Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, Appendices 3 and 4

One of 10 reports in the series: NUREG available on this site.

PDF Version Also Available for Download.

Description

From section 1: In the quantitative system probability estimates performed in this study, component behavior data in the form of failure rates and repair times are required as inputs to the system models. Since the goal of this study is risk assessment, as opposed to reliability analysis, larger errors (e.g. order of magnitude type accuracy) can be tolerated in the quantified results. This has important implications on the treatment of available data. In standard reliability analysis, point values (i.e., "best-estimates") are generally used for both data and results in quantifying the system model. In risk assessment, since results accurate to … continued below

Physical Description

168 p. : ill., maps ; 28 cm.

Creation Information

U.S. Nuclear Regulatory Commission October 1975.

Context

This report is part of the collection entitled: Technical Report Archive and Image Library and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 252 times. More information about this report can be viewed below.

Who

People and organizations associated with either the creation of this report or its content.

Distributor

Originator

Publisher

Provided By

UNT Libraries Government Documents Department

Serving as both a federal and a state depository library, the UNT Libraries Government Documents Department maintains millions of items in a variety of formats. The department is a member of the FDLP Content Partnerships Program and an Affiliated Archive of the National Archives.

Contact Us

What

Descriptive information to help identify this report. Follow the links below to find similar items on the Digital Library.

Titles

  • Added Title: Failure Data
  • Added Title: Common Mode Failures: Bounding Techniques and Special Techniques
  • Main Title: Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, Appendices 3 and 4
  • Series Title: NUREG
  • Series Title: Nuclear Regulatory Commission Reports
  • Added Title: Nuclear Regulatory Commission Report WASH-1400
  • Added Title: Nuclear Regulatory Commission Report NUREG-75/014

Description

From section 1: In the quantitative system probability estimates performed in this study, component behavior data in the form of failure rates and repair times are required as inputs to the system models. Since the goal of this study is risk assessment, as opposed to reliability analysis, larger errors (e.g. order of magnitude type accuracy) can be tolerated in the quantified results. This has important implications on the treatment of available data. In standard reliability analysis, point values (i.e., "best-estimates") are generally used for both data and results in quantifying the system model. In risk assessment, since results accurate to about an order of magnitude are sufficient, data and results using random variable and probabilistic approaches, can be usefully employed. The base of applicable failure rate data is thus significantly broadened since data with large error spreads and uncertainties can now be utilized. The data and associated material that were assembled for use in this study and that are presented here are to be used in the random variable framework (which will be described). The data and the accompanying framework are deemed sufficient for the study's needs. Care must be taken, however, since this data may not be sufficiently detailed, or accurate enough for use in general quantitative reliability models.

Physical Description

168 p. : ill., maps ; 28 cm.

Notes

"Appendices III and IV."

Language

Item Type

Identifier

Unique identifying numbers for this report in the Digital Library or other systems.

Collections

This report is part of the following collection of related materials.

Technical Report Archive and Image Library

The Technical Report Archive & Image Library (TRAIL) identifies, acquires, catalogs, digitizes and provides unrestricted access to U.S. government agency technical reports. The mission of TRAIL is to ensure preservation, discoverability, and persistent open access to government technical publications regardless of form or format.

What responsibilities do I have when using this report?

When

Dates and time periods associated with this report.

Creation Date

  • October 1975

Added to The UNT Digital Library

  • July 14, 2017, 6:39 a.m.

Description Last Updated

  • Feb. 19, 2026, 12:23 p.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 252

Where

Geographical information about where this report originated or about its content.

Place Name

Publication Place

Map Information

  • map marker Place Name coordinates. (May be approximate.)
  • Repositioning map may be required for optimal printing.

Mapped Locations

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

PDF Version Also Available for Download.

International Image Interoperability Framework

IIF Logo

We support the IIIF Presentation API

U.S. Nuclear Regulatory Commission. Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, Appendices 3 and 4, report, October 1975; Washington D.C.. (https://digital.library.unt.edu/ark:/67531/metadc784368/: accessed June 6, 2026), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

Back to Top of Screen