U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation
Label
U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation
Name
U.S. Nuclear Regulatory Commission
Subordinate unit
Office of Nuclear Reactor Regulation
Actions
Incoming Resources
- Metal-clad circuit breaker maintenance issues identified by NRC inspections
- Failures of voltage-dropping resistors in the power supply circuitry of electric governor systems
- Overgreasing of electric motor bearings
- Inadequate fire suppression system testing
- Potential overpressurization of main steam system
- Natural gas hazards at Fort St. Vrain Nuclear Generating Station
- Construction-related experience with flood protection features
- Fuel damage during cleaning at a foreign pressurized water reactor
- Crack in weld area of reactor coolant system hot leg piping at V.C. Summer
- Flow blockage of cooling water to safety system components
- Generic environmental impact statement for license renewal of nuclear plants, supplement 53, regarding Sequoyah nuclear plant, units 1 and 2 : draft report for comment
- Dual-unit scram at Peach Bottom units 2 and 3
- Recent operator performance issues at nuclear power plants
- Component cooling water system gas accumulation and other performance issues
- Single failures in auxiliary feedwater systems
- Emergency response data system test schedule revised
- Depressurization of reactor coolant systems in pressurized-water reactors
- Hydrogen combustion events in foreign BWR piping
- Defective molded phenolic armature carriers found in Elmwood contactors
- Failures reported in Eaton/Cutler Hammer A200 and Freedom Series contactors
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 59
- Lasalle Unit 2 loss of recirculation pumps with power oscillation event
- Potential vulnerabilities of time-reliant computer-based systems due to change in daylight saving time dates
- Recent issues identified when using reverse engineering techniques in the procurement of safety-related components
- Questionable certification of fasteners
- Event report guidelines, 10 CFR 50.72(b)(3)(xiii), draft report for comment, prepared by Aaron Lewin
- Reactor vessel top guide and core plate cracking
- Fire in annunciator control cabinets
- Inadequate test procedure fails to detect inoperable criticality accident alarm horns
- Potential failures of thermostatic control valves for diesel generator jacket cooling water
- Unanticipated effect of ventilation system on tank level indications and engineering safety features actuation system setpoint
- Emergency diesel generator vulnerability to failure from cold fuel oil
- Failure of primary system compression fitting
- Potential flooding through unsealed concrete floor cracks
- Impacts on normal plant operations due to leaks or spills of chemicals
- Disposition of public comments on the draft subsequent license renewal guidance documents NUREG-2191 and NUREG-2192
- Degradation of wire rope used in fuel handling applications
- Marking, handling, control, storage and destruction of safeguards information
- Potential loss of safe shutdown equipment due to premature silicon controlled rectifier failure
- Recent issue with the definition of core quadrant
- Problems with diaphragms in safety-related tanks
- Degradation of leak-chase channel systems for floor welds of metal containment shell and concrete containment metallic liner
- Results of thermo-lag 330-1 combustibility testing
- Effects of thermal aging on fracture toughness and charpy-impact strength of stainless steel pipe welds, prepared by D.J. Gavenda [and four others]
- Inadequate design and installation of seismic-gap fire barriers
- Intravascular brachytherapy misadministrations
- Inadequate control of temporary modifications to safety-related systems
- Potential loss of net positive suction head (NPSH) of standby liquid control system pumps
- Improper installation of instrumentation modules
- Malfunction of a pressurized code safety valve
- Creator of22
- Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, docket nos. 50-390 and 50-391, Tennessee Valley Authority
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 55
- Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Unite 2, docket no. 50-391, Tennessee Valley Authority
- Generic environmental impact statement for license renewal of nuclear plants, regarding Monticello nuclear generating plant, draft report, Supplement 26
- Generic environmental impact statement for license renewal of nuclear plants, supplement 54, regarding Byron Station, units 1 and 2 : draft report for comment
- Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, docket nos. 50-390 and 50-391, Tennessee Valley Authority
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 55
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 57
- Safety evaluation report related to the operation of Watts Bar Nuclear Plant, unit 2, docket number 50-391, Tennessee Valley Authority
- Final environmental statement, related to the operation of Watts Bar Nuclear Plant, unit 2, supplement 2, final report
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 53
- Environmental impact statement for the construction permit for the SHINE medical radioisotope production facility, draft report for comment
- Draft final environmental statement, Supplement 2
- Environmental impact statement for license renewal of the National Bureau of Standards Reactor, final report
- Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, docket nos. 50-390 and 50-391, Tennessee Valley Authority
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 46
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 38
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 56
- Generic environmental impact statement for license renewal of nuclear plants, supplement 50, regarding Grand Gulf Nuclear Powerplant, unit 1, draft report for comment
- Environmental impact statement for the construction permit for the SHINE medical radioisotope production facility, final report
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 54
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 52
- Focus of3
- Author of15
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 55
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 46
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 38
- Final environmental statement, related to the operation of Watts Bar Nuclear Plant, unit 2, supplement 2, final report
- Environmental impact statement for the construction permit for the SHINE medical radioisotope production facility, draft report for comment
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 53
- Draft final environmental statement, Supplement 2
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 54
- Environmental impact statement for the construction permit for the SHINE medical radioisotope production facility, final report
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 56
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 57
- Safety evaluation report related to the operation of Watts Bar Nuclear Plant, unit 2, docket number 50-391, Tennessee Valley Authority
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 55
- Generic environmental impact statement for license renewal of nuclear plants, supplement 54, regarding Byron Station, units 1 and 2 : draft report for comment
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 52
- Improper installation of instrumentation modules
- Generic environmental impact statement for license renewal of nuclear plants, supplement 53, regarding Sequoyah nuclear plant, units 1 and 2 : draft report for comment
- Inadequate control of temporary modifications to safety-related systems
- Depressurization of reactor coolant systems in pressurized-water reactors
- Natural gas hazards at Fort St. Vrain Nuclear Generating Station
- Inadequate fire suppression system testing
- Component cooling water system gas accumulation and other performance issues
- Incorrect relay used in emergency diesel generator output breaker control circuitry
- Overgreasing of electric motor bearings
- Single failures in auxiliary feedwater systems
- Disablement of turbine-driven auxiliary feedwater pump due to closure of one of the parallel steam supply valves
- Failures of voltage-dropping resistors in the power supply circuitry of electric governor systems
- Recent issues identified when using reverse engineering techniques in the procurement of safety-related components
- Failure of primary system compression fitting
- Safety evaluation report related to the license renewal of Davis-Besse Nuclear Power Station, supplement 1, docket nos. 50-346, FirstEnergy Nuclear Operating Company, Division of License Renewal, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
- Generic environmental impact statement for license renewal of nuclear plants, Supplement 59
- Fire in annunciator control cabinets
- Questionable certification of fasteners
- Potential loss of safe shutdown equipment due to premature silicon controlled rectifier failure
- Failures reported in Eaton/Cutler Hammer A200 and Freedom Series contactors
- Partial plugging of suppression pool strainers at a foreign BWR
- Degradation of leak-chase channel systems for floor welds of metal containment shell and concrete containment metallic liner
- Potential failures of thermostatic control valves for diesel generator jacket cooling water
- Isolation transfer switches and post-fire shutdown capability
- Results of thermo-lag 330-1 combustibility testing
- Problems with diaphragms in safety-related tanks
- Technical bases for changes in the subsequent license renewal guidance documents NUREG-2191 and NUREG-2192
- Impacts on normal plant operations due to leaks or spills of chemicals
- Loss of emergency boration capability due to nitrogen gas intrusion
- Disposition of public comments on the draft subsequent license renewal guidance documents NUREG-2191 and NUREG-2192
- Water leakage from yard area through conduits into buildings
- Defective molded phenolic armature carriers found in Elmwood contactors
- Flow blockage of cooling water to safety system components
- Potential loss of net positive suction head (NPSH) of standby liquid control system pumps
- Effects of thermal aging on fracture toughness and charpy-impact strength of stainless steel pipe welds, prepared by D.J. Gavenda [and four others]
- Potential problems from the use of space heaters
- Pump wear and foreign objects in plant piping systems
- Standard review plan on power reactor licensee financial qualifications and decommissioning funding assurance
- Consideration of thermal conditions in the design and installation of supports for diesel generator exhaust silencers
- Lasalle Unit 2 loss of recirculation pumps with power oscillation event
- Marking, handling, control, storage and destruction of safeguards information
- Recent issue with the definition of core quadrant
- Improper reset causes emergency diesel generator failures
- Event report guidelines, 10 CFR 50.72(b)(3)(xiii), draft report for comment, prepared by Aaron Lewin
- Failure of remote shutdown system instrumentation because of incorrectly installed components
- Slower-than-expected rod-drop times
- Battery and battery charger short-circuit current contributions to a fault on the direct current distribution system
- Reactor trip breaker, Westinghouse model DS-416, failed to open on manual initiation from the control room
- Emergency action level thresholds outside the range of radiation monitors
- Final results of the hydrogen igniter experimental program, prepared by W. E. Lowry, B. R. Bowman, B. W. Davis