Regulatory Guide 3.57: Difference between revisions
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{{Adams | {{Adams | ||
| number = | | number = ML12220A066 | ||
| issue date = 10/31/1986 | | issue date = 10/31/1986 | ||
| title = | | title = Administrative Practices for Nuclear Criticality Safety at Fuels and Materials Facilities | ||
| author name = | | author name = | ||
| author affiliation = NRC/RES | | author affiliation = NRC/RES | ||
| Line 10: | Line 10: | ||
| license number = | | license number = | ||
| contact person = | | contact person = | ||
| document report number = RG-3. | | case reference number = CE-501-4 | ||
| document report number = RG-3.057 | |||
| document type = Regulatory Guide | | document type = Regulatory Guide | ||
| page count = 4 | | page count = 4 | ||
}} | }} | ||
{{#Wiki_filter:U.S. NUCLEAR REGULATORY | {{#Wiki_filter:A U.S. NUCLEAR REGULATORY | ||
COMMISSION | COMMISSION | ||
October 1986) REGULATORY | October 1986) REGULATORY | ||
GUIDE OFFICE OF NUCLEAR REGULATORY | GUIDE OFFICE OF NUCLEAR REGULATORY | ||
RESEARCH REGULATORY | RESEARCH REGULATORY | ||
GUIDE 3.57 (Task CE 501-4) ADMINISTRATIVE | GUIDE 3.57 (Task CE 501-4)ADMINISTRATIVE | ||
PRACTICES | PRACTICES | ||
FOR NUCLEAR CRITICALITY | FOR NUCLEAR CRITICALITY | ||
| Line 26: | Line 27: | ||
==A. INTRODUCTION== | ==A. INTRODUCTION== | ||
Section 70.22, "Contents of Applications," of 10 CFR Part 70, "Domestic Licensing of Special Nuclear Mate rial," requires that applications for a specific license to own, acquire, deliver, receive, possess, use, or initially transfer special nuclear material contain proposed proce dures to avoid accidental conditions of criticality. | Section 70.22, "Contents of Applications," of 10 CFR Part 70, "Domestic Licensing of Special Nuclear Mate-rial," requires that applications for a specific license to own, acquire, deliver, receive, possess, use, or initially transfer special nuclear material contain proposed proce-dures to avoid accidental conditions of criticality. | ||
Section 70.24, "Criticality Accident Requirements," of 10 CFR Part 70 requires licensees who are authorized to possess special nuclear material in excess of certain amounts to maintain emergency procedures for each area in which such licensed special nuclear material is handled, used, or stored to ensure that all personnel withdraw to an area of safety upon the sounding of a criticality accident alarm. | Section 70.24, "Criticality Accident Requirements," of 10 CFR Part 70 requires licensees who are authorized to possess special nuclear material in excess of certain amounts to maintain emergency procedures for each area in which such licensed special nuclear material is handled, used, or stored to ensure that all personnel withdraw to an area of safety upon the sounding of a criticality accident alarm.The above procedures are elements of ? nuclear criticality safety program for operations with fissionable materials at fuels and materials facilities (i.e., fuel cycle facilities other than nuclear reactors) | ||
in which there exists a potential for criticality accidents. | in which there exists a potential for criticality accidents. | ||
This guide describes | This guide describes pra9tices acceptable to the NRC staff for administration of such a program.Any information collection activities mentioned in this regulatory guide are contained as requirements in 10 CFR Part 70, which provides the regulatory basis for this guide. The information collection requirements in 10 CFR Part 70 have been cleared under OMB Clearance No. 3150-0009. | ||
Any information collection activities mentioned in this regulatory guide are contained as requirements in 10 CFR Part 70, which provides the regulatory basis for this guide. The information collection requirements in 10 CFR Part 70 have been cleared under OMB Clearance No. 3150-0009. | |||
==B. DISCUSSION== | ==B. DISCUSSION== | ||
ANSI/ANS-8.19-1984, "Administrative Practices for Nuclear Criticality Safety,"* | ANSI/ANS-8.19-1984, "Administrative Practices for Nuclear Criticality Safety,"* | ||
was prepared by Subcom mittee 8, Fissionable Materials Outside Reactors, of the *Copies may be obtained from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60525.Standards Committee of the American Nuclear Society. | was prepared by Subcom-mittee 8, Fissionable Materials Outside Reactors, of the*Copies may be obtained from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60525.Standards Committee of the American Nuclear Society.ANSI/ANS-8.19-1984 was approved by the American National Standards Committee N16, Nuclear Criticality Safety, in early 1984 and by the American National Standards Institute (ANSI) on October 1, 1984.ANSI/ANS-8.19-1984 provides guidance for administra- tion of a nuclear criticality safety program for operations outside of reactors in which there exists a potential for criticality accidents. | ||
ANSI/ANS-8.19-1984 was approved by the American National Standards Committee N16, Nuclear Criticality Safety, in early 1984 and by the American National Standards Institute (ANSI) on October 1, 1984. | |||
This guidance includes delineation of the responsibilities of management, supervision, and the nuclear criticality safety staff as well as objectives and characteristics of operating and emergency procedures. | This guidance includes delineation of the responsibilities of management, supervision, and the nuclear criticality safety staff as well as objectives and characteristics of operating and emergency procedures. | ||
| Line 52: | Line 48: | ||
==D. IMPLEMENTATION== | ==D. IMPLEMENTATION== | ||
The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for using this regulatory guide. | The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for using this regulatory guide.The methods described in this guide were applied to a number of specific cases during reviews and selected USNRC REGULATORY | ||
GUIDES The guides are | GUIDES The guides are issued In the following ten broad divisions: | ||
Regulatory Guides are | Regulatory Guides are Issued to describe and make available to the public methods acceptable to the NRC staff of Implementing | ||
1. Power Reactors 6. Products specific parts of the Commission's regulations, to delineate tech- 2. Research and Test Reactors 7. Transportation niques used by the staff | 1. Power Reactors 6. Products specific parts of the Commission's regulations, to delineate tech- 2. Research and Test Reactors 7. Transportation niques used by the staff In evaluating specific problems or postu- 3. Fuels and Materials Facilities | ||
8. Occupational Health lated accidents or to provide guidance to applicants. | 8. Occupational Health lated accidents or to provide guidance to applicants. | ||
Regulatory | Regulatory | ||
4. Environmental and Siting 9. Antitrust and Financial Review Guides are not substitutes for regulations, and compliance with 5. Materials and Plant Protection | 4. Environmental and Siting 9. Antitrust and Financial Review Guides are not substitutes for regulations, and compliance with 5. Materials and Plant Protection | ||
10. General them | 10. General them Is not required. | ||
Methods and solutions different from those set out | Methods and solutions different from those set out in the guides will be acceptable If they provide a basis for the findings requisite to the Issuance or continuance of a permit or Copies of Issued guides may be purchased from the Government license by the Commission. | ||
Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of This guide was | Printing Office at the current GPO price. Information on current.GPO prices may be obtained by contacting the Superintendent of This guide was Issued after consideration of comments received from Documents, U.S. Government Printing Office, Post Office Box the public. Comments and suggestions for Improvements In these 37082, Washington, DC 20013-7082, telephone | ||
(202)275-2060 | (202)275-2060 | ||
or guides are encouraged at all times, and guides will be revised, as (202)275-2171. | or guides are encouraged at all times, and guides will be revised, as (202)275-2171. | ||
appropriate, to accommodate comments and to reflect new Informa tion or experience. | appropriate, to accommodate comments and to reflect new Informa-tion or experience. | ||
Issued guides may also be purchased from the National Technical Written comments may be submitted to the Rules and Procedures | Issued guides may also be purchased from the National Technical Written comments may be submitted to the Rules and Procedures information Service on a standing order basis. Details on this Branch, DRR ADM, U.S. Nuclear Regulatory Commission, service may be obtained by writing NTIS, 5285 Rort Royal Road, Washington, D6 20555. Springfield, VA 22161. | ||
licensing actions. These methods reflect the latest gen eral NRC approach to administration of nuclear critical ity safety programs for operations with fissionable materials at fuels and materials facilities. | licensing actions. These methods reflect the latest gen-eral NRC approach to administration of nuclear critical-ity safety programs for operations with fissionable materials at fuels and materials facilities. | ||
Therefore, except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the methods described in this guide will be used in the evaluation of submittals in connection with license applications submitted under 10 CFR Part 70.3. | Therefore, except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the methods described in this guide will be used in the evaluation of submittals in connection with license applications submitted, under 10 CFR Part 70.i.3.5 7-2 VALUE/IMPACT | ||
STATEMENT The NRC staff performed a value/impact assessment to | STATEMENT The NRC staff performed a value/impact assessment to determine the proper procedural approach for providing guidance on administration of nuclear criticality safety programs for operations with fissionable materials at fuels and materials facilities. | ||
The NRC staff has been involved in the development, review, and approval of ANSI/ANS 8.19-1984, "Administrative Practices for Nuclear Criticality Safety," which was approved by the American National Standards Institute on October 1, 1984. The assessment resulted in a decision to develop a regulatory guide that would endorse, with possible supplemental provisions, ANSI/ANS-8.19-1984. | The NRC staff has been involved in the development, review, and approval of ANSI/ANS-8.19-1984, "Administrative Practices for Nuclear Criticality Safety," which was approved by the American National Standards Institute on October 1, 1984. The assessment resulted in a decision to develop a regulatory guide that would endorse, with possible supplemental provisions, ANSI/ANS-8.19-1984. | ||
The results of this assessment were included in a draft regulatory guide on this subject, CE 501-4, that was issued for public comment in February 1986. Comments received from the public and additional NRC staff review have shown no need to change the value/impact statement published with the proposed regulatory guide. Therefore, the value/impact statement published with the proposed guide is still applicable. | The results of this assessment were included in a draft regulatory guide on this subject, CE 501-4, that was issued for public comment in February 1986. Comments received from the public and additional NRC staff review have shown no need to change the value/impact statement published with the proposed regulatory guide. Therefore, the value/impact statement published with the proposed guide is still applicable. | ||
A copy of the draft regulatory guide (identi fied by its task number, CE 501-4) and its associated value/impact statement is available for inspection and copying for a fee at the NRC Public Document Room at 1717 H Street NW., Washington, DC.3.57-3 | A copy of the draft regulatory guide (identi-fied by its task number, CE 501-4) and its associated value/impact statement is available for inspection and copying for a fee at the NRC Public Document Room at 1717 H Street NW., Washington, DC.3.57-3 | ||
.UNITED STATES NUCLEAR, REGULATORY | |||
COMMISSION | COMMISSION | ||
WASHINGTON, D.C. 20555 | WASHINGTON, D.C. 20555 FIRTCLASSMAIL | ||
IPOSTAGE II HE&E PAOID Ius",cI PEMI o. 0.OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300}} | |||
{{RG-Nav}} | {{RG-Nav}} | ||
Revision as of 02:42, 18 September 2018
| ML12220A066 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1986 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| References | |
| CE-501-4 RG-3.057 | |
| Download: ML12220A066 (4) | |
A U.S. NUCLEAR REGULATORY
COMMISSION
October 1986) REGULATORY
GUIDE OFFICE OF NUCLEAR REGULATORY
RESEARCH REGULATORY
GUIDE 3.57 (Task CE 501-4)ADMINISTRATIVE
PRACTICES
FOR NUCLEAR CRITICALITY
SAFETY AT FUELS AND MATERIALS
FACILITIES
A. INTRODUCTION
Section 70.22, "Contents of Applications," of 10 CFR Part 70, "Domestic Licensing of Special Nuclear Mate-rial," requires that applications for a specific license to own, acquire, deliver, receive, possess, use, or initially transfer special nuclear material contain proposed proce-dures to avoid accidental conditions of criticality.
Section 70.24, "Criticality Accident Requirements," of 10 CFR Part 70 requires licensees who are authorized to possess special nuclear material in excess of certain amounts to maintain emergency procedures for each area in which such licensed special nuclear material is handled, used, or stored to ensure that all personnel withdraw to an area of safety upon the sounding of a criticality accident alarm.The above procedures are elements of ? nuclear criticality safety program for operations with fissionable materials at fuels and materials facilities (i.e., fuel cycle facilities other than nuclear reactors)
in which there exists a potential for criticality accidents.
This guide describes pra9tices acceptable to the NRC staff for administration of such a program.Any information collection activities mentioned in this regulatory guide are contained as requirements in 10 CFR Part 70, which provides the regulatory basis for this guide. The information collection requirements in 10 CFR Part 70 have been cleared under OMB Clearance No. 3150-0009.
B. DISCUSSION
ANSI/ANS-8.19-1984, "Administrative Practices for Nuclear Criticality Safety,"*
was prepared by Subcom-mittee 8, Fissionable Materials Outside Reactors, of the*Copies may be obtained from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60525.Standards Committee of the American Nuclear Society.ANSI/ANS-8.19-1984 was approved by the American National Standards Committee N16, Nuclear Criticality Safety, in early 1984 and by the American National Standards Institute (ANSI) on October 1, 1984.ANSI/ANS-8.19-1984 provides guidance for administra- tion of a nuclear criticality safety program for operations outside of reactors in which there exists a potential for criticality accidents.
This guidance includes delineation of the responsibilities of management, supervision, and the nuclear criticality safety staff as well as objectives and characteristics of operating and emergency procedures.
C. REGULATORY
POSITION The delineation of responsibilities of management, supervision, and the nuclear criticality safety staff as well as objectives and characteristics of operating and emergency procedures contained in ANSI/ANS-8.19-1984 describe practices generally acceptable to the NRC staff for administration of a nuclear criticality safety program for operations with fissionable materials at fuels and materials facilities in which there exists a potential for criticality accidents.
Section 11 of ANSI/ANS-8.19-1984 lists additional documents referred to in the standard.
Endorsement of ANSI/ANS-8.19-1984 by this regulatory guide does not constitute an endorsement of these documents.
D. IMPLEMENTATION
The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for using this regulatory guide.The methods described in this guide were applied to a number of specific cases during reviews and selected USNRC REGULATORY
GUIDES The guides are issued In the following ten broad divisions:
Regulatory Guides are Issued to describe and make available to the public methods acceptable to the NRC staff of Implementing
1. Power Reactors 6. Products specific parts of the Commission's regulations, to delineate tech- 2. Research and Test Reactors 7. Transportation niques used by the staff In evaluating specific problems or postu- 3. Fuels and Materials Facilities
8. Occupational Health lated accidents or to provide guidance to applicants.
Regulatory
4. Environmental and Siting 9. Antitrust and Financial Review Guides are not substitutes for regulations, and compliance with 5. Materials and Plant Protection
10. General them Is not required.
Methods and solutions different from those set out in the guides will be acceptable If they provide a basis for the findings requisite to the Issuance or continuance of a permit or Copies of Issued guides may be purchased from the Government license by the Commission.
Printing Office at the current GPO price. Information on current.GPO prices may be obtained by contacting the Superintendent of This guide was Issued after consideration of comments received from Documents, U.S. Government Printing Office, Post Office Box the public. Comments and suggestions for Improvements In these 37082, Washington, DC 20013-7082, telephone
(202)275-2060
or guides are encouraged at all times, and guides will be revised, as (202)275-2171.
appropriate, to accommodate comments and to reflect new Informa-tion or experience.
Issued guides may also be purchased from the National Technical Written comments may be submitted to the Rules and Procedures information Service on a standing order basis. Details on this Branch, DRR ADM, U.S. Nuclear Regulatory Commission, service may be obtained by writing NTIS, 5285 Rort Royal Road, Washington, D6 20555. Springfield, VA 22161.
licensing actions. These methods reflect the latest gen-eral NRC approach to administration of nuclear critical-ity safety programs for operations with fissionable materials at fuels and materials facilities.
Therefore, except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the methods described in this guide will be used in the evaluation of submittals in connection with license applications submitted, under 10 CFR Part 70.i.3.5 7-2 VALUE/IMPACT
STATEMENT The NRC staff performed a value/impact assessment to determine the proper procedural approach for providing guidance on administration of nuclear criticality safety programs for operations with fissionable materials at fuels and materials facilities.
The NRC staff has been involved in the development, review, and approval of ANSI/ANS-8.19-1984, "Administrative Practices for Nuclear Criticality Safety," which was approved by the American National Standards Institute on October 1, 1984. The assessment resulted in a decision to develop a regulatory guide that would endorse, with possible supplemental provisions, ANSI/ANS-8.19-1984.
The results of this assessment were included in a draft regulatory guide on this subject, CE 501-4, that was issued for public comment in February 1986. Comments received from the public and additional NRC staff review have shown no need to change the value/impact statement published with the proposed regulatory guide. Therefore, the value/impact statement published with the proposed guide is still applicable.
A copy of the draft regulatory guide (identi-fied by its task number, CE 501-4) and its associated value/impact statement is available for inspection and copying for a fee at the NRC Public Document Room at 1717 H Street NW., Washington, DC.3.57-3
.UNITED STATES NUCLEAR, REGULATORY
COMMISSION
WASHINGTON, D.C. 20555 FIRTCLASSMAIL
IPOSTAGE II HE&E PAOID Ius",cI PEMI o. 0.OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300