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Publication Laka-library:
NRC Staff Evaluation of the General Electric Company Nuclear Reactor Study ("Reed Report") (1987)

AuthorUS NRC
DateJuly 1987
Classification 6.01.3.20/29 (NUCLEAR SAFETY - REACTORS - PRESSURIZED WATER (PWR) / BOILING WATER (BWR))
Front

From the publication:

EXECUTIVE SUMMARY

The purpose of this NRC staff evaluation of the General Electric Nuclear Reactor
Study (the Reed Report) and its 10 subtask reports is to reconsider the issues and 
concerns identified in the report in the light of current knowledge, recent operating 
experience, and regulatory issues as they have developed since the report was 
issued in 1975.

A History of the Reed Report

The Reed Report was a self-critical study performed by the staff of the General 
Electric Company (GE) in 1975. It was intended as a product-improvement study 
to enhance the availability and performance of GE's boiling water reactors (BWRs). 
The report, by its nature a candid self-analysis, was intended for GE's internal use 
only. It has always been held by GE to be "proprietary," and thus not subject to 
public disclosure.

The principal author of the report was Dr. Charles E. Reed, a Senior Vice President 
of GE. Contributors included technical and professional personnel from a variety of 
GE departments. Two products resulted from their efforts. One was the Nuclear 
Reactor Study, referred to today as the Reed Report; the second was a set of 10 
subtask reports that provided the detailed technical information used to develop 
the Nuclear Reactor Study.

The Structure of the Reed Report

The Reed Report addressed operating BWRs and the design of future GE 
products and services in the nuclear field.

For reactors in operation at the time, the report discussed ways to improve plant 
availability and its electrical generating capacity factor through improvements in 
plant hardware and through improvements in service, fuel, equipment, and operating 
procedures. For future reactors, the report considered GE's then-new BWR design, the 
BWR-6, and discussed problems regarding final design details, licensing, and full-
power operation of BWR-6 plants.

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