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Event reports

Summag Report Screening and Evaluation of Ricense Event Reports for 1979, Nuclear Safety Analysis Center Report, NSAC-2, Palo Alto, Calif., 1980. [Pg.246]

PRISIM embodies the IREP model of Arkansas 1. It includes extensive grapitivs of. simplified flow diagrams and relevant operating history from LERs (Licensee Event Reports required by Regulatory Guide 1.16) The plant model consists of 500 cutsets truncated by probabilities determined from normal operation. [Pg.135]

Data Summaries of Licerisee Event Reports at U.S. Nuclear Power Plants... [Pg.154]

The LER-HEP method (NUREG/ CR-3519) is a means of analyzing field data to estimate HEPs. It considers available data on specific human errors in similar to those being considered in the risk as.sessment. The application of the method in NUREG/CR-3519 is to the Licensee Event Report (LER) file so it is called the LER-HEP method. For each error analyzed by this method, an error rate is derived by dividing the number of similar errors by the estimated number of... [Pg.176]

Considerable effort has been spent in evaluating the fire events cataloged in licensee event reports and data from the American... [Pg.197]

Flood Event Frequency Estimates were developed from flooding events in nuclear power plants with adjustments for plant-specific features and data. The data were from the IPE Surry flood analysis, industry sources, and licensing event reports (LERs). Some plant specific models were developed for the circulating water (CW) and service water (SW) lines... [Pg.389]

Sullivan, W. H. and Poloski, J. P., Data Summaries of Licensee Event Reports of Pumps at (, Commercial Nuclear Power Plants, January 1, 1972-April 30, 1978, Lvj .o,... [Pg.468]

Sams, D. W. and M. T rojovsky, Data Summaries of Licensee Event Reports of Primary Containment Penetrations at U.S. Commercial Nuclear Plants, EG G, Septt 1980,... [Pg.468]

Voska, K.J. and J.N. O Brien, Human Error Probability Estimation Using Licensee Event Reports, BNL, July 1984. [Pg.470]

Analysis of Dependent Failure Events and Failure Events Caused by Harsh Environment Conditions Nuclear 700 events representing common cause failures and failures caused by harsh environments Licensee Event Reports on failures of 26 component and subcomponent types listed below 94. [Pg.91]

Emergency Diesel Generator Operating Experience Nuclear 600 occurrences of failure from event reports and questionnaires Diesel generators 95. [Pg.91]

Data Summaries of Licensee Event Reports at U.S. Commercial Nuclear Power Plants (Vanous Components) Nuclear 11209 one-fine event descriptions on specific component types failure rates and error factors Pumps, valves, diesels inverters, relays, circuit breakers (in separate reports) 100. [Pg.91]

Survey and Evaluation of System Interaction Events and Sources Nuclear 4(X) occurrences of snubber failure at U.S. nuclear power plants from event reports Hydraulic and mechanical snubbers 103. [Pg.91]

Investigation of Valve Failure Problems in LWR Power Plants Nuclear 195 LERs valve failures causing trips from 12/72 to 12/78. plus all valve failures for 10 stations from 2/66 to 1/79 Valve-related events reported in LERs. as noted above 105. [Pg.92]

DATA BOUNDARY Licensee Event Reports on failures of 26 component and... [Pg.94]

EGSG Idaho s Idaho National Engineering Laboratory reviewed Licensee Event Reports (LERs), both qualitatively and quantitatively, to extract reliability information in support of the USNRC s effort to gather and analyze component failure data for U.S. commercial nuclear power plants. LERs describing failures or command faults (failure due to lack of needed input) for selected components have been analyzed in this program. Separate reports have been issued for batteries and battery chargers, control rods and drive mechanisms, diesel generators, ISC, Inverters, primary containment penetrations, protective relays and circuit breakers, pumps, and valves. [Pg.100]

DATA BOUNDARY Valve-related events reported in LERs, as noted above... [Pg.105]

This report is a statistical description of pipe system failures. The characteristics of these failures have been derived from reports submitted by the utilities to the Nuclear Regulatory Commission. The bulk of the data is from Licensee Event Reports supplemented as necessary by plant outage and maintenance data. [Pg.114]

Appendix III of this report provides a detailed description of the reliability data used in event tree and fault tree quantification. Because of its extensive operating experience and the uniqueness of the BRP design, BRP plant-specific data was used whenever possible. Plant-specific data sources included plant maintenance orders, control room log books, surveillance tests, LERs, event reports, deviation reports, plant review committee meeting minutes, and USNRC correspondence. The plant-specific data used spanned the period from 1970 to 1979. Data before 1970 did not include maintenance orders or surveillance tests and therefore were excluded. The plant-specific data collected for BRP is presented in detail in Appendix XIII. Table III-4 summarizes 30 plant-specific component failure rates and Table 11-06 contains plant-specific maintenance unavailabilities for 20 components. These tables are a summary of the BRP component failure and maintenance outages. [Pg.117]

The failure data for these rates is obtained from maintenance work requests supplemented by incidence reports and Licensee Event Reports from the 1975-1980 time period. The work requests provide a complete history of all repairs performed at Oconee. They are not restricted to safety-related systems, they are written during all modes of unit operation, and they are not produced in response to licensing-based criteria. [Pg.122]

Military Handbook 217E). Data Summaries of Licensee Event Reports at 4.7-8... [Pg.127]

Other reports used within facilities record failures of particular interest because of failure mode and system or equipment affected. Some facilities may issue special reports when the plant experiences a shutdown (outage report) or when the occurrence is sufficiently unique or troublesome to warrant further investigation (unusual event report). In general, these reports can be characterized by their relatively restrictive focus (when compared to the maintenance records) and their smaller number. [Pg.214]

Related Equipment Event Report Nos Failure Diagnosis Report. ... [Pg.218]

The Vaccine Adverse Event Reporting System (VAERS) is a national vaccine safety surveillance program co-sponsored by the Centers for Disease Control and Prevention (CDC) and the Food and Drug Administration (FDA). VAERS collects and analyzes information from reports of adverse reactions after immunization. Anyone can report to VAERS, and reports are sent in by vaccine manufacturers, health care providers, and vaccine recipients and their parents or guardians. An example of the VAERS and instructions for completing the form are found in Appendix F. Any clinically significant adverse event that occurs after the administration of any vaccine should be reported. Individuals are encouraged to provide the information on the form even if the individual is uncertain if the event was related to the... [Pg.581]

The FDA Safety Information and Adverse Event Reporting Program... [Pg.657]

The FDA Safety Information and Adverse Event Reporting Program Food and Drug Administrstion 5600 Fishers Lene Rockville, MD 20852-9787... [Pg.658]

Appendix F is a Vaccine Adverse Event Reporting Form. [Pg.689]

GL24 Pharmacovigilance Pharmacovigilance of veterinary medicinal products management of Adverse Event Reports (AERs)... [Pg.132]

GL42 Pharmacovigilance Data elements Pharmacovigilance Data Elements for Submission of Adverse Events Reports... [Pg.133]

Investigation should be performed in circumstances similar to the intended use conditions. Adverse Event Reporting... [Pg.189]

Corrections or removals of devices from the market may be necessitated either as a consequence of adverse event reports or the discovery of manufacturing or other defects that pose a risk to public health. The manufacturer must submit a report to the FDA within 10 days of initiating such corrections or removals. This should provide information on the identity and number of devices concerned, the reasons for doing so, and the communication of the action. The manufacturer must also maintain records of other corrections or removals that need not be reported. [Pg.273]


See other pages where Event reports is mentioned: [Pg.237]    [Pg.58]    [Pg.158]    [Pg.462]    [Pg.103]    [Pg.290]    [Pg.669]    [Pg.41]    [Pg.87]    [Pg.188]    [Pg.256]   
See also in sourсe #XX -- [ Pg.28 ]




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