Regulatory Guide 3.57: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(3 intermediate revisions by the same user not shown)
Line 1: Line 1:
{{Adams
{{Adams
| number = ML003739485
| number = ML12220A066
| issue date = 10/31/1986
| issue date = 10/31/1986
| title = (Task CE 501-4), Administrative Practices for Nuclear Criticality Safety at Fuels and Materials Facilities (Withdrawn 8/1998)
| 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-3.57
| 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
COMMISSION
                        U.S. NUCLEAR REGULATORY COMMISSION                                                                 October 1986
October 1986) REGULATORY  
                  ) REGULATORY GUIDE
GUIDE OFFICE OF NUCLEAR REGULATORY  
                        OFFICE OF NUCLEAR REGULATORY RESEARCH
RESEARCH REGULATORY  
                                                      REGULATORY GUIDE 3.57 (Task CE 501-4)
GUIDE 3.57 (Task CE 501-4) ADMINISTRATIVE  
                    ADMINISTRATIVE PRACTICES FOR NUCLEAR CRITICALITY SAFETY
PRACTICES  
                                        AT FUELS AND MATERIALS FACILITIES
FOR NUCLEAR CRITICALITY  
SAFETY AT FUELS AND MATERIALS  
FACILITIES


==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.
Standards Committee of the American Nuclear Society.


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 a nuclear criticality safety program for operations with fissionable
ANSI/ANS-8.19-1984 was approved by the American Section 70.22, "Contents of Applications," of 10 CFR               National Standards Committee N16, Nuclear Criticality Part 70, "Domestic Licensing of Special Nuclear Mate-                  Safety, in early 1984 and by the American National rial," requires that applications for a specific license              Standards Institute (ANSI) on October 1, 1984.
-' 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 praqtices acceptable to the NRC staff for administration of such a program.
to own, acquire, deliver, receive, possess, use, or initially transfer special nuclear material contain proposed proce-                  ANSI/ANS-8.19-1984 provides guidance for administra- dures to avoid accidental conditions of criticality.                  tion of a nuclear criticality safety program for operations Section 70.24, "Criticality Accident Requirements," of                outside of reactors in which there exists a potential for
10 CFR Part 70 requires licensees who are authorized                  criticality accidents. This guidance includes delineation of to possess special nuclear material in excess of certain              the responsibilities of management, supervision, and the amounts to maintain emergency procedures for each                      nuclear criticality safety staff as well as objectives and area in which such licensed special nuclear material is                characteristics of operating and emergency procedures.


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.
handled, used, or stored to ensure that all personnel withdraw to an area of safety upon the sounding of a                                   


==B. DISCUSSION==
==C. REGULATORY POSITION==
ANSI/ANS-8.19-1984, "Administrative Practices for Nuclear Criticality Safety,"*
criticality accident alarm.
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.
The delineation of responsibilities of management, The above procedures are elements of ? nuclear                    supervision, and the nuclear criticality safety staff as criticality safety program for operations with fissionable            well as objectives and characteristics of operating and materials at fuels and materials facilities (i.e., fuel cycle          emergency procedures contained in ANSI/ANS-8.19-1984 facilities other than nuclear reactors) in which there                describe practices generally acceptable to the NRC staff exists a potential for criticality accidents. This guide              for administration of a nuclear criticality safety program describes pra9tices acceptable to the NRC staff for                    for operations with fissionable materials at fuels and administration of such a program.                                      materials facilities 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.
Any information collection activities mentioned in this regulatory guide are contained as requirements in                      Section 11 of ANSI/ANS-8.19-1984 lists additional
10 CFR Part 70, which provides the regulatory basis for                documents referred to in the standard. Endorsement of this guide. The information collection requirements in                  ANSI/ANS-8.19-1984 by this regulatory guide does not
10 CFR Part 70 have been cleared under OMB Clearance                  constitute an endorsement of these documents.


C. REGULATORY
No. 3150-0009.
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.
==D. IMPLEMENTATION==


Endorsement of ANSI/ANS-8.19-1984 by this regulatory guide does not constitute an endorsement of these documents.
==B. DISCUSSION==
The purpose of this section is to provide information ANSI/ANS-8.19-1984, "Administrative Practices for                  to applicants and licensees regarding the NRC staff's Nuclear Criticality Safety,"* was prepared by Subcom-                  plans for using this regulatory guide.


==D. IMPLEMENTATION==
mittee 8, Fissionable Materials Outside Reactors, of the
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  
    *Copies may be obtained from the American Nuclear Society,              The methods described in this guide were applied to
GUIDES The guides are Issued in the following ten broad divisions:  
555 North Kensington Avenue, La Grange Park, Illinois 60525.          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
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.
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
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.
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.
appropriate, to accommodate comments and to reflect new Informa- tion or experience.


Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of This guide was issued afterconsideration 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
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.
(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.
licensing actions. These methods reflect the latest gen-        an acceptable alternative method for complying with eral NRC approach to administration of nuclear critical-        specified portions of the Commission's regulations, the ity safety programs for operations with fissionable              methods described in this guide will be used in the materials at fuels and materials facilities. Therefore,          evaluation of submittals in connection with license i.


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, DC 20555. Springfield, VA 22161.
except in those cases in which the applicant proposes            applications submitted, under 10 CFR Part 70.


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.
3.5 7-2


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 70.3.57-2 VALUE/IMPACT  
VALUE/IMPACT STATEMENT
STATEMENT The NRC staff performed a value/impact assessment to S"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 performed a value/impact assessment to           included in a draft regulatory guide on this subject, determine the proper procedural approach for providing             CE 501-4, that was issued for public comment in guidance on administration of nuclear criticality safety           February 1986. Comments received from the public and programs for operations with fissionable materials at fuels       additional NRC staff review have shown no need to and materials facilities. The NRC staff has been involved          change the value/impact statement published with the in the development, review, and approval of ANSI/ANS-              proposed regulatory guide. Therefore, the value/impact
8.19-1984, "Administrative Practices for Nuclear Criticality      statement published with the proposed guide is still Safety," which was approved by the American National              applicable. A copy of the draft regulatory guide (identi- Standards Institute on October 1, 1984. The assessment            fied by its task number, CE 501-4) and its associated resulted in a decision to develop a regulatory guide that          value/impact statement is available for inspection and would endorse, with possible supplemental provisions,              copying for a fee at the NRC Public Document Room ANSI/ANS-8.19-1984. The results of this assessment were            at 1717 H Street NW., Washington, DC.


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.
3.57-3


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.
.UNITED STATES            FIRTCLASSMAIL
NUCLEAR, REGULATORY COMMISSION    IPOSTAGE II HE&EPAOID
    WASHINGTON, D.C. 20555          Ius",cI
                                      PEMI o.0.


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
OFFICIAL BUSINESS
)UNITED STATES NUCLE-,.. -EGULATORY
    PENALTY FOR PRIVATE USE, $300}}
COMMISSION
WASHINGTON, D.C. 20555-0001
/OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 PRINTED ON RECYCLED PAPER FIRST CL )MAIL POSTAGE AND FEES PAID USNRC PERMIT NO. G 67}}


{{RG-Nav}}
{{RG-Nav}}

Latest revision as of 01:05, 12 November 2019

Administrative Practices for Nuclear Criticality Safety at Fuels and Materials Facilities
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

Standards Committee of the American Nuclear Society.

ANSI/ANS-8.19-1984 was approved by the American Section 70.22, "Contents of Applications," of 10 CFR National Standards Committee N16, Nuclear Criticality Part 70, "Domestic Licensing of Special Nuclear Mate- Safety, in early 1984 and by the American National rial," requires that applications for a specific license Standards Institute (ANSI) on October 1, 1984.

to own, acquire, deliver, receive, possess, use, or initially transfer special nuclear material contain proposed proce- ANSI/ANS-8.19-1984 provides guidance for administra- dures to avoid accidental conditions of criticality. tion of a nuclear criticality safety program for operations Section 70.24, "Criticality Accident Requirements," of outside of reactors in which there exists a potential for

10 CFR Part 70 requires licensees who are authorized criticality accidents. This guidance includes delineation of to possess special nuclear material in excess of certain the responsibilities of management, supervision, and the amounts to maintain emergency procedures for each nuclear criticality safety staff as well as objectives and area in which such licensed special nuclear material is characteristics of operating and emergency procedures.

handled, used, or stored to ensure that all personnel withdraw to an area of safety upon the sounding of a

C. REGULATORY POSITION

criticality accident alarm.

The delineation of responsibilities of management, The above procedures are elements of ? nuclear supervision, and the nuclear criticality safety staff as criticality safety program for operations with fissionable well as objectives and characteristics of operating and materials at fuels and materials facilities (i.e., fuel cycle emergency procedures contained in ANSI/ANS-8.19-1984 facilities other than nuclear reactors) in which there describe practices generally acceptable to the NRC staff exists a potential for criticality accidents. This guide for administration of a nuclear criticality safety program describes pra9tices acceptable to the NRC staff for for operations with fissionable materials at fuels and administration of such a program. materials facilities in which there exists a potential for criticality accidents.

Any information collection activities mentioned in this regulatory guide are contained as requirements in Section 11 of ANSI/ANS-8.19-1984 lists additional

10 CFR Part 70, which provides the regulatory basis for documents referred to in the standard. Endorsement of this guide. The information collection requirements in ANSI/ANS-8.19-1984 by this regulatory guide does not

10 CFR Part 70 have been cleared under OMB Clearance constitute an endorsement of these documents.

No. 3150-0009.

D. IMPLEMENTATION

B. DISCUSSION

The purpose of this section is to provide information ANSI/ANS-8.19-1984, "Administrative Practices for to applicants and licensees regarding the NRC staff's Nuclear Criticality Safety,"* was prepared by Subcom- plans for using this regulatory guide.

mittee 8, Fissionable Materials Outside Reactors, of the

  • Copies may be obtained from the American Nuclear Society, The methods described in this guide were applied to

555 North Kensington Avenue, La Grange Park, Illinois 60525. 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- an acceptable alternative method for complying with eral NRC approach to administration of nuclear critical- specified portions of the Commission's regulations, the ity safety programs for operations with fissionable methods described in this guide will be used in the materials at fuels and materials facilities. Therefore, evaluation of submittals in connection with license i.

except in those cases in which the applicant proposes applications submitted, under 10 CFR Part 70.

3.5 7-2

VALUE/IMPACT STATEMENT

The NRC staff performed a value/impact assessment to included in a draft regulatory guide on this subject, determine the proper procedural approach for providing CE 501-4, that was issued for public comment in guidance on administration of nuclear criticality safety February 1986. Comments received from the public and programs for operations with fissionable materials at fuels additional NRC staff review have shown no need to and materials facilities. The NRC staff has been involved change the value/impact statement published with the in the development, review, and approval of ANSI/ANS- proposed regulatory guide. Therefore, the value/impact

8.19-1984, "Administrative Practices for Nuclear Criticality statement published with the proposed guide is still Safety," which was approved by the American National applicable. A copy of the draft regulatory guide (identi- Standards Institute on October 1, 1984. The assessment fied by its task number, CE 501-4) and its associated resulted in a decision to develop a regulatory guide that value/impact statement is available for inspection and would endorse, with possible supplemental provisions, copying for a fee at the NRC Public Document Room ANSI/ANS-8.19-1984. The results of this assessment were at 1717 H Street NW., Washington, DC.

3.57-3

.UNITED STATES FIRTCLASSMAIL

NUCLEAR, REGULATORY COMMISSION IPOSTAGE II HE&EPAOID

WASHINGTON, D.C. 20555 Ius",cI

PEMI o.0.

OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300