 CFR 50, Appendix R)
- Licensed fuel facility status report
- Licensee control of contracted services providing training
- Licensee event report (LER) format modification
- Lightning strikes at nuclear power generating stations
- Limitorque HOBC, H1BC, H2BC, and H3BC gearheads
- Limitorque valve geared limit switch lubricant
- Load sequencers for emergency diesel generators
- Locking devices inadequately installed on main steam isolation valves
- Loose parts in the secondary side of steam generators at pressurized water reactors
- Loose parts obstruct control rod drive mechanism
- Loose phosphor in Panasonic 800 series badge thermoluminescent dosimeter (TLD) elements
- Loosening of locking nut on Limitorque operator
- Loss of all AC power
- Loss of decay heat removal capability at Davis-Besse Unit 1 while in a refueling mode
- Loss of high head safety injection emergency boration and reactor coolant makeup capability
- Loss of nonsafety-related reactor coolant system instrumentation during operation
- Loss of offsite power caused by problems in fiber optics systems
- Loss of safety injection capability
- Loss of suction to emergency feedwater pumps
- Loss of suction to low-pressure service water system pumps resulting from loss of siphon
- Loss of thermal sleeves in reactor coolant system piping at certain Westinghouse Pwr power plants
- Lost iridium-192 source resulting in the death of eight persons in Morocco
- Lost parts in primary coolant system
- Low-level radioactive waste burial criteria
- Low-level radioactive waste scaling factors, 10 CFR Part 61
- Lower reactor vessel head insulation support problem
- Main steam isolation valve (MSIV) leakage
- Main steam isolation valve closure logic
- Main steam line break effect on environmental qualification of equipment
- Main steam safety valve failures caused by failed cotter pins
- Main steam safety valve test failures and ringed setting adjustments
- Main transformer failures at the North Anna Nuclear Power Station
- Main turbine electrohydraulic control system
- Malfunction of a dry-storage, panoramic, gamma exposure irradiator
- Malfunction of solenoid valves manufactured by VALCOR Engineering Corporation
- Malfunctions of ITT Barton model 580 series switches during requalification testing
- Maloperation of Gould-Brown Boveri 480 volt-type K-600s and K-DON 600s circuit breakers
- Methodology for evaluation of emergency response facilities, draft report for comment
- Microbiologically induced corrosion of containment service water system
- Misadministrations to patients undergoing thyroid scans
- Misapplication of generic emergency operating procedures (EOP) guidelines
- Misapplication of valves by throttling beyond design range
- Missing jumpers from Westinghouse reactor protection system cards for the over-power delta temperature trip function
- Miswiring in a Westinghouse rod control system
- Modification of solid state AC undervoltage relays type ITE-27
- Molybdenum breakthrough from technetium-99m generators
- Motor-operated valve failures due to hammering effect
- Motor-operated valve torque switches set below the manufacturer's recommended value
- NIOSH recall of recirculating-mode (closed circuit) self-contained breathing apparatus (rebreather)
- NRC enforcement policy--NRC licensed individuals
- NRC on-scene response during a major emergency
- NRC position of electrical cable support systems
- Need to environmentally qualify epoxy grouts and sealers
- Nonconforming pipe support struts
- Nonconforming structural steel for safety-related use
- Nonconformities with materials supplied by Tube Line Corporation
- Nonidentical replacement parts
- Nonrepresentative sampling of contaminated oil
- Notification of significant events at operating power reactor facilities
- Notification of the Nuclear Regulatory Commission (NRC
- Notifications to the NRC Operations Center and reporting events in licensee event reports
- Nuclear incident at Three Mile Island
- Open equalizing valve of differential pressure transmitter causes reactor scram and loss of redundant safety signals
- Operability of required auxiliary equipment
- Operating a nuclear power plant at voltage levels lower than analyzed
- Operating experience related to moisture intrusion in safety-related electrical equipment at commercial power plants
- Operating problems with solenoid operated valves at nuclear power plants
- Operation of emergency diesel generators
- Operational response to events concerning deliberate acts directed against plant equipment
- Overexposure of diver during work in fuel storage pool
- Overexposure of diver in pressurized water reactor (PWR) refueling cavity
- Overexposures in PWR cavities
- Overloading of structural elements due to pipe support loads
- Overpressurization of containment of a PWR plant after a main steam line break
- Overpressurization of reactor coolant system
- PWR auxiliary feedwater pump turbine control problems
- PWR low temperature overpressure protection
- Partial loss of AC power and diesel generator degradation
- Partial loss of non-nuclear instrument system power supply during operation
- Performance of NRC licensed individuals whke on duty
- Physical qualification of individuals to use respiratory protective devices
- Pipe cracks in stagnant borated water systems at PWR plants
- Pipe whip restraints
- Piping thermal deflection induced by stratified flow
- Plant transients induced by failure of non-nuclear instrumentation power
- Portable moisture/density gauges : recent incidents and common violations of requirements for use, transportation, and storage
- Possible failures of General Electric type HFA relays
- Possible loss of emergency notification system due to loss of AC power
- Possible occupational health hazard associates with closed cooling systems for operating power plants
- Possible seismic vulnerability of old lead storage batteries
- Possible sticking of ASCO solenoid valves
- Possible weapons smuggling pouch
- Posttensioned containment tendon anchor head failure
- Potential damage to redundant safety equipment as a result of backflow through the equipment and floor drain
- Potential deficiencies in environmental qualification of Limitorque motor valve operator wiring
- Potential deficiency in improperly rated field wiring to solenoid valves
- Potential deficiency in motor-operated valve control circuits and annunciation
- Potential deficiency of certain AGASTAT E-7000 series time-delay relays
- Potential effect of line-induced vibration on certain target rock solenoid-operated valves
- Potential failure of BWR backup manual scram capability
- Potential failure of all emergency diesel generators
- Potential failures of General Electric PK-2 test blocks
- Potential failures of Westinghouse Electric Corporation type SA-1 differential relays
- Potential falsification of test reports on flanges manufactured by Golden Gate Forge and Flange, Inc
- Potential for common-mode failure of standby gas treatment system on loss of off-site power
- Potential for failure of replacement AC coils supplied by the Westinghouse Electric Corporation for use in class 1E motor starters and contactors
- Potential for loss of minimum flow paths leading to ECCS pump damage during a LOCA
- Potential for loss of water from the refueling cavity
- Potential for unacceptable interaction between the control rod drive scram function and non-essential control air at certain GE BWR facilities
- Potential for water hammer during restart of residual heat removal
- Potential hazards associated with interchangeable parts on radiographic equipment
- Potential inaccuracies in wide range pressure instruments used in Westinghouse designed plants
- Potential loss of direct access to ultimate heat sink
- Potential loss of solid-state instrumentation following failure of control room cooling
- Potential misassembly problem with Automatic Switch Company (ASCO) solenoid valve model NP 8316
- Potential overstress of shafts on Fisher series 9200 butterfly valves with expandable T rings
- Potential problem with water-soluble purge dam materials used during inert gas welding
- Potential problems in Westinghouse molded case circuit breakers equipped with a shunt trip
- Potential problems in generators manufactured by Electrical Products Incorporated
- Potential seismic interaction involving the movable in-core flux mapping system used in Westinghouse designed plants
- Potentially significant equipment failures resulting from contamination of air-operated systems
- Primary containment isolation valve discrepancies
- Problems noted in control room emergency ventilation systems
- Problems resulting in erroneously high reading with Panasonic 800 Series thermoluminescent dosimeters
- Problems with design, maintenance, and operation of offsite power systems
- Problems with liquid nitrogen cooling components below the nil ductility temperature
- Problems with silver zeolite sampling of airborne radioiodine
- Prompt reporting of information in accordance with 10 CFR 50.55(e)
- Pump shaft fatigue cracking
- Qualification of systems
- Quality control of onsite dewatering/solidification operations by outside contractors
- Quality control problems of meteorological measurements programs
- RCIC and HPCI turbine exhaust check valve failures
- RHR valve misalignment causes degradation of ECCS in PWRS
- Radiation exposure from gloves contaminated with uranium daughter products
- Radioactive waste gas system events
- Radiography events at power reactors
- Ray Miller, Inc
- Reactor coolant pump shaft failure at Crystal River
- Reactor mode switch malfunctions
- Reactor trip breaker malfunctions (undervoltage trip devices on GE Type AK-2-25 breakers)
- Reactor trips at Turkey Point Units 3 and 4
- Recent Identified problems with Limitorque motor operators
- Recent emergency diesel generator problems
- Recent engine failures of emergency diesel generators
- Recent fuel handling events
- Recent hammer events
- Recent serious violations of NRC requirements by medical licensees
- Recent serious violations of NRC requirements by moisture density gauge licensees
- Recent serious violations of NRC requirements by radiography licensees
- Recent serious violations of NRC requirements by well-logging licensees
- Recent snubber inservice testing with high failure rates
- Recognition of American Society of Mechanical Engineers accreditation program for N stamp holders
- Reconcentration of radionuclides involving discharges into sanitary sewage systems permitted under 10 CFR 20.303
- Reduction of reactor coolant inventory because of misalignment of RHR valves
- Relay calibration problem
- Reliability of main steam safety valves
- Reliance on water level instrumentation with a common reference leg
- Remarks presented (questions/answers discussed) at public regional meetings to discuss regulations (10 CFR part 21) for reporting of defects and noncompliance, July 12-26, 1977
- Repetitive failures of Limitorque operator SMB-4 motor-to-shaft key
- Replacement diaphragms for Robertshaw valve (model no. VC-210
- Reporting of defects and noncompliance, 10 CFR Part 21
- Reporting of radiological releases
- Request for collection of licensee radioactivity measurements attributed to the Chernobyl Nuclear Plant Accident
- Respirator user warning : defective self-contained breathing apparatus air cylinders
- Respirator users notice : increased inspection frequency for certain self-contained breathing apparatus air cylinders
- Respirator users notice for certain 5-minute emergency escape self-contained breathing apparatus
- Respirator users notice: defective self-contained breathing apparatus air cylinders
- Respirator users warning for certain 5-minute emergency escape self-contained breathing apparatus
- Response time of scram instrument volume level detectors
- Results of the NRC-sponsored qualification methodology research test on ASCO solenoid valves
- Reversed differential pressure instrument sensing lines
- Revised emergency exercise frequency rule
- Robertshaw thermostatic flow control valves
- Rosemount differential pressure transmitter zero point shift
- Rupture of a nominal 40-millicurie iodine-125 brachytherapy seed causing significant spread of radioactive contamination
- Rupture of americium-241 source(s) contained in a well logging device
- Rupture of cesium-137 source used in well-logging operations
- Rupture of radwaste
- Safety and security of irradiators
- Safety parameter display system malfunctions
- Safety suggestions from employees
- Sampling and prevention of intrusion of organic chemicals into reactor coolant systems
- Scheduling of pre-licensing emergency preparedness exercises
- Scram solenoid pilot valve (SSSPV) rebuild kit problems
- Seal table leaks at PWRs
- Section 235 and 236 amendments to the Atomic Energy Act of 1954
- Segregation of hazardous and low-level radioactive wastes
- Seismic qualification of Westinghouse AR relay with latch attachments used in system
- Separation of electrical cables for HPCI and ADS
- Separation of primary reactor coolant pump shaft and impeller
- Service degradation of thick wall stainless steel recirculation system piping at a BWR plant
- Service life of relays in safety-related systems
- Shaft seal packing causes binding in main steam swing disc check and isolation valves
- Skylab reentry
- Source holder assembly damage from misfit between assembly and reactor upper grid plate
- Spill of radioactively contaminated resin
- Spurious system isolations caused by Panalarm model 86 thermocouple monitor
- Standby gas treatment system heater high temperature trip setpoint adjustment
- Standby gas treatment system problems
- Standby liquid control system squib valves failure to fire
- Station battery problems
- Steam binding of auxiliary feedwater pumps
- Storage and handling of ophthalmic beta radiation applicators
- Stress analysis of safety-related piping
- Stress corrosion cracking in nonsensitized 316 stainless steel
- Stress corrosion cracking in pressurized water reactor systems
- Stuck control rod
- Surveillance of flow in RTD bypass loops used in Westinghouse plants
- Surveillance of hydraulic snubbers
- Surveys of wastes before disposal from nuclear reactor facilities
- Systems interaction event resulting in reactor system safety relief valve opening following a fire-protection deluge system malfunction
- TMI-1 steam generator/reactor coolant system chemistry/corrosion problem
- Target Rock two-stage SRV setpoint drift
- Telephone numbers to the NRC Operations Center and regional offices
- Teletherapy unit full calibration and qualified expert requirements (10 CFR 35.23 and 10 CFR 35.24)
- Teletherapy unit malfunction
- Temporary strainers left installed in pump suction piping
- Test failures or electrical penetration assemblies
- The States Company sliding link electrical terminal block
- Therapy misadministrations to patients undergoing cobalt-60 teletherapy treatments
- Time/current trip curve discrepancy of ITE/Siemens-Allis molded case circuit breaker
- Timely declaration of an emergency class, implementation of an emergency plan, and emergency notifications
- Traceability and material control of material and equipment, particularly fasteners
- Training program deficiencies
- Transamerica Delaval diesel generator crankshaft failure
- Transfer and/or disposal of spent generators
- Transformer failure resulting from degraded internal connection cables
- Transient due to loss of power to integrated control system at a pressurized water reactor designed by Babcock & Wilcox
- Transportation of pyrophoric uranium
- Transportation of radiography devices
- Transportation of type a quantities of non-fissile radioactive material
- Two events involving unauthorized entries into PWR reactor cavities
- Unanalyzed post-LOCA release paths
- Unauthorized service on teletherapy units by nonlicensed maintenance personnel
- Unauthorized transfer and loss of control of industrial nuclear gauges
- Uncontrolled leakage of reactor coolant outside containment
- Underground pathways into protected areas, vital areas, material access areas, and controlled access areas
- Underrated fuses which may adversely affect operation of essential electrical equipment
- Underrated terminal blocks that may adversely affect operation of essential electrical equipment
- Underresponse of radiation survey instrument to high radiation fields
- Undersized nozzle-to-shell welded joints in tanks and heat exchangers constructed under the rules of the Asme Boiler and Pressure Vessel Code
- Undetected unavailability of the turbine-driven auxiliary feedwater train
- Unit startup with degraded high pressure safety injection system
- Unnecessary radiation exposures to the public and workers during events involving thickness and level measuring devices
- Update of failure of automatic sprinkler system valves to operate
- Use of improper materials in safety-related components
- Use of incorrect amplified response spectra (ARS)
- Use of lifted leads and jumpers during maintenance or surveillance testing
- Use of portable radio transmitters inside nuclear power plants
- Use of sealing compounds in an operating system
- Use of specialized "stiff" pipe clamps
- Use of unqualified sources in well logging applications
- Vacuum relief system for boiling water reactor Mark I and Mark II containments
- Valve stem corrosion failures
- Valve-shaft-to-actuator key may fall out of place when mounted below horizontal axis
- Various battery problems
- Velan swing check valves
- Vibration-induced valve failures
- Water leaking from uranium hexafluoride overpacks
- Welds in main control panels
- Westinghouse NBFD relay failures in reactor protection systems
- Westinghouse NBFD relay failures in reactor protection systems at certain nuclear power plants
- Westinghouse type DS circuit breakers, potential failure of electric closing feature because of broken spring release latch lever
- Access control at nuclear facilities
Focus of
No resources found
No enriched resources found
Issuing body of
No resources found
No enriched resources found
- 8X8R water rod lower end plug wear
- Access control at nuclear facilities
- Lack of detailed instruction and inadequate observance of precautions during maintenance and testing of diesel generator Woodward governors
- Lead shielding attached to safety-related systems without 10 CFR 50.59 evaluations
- Qualification of systems
- Actuation of ECCS in the recirculation mode while in hot shutdown
- Actuation of fire suppression system causing inoperability of safety-related equipment
- Quality control of onsite dewatering/solidification operations by outside contractors
- Leak of reactor water to reactor building caused by scram solenoid valve problem
- Actuation of fire suppression system causing inoperability of safety-related ventilation equipment
- Age/environment induced electrical cable failures
- Leaking and dislodged iodine-125 implant seeds
- Use of incorrect amplified response spectra (ARS)
- Air/gas entrainment events resulting in system failures
- Lessons learned from NRC inspections of fire protection SafeShutdown systems (10 CFR 50, Appendix R)
- Alleged use of stand-ins for welder qualification tests
- Quality control problems of meteorological measurements programs
- Alternate rod Insertion for BWR scram represents a potential path for loss of primary coolant
- Transportation of radiography devices
- Anchorage and support of safety-related electrical equipment
- Licensee control of contracted services providing training
- Apparent improper modification of a component affecting plant safety
- Apparently improper use of commercial grade components in safety-related systems
- RCIC and HPCI turbine exhaust check valve failures
- Applicability of 10 CFR 21 to consulting firms providing training
- Licensee event report (LER) format modification
- Assessment of intakes of radioactive material by workers
- Spurious system isolations caused by Panalarm model 86 thermocouple monitor
- Standby gas treatment system heater high temperature trip setpoint adjustment
- Attempted damage to new fuel assemblies
- Auditability of electrical equipment qualification records at licensees' facilities
- Lightning strikes at nuclear power generating stations
- Limitorque HOBC, H1BC, H2BC, and H3BC gearheads
- Auxiliary feed pump turbine bearing failures
- Auxiliary feedwater pump lockout resulting from Westinghouse W-2 switch circuit modification
- RHR valve misalignment causes degradation of ECCS in PWRS
- Limitorque valve geared limit switch lubricant
- Auxiliary feedwater sparger and pipe hanger damage
- Transportation of type a quantities of non-fissile radioactive material
- Axial (longitudinal) oriented cracking in piping
- BBC Brown Boveri low-voltage K-line circuit breakers, with deficient overcurrent trip devices models OD-4 and 5
- Load sequencers for emergency diesel generators
- Radiation exposure from gloves contaminated with uranium daughter products
- BWR fuel exposure in excess of limits
- BWR high-pressure coolant injection (HPCI) initiation seal-in and indication
- Westinghouse NBFD relay failures in reactor protection systems
- BWR post-scram drywell pressurization
- Loose parts in the secondary side of steam generators at pressurized water reactors
- Radioactive waste gas system events
- Backup telephone numbers to the NRC Operations Center
- Boiling water reactor safety/relief valve failures
- Radiography events at power reactors
- Boron dilution of reactor coolant during steam generator decontamination
- Loose parts obstruct control rod drive mechanism
- Loose phosphor in Panasonic 800 series badge thermoluminescent dosimeter (TLD) elements
- Breach of containment integrity
- Standby gas treatment system problems
- Breakdowns in contamination control programs
- Broken inner-external closure springs on Atwood & Morrill main steam isolation valves
- Loosening of locking nut on Limitorque operator
- Broken studs on terry turbine steam inlet flange
- Standby liquid control system squib valves failure to fire
- Buildup of enriched uranium in effluent treatment tanks
- Loss of all AC power
- Buildup of enriched uranium in ventilation ducts and associated effluent treatment systems
- Ray Miller, Inc
- Loss of decay heat removal capability at Davis-Besse Unit 1 while in a refueling mode
- Calibration of liquid level instruments
- Reactor coolant pump shaft failure at Crystal River
- Calibration problems - Eberline Instrument model 6112b analog teletectors
- Two events involving unauthorized entries into PWR reactor cavities
- Change in NRC practice regarding issuance of confirming letters to principal contractors
- Loss of high head safety injection emergency boration and reactor coolant makeup capability
- Change in format and distribution system for Ie Bulletins, Circulars, and Information Notices
- Check valve failures
- Reactor mode switch malfunctions
- Loss of nonsafety-related reactor coolant system instrumentation during operation
- Check valve failures on diesel generator engine cooling system
- Station battery problems
- Check valve problems
- Checklist for licensees making notifications of significant events in accordance with 10 CFR 50.72
- Loss of offsite power caused by problems in fiber optics systems
- Chemical cleaning of steam generators at Millstone 2
- Reactor trip breaker malfunctions (undervoltage trip devices on GE Type AK-2-25 breakers)
- Chloride contamination of safety related piping and components
- Loss of safety injection capability
- Use of lifted leads and jumpers during maintenance or surveillance testing
- Circuit breaker position verification
- Loss of suction to emergency feedwater pumps
- Clarification of certain requirements for exclusive-use shipments of radioactive materials
- Loss of suction to low-pressure service water system pumps resulting from loss of siphon
- Clarification of conditions for waste shipments subject to hydrogen gas generation
- Clarification of emergency plan exercise requirements