Regulatory Guide 5.1: Difference between revisions
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{{#Wiki_filter:12/20/72 U.S. ATOMIC ENERGY COMMISSION | {{#Wiki_filter:12/20/72 U.S. ATOMIC ENERGY COMMISSION | ||
REGULATORY | REGULATORY | ||
DIRECTORATE | DIRECTORATE OF REGULATORY STANDARDS | ||
OF REGULATORY | GUIDE | ||
REGULATORY GUIDE 5.1 SERIAL NUMBERING OF FUEL ASSEMBLIES FOR LIGHT-WATER-COOLED | |||
GUIDE 5.1 SERIAL NUMBERING | NUCLEAR POWER REACTORS | ||
OF FUEL ASSEMBLIES | |||
FOR LIGHT-WATER-COOLED | |||
NUCLEAR POWER REACTORS | |||
==A. INTRODUCTION== | ==A. INTRODUCTION== | ||
Part 70 of the Atomic Energy Commission's regulations requires that certain licensees establish and | reprocessing in that fuel assemblies can be readily identified according to origin and irradiation history, Part 70 of the Atomic Energy Commission's thus avoiding confusion in formation of dissolver regulations requires that certain licensees establish and batches. | ||
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. | maintain written material control and accounting procedures which are sufficient to enable the licensee to The Fuel Assembly Identification Working Group of account for the special nuclear material (SNM) in his Subcommittee ANS-13, Fuel Assembly Criteria, has possession. In the case of SNM contained in fuel developed a standard (ANS 13.8) for fuel assembly assemblies, a system of control based on unique item identification. This standard was approved by the identification of each fuel assembly is desirable to American National Standards Institute as N18.3-1972! | ||
achieve an acceptable level of accountability control. on May 10, 1972. | |||
This guide describes an acceptable numbering method for item identification of fuel assemblies for Some fabricators purposely manufacture fuel light-water-cooled nuclear power reactors. assemblies that can be dismantled without any metal-cutting operation. This design feature allows | |||
==B. DISCUSSION== | ==B. DISCUSSION== | ||
relatively easy substitution of fuel rods, but complicates the verification of discrete power reactor fuel items. | |||
Power reactor fuel is relatively inaccessible while at a reactor facility. The SNM itself is securely contained within the fuel cladding. Accurate quantitative | |||
==C. REGULATORY POSITION== | |||
measurements of the SNM content of the fuel assemblies are exceedingly difficult, and as yet not feasible except 1. The provisions contained in ANSI N18.3-1972, through use of techniques requiring disassembly into "Fuel Assembly Identification," are generally acceptable individual fuel rods. The SNM content of a fuel assembly and provide an adequate numbering basis for is currently obtained by determining the SNM content in identification of individual fuel assemblies from the time each discrete item (element or rod), and then verifying of final fuel rod consolidation at the fabricator's facility the presence of such items. The principal diversion until the assembly is dissolved as an entity. | |||
threat for SNM at the reactor consists of theft of identifiable items. Accordingly, the AEC's material 2. In the special case of fuel assemblies from which a protection inspection practices for SNM contained in fuel rod or other SNM-containing component may be completed fuel assemblies on inventory at light-water removed without the need of a metal-cutting operation, reactor facilities are based on assuring that all further identification and accounting measures in individually identifiable fuel pieces received at the addition to those required in ANSI N18.3-1972 may be facility are still on hand or have been shipped to other necessary. This determination will be made on an licensed facilities. individual case basis. | |||
A substantial level of assurance can be provided within this context if each fuel assembly is uniquely 'Copies may be obtained from the American National identified by a number inscribed in its structure. The Standards Institute, Inc., 1430 Broadway, New York. New York unique numbering also offers an advantage at the time of 10018. | |||
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. | |||
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. | |||
evaluating specific problems or postulated accidents, or to provide guidance to Attention: Chief, Public Proceedings Staff. | |||
Chief, Public Proceedings Staff | |||
Regulatory Guides are not substitutes for regulations and compliance with them Is not required. | 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=== | ===7. Transportation=== | ||
3. Fuels and Materials Facilities | 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}} | ||
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}} | |||
{{RG-Nav}} | {{RG-Nav}} | ||
Revision as of 01:12, 12 November 2019
| ML12191A014 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1972 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| References | |
| 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
reprocessing in that fuel assemblies can be readily identified according to origin and irradiation history, Part 70 of the Atomic Energy Commission's thus avoiding confusion in formation of dissolver regulations requires that certain licensees establish and batches.
maintain written material control and accounting procedures which are sufficient to enable the licensee to The Fuel Assembly Identification Working Group of account for the special nuclear material (SNM) in his Subcommittee ANS-13, Fuel Assembly Criteria, has possession. In the case of SNM contained in fuel developed a standard (ANS 13.8) for fuel assembly assemblies, a system of control based on unique item identification. This standard was approved by the identification of each fuel assembly is desirable to American National Standards Institute as N18.3-1972!
achieve an acceptable level of accountability control. on May 10, 1972.
This guide describes an acceptable numbering method for item identification of fuel assemblies for Some fabricators purposely manufacture fuel light-water-cooled nuclear power reactors. assemblies that can be dismantled without any metal-cutting operation. This design feature allows
B. DISCUSSION
relatively easy substitution of fuel rods, but complicates the verification of discrete power reactor fuel items.
Power reactor fuel is relatively inaccessible while at a reactor facility. The SNM itself is securely contained within the fuel cladding. Accurate quantitative
C. REGULATORY POSITION
measurements of the SNM content of the fuel assemblies are exceedingly difficult, and as yet not feasible except 1. The provisions contained in ANSI N18.3-1972, through use of techniques requiring disassembly into "Fuel Assembly Identification," are generally acceptable individual fuel rods. The SNM content of a fuel assembly and provide an adequate numbering basis for is currently obtained by determining the SNM content in identification of individual fuel assemblies from the time each discrete item (element or rod), and then verifying of final fuel rod consolidation at the fabricator's facility the presence of such items. The principal diversion until the assembly is dissolved as an entity.
threat for SNM at the reactor consists of theft of identifiable items. Accordingly, the AEC's material 2. In the special case of fuel assemblies from which a protection inspection practices for SNM contained in fuel rod or other SNM-containing component may be completed fuel assemblies on inventory at light-water removed without the need of a metal-cutting operation, reactor facilities are based on assuring that all further identification and accounting measures in individually identifiable fuel pieces received at the addition to those required in ANSI N18.3-1972 may be facility are still on hand or have been shipped to other necessary. This determination will be made on an licensed facilities. individual case basis.
A substantial level of assurance can be provided within this context if each fuel assembly is uniquely 'Copies may be obtained from the American National identified by a number inscribed in its structure. The Standards Institute, Inc., 1430 Broadway, New York. New York unique numbering also offers an advantage at the time of 10018.
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