Regulatory Guide 5.3

Statistical Terminology and Notation for Special Nuclear Materials Control and Accountability

ML003739531
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Issue date:	02/02/1973
From:	Office of Nuclear Regulatory Research
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RG-5.3
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2/2f73 U.S. ATOMIC ENERGY COMMISSION

REGULATORY

DIRECTORATE OF REGULATORY STANDARDS

GI JIDE

REGULATORY GUIDE 5.3 STATISTICAL TERMINOLOGY AND NOTATION FOR SPECIAL

NUCLEAR MATERIALS CONTROL AND ACCOUNTABILITY

A. INTRODUCTION

describing material protection systems for controlling special nuclear material. Among these systems are Part 70 of Title 10 of the Code of Federal process control, sampling, error propagation, quality Regulations requires certain AEC special nuclear assurance, measurement, estimation, data recording, material licensees to establish and maintain sufficient reporting, and inventory control as well as verification, written material control and accounting procedures to auditing, and inspection of special nuclear materials. All enable the licensee to account for the special nuclear entail varying degrees of statistical evaluation and each material in his possession. Part 70 also requires interacts with the others. In recognition of the need for applicants for certain AEC licenses for special nuclear standarizing statistical terminology, the American material to submit to the Commission as part of the National Standards Insitute (ANSI) Subcommittee application a full description of such procedures, NI 5-3, Statistics, has developed a standard for statistical including recording, reporting, physical inventory, and terminology and notation for nuclear materials measurement procedures for special nuclear material. management.

Essential to satisfactory material control and accounting procedures me measurement and statistical control

C. REGULATORY POSITION

This guide identifies acceptable terminology and notation concerning statistical anaylses of accountability The terminology and notation contained in ANSI

data for special nuclear material control purposes. N15.5-1972 "Statistical Terminology and Notation for Nuclear Materials Management"' approved May 24,

S. DISCUSSION

1972, are generally acceptable for use in written special nuclear material control procedures. Further Statistical techniques have been developed for and clarification of one term Is provided as follows: the AEC

applied to special nuclear materials control and Regulatory staff has construed "Unmit of Error" as the accountability systems to enable licensees of fuel uncertainty component used to construct a 95%

procening and fuel fabrication facilities to account for confidence interval associated with a quantity when the the special nuclear material they possess and to localize effect of any recognized bins has been accounted for or losm when they occur. Because of the diverse yet otherwise eliminated by the user. The uncertainty overlapping applications of statistical controls, it is component should include systematic as well as random desirable that a uniform terminology be used to improve errors.

comprehension and communication and to assure effective implementation of special nuclear materials tCopies may be obtained from the American Notlonsl control and accountability programs. The Standards Instiute, Inc.. 1430 roadway, New York, New York

10018.

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