Regulatory Guide 3.45: Difference between revisions

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{{Adams
{{Adams
| number = ML12184A017
| number = ML122430316
| issue date = 11/30/1980
| issue date = 04/30/1989
| title = Nuclear Criticality Safety for Pipe Intersections Containing Aqueous Solutions of Enriched Uranyl Nitrate.
| title = Nuclear Criticality Safety for Steel-Pipe Intersections Containing Aqueous Solutions of Fissile Materials
| author name =  
| author name =  
| author affiliation = NRC/RES, NRC/OSD
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| case reference number = Task FP 925-5
| case reference number = CE 802-5
| document report number = RG-3.045
| document report number = RG 3.45, Rev. 1
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 2
| page count = 4
}}
}}
{{#Wiki_filter:November.
{{#Wiki_filter:Z ~ .- r"~ , %- (U.S. NUCLEAR REGULATORY  
 
.1 B8 U.S. NUCLEAR REGULATORY  
COMMISSION
COMMISSION
REGULATORY  
REGULATORY
GUIDE'" OFFICE OF STANDARDS
Revision 1 April 1989 GUIDE OFFICE OF NUCLEAR REGULATORY
DEVELOPMENT
RESEARCH REGULATORY  
REGULATORY  
GUIDE 3.45 (Task CE 802-5)NUCLEAR CRITICALITY  
GUIDE 3.45 (Task FP 925-5)NUCLEAR CRITICALITY  
SAFETY FOR STEEL-PIPE  
SAFETY FOR PIPE INTERSECTIONS  
INTERSECTIONS  
CONTAINING
CONTAINING
AQUEOUS SOLUTIONS  
AQUEOUS SOLUTIONS  
OF ENRICHED URANYL NITRATE
OF FISSILE MATERIALS


==A. INTRODUCTION==
==A. INTRODUCTION==
Section 70.22, "Contents of Applications," of 10 CFR Part 70,"Domestic Licensing of Special Nuclear Material," requires that applications for a specific license to own, acquire, deliver, receive, possess, use, or transfer special nuclear material con-tain proposed procedures to avoid accidental conditions of criticality.
Section 70.22, "Contents of Applications," of 10 CFR Part 70, "Domestic Licensing of Special Nu-clear Material," requires that applications for a spe-cific license to own, acquire, deliver, receive, possess, use, or transfer special nuclear material contain pro-posed procedures to avoid accidental conditions of criticality.


This regulatory guide provides guidance for com-plying with this portion of the Commission's regulations by describing procedures acceptable to the NRC staff for the prevention of criticality accidents in the storage and process-ing of aqueous solutions of enriched uranyl nitrate in pipe intersections.
This regulatory guide provides guidance for complying with this portion of the Commission's regu-lations by describing procedures acceptable to the NRC staff for the prevention of criticality accidents in the storage and processing of aqueous solutions of fis-sile materials in steel-pipe intersections.
 
Any information collection activities mentioned in this regulatory guide are contained as requirements in 10 CFR Part 70, which provides the regulatory ba-sis for this guide. The information collection require-ments in 10 CFR Part 70 have been cleared under OMB Clearance No. 3150-0009.


==B. DISCUSSION==
==B. DISCUSSION==
ANSI/ANS 8.9-1978, "Nuclear Criticality Safety Guide for Pipe Intersections Containing Aqueous Solutions of Enriched Uranyl Nitrate,"I
ANSI/ANS-8.9-1987, "Nuclear Criticality Safety Criteria for Steel-Pipe Intersections Containing Aque-ous Solutions of Fissile Material,"'
was prepared by Subcommittee  
was prepared by Subcommittee  
8, Fission-able Materials Outside Reactors, of the Standards Committee of the American Nuclear Society. ANSI/ANS 8.9-1978 was approved by the American National Standards Committee N 16, Nuclear Criticality Safety, in 1977 and subsequently by the American National Standards Institute (ANSI) on February 15, 1978.ANSI/ANS 8.9-1978 is applicable only to the storage and processing of homogeneous aqueous solutions of uranyl nitrate containing no more than 93.5 wt-% U-235 in intersecting pipe geometries consisting of single central columns with smaller intersecting arms. The standard presents tabulated maximum safe values, derived from an empirical model based on validated calculations and experimental data, for both the central column diameter and the total area of intersection of the arms with the column for conditions of partial and total reflection.
8, Fissionable Materials Outside Reac-tors, of the Standards Committee of the American Nuclear Society. ANSI/ANS 8.9-1987 was approved'Copies may be obtained from the American Nuclear Society, 555 N. Kensington Avenue, La Grange Park, IL 60525.by the American National Standards Institute (ANSI)on April 3, 1987.ANSI/ANS-8.9-1987 provides specifications for pipe intersections containing homogeneous aqueous solutions of fissile materials.
 
The standard also presents a general procedure to ascertain the safety of specific pipe intersections as well as guidance on model parameters and ICopies may be obtained from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60525.limitations.


In intersecting pipe geometries where the model does not apply, e.g., multiple columns or columns in the vicinity of other fissionable materials, the standard requires that experimental data or validated computational techniques be used to determine the safe configuration.
All dimensions are inter-preted as nominal values of schedule 10 or heavier standard steel pipe. Only single columns with inter-sections are considered in the standard.


C. REGULATORY
For multiple columns or columns in the vicinity of other fissile ma-terials and the influence of environmental factors, the standard requires that experimental data or validated computational techniques be used to determine the safe configuration.
POSITION The nuclear criticality safety practices and guidance for calculating safe pipe intersections for enriched uranyl nitrate solutions contained in ANSI/ANS 8.9-1978 provide procedures generally acceptable to the NRC staff for the prevention of criticality accidents in the storage and processing of aqueous solutions of enriched uranyl nitrate in pipe intersections.


Section 6 of ANSI/ANS 8.9-1978 lists additional documents referred to in the standard.
Criteria and data provided are based on criticality experiments and validated calcu-lations that are generally applicable to homogeneous aqueous solutions of fissile materials.


The specific applicability or acept-ability of two of these listed documents has been addressed in the latest version of the regulatory guides identified below: Standard'ANSI N16.1-1975 ANSI N16.9-1975 Regulatory Guide 3.4 3.41
Specific infor-mation is included on fissile solutions containing ura-nium enriched in the 2 35U or 2 3 3 U isotope or pluto-nium and on uranium solutions having a 2 3U content not exceeding
5 weight-percent of the total uranium.C. REGULATORY
POSITION The nuclear criticality safety practices and guid-ance for calculating safe steel-pipe intersections for aqueous solutions of fissile materials contained in ANSI/ANS-8.9-1987 provide procedures generally acceptable to the NRC staff for the prevention of criticality accidents in the storage and processing of aqueous solutions of fissile materials.


==D. IMPLEMENTATION==
USNRC REGUIATORY
The purpose of this section is to provide information to applicants regarding the NRC staff's plan for using this regulatory guide.The methods described in this guide were applied in a unnber of specific cases during reviews and selected licensing actions.These methods reflect the latest general NRC approach to criticality safety in the storage and processing of aqueous solu-tions of enriched uranyl nitrate in pipe intersections.
GUIDES Regulatory Guides are Issued to describe and make available to the pub-lic methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specific problems or postulated accidents, or to pro-vide guidance to applicants.


There-fore, except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used in the evaluation of submittals for license applications submitted pursuant to 10 CFR Part 7
Regulatory Guides are not substitutes for regulations, and compliance with them is not required.


===0. USNRC REGULATORY ===
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 continu-ance of a permit or license by the Commission.
GUIDES Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission Washington, D.C. 20555, Regulatory Guides are Issued to describe and make available to the Attention:
Docketing and Service Branch.Public methods acceptable to the NRC staff of Implementing specific parts of the Commission's regulations, to delineate tech. The guides are Issued In the following ten broad divisions:
niques used by the staff In evaluating specific problems or postu-lated accidents, or to provide guidance to applicants.


Regulatory
This guide was issued after consideration of comments received from the public. Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as ap-propriate, to accommodate comments and to reflect new information or experience.
1. Power Reactors 6. Products Guides are not substitutes for regulations, and compliance with 2. Research and Test Reactors 7. Transportation them Is not required.


Methods and solutions different from those set 3. Fuels and Materials Facilities  
Written comments may be submitted to the Regulatory Publications Branch, DFIPS, ARM, U.S. Nuclear Regulatory Commission, Washing-ton, DC 20555.The guides are Issued in the following ten broad divisions:
8. Occupational Health out In the guides will be acceptable If they Provide a basis for the 4. Environmental and Siting 9. Antitrust and Financial Review findings requisite to the issuance or continuance of a permit or 5. Materials and Plant Protection  
1. Power Reactors 2. Research and Test Reactors 3. Fuels and Materials Facilities
10. General license by the Commission.
4. Environmental and Siting 5. Materials and Plant Protection
6. Products


Copies of Issued guides may be Purchased at the current Government Comments and suggestions for Improvements in these guides are Printing Office price. A subscription service for future guldes In ap-encouraged at all times, and guides will be revised, as appropriate, cific divisions Is available through the Government Prnting Office.to accommodate comments and to reflect new information or Information on the subscription service and current GPO Prices may experience.
===7. Transportation===
8. Occupational Health 9. Antitrust and Financial Review 10. General Copies of issued guides may be purchased from the Government Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of Documents, U.S.Government Printing Office, Post Office Box 37082, Washington, DC 20013-70B2, telephone
(202)275-2060
or (202)275-2171.


This guide was revised as a result of substantive com- be obtained by writing the U.S. Nuclear Regulatory Commission, ments received from the public and additional staff review. Washington, D.C. 20555, Attention:
Issued guides may also be purchased from the National Technical Infor-mation Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22161.
Publications Sales Manager.


VALUE/IMPACT
==D. IMPLEMENTATION==
STATEMENT*
The purpose of this section is to provide informa-tion to applicants regarding the NRC staff's plan for using this regulatory guide.These methods reflect the latest general NRC ap-proach to criticality safety in the storage and process-ing of aqueous solutions of fissile materials in steel-pipe intersections.
Regulatory Guide 3.45 (Task FP 925-5) endorses ANSI/ANS 8.9-1978, "Nuclear Criticality Safety Guide for Pipe Intersections Containing Aqueous Solutions of Enriched Uranyl Nitrate," which was approved by the American National Standards Institute on February 15, 1978. The A copy of the draft value/impact statement (published with Draft Guide FP 92$-5 in January 1980) is available for public inspection at 1717 H Street NW., Washington, D.C.nuclear criticality safety practices and guidance for calcula-ting safe pipe intersections contained in ANSI/ANS 8.9-1978 are acceptable to the NRC staff and to industry.


The guide provides a convenient reference for the licensee or license applicant in designing nuclear criticality safety programs to meet regulatory requirements and standards of good nuclear criticality safety practice.
Therefore, except in those cases in which the applicant proposes an acceptable alterna-tive method for complying with the specified portions of the Commission's regulations, the method de-scribed here will be used in the evaluation of submit-tals for license applications submitted pursuant to 10 CFR Part 70.3.45-2 VALUE/IMPACT
STATEMENT A draft value/impact statement was published with the proposed Revision 1 to Regulatory Guide 3.45 (Task CE 802-5) when the draft guide was pub-lished for public comment in May 1988. No changes were necessary, so a separate value/impact statement for the final guide has not been prepared.


The use of this guide should facilitate the licensing process with minimum impact on the NRC staff and industry.4 at Zt (U z 2 u~ 0 00 L)-00 44 -4 U 0 LU z LU..4 z rL)L a- z zL", Z L-40Z W 0 0-" >00 <~0 W l LL-C.,~z 00' C 0.- 0_tb- "0w 0 3.45-2}}
A copy of the draft value/impact statement is available for in-spection and copying for a fee at the Commission's Public Document Room at 2120 L Street NW., Wash-ington, DC, under Task CE 802-5.3.45-3 UNITED STATES NUCLEAR REGULATORY
COMMISSION
WASHINGTON, D.C. 20555 FIRST CLASS MAIL POSTAGE b FEES PAID USNRC PERMIT No. G,67 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300}}


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

Revision as of 06:52, 12 May 2019

Nuclear Criticality Safety for Steel-Pipe Intersections Containing Aqueous Solutions of Fissile Materials
ML122430316
Person / Time
Issue date: 04/30/1989
From:
Office of Nuclear Regulatory Research
To:
References
CE 802-5 RG 3.45, Rev. 1
Download: ML122430316 (4)
v • d • e


Z ~ .- r"~ , %- (U.S. NUCLEAR REGULATORY

COMMISSION

REGULATORY

Revision 1 April 1989 GUIDE OFFICE OF NUCLEAR REGULATORY

RESEARCH REGULATORY

GUIDE 3.45 (Task CE 802-5)NUCLEAR CRITICALITY

SAFETY FOR STEEL-PIPE

INTERSECTIONS

CONTAINING

AQUEOUS SOLUTIONS

OF FISSILE MATERIALS

A. INTRODUCTION

Section 70.22, "Contents of Applications," of 10 CFR Part 70, "Domestic Licensing of Special Nu-clear Material," requires that applications for a spe-cific license to own, acquire, deliver, receive, possess, use, or transfer special nuclear material contain pro-posed procedures to avoid accidental conditions of criticality.

This regulatory guide provides guidance for complying with this portion of the Commission's regu-lations by describing procedures acceptable to the NRC staff for the prevention of criticality accidents in the storage and processing of aqueous solutions of fis-sile materials in steel-pipe intersections.

Any information collection activities mentioned in this regulatory guide are contained as requirements in 10 CFR Part 70, which provides the regulatory ba-sis for this guide. The information collection require-ments in 10 CFR Part 70 have been cleared under OMB Clearance No. 3150-0009.

B. DISCUSSION

ANSI/ANS-8.9-1987, "Nuclear Criticality Safety Criteria for Steel-Pipe Intersections Containing Aque-ous Solutions of Fissile Material,"'

was prepared by Subcommittee

8, Fissionable Materials Outside Reac-tors, of the Standards Committee of the American Nuclear Society. ANSI/ANS 8.9-1987 was approved'Copies may be obtained from the American Nuclear Society, 555 N. Kensington Avenue, La Grange Park, IL 60525.by the American National Standards Institute (ANSI)on April 3, 1987.ANSI/ANS-8.9-1987 provides specifications for pipe intersections containing homogeneous aqueous solutions of fissile materials.

All dimensions are inter-preted as nominal values of schedule 10 or heavier standard steel pipe. Only single columns with inter-sections are considered in the standard.

For multiple columns or columns in the vicinity of other fissile ma-terials and the influence of environmental factors, the standard requires that experimental data or validated computational techniques be used to determine the safe configuration.

Criteria and data provided are based on criticality experiments and validated calcu-lations that are generally applicable to homogeneous aqueous solutions of fissile materials.

Specific infor-mation is included on fissile solutions containing ura-nium enriched in the 2 35U or 2 3 3 U isotope or pluto-nium and on uranium solutions having a 2 3U content not exceeding

5 weight-percent of the total uranium.C. REGULATORY

POSITION The nuclear criticality safety practices and guid-ance for calculating safe steel-pipe intersections for aqueous solutions of fissile materials contained in ANSI/ANS-8.9-1987 provide procedures generally acceptable to the NRC staff for the prevention of criticality accidents in the storage and processing of aqueous solutions of fissile materials.

USNRC REGUIATORY

GUIDES Regulatory Guides are Issued to describe and make available to the pub-lic methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specific problems or postulated accidents, or to pro-vide guidance to 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 will be acceptable if they provide a basis for the findings requisite to the Issuance or continu-ance of a permit or license by the Commission.

This guide was issued after consideration of comments received from the public. Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as ap-propriate, to accommodate comments and to reflect new information or experience.

Written comments may be submitted to the Regulatory Publications Branch, DFIPS, ARM, U.S. Nuclear Regulatory Commission, Washing-ton, DC 20555.The guides are Issued in the following ten broad divisions:

1. Power Reactors 2. Research and Test Reactors 3. Fuels and Materials Facilities

4. Environmental and Siting 5. Materials and Plant Protection

6. Products

7. Transportation

8. Occupational Health 9. Antitrust and Financial Review 10. General Copies of issued guides may be purchased from the Government Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of Documents, U.S.Government Printing Office, Post Office Box 37082, Washington, DC 20013-70B2, telephone

(202)275-2060

or (202)275-2171.

Issued guides may also be purchased from the National Technical Infor-mation Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22161.

D. IMPLEMENTATION

The purpose of this section is to provide informa-tion to applicants regarding the NRC staff's plan for using this regulatory guide.These methods reflect the latest general NRC ap-proach to criticality safety in the storage and process-ing of aqueous solutions of fissile materials in steel-pipe intersections.

Therefore, except in those cases in which the applicant proposes an acceptable alterna-tive method for complying with the specified portions of the Commission's regulations, the method de-scribed here will be used in the evaluation of submit-tals for license applications submitted pursuant to 10 CFR Part 70.3.45-2 VALUE/IMPACT

STATEMENT A draft value/impact statement was published with the proposed Revision 1 to Regulatory Guide 3.45 (Task CE 802-5) when the draft guide was pub-lished for public comment in May 1988. No changes were necessary, so a separate value/impact statement for the final guide has not been prepared.

A copy of the draft value/impact statement is available for in-spection and copying for a fee at the Commission's Public Document Room at 2120 L Street NW., Wash-ington, DC, under Task CE 802-5.3.45-3 UNITED STATES NUCLEAR REGULATORY

COMMISSION

WASHINGTON, D.C. 20555 FIRST CLASS MAIL POSTAGE b FEES PAID USNRC PERMIT No. G,67 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300


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