Regulatory Guide 5.1

Serial Numbering of Fuel Assemblies for Light-Water-Cooled Nuclear Power Plants

ML12191A014
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Issue date:	12/31/1972
From:	Office of Nuclear Regulatory Research
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RG-5.001
Download: ML12191A014 (4)

12/20/72 U.S. ATOMIC ENERGY COMMISSION

REGULATORY

DIRECTORATE

OF REGULATORY

STANDARDS GUIDE REGULATORY

GUIDE 5.1 SERIAL NUMBERING

OF FUEL ASSEMBLIES

FOR LIGHT-WATER-COOLED

NUCLEAR POWER REACTORS

A. INTRODUCTION

Part 70 of the Atomic Energy Commission's regulations requires that certain licensees establish and maintain written material control and accounting procedures which are sufficient to enable the licensee to account for the special nuclear material (SNM) in his possession.

In the case of SNM contained in fuel assemblies, a system of control based on unique item identification of each fuel assembly is desirable to achieve an acceptable level of accountability control.This guide describes an acceptable numbering method for item identification of fuel assemblies for light-water-cooled nuclear power reactors.

B. DISCUSSION

Power reactor fuel is relatively inaccessible while at a reactor facility.

The SNM itself is securely contained within the fuel cladding.

Accurate quantitative measurements of the SNM content of the fuel assemblies are exceedingly difficult, and as yet not feasible except through use of techniques requiring disassembly into individual fuel rods. The SNM content of a fuel assembly is currently obtained by determining the SNM content in each discrete item (element or rod), and then verifying the presence of such items. The principal diversion threat for SNM at the reactor consists of theft of identifiable items. Accordingly, the AEC's material protection inspection practices for SNM contained in completed fuel assemblies on inventory at light-water reactor facilities are based on assuring that all individually identifiable fuel pieces received at the facility are still on hand or have been shipped to other licensed facilities.

A substantial level of assurance can be provided within this context if each fuel assembly is uniquely identified by a number inscribed in its structure.

The unique numbering also offers an advantage at the time of reprocessing in that fuel assemblies can be readily identified according to origin and irradiation history, thus avoiding confusion in formation of dissolver batches.The Fuel Assembly Identification Working Group of Subcommittee ANS-13, Fuel Assembly Criteria, has developed a standard (ANS 13.8) for fuel assembly identification.

This standard was approved by the American National Standards Institute as N18.3-1972!

on May 10, 1972.Some fabricators purposely manufacture fuel assemblies that can be dismantled without any metal-cutting operation.

This design feature allows relatively easy substitution of fuel rods, but complicates the verification of discrete power reactor fuel items.C. REGULATORY

POSITION 1. The provisions contained in ANSI N18.3-1972,"Fuel Assembly Identification," are generally acceptable and provide an adequate numbering basis for identification of individual fuel assemblies from the time of final fuel rod consolidation at the fabricator's facility until the assembly is dissolved as an entity.2. In the special case of fuel assemblies from which a fuel rod or other SNM-containing component may be removed without the need of a metal-cutting operation, further identification and accounting measures in addition to those required in ANSI N18.3-1972 may be necessary.

This determination will be made on an individual case basis.'Copies may be obtained from the American National Standards Institute, Inc., 1430 Broadway, New York. New York 1001

8. USAEC REGULATORY

GUIDES Copies of published guides may be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington, D.C. 20545, Regulatory Guides are issued to describe and make available to the public Attention:

Director of Regulatory Standards.

Comments and suggestions for methods acceptable to the AEC Regulatory staff of Implementing specific parts of improvements In these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques used by the staff in of the Commission, U.S. Atomic Energy Commission, Washington, D.C. 20545.evaluating specific problems or postulated accidents, or to provide guidance to Attention:

Chief, Public Proceedings Staff.applicants.

Regulatory Guides are not substitutes for regulations and compliance with them Is not required.

Methods and solutions different from those set out in The guides ere issued in the following ten broad divisions:

the guides will be acceptable if they provide a basil for the findings requisite to the Issuance or continuance of a permit or license by the Commission.

1. Power Reactors 8. Products 2. Reaeerch end Test Reactors

7. Transportation

3. Fuels and Materials Facilities

8. Occupational Health Published guides will be revised periodically, as appr.,rwate, to accommodate

4. Environmental and Siting 9. Antitrust Review comments and to reflect new information or experience.

5. Materials and Plant Protection

10. General