Regulatory Guide 3.1: Difference between revisions
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{{Adams | {{Adams | ||
| number = | | number = ML12184A009 | ||
| issue date = | | issue date = 01/31/1982 | ||
| title = Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material | | title = Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material. | ||
| 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-3.001, Rev. 1 | |||
| document report number = RG-3.001, Rev. | |||
| document type = Regulatory Guide | | document type = Regulatory Guide | ||
| page count = | | page count = 3 | ||
}} | }} | ||
{{#Wiki_filter: | {{#Wiki_filter:U.S. NUCLEAR REGULATORY | ||
COMMISSION | COMMISSION | ||
REGULATORY | Revision 1 January 1982 REGULATORY | ||
GUIDE OFFICE OF NUCLEAR REGULATORY | GUIDE OFFICE OF NUCLEAR REGULATORY | ||
RESEARCH REGULATORY | RESEARCH REGULATORY | ||
GUIDE 3.1 (Task | GUIDE 3.1 (Task FP 027-5)USE OF BOROSILICATE-GLASS | ||
RASCHIG RINGS AS A NEUTRON ABSORBER IN SOLUTIONS | RASCHIG RINGS AS A NEUTRON ABSORBER IN SOLUTIONS | ||
OF FISSILE MATERIAL | OF FISSILE MATERIAL | ||
Line 30: | Line 28: | ||
Procedures for this purpose include incorporating neutron-absorbing material such as boron in process equipment. | Procedures for this purpose include incorporating neutron-absorbing material such as boron in process equipment. | ||
This regulatory guide provides guidance for complying with this portion of the Commission's regulations by describing procedures accept-able to the NRC staff for the prevention of criticality accidents by use of borosilicate-glass raschig rings as a neutron absorber in solutions of fissile material | This regulatory guide provides guidance for complying with this portion of the Commission's regulations by describing procedures accept-able to the NRC staff for the prevention of criticality accidents by use of borosilicate-glass raschig rings as a neutron absorber in solutions of fissile material. | ||
==B. DISCUSSION== | ==B. DISCUSSION== | ||
ANSI/ANS | ANSI/ANS 8.5-1979, "Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material," 1 is a revision of ANSI N16.4-1971 and was prepared by Subcommittee | ||
8, Fissionable Materials Outside Reactors, of the Standards Committee of the American Nuclear Society. ANSI/ANS | 8, Fissionable Materials Outside Reactors, of the Standards Committee of the American Nuclear Society.ANSI/ANS 8.5-1979 was approved by the American National Standards Committee N16, Nuclear Criticality Safety, in early 1979 and by the American National Stand-ards Institute (ANSI) on October 9, 1979.ANSI/ANS 8.5-1979 provides guidance on the use of borosilicate-glass raschig rings as a neutron absorber in solutions of fissile material. | ||
The standard applies to the use of borosilicate-glass raschig rings for primary and for secondary criticality control in solutions containing | The standard applies to the use of borosilicate-glass raschig rings for primary and for secondary criticality control in solutions containing | ||
235U, 2 3 9 pu, and 2 3 3 U. The chemical and physical environment, properties of the rings and packed vessels, maintenance inspection procedures, and Zriticality operating limits are specified in the standard.Maximum permissible concentrations of homogeneous solutions of plutonium or of uranium in vessels of unlimited size packed with borosilicate-glass raschig rings are specified in the standard. | |||
The concentration of these solutions is expressed as the mass of plutonium or of uranium per unit volume. The density of hydrogen in any solution cannot be less than 75 g/liter nor greater than 115 g/liter.Limitations on the relative abundance of the various isotopes of | The concentration of these solutions is expressed as the mass of plutonium or of uranium per unit volume. The density of hydrogen in any solution cannot be less than 75 g/liter nor greater than 115 g/liter. Limitations on the relative abundance of the various isotopes of pluto-nium are imposed in the specifications applicable .to pluto-nium solutions. | ||
The concentrations specified for solutions of 2 3 3 U also apply to mixtures of 2 3 3 U and other uranium isotopes.C. REGULATORY | The concentrations specified for uranium enriched in 235U apply regardless of the 235U enrichment but with a limitation on the 233U content. For solutions of uranium containing up to 5.0 wt-% 2 3 5 U and no 233U, the limitations are expressed as mass of 235 U per unit volume.The concentrations specified for- solutions of 2 3 3 U also apply to mixtures of 2 3 3 U and other uranium isotopes provided the 2 3 3 U content is greater than 1 wt-% of all the uranium.C. REGULATORY | ||
POSITION The guidance contained in ANSI/ANS | POSITION The guidance contained in ANSI/ANS 8.5-1979 for the use of borosilicate-glass raschig rings as a neutron absorber in solutions of fissile material provides a procedure generally acceptable to the NRC staff for the prevention of accidental conditions of criticality. | ||
Section 8.0 of ANSI/ANS 8.5-1979 lists additional docu-ments referred to in the standard. | |||
The specific applicability or acceptability of these listed documents will be covered separately in other regulatory guides, where appropriate. | |||
==D. IMPLEMENTATION== | |||
The purpose of this section is to provide information to applicants regarding the NRC staff's plan for using this regulatory guide.Lines indicate substantive changes from previous issue.ICopies may be obtained from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 6052 | |||
===5. USNRC REGULATORY === | |||
GUIDES Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate tech-niques used by the staff in evaluating specific problems or postu-lated accidents, or to provide 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 continuance 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 appropriate, to accommodate comments and to reflect new informa-tion or experience. | |||
Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: | |||
Docketing and Service Branch.The guides are issued in the following ten broad divisions: | |||
1. Power Reactors 6. Products 2. Research and Test Reactors | 1. Power Reactors 6. Products 2. Research and Test Reactors | ||
Line 58: | Line 65: | ||
3. Fuels and Materials Facilities | 3. Fuels and Materials Facilities | ||
8. Occupational Health 4. Environmental and Siting 9. Antitrust and Financial Review 5. Materials and Plant Protection | 8. Occupational Health 4. Environmental and Siting 9. Antitrust and Financial Review 5. Materials and Plant Protection | ||
10. General Copies of | 10. General Copies of issued guides may be purchased at the current Government Printing Office price. A subscription service for future guides in spe-cific divisions is available through the Government Printing Office.Information on the subscription service and current GPO prices may be obtained by writing the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: | ||
Publications Sales Manager. | |||
The methods described in this guide were applied in a number of specific cases during reviews and selected licensing actions. These methods reflect the latest general NRC approach to criticality safety, in operations involving use of borosilicate-glass raschig rings as a neutron absorber in solutions of fissile material. | |||
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 herein will be used after the issuance of this guide in the evaluation | |||
4 of submittals in connection with license applications submitted under 10 CFR Part 70.VALUE/IMPACT | |||
STATEMENT The NRC staff performed a value/impact assessment to determine the proper procedural approach for updating Regulatory Guide 3.1, "Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material," dated January 1973, which endorsed ANSI Standard N16.4-1971. | |||
The NRC staff has been involved in the development, review, and approval of a revision to ANSI N16.4-1971 (designated ANSI/ANS 8.5-1979), which was approved by. the American National Standards Institute on October 9, 1979. The assessment resulted in a decision to develop a revision to Regulatory Guide 3.1 that would endorse, with possible supplemental provisions, ANSI/ANS 8.5-1979. | |||
The | The results of this assessment were included in a draft regulatory guide on this subject that was issued for public comment in May 1981. Since no comments have been received from the public, there has been no need to change the regulatory position of the proposed revision to Regulatory Guide 3.1. A copy of the draft regulatory guide and the associated value/impact statement (identified by its task number, FP 027-5) is available for inspection and copying for a fee at the Commission's Public Document Room at 1717 H Street NW., Washington, D.C.3.1-2 UNITED STATES NUCL-AR REGULATORY | ||
COMMISSION | |||
WASHINGTON. | |||
D. C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 POSTAGE AND FEES PAID U.S. NUCLEAR REGULATORY | |||
COMMISSION | COMMISSION | ||
119406002001 | |||
1 US NRC REGION .I R J BORES 631 PARK AVENUE REGION I KING OF PRUSSIA QP PA 19406}} | |||
{{RG-Nav}} | {{RG-Nav}} |
Revision as of 17:19, 28 June 2019
ML12184A009 | |
Person / Time | |
---|---|
Issue date: | 01/31/1982 |
From: | Office of Nuclear Regulatory Research |
To: | |
References | |
RG-3.001, Rev. 1 | |
Download: ML12184A009 (3) | |
U.S. NUCLEAR REGULATORY
COMMISSION
Revision 1 January 1982 REGULATORY
GUIDE OFFICE OF NUCLEAR REGULATORY
RESEARCH REGULATORY
GUIDE 3.1 (Task FP 027-5)USE OF BOROSILICATE-GLASS
RASCHIG RINGS AS A NEUTRON ABSORBER IN SOLUTIONS
OF FISSILE MATERIAL
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 contain proposed procedures to avoid accidental conditions of criticality.
Procedures for this purpose include incorporating neutron-absorbing material such as boron in process equipment.
This regulatory guide provides guidance for complying with this portion of the Commission's regulations by describing procedures accept-able to the NRC staff for the prevention of criticality accidents by use of borosilicate-glass raschig rings as a neutron absorber in solutions of fissile material.
B. DISCUSSION
ANSI/ANS 8.5-1979, "Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material," 1 is a revision of ANSI N16.4-1971 and was prepared by Subcommittee
8, Fissionable Materials Outside Reactors, of the Standards Committee of the American Nuclear Society.ANSI/ANS 8.5-1979 was approved by the American National Standards Committee N16, Nuclear Criticality Safety, in early 1979 and by the American National Stand-ards Institute (ANSI) on October 9, 1979.ANSI/ANS 8.5-1979 provides guidance on the use of borosilicate-glass raschig rings as a neutron absorber in solutions of fissile material.
The standard applies to the use of borosilicate-glass raschig rings for primary and for secondary criticality control in solutions containing
235U, 2 3 9 pu, and 2 3 3 U. The chemical and physical environment, properties of the rings and packed vessels, maintenance inspection procedures, and Zriticality operating limits are specified in the standard.Maximum permissible concentrations of homogeneous solutions of plutonium or of uranium in vessels of unlimited size packed with borosilicate-glass raschig rings are specified in the standard.
The concentration of these solutions is expressed as the mass of plutonium or of uranium per unit volume. The density of hydrogen in any solution cannot be less than 75 g/liter nor greater than 115 g/liter. Limitations on the relative abundance of the various isotopes of pluto-nium are imposed in the specifications applicable .to pluto-nium solutions.
The concentrations specified for uranium enriched in 235U apply regardless of the 235U enrichment but with a limitation on the 233U content. For solutions of uranium containing up to 5.0 wt-% 2 3 5 U and no 233U, the limitations are expressed as mass of 235 U per unit volume.The concentrations specified for- solutions of 2 3 3 U also apply to mixtures of 2 3 3 U and other uranium isotopes provided the 2 3 3 U content is greater than 1 wt-% of all the uranium.C. REGULATORY
POSITION The guidance contained in ANSI/ANS 8.5-1979 for the use of borosilicate-glass raschig rings as a neutron absorber in solutions of fissile material provides a procedure generally acceptable to the NRC staff for the prevention of accidental conditions of criticality.
Section 8.0 of ANSI/ANS 8.5-1979 lists additional docu-ments referred to in the standard.
The specific applicability or acceptability of these listed documents will be covered separately in other regulatory guides, where appropriate.
D. IMPLEMENTATION
The purpose of this section is to provide information to applicants regarding the NRC staff's plan for using this regulatory guide.Lines indicate substantive changes from previous issue.ICopies may be obtained from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 6052
5. USNRC REGULATORY
GUIDES Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate tech-niques used by the staff in evaluating specific problems or postu-lated accidents, or to provide 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 continuance 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 appropriate, to accommodate comments and to reflect new informa-tion or experience.
Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention:
Docketing and Service Branch.The guides are issued in the following ten broad divisions:
1. Power Reactors 6. Products 2. Research and Test Reactors
7. Transportation
3. Fuels and Materials Facilities
8. Occupational Health 4. Environmental and Siting 9. Antitrust and Financial Review 5. Materials and Plant Protection
10. General Copies of issued guides may be purchased at the current Government Printing Office price. A subscription service for future guides in spe-cific divisions is available through the Government Printing Office.Information on the subscription service and current GPO prices may be obtained by writing the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention:
Publications Sales Manager.
The methods described in this guide were applied in a number of specific cases during reviews and selected licensing actions. These methods reflect the latest general NRC approach to criticality safety, in operations involving use of borosilicate-glass raschig rings as a neutron absorber in solutions of fissile material.
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 herein will be used after the issuance of this guide in the evaluation
4 of submittals in connection with license applications submitted under 10 CFR Part 70.VALUE/IMPACT
STATEMENT The NRC staff performed a value/impact assessment to determine the proper procedural approach for updating Regulatory Guide 3.1, "Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material," dated January 1973, which endorsed ANSI Standard N16.4-1971.
The NRC staff has been involved in the development, review, and approval of a revision to ANSI N16.4-1971 (designated ANSI/ANS 8.5-1979), which was approved by. the American National Standards Institute on October 9, 1979. The assessment resulted in a decision to develop a revision to Regulatory Guide 3.1 that would endorse, with possible supplemental provisions, ANSI/ANS 8.5-1979.
The results of this assessment were included in a draft regulatory guide on this subject that was issued for public comment in May 1981. Since no comments have been received from the public, there has been no need to change the regulatory position of the proposed revision to Regulatory Guide 3.1. A copy of the draft regulatory guide and the associated value/impact statement (identified by its task number, FP 027-5) is available for inspection and copying for a fee at the Commission's Public Document Room at 1717 H Street NW., Washington, D.C.3.1-2 UNITED STATES NUCL-AR REGULATORY
COMMISSION
D. C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 POSTAGE AND FEES PAID U.S. NUCLEAR REGULATORY
COMMISSION
119406002001
1 US NRC REGION .I R J BORES 631 PARK AVENUE REGION I KING OF PRUSSIA QP PA 19406