The following data provides the code for the SABRES II model.

SABRES II is an individual resolution computer simulation of combat between two small groups using small arms weapons.

"In addition to BWR background information, this document contains a description of the experimental hardware with details on how the experiment was instrumented and diagnosed, a description of the test progression, and a presentation on the on-line instruments."

This report discusses the results of a comparative review of the selection, training, qualification, and requalification of Maitenncace personnel, operators, shift supervisors, and senior onsite managers involved in the operation and/or maintenance of nuclear power plants.

This report was compiled at the Hanford Engineering Development Laboratory operated by Westinghouse Hanford Company, a subsidiary of Westinghouse Electric Corpoation, for the United States Department of Energy and the Nuclear Regulatory Commission, under DOE contract number DE-AC14-76FF02170 and NRC service request number TV-0176.

A report discussing work performed at the Oak Ridge National Laboratory in support of the ORNL Design Criteria for Piping and Nozzle Program being conducted for the U.S. Nuclear Regulatory Research.

This report examines the adequacy of existing fire-hazards analysis methodology in the context of nuclear power plant safety

"The objective of this study is to provide an up-to-date documentation of the costs of nuclear electrical generating plants as they relate to site characteristics, in the following areas and systems: Main condenser cooling systems, Transmission, Site access, Food Protection, Plant site earthwork."

A final report regarding a Multiloop Integral System Test, or MIST.

Report presenting data plots for selected parameters measured during Test PCM-4 of the Power-Cooling-Mismatch Test Series.

"This report describes the methods, analyses, results, and conclusions of two different aging studies."

Report providing quantitative information of containment seismic capacity considering a rather complete list of limit states along with a discussion of factors that are significant for determining seismic capacity and recommendations for future work.

Tables detailing aging tallies produced as part of the aging failure survey. The tables display the detailed breakdown for the data by component, system effect, failure category, and age of component at the time of failure. (p. E-3 of report).

A report discussing a leak and structural test of a personal airlock, for LWR contaminants, subjected to pressures and temperatures beyond the design limits.

Graphs presenting peak power history, ratio of local rod power to rod average power (P/A), total heat transfer coefficient history, and coolant pressure history conditions in the test assembly during the transient phase of the TC-1 tests.

"The program concerning Acoustic Emission/Flaw Relationships for Inservice Monitoring of LWRs was entitled in FY76 with the objective of validating the application of acoustic emission (AE) to monitor nuclear reactor pressure-containing components during operation to detect cracking."

A catalog had been prepared which contains information for world-wide, ground-motion accelerograms, the accelerogaph sites where these records were obtained, and the seismological parameters of the causative earthquakes.

A report regarding the results of a PBF severe fuel damage test

This report presents the results of the first three power-cooling-mismatch tests - Tests 8-1 RS CHF Scoping, and 8-1 RF - performed in the PCM Test Series.

Report presenting time history plots of selected parameters measured during the three tests: PCM 8-1 RS, CHF Scoping, and PCM 8-1 RF.

Dataset documenting the software programs used in the acoustic emission (AE) instruments systems developed under the U. S. Nuclear Regulatory Commission (NRC) / Pacific Northwest Laboratory (PNL) AE program.

This report presents and discusses the results from the Reactivity Initiated Accident Test RIA1-2 conducted in the Power Burst Facility at the Idaho National Engineering Laboratory.

Report describing small-scale laboratory experiments using a Beckman model 7C thermal conductivity cell conducted in order to provide a better understanding of the response of the hydrogen monitor during Power Burst Facility (PDF) Severe Fuel Damage (SFD) tests (p. 1).

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for system characteristics, load and capacity, and consequences of delay.