Nuclear power plants -- United States -- Safety measures
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Nuclear power plants -- United States -- Safety measures
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- Weakness in emergency operating procedures found as result of steam generator tube rupture
- "Functional criteria for emergency response facilities", NUREG-0696
- 2002 Davis-Besse reactor pressure vessel head degradation knowledge management digest
- A Consensus estimation study of nuclear power plant structural loads
- A Measurement control program for nuclear material accounting
- A Methodology for allocating nuclear power plant control functions to human or automatic control
- A Reliability program for emergency diesel generators at nuclear power plants
- A Scoping study of the potential effectiveness of an operational safety reliability program in addressing generic safety problems
- A digraph-fault tree methodology for the assessment of material control systems
- A method to characterize local meteorology at nuclear facilities for application to emergency response needs
- A methodology to assist in contingency planning for protection of nuclear power plants against land vehicle bombs
- A procedure for conducting a human reliability analysis for nuclear power plants : draft report
- A procedure for conducting a human reliability analysis for nuclear power plants : final report
- A review of issues related to improving nuclear power plant diesel generator reliability
- A review of nuclear safety in light of the impact of natural disasters on Japanese nuclear facilities : hearing before a subcommittee of the Committee on Appropriations, United States Senate, One Hundred Twelfth Congress, second session, special hearing, March 30, 2011, Washington, DC
- A review of regulatory requirements governing control room habitability systems
- A risk analysis of fixed nuclear gauges
- A short history of fire safety research sponsored by the U.S. Nuclear Regulatory Commission, 1975-2008
- A survey of the state-of-the-art in aging of electronics with application to nuclear power plant instrumentation
- Aging and service wear of hydraulic and mechanical snubbers used on safety-related piping and components of nuclear power plants
- Aging nuclear power plants : managing plant life and decommissioning
- Air/gas entrainment events resulting in system failures
- Allowable shipment frequencies for the transport of toxic gases near nuclear power plants
- Allowable shipment frequencies for the transport of toxic gases near nuclear power plants
- Alternative approaches to providing engineering expertise on shift
- An Assessment of the safety implications of control at the Oconee 1 Nuclear Plant : final report
- An Empirical analysis of selected nuclear power plant maintenance factors and plant safety
- An analysis of evacuation time estimates around 52 nuclear power plant sites
- An analysis of the NRC safety goals for nuclear power
- An empirical assessment of near-source strong ground motion for a 6.6 mb (7.5 Ms) earthquake in the Eastern United States
- Analysis of balance-of-plant regulatory issues : final report
- Analysis of reactor trips originating in balance of plant systems
- Annotated bibliography of safety-related events at boiling-water nuclear power plants as reported in 1977
- Apparent improper modification of a component affecting plant safety
- Apparently improper use of commercial grade components in safety-related systems
- Application of SLIM-MAUD : a test of an interactive computer-based method for organizing expert assessment of human performance and reliability
- Application of Sandia physical protection methods
- Assessment of emergency response planning and implementation for large scale evacuations
- Assessment of modular construction for safety-related structures at advanced nuclear power plants
- Assessment of system interaction experience in nuclear power plants
- Assurance of equipment operability and containment integrity during design-basis accident conditions
- Availability of NUREG-0933 "A Prioritization of generic safety issues"
- Availability of supplement 1 to NUREG-0933,"A Prioritization of generic safety issues"
- Availability of supplement 4 to NUREG-0933, "A Prioritization of generic safety issues"
- Availability of supplements 2 and 3 to NUREG-0933, "A Prioritization of generic safety issues"
- Backfitting guidelines
- Barrier integrity research program : final report
- Boron flushing during a BWR anticipated transient without scram
- Breakdowns in contamination control programs
- Bubble behavior in LMFBR core disruptive accidents : annual report, October 1979 - September 1980
- Buoyancy, transport, and head loss of fibrous reactor insulation
- Bypassed and inoperable status indication for nuclear power plant safety systems
- Capacity of nuclear power plant structures to resist blast loadings
- Clarification of TMI action plan requirements
- Clarification of TMI action plan requirements : requirements for emergency response capability
- Clarification to Generic Letter 81-07 regarding response to NUREG-0612, "Control of heavy loads at nuclear power plants"
- Closeout of IE Bulletin 79-15 : deep draft pump deficiencies
- Closeout of IE bulletin 79-11 : faulty overcurrent trip device in circuit breakers for engineered safety systems
- Closeout of IE bulletin 80-15 : possible loss of Emergency Notification System (ENS) with loss of offsite power
- Closeout of IE bulletin 80-25 : operating problems with Target Rock safety-relief valves at boiling water reactors : final report
- Closeout of IE bulletin 82-04 : deficiencies in primary containment electrical penetration assemblies
- Closeout of IE bulletin 83-03 : check valve failures in raw water cooling systems of diesel generators
- Commercial-grade structural framing components supplied as nuclear safety-related equipment
- Common-cause failure database and analysis system
- Common-cause failure database and analysis system : event data collection, classification, and coding
- Common-cause failure parameter estimations
- Compendium of cost-effectiveness evaluations of modifications for dose reduction at nuclear power plants
- Compilation of health physics related information Items
- Completion of phase II of "Control of heavy loads at nuclear power plants" NUREG-0612
- Considerations on nuclear data link implementation in relation to the technical support center, emergency operations facility and safety parameter display system
- Containment penetration system (CPS) tests under accident loads
- Control of heavy loads
- Control of heavy loads
- Control of heavy loads at nuclear power plants : resolution of Generic Technical Activity A-36
- Controlling principles for prior probability assignments in nuclear risk assessment
- Crediting of operator actions in place of automatic actions and modifications of operator actions, including response times
- Criteria for preparation and evaluation of radiological emergency response plans and preparedness in support of nuclear power plants
- Criteria for preparation and evaluation of radiological emergency response plans and preparedness in support of nuclear power plants : criteria for emergency planning in an early site permit application, draft report for comment
- Criteria for preparation and evaluation of radiological emergency response plans and preparedness in support of nuclear power plants : criteria for utility offsite planning and preparedness, final report
- Criteria for preparation and evaluation of radiological emergency response plans and preparedness in support of nuclear power plants : guidance for protective action strategies
- Criteria for safety-related nuclear plant operator actions : a preliminary assessment of available data
- Criteria for safety-related nuclear power plant operator actions : 1982 pressurized water reactor (PWR) simulator exercises
- Criteria for safety-related nuclear power plant operator actions : initial boiling water reactor (BWR) simulator exercises
- Criteria for safety-related nuclear power plant operator actions : initial pressurized water reactor (PWR) simulator exercises
- Criteria for safety-related nuclear power plant operator actions : initial simulator to field data calibration
- Critical excitation method for calculating earthquake effects on nuclear plant structures : an assessment study
- Data base on nuclear power plant dose reduction research projects
- Data summaries of licensee event reports of control rods and drive mechanisms at U.S. commercial nuclear power plants : January 1, 1972 to April 30, 1978
- Data summaries of licensee event reports of diesel generators at U.S. commercial nuclear power plants : January 1, 1976 to December 31, 1978
- Data summaries of licensee event reports of inverters at U.S. commercial nuclear power plants January 1, 1976 to December 31, 1982
- Data summaries of licensee event reports of pumps at U.S. commercial nuclear power plants : January 1, 1972 to April 30, 1978
- Data summaries of licensee event reports of valves at U.S. commercial nuclear power plants : January 1, 1976 to December 31, 1980
- Data summaries of licensee event reports of valves at U.S. commercial nuclear power plants : January 1, 1976-December 31, 1978
- Delayed access to safety-related areas and equipment during plant emergencies
- Demonstrating the feasibility and reliability of operator manual actions in response to fire : final report
- Design and testing deficiencies of tornado dampers at nuclear power plants
- Design provisions for tangential shear in containment walls
- Design-basis flood estimation for site characterization at nuclear power plants in the United States of America
- Development and testing of a model for fire potential in nuclear power plants
- Development and testing of a model for fire potential in nuclear power plants
- Development of a checklist for evaluating maintenance, test, and calibration procedures used in nuclear power plants
- Development, use, and control of maintenance procedures in nuclear power plants : problems and recommendations
- Diesel generator events
- Disposal of sludge from onsite sewage treatment facilities at nuclear power stations
- Effects of ethernet-based, non-safety related controls on the safe and continued operations of nuclear power stations
- Emergency diesel generator voltage regulator problems
- Emergency preparedness & incident response
- Emergency preparedness : NRC needs to better understand likely public response to radiological incidents at nuclear power plants : report to congressional requesters
- Emergency response data system test schedule revised
- Enhancement of the nuclear materials management and safeguards system : final report
- Evaluation of Generic issue 125.II.7, reevaluate provision to automatically isolate feedwater from steam generator during a line break
- Evaluation of aircraft crash hazards analyses for nuclear power plants
- Evaluation of emergency operating procedures for nuclear power plants
- Evaluation of loss of offsite power events at nuclear power plants, 1980-1996
- Evaluation of safety implications of control systems in LWR nuclear power plants : technical findings related to USI A-47
- Evaluation of severe accident risks and the potential for risk reduction
- Evaluation of systems interactions in nuclear power plants : technical findings related to unresolved safety issue A-17
- Evaluation of the prompt alerting systems at four nuclear power stations
- Evaluation of treatment of effects of debris in coolant on ECCS and CSS performance in pressurized water reactors and boiling water reactors
- Evaluation report : evaluation of NRC's oversight of tritium production at commercial nuclear power plants
- Experiment data report for semiscale Mod-2B power loss test series (tests S-PL-1, -2, and -3)
- FRANTIC II applications to standby safety systems
- Failure evaluation of General Electric SB-1 and SB-9 reactor mode switches
- Final report phase I systems interaction methodology applications program
- Final report, September 1975-September 1978 : radiation dose to construction workers at operating nuclear power plant sites
- Final report, assessment of potential phosphate ion-cementitious materials interactions
- Findings of the peer review panel on the draft reactor risk reference document, NUREG-1150
- Fire barrier penetration seals in nuclear power plants
- Fire protection research : quarterly progress report October-December 1977
- Fire protection research program corner effects tests
- Fire protection rule (45 FR 76602, November 19, 1980)
- Five additional TMI-2 related requirements--erata sheets to 5/7/80 letter
- Fumigation potential at inland and coastal power plant sites
- Functional criteria for emergency response facilities (NUREG-0696)
- Functional criteria for emergency response facilities, final report
- Guidance for the review of changes to human actions, final report
- Guidelines for preparing emergency procedures for nuclear power plants
- Guidelines on modeling common-cause failures in probabilistic risk assessment
- Handbook of human reliability analysis with emphasis on nuclear power plant applications : draft report for interim use and comment
- Handbook of parameter estimation for probabilistic risk assessment
- Handbook of parameter estimation for probabilistic risk assessment
- Hardening existing strategic special nuclear material storage facilities
- Hazardous material accidents near nuclear power plants : an evaluation of analyses and approaches
- Hazards of inerting atmospheres
- Historical summary of occupational radiation exposure experience in U.S. commercial nuclear power plants
- Human error probability estimation using licensee event reports
- Identification and analysis of human errors underlying electrical/electronic component related events reported by nuclear power plant licensees
- Impact of non-safety related electrical support system vulnerabilities on safety systems
- Implications of the accident at Chernobyl for safety regulation of commercial nuclear power plants in the United States, final report
- Importance of review and analysis of safeguards event logs
- Importance ranking based on aging considerations of components included in probabilistic risk assessments
- Inadequate or poorly-controlled, non-safety-related maintenance activities unnecessarily challenged safety systems
- Inadequate physical separation and electrical isolation of non-safety-related circuits from reactor protection system circuits
- Inadvertent criticality events at Oskarshamn and at U.S. nuclear power plants
- Independent verification
- Independent verification of the mitigating systems performance index (MSPI) results for the pilot plants, final report
- Indequate control over vehicular traffic at nuclear power plant sites
- Individual plant examination : submittal guidance, final report
- Individual plant examination for severe accident vulnerabilities--10 CFR 50.54(f)
- Individual plant examination program : perspectives on reactor safety and plant performance : draft report for comment
- Industry experience on certain materials used in safety-related equipment
- Insights into PRA methodologies
- Inspecting operating nuclear powerplants : shortcomings in the Nuclear Regulatory Commission program : fourth report together with additional views
- Integration of emergency action levels with combustion engineering emergency operating procedures : by use of Combustion Engineering Owners' Group : emergency operating procedure technical guidelines
- Intentional bypassing of automatic actuation of plant protective features
- Interim reliability evaluation program procedures guide
- Investigation of shell cracking on the steam generators at Indian Point, unit no. 3
- Issuance of supplement 1 to NUREG-1358, lessons learned from the special inspection program for emergency operating procedures (conducted October 1988-September 1991)
- Lessons from Fukushima one year later : NRC's implementation of recommendations for enhancing nuclear reactor safety in the 21st century : joint hearing before the Subcommittee on Clean Air and Nuclear Safety and the Committee on Environment and Public Works, United States Senate, One Hundred Twelfth Congress, second session, March 15, 2012
- Lessons learned tech specs
- Licensee control of contracted services providing training
- Licensee report of defective refurbished valves
- Load Combination Program Project II load combination methodology development, Interim report II
- Long-term research plan for human factors affecting safeguards at nuclear power plants
- Loose phosphor in Panasonic 800 series badge thermoluminescent dosimeter (TLD) elements
- Loose-part monitoring programs and recent operational experience in selected U.S. and Western European commercial nuclear power stations
- Low-level ionizing radiation : hearings before the Subcommittee on Energy Research and Production and the Subcommittee on Natural Resources and Environment of the Committee on Science and Technology, U.S. House of Representatives, Ninety-sixth Congress, first session, June 13, 14, 15, 1979
- Major alternatives for government policies, organizational structures, and actions in civilian nuclear reactor emergency management in the United States : report to M. Rogovin for the NRC Three Mile Island Special Inquiry
- Management of severe accidents
- Marking, handling, control, storage and destruction of safeguards information
- McGuire Nuclear Station Unit 1 auxiliary feedwater system reliability study evaluation
- Methodology for combining dynamic responses
- Methods for implementing revisions to emergency operating procedures
- Methods for review and evaluation of emergency procedure guidelines
- Methods of determining and controlling bias in nuclear material accounting measurements
- Molybdenum-99 breakthrough in molybdenum-99/technetium-99m generators
- Monitoring the random errors of nuclear material measurements
- Multiloop integral system test (MIST) : MIST facility functional specification
- Multiloop integral system test (MIST) : final report
- Multiple system responses program : identification of concerns related to a number of specific regulatory issues
- NRC authorization and legislative proposals : hearing before the Subcommittee on Energy and Mineral Resources of the Committee on Natural Resources, House of Representatives, One Hundred Third Congress, first session, on H.R. 2143, to authorize appropriations for the Nuclear Regulatory Commission for the fiscal years 1994 and 1995; H.R. 2170, to amend the Energy Reorganization Act of 1974 and the Atomic Energy Act of 1954 to enhance the safety and security of nuclear power facilities, and for other purposes : hearing held in Washington, DC, May 27, 1993
- NRC staff review of responses to I&E Bulletins 79-06 and 79-06a
- NRC's implementation of the Fukushima Near-Term Task Force recommendations and other actions to enhance and maintain nuclear safety : hearing before the Committee on Environment and Public Works, United States Senate, One Hundred Thirteenth Congress, second session, December 3, 2014
- NRC's implementation of the Fukushima Near-Term Task Force recommendations and other actions to enhance and maintain nuclear safety : hearing before the Committee on Environment and Public Works, United States Senate, One Hundred Thirteenth Congress, second session, June 4, 2014
- NRC's response to the report of the President's Commission on Three Mile Island : hearing before the Subcommittee on Energy and Power of the Committee on Interstate and Foreign Commerce, House of Representatives, Ninety-sixth Congress, first session, November 5, 1979
- National reliablity evaluation program (NREP) options study
- Near-term improvements for nuclear power plant control room annunciator systems
- New reactors : striving for enhanced safety
- No undue risk : regulating the safety of operating nuclear power plants
- Nonconservative inputs for boron dilution event analysis
- Nuclear Power Plant Alarm Prioritization (NPPAP) : program status report, January 1, 1983 to September 31, 1983
- Nuclear Regulatory Commission : oversight and status of implementing a risk-informed approach to fire safety : report to congressional requesters
- Nuclear Regulatory Commission : oversight of 2003 programs : hearing before the Subcommittee on Clean Air, Climate Change, and Nuclear Safety of the Committee on Environment and Public Works, United States Senate, One Hundred Eighth Congress, first session, February 13, 2003
- Nuclear Regulatory Commission : oversight of nuclear power plant safety has improved, but refinements are needed : report to congressional requesters
- Nuclear Regulatory Commission : preliminary observations on its process to oversee the safe operations of nuclear power plants : testimony before the Subcommittee on Oversight and Investigations, Committee on Energy and Commerce, U.S. House of Representatives
- Nuclear Regulatory Commission : strategy needed to develop a risk-informed safety approach : statement of Gary L. Jones, Associate Director, Energy, Resources, and Science Issues, Resources, Community, and Economic Development Division, before the Subcommittee on Clean Air, Wetlands, Private Property, and Nuclear Safety, Committee on Environment and Public Works, U.S. Senate
- Nuclear Regulatory Commission's licensing and relicensing process for nuclear plants : hearing before the Subcommittee on Clean Air and Nuclear Safety of the Committee on Environment and Public Works, United States Senate, One Hundred Tenth Congress, second session, July 16, 2008
- Nuclear employee safety concerns : allegation system offers better protection, but important issues remain : report to congressional requesters
- Nuclear energy : research, development, and new technologies roadmap
- Nuclear energy production in the coming decade : hearing before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, U.S. House of Representatives, Ninety-sixth Congress, first session, September 20, 1979
- Nuclear energy risk management : hearing before the Subcommittee on Investigations and Oversight joint with the Subcommittee on Energy and Environment, Committee on Science, Space, and Technology, House of Representatives, One Hundred Twelfth Congress, first session, Friday, May 13, 2011
- Nuclear power plant licensing process
- Nuclear power plant simulators : their use in operator training and requalification
- Nuclear power safety : industry concerns with federal whistleblower protection system : report to the chairman, Subcommittee on Oversight and Investigations, Committee on Commerce, House of Representatives
- Nuclear power safety reporting system : feasibility analysis
- Nuclear power safety reporting system : final evaluation results
- Nuclear power safety reporting system : implementation and operational specifications
- Nuclear powerplant safety : source terms
- Nuclear powerplant safety after Three Mile Island : report
- Nuclear regulation : progress made in emergency preparedness at Indian Point 2, but additional improvements needed : report to congressional requesters
- Nuclear regulation : strategy needed to regulate safety using information on risk : report to congressional requesters
- Nuclear research programs to ensure public health and safety
- Objective indicators of organizational performance at nuclear power plants
- Open secondary testing of window-type current transformers
- Operating experience and aging-seismic assessment of electric motors
- Operating experience feedback report : commercial power reactors
- Optimization of public and occupational radiation protection at nuclear power plants
- Optimization of public and occupational radiation protection at nuclear power plants
- Optimization of the control of contamination at nuclear power plants
- Organization and safety in nuclear power plants
- Organizational analysis and safety for utilities with nuclear power plants
- Oversight hearing : NRC's implementation of the Fukushima Near-Term Task Force recommendations and other actions to enhance and maintain nuclear safety : joint hearing before the Subcommittee on Clean Air and Nuclear Safety of the Committee on Environment and Public Works, United States Senate and the Committee on Environment and Public Works, United States Senate, One Hundred Thirteenth Congress, second session, January 30, 2014
- Oversight hearing : Nuclear Regulatory Commission : hearing before the Subcommittee on Clean Air and Nuclear Safety of the Committee on Environment and Public Works, United States Senate, One Hundred Eleventh Congress, second session, May 5, 2010
- Oversight hearing : the Nuclear Regulatory Commission's preliminary results of the Nuclear Safety Review in the United States following the emergency at the Fukushima Daiichi power plant in Japan : joint hearing before the Committee on Environment and Public Works, United States Senate and the Subcommittee on Clean Air and Nuclear Safety, One Hundred Twelfth Congress, first session, June 16, 2011
- Oversight of the Nuclear Regulatory Commission : hearing before the Subcommittee on Clean Air, Climate Change, and Nuclear Safety of the Committee on Environment and Public Works, United States Senate, One Hundred Eighth Congress, second session, May 20, 2004
- Oversight of the Nuclear Regulatory Commission : joint hearing before the Subcommittee on Energy and Power and the Subcommittee on Environment and the Economy of the Committee on Energy and Commerce, House of Representatives, One Hundred Fourteenth Congress, first session, September 9, 2015
- Oversight of the Nuclear Regulatory Commission : joint hearing before the Subcommittee on Energy and Power and the Subcommittee on Environment and the Economy of the Committee on Energy and Commerce, House of Representatives, One Hundred Fourteenth Congress, first session, September 9, 2015
- Oversight on the Nuclear Regulatory Commission : hearing before the Subcommittee on Clean Air, Climate Change, and Nuclear Safety and the Committee on Environment and Public Works, United States Senate, One Hundred Ninth Congress, first session, May 26, 2005
- Oversight on the regulatory processes for new and existing nuclear plants : hearing before the Subcommittee on Clean Air, Climate Change, and Nuclear Safety of the Committee on Environment and Public Works, United States Senate, One Hundred Ninth Congress, second session, June 22, 2006
- Periodic verification of design-basis capability of safety-related motor-operated valves
- Permissible radionuclide loading for organic ion exchange resins from nuclear power plants
- Personnel exposure from right cylindrical sources (PERCS) : the theory, the code, and examples
- Piping reliability model validation and potential use for licensing regulation development : piping reliability project
- Planning basis for the development of state and local government radiological emergency response plans in support of light water nuclear power plants
- Plans for improved safety of nuclear power plants following the Three Mile Island accident : hearing before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, U.S. House of Representatives, Ninety-sixth Congress, first session, September 19, 1979
- Plant operation beyond analyzed conditions
- Plant/site selection assessment report : seismic safety margins research program
- Potential failure of the instantaneous trip function of General Electric RMS-9 programmers
- Potential for high post-accident closed-cycle cooling water temperatures to disable equipment important to safety
- Potential for loss of automatic engineered safety feature actuation
- Potential nitrogen accumulation resulting from backleakage from safety injection tanks
- Potential pressure-locking of safety-related power-operated gate valves
- Potential unreviewed safety question on interaction between non-safety grade systems and safety grade systems
- Preliminary clarification of TMI action plan requirements
- Preliminary clarification of TMI action plan requirements--addendum to 9/5/80 letter
- Probabilistic safety analysis procedures guide
- Probability based load combination criteria for design of concrete containment structures
- Probability based load criteria for the design of nuclear structures : a critical review of the state-of-the-art
- Probability based load criteria for the design of nuclear structures : a critical review of the state-of-the-art
- Probability of pipe failure in the reactor coolant loops of Westinghouse PWR plants
- Probability of pipe fracture in the primary coolant loop of a PWR plant
- Procedural and submittal guidance for the individual plant examination of external events (IPEEE) for severe accident vulnerabilities, final report
- Procedures evaluation checklist for maintenance, test, and calibration procedures
- Procedures evaluation checklist for maintenance, test, and calibration procedures used in nuclear power plants
- Procedures for treating common cause failures in safety and reliability studies
- Protection of safeguards information
- Protection of safeguards information : requirement for tribes participating in the advance notification of irradiated reactor fuel shipments
- Public comment analysis and adjudication : supplement 3 to NUREG-0654/FEMA-REP-1, "Guidance for protectiive action strategies"
- Qualification of systems
- RELAP5 and TRACE calculations of LOCA in PWR
- Radionuclide release calculations for selected severe accident scenarios
- Rates of initiating events at U.S. nuclear power plants : 1987 - 1995
- Reactor license renewal : preparing for tomorrow's safety today
- Reactor safety system design using hardened computers
- Reactor trips caused by breaker testing with fault protection bypassed
- Recent loss or severe degradation of service water systems
- Recent safety-related incidents at large irradiators
- Recommendations for enhancing reactor safety in the 21st century : the Near-Term Task Force review of insights from the Fukushima Dai-ichi accident
- Recurring events involving emergency diesel generator operability
- Regional meetings to discuss impacts on emergency planning
- Regulatory Guide 1.201 : guidelines for categorizing structures, systems, and components in nuclear power plants according to their safety significance
- Regulatory analysis for the resolution of generic issue C-8, "main steam isolation valve leakage and LCS failure"
- Regulatory effectiveness of the anticipated transient without scram rule
- Regulatory guide 1.57 : design limits and loading combinations for metal primary reactor containment system components
- Regulatory guide 1.68 : initial test programs for water-cooled nuclear power plants
- Reliability of emergency AC power systems at nuclear power plants
- Removal of accelerated testing and special reporting requirements for emergency diesel generators
- Report of the Reactor Safety Research Review Group
- Reporting of safeguards events
- Reporting requirement for heat and smoke detector failures in 10 CFR Part 36 Irradiators
- Reporting safety concerns to the NRC
- Reporting safety concerns to the NRC
- Request for information on the status of licensee implementation of generic safety issues resolved with imposition of requirements or corrective actions
- Results of blind testing for the program to assess the reliability of emerging nondestructive techniques
- Review and evaluation of system interactions methods
- Review and evaluation of the zion probabilistic safety study
- Review guidelines for field-programmable gate arrays in nuclear power plant safety systems
- Review of selected areas of Yankee Rowe probabilistic safety study
- Review of systems interaction methodologies
- Review of the Brunswick Steam Electric Plant probabilistic risk assessment
- Revised schedule for completion of TMI action plan Item II.d.1, relief and safety valve testing
- Risk-informed and performance-based oversight of radiological emergency response programs
- SLIM-MAUD : an approach to assessing human error probabilities using structured expert judgment
- SSI sensitivity studies and model improvements for the US NRC seismic safety margins research program
- Safe enough? : a history of nuclear power and accident risk
- Safeguards user's manual for nuclear materials management and safeguards system : final report
- Safety and occupational health program for managers and supervisors : what you should know
- Safety aspects of forced flow cooldown transients in modular high temperature gas-cooled reactors
- Safety evaluation report on Tennessee Valley Authority
- Safety evaluation report related to the license renewal of Brunswick steam electric plant, units 1 and 2, docket nos. 50-325 and 50-324, Carolina Power & Light Company
- Safety evaluation report related to the license renewal of Hope Creek Generating Station : docket no. 50-354 : PSEG Nuclear, LLC
- Safety evaluation report related to the license renewal of the Virgil C. Summer Nuclear Station : docket no. 50-395, South Carolina Electric & Gas Company
- Safety goal sensitivity studies
- Safety research programs sponsored by Office of Nuclear Regulatory Research
- Safety second : the NRC and America's nuclear power plants
- Safety suggestions from employees
- Safety system problems caused by modifications that were not adequately reviewed and tested
- Safety system status monitoring
- Safety-related operator actions : methodology for developing criteria
- Scheduling of pre-licensing emergency preparedness exercises
- Security officer response strategies (SECURORS)
- Seismic Safety Margins Research Program : progress report no.11, June 30, 1981
- Seismic and dynamic qualification of safety related electrical and mechanical equipment
- Severe accident risks : an assessment for five U.S. nuclear power plants, final summary report
- Shear transfer in large scale reinforced concrete containment elements : report no. 1
- Shear transfer in large scale reinforced concrete containment elements : report no. 2
- Significant enforcement actions
- Skylab reentry
- Soil structure interaction : the status of current analysis methods and research : Seismic Safety Margins Research Program
- Some observations on risk-informing appendices A and B to 10 CFR part 50 : prepared for the Advisory Committee on Reactor Safeguards
- Staff recommended actions stemming from NRC integrated program for the resolution of unresolved safety issues regarding steam generator tube integrity
- Standard review plan for review of license renewal applications for nuclear power plants
- Standard review plan for review of license renewal applications for nuclear power plants, final report
- Standard review plan for safeguards contingency response plans for category 1 fuel facilities
- State-of-the-art-reactor consequence analyses (SOARCA) report
- State-of-the-art-reactor consequence analysis (SOARCA) project : Sequoyah integrated deterministic and uncertainty analyses
- State-of-the-art-reactor consequence analysis (SOARCA) report : draft report for comment
- Station blackout accident analysis (part of NRC task action plan A-44)
- Stress analysis of safety-related piping
- Structural review of the Palisades Nuclear Power Plant unit 1, containment structure under combined loads for the systematic evaluation program
- Subsystem response review : seismic safety margins research program
- Supplement 17 to NUREG-0933 : "a prioritization of generic safety issues" : revision insertion instructions
- TMI-2 Lessons Learned Task Force final report
- TMI-2 lessons learned
- Task action plans for generic activities : category A
- Technical basis for an ASTM standard on determining the reference temperature, T0, for ferritic steels in the transition range
- Testing of nuclear grade lubricants and their effect on A540 B24 and A193 B7 bolting materials
- Testing of safety-related nuclear power plant equipment at the central receiver test facility
- The Role of security during safety-related emergencies at nuclear power plants
- The SKYSHINE-II procedure : calculation of the effects of structure design on neutron, primary gamma-ray, and secondary gamma-ray dose rates in air
- The Structured assessment analysis of facility x
- The U.S. government response to the nuclear power plant incident in Japan : hearing before the Subcommittee on Oversight and Investigations of the Committee on Energy and Commerce, House of Representatives, One Hundred Twelfth Congress, first session, April 6, 2011
- The Use of in-situ procedures for seismic qualification of equipment in currently operating plants
- The answer : why only inherently safe, mini nuclear power plants can save our world
- The estimation of very-low probability hurricane storm surges for design and licensing of nuclear power plants in coastal areas
- The insider threat to secure facilities : a synopsis of nine interviews
- The management of ATWS by boron injection
- The risk management implications of NUREG-1150 methods and results
- The use of performance shaping factors and quantified expert judgement in the evaluation of human reliability : an initial appraisal
- Thermally induced accelerated aging and failure of ITE/Gould A.C. relays used in safety-related applications
- Transmittal of information on NRC "Nuclear data link specifications"
- Transmitting NUREG-0578, TMI-2 lessons learned
- U.S. Nuclear Regulatory Commission's decommissioning program
- Uncertainty in soil-structure interaction analysis arising from differences in analytical techniques : Seismic Safety Margins Research Program
- United States Nuclear Regulatory Commission package performance study test protocols : draft report for comment
- Updated best-estimate LOCA radiation signature
- Uses of human reliability analysis probabilistic risk assessment results to resolve personnel performance issues that could affect safety
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Data Citation of the Concept Nuclear power plants -- United States -- Safety measures
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<div class="citation" vocab="http://schema.org/"><i class="fa fa-external-link-square fa-fw"></i> Data from <span resource="http://link.library.mst.edu/resource/2_pqucCz8ZM/" typeof="CategoryCode http://bibfra.me/vocab/lite/Concept"><span property="name http://bibfra.me/vocab/lite/label"><a href="http://link.library.mst.edu/resource/2_pqucCz8ZM/">Nuclear power plants -- United States -- Safety measures</a></span> - <span property="potentialAction" typeOf="OrganizeAction"><span property="agent" typeof="LibrarySystem http://library.link/vocab/LibrarySystem" resource="http://link.library.mst.edu/"><span property="name http://bibfra.me/vocab/lite/label"><a property="url" href="http://link.library.mst.edu/">Missouri University of Science & Technology Library</a></span></span></span></span></div>
