Regulatory Guide 3.1: Difference between revisions
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{{Adams | {{Adams | ||
| number = | | number = ML12220A057 | ||
| issue date = 09/30/1987 | | issue date = 09/30/1987 | ||
| title = | | 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 = | ||
| case reference number = CE 602-4 | |||
| document report number = RG-3.001, Rev. 2 | | document report number = RG-3.001, Rev. 2 | ||
| document type = Regulatory Guide | | document type = Regulatory Guide | ||
Line 20: | Line 21: | ||
GUIDE OFFICE OF NUCLEAR REGULATORY | GUIDE OFFICE OF NUCLEAR REGULATORY | ||
RESEARCH REGULATORY | RESEARCH REGULATORY | ||
GUIDE 3.1 (Task CE 602-4) USE OF BOROSILICATE-GLASS | GUIDE 3.1 (Task CE 602-4)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 29: | Line 30: | ||
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.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. | |||
==B. DISCUSSION== | ==B. DISCUSSION== | ||
ANSI/ANS-8.5-1986, "Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Mate rial," | ANSI/ANS-8.5-1986, "Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Mate-rial,"' is a revision of ANSI/ANS-8.5-1979 and was pre-pared by Subcommittee | ||
8, Fissionable Materials Outside Reactors, of the Standards Committee of the American Nuclear Society. ANSI/ANS-8.5-1986 was approved by the American National Standards Committee N16, Nuclear Criticality Safety, in 1985 and by the American National Standards Institute (ANSI) on January 3, 1986. | 8, Fissionable Materials Outside Reactors, of the Standards Committee of the American Nuclear Society. ANSI/ANS-8.5-1986 was approved by the American National Standards Committee N16, Nuclear Criticality Safety, in 1985 and by the American National Standards Institute (ANSI) on January 3, 1986.1Copies may be obtained from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60525.ANSI/ANS-8.5-1986 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 | ||
2 3 5 U, 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 criticality 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 plutonium are imposed in the specifications applicable to plutonium solutions.. | |||
The concentrations specified for uranium enriched in 2 3 sU apply regardless of the 2 3 5 U enrichment content but with a limitation on the 2 3 3 U content. For solutions of uranium containing up to 5.0 wt-% 2 3 5 U and up to 0.01 wt-% 2 3 3 U (see Table 12 on page 8 of the standard), the maximum permissible solution concentration is unrestricted. | |||
The | 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 | ||
POSITION The guidance contained in ANSI/ANS-8.5-1986 for the use of borosilicate-glass raschig rings as a neutron absorber in solutions of fissile material provides a procedure 2 4 1 2 Note that in Tble 1 (3 1 4) on page 8 of the standard, 41Pu >Pu should read Pu > u4 PU.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. | |||
Written comments may be submitted to the Rules and Procedures Branch, DRR ADM, U.S. Nuclear Regulatory Commission, Washington, D6 20555.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 | |||
===7. Transportation=== | |||
4. Environmental and Siting 9. Antitrust and Financial Review | 3. Fuels and Materials Facilities | ||
10. General | 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 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 20013-7082, telephone | |||
Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of | |||
(202)275-2060 | (202)275-2060 | ||
or | or (202)275-2171. | ||
Issued guides may also be purchased from the National Technical Information Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Rort Royal Road, Springfield, VA 22161. | |||
Issued guides may also be purchased from the National Technical | |||
generally acceptable to the NRC staff for the prevention of accidental conditions of criticality. | generally acceptable to the NRC staff for the prevention of accidental conditions of criticality. | ||
Section 8.0 of ANSI/ANS-8.5-1986 lists additional docu ments referred to in the standard. | Section 8.0 of ANSI/ANS-8.5-1986 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. | The specific applicability or acceptability of these listed documents will be covered separately in other regulatory guides, where appropriate. | ||
Line 82: | Line 73: | ||
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 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. | 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 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 alter native 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 | Therefore, except in those cases in which the applicant proposes an acceptable alter-native 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 Uinder 10 CFR Part 70.3.1-2 VALUE/IMPACT | ||
STATEMENT A draft value/impact statement was published with the oposed Revision 2 to Regulatory Guide 3.1 (Task CE 602-4) when the draft guide was published for public comment in March 1987. No changes were necessary, so a separate value/impact statement for the final guide has not been prepared. | STATEMENT A draft value/impact statement was published with the oposed Revision 2 to Regulatory Guide 3.1 (Task CE 602-4) when the draft guide was published for public comment in March 1987. 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 inspection and copying for a fee at the Commission's Public Document Room at 1717 H Street NW., Washington, DC, under Task CE 602-4. | A copy of the draft value/impact statement is available for inspection and copying for a fee at the Commission's Public Document Room at 1717 H Street NW., Washington, DC, under Task CE 602-4.,.S. G.P.O. 1987-181-682:60212 | ||
3.1-3 UNITED STATES NUCLEAR REGULATORY | 3.1-3 UNITED STATES NUCLEAR REGULATORY | ||
COMMISSION | COMMISSION | ||
WASHINGTON, D.C. 20555 FIRST CLASS MAIL POSTAGE | WASHINGTON, D.C. 20555 FIRST CLASS MAIL POSTAGE It FEES PAID USNRC PERMIT No. G-67 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300}} | ||
{{RG-Nav}} | {{RG-Nav}} |
Revision as of 09:52, 13 October 2018
ML12220A057 | |
Person / Time | |
---|---|
Issue date: | 09/30/1987 |
From: | Office of Nuclear Regulatory Research |
To: | |
References | |
CE 602-4 RG-3.001, Rev. 2 | |
Download: ML12220A057 (4) | |
Revision 2 September
1987 U.S. NUCLEAR REGULATORY
COMMISSION
REGULATORY
GUIDE OFFICE OF NUCLEAR REGULATORY
RESEARCH REGULATORY
GUIDE 3.1 (Task CE 602-4)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.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-8.5-1986, "Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Mate-rial,"' is a revision of ANSI/ANS-8.5-1979 and was pre-pared by Subcommittee
8, Fissionable Materials Outside Reactors, of the Standards Committee of the American Nuclear Society. ANSI/ANS-8.5-1986 was approved by the American National Standards Committee N16, Nuclear Criticality Safety, in 1985 and by the American National Standards Institute (ANSI) on January 3, 1986.1Copies may be obtained from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60525.ANSI/ANS-8.5-1986 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
2 3 5 U, 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 criticality 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 plutonium are imposed in the specifications applicable to plutonium solutions..
The concentrations specified for uranium enriched in 2 3 sU apply regardless of the 2 3 5 U enrichment content but with a limitation on the 2 3 3 U content. For solutions of uranium containing up to 5.0 wt-% 2 3 5 U and up to 0.01 wt-% 2 3 3 U (see Table 12 on page 8 of the standard), the maximum permissible solution concentration is unrestricted.
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
POSITION The guidance contained in ANSI/ANS-8.5-1986 for the use of borosilicate-glass raschig rings as a neutron absorber in solutions of fissile material provides a procedure 2 4 1 2 Note that in Tble 1 (3 1 4) on page 8 of the standard, 41Pu >Pu should read Pu > u4 PU.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.
Written comments may be submitted to the Rules and Procedures Branch, DRR ADM, U.S. Nuclear Regulatory Commission, Washington, D6 20555.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 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 20013-7082, telephone
(202)275-2060
or (202)275-2171.
Issued guides may also be purchased from the National Technical Information Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Rort Royal Road, Springfield, VA 22161.
generally acceptable to the NRC staff for the prevention of accidental conditions of criticality.
Section 8.0 of ANSI/ANS-8.5-1986 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.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 alter-native 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 Uinder 10 CFR Part 70.3.1-2 VALUE/IMPACT
STATEMENT A draft value/impact statement was published with the oposed Revision 2 to Regulatory Guide 3.1 (Task CE 602-4) when the draft guide was published for public comment in March 1987. 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 inspection and copying for a fee at the Commission's Public Document Room at 1717 H Street NW., Washington, DC, under Task CE 602-4.,.S. G.P.O. 1987-181-682:60212
3.1-3 UNITED STATES NUCLEAR REGULATORY
COMMISSION
WASHINGTON, D.C. 20555 FIRST CLASS MAIL POSTAGE It FEES PAID USNRC PERMIT No. G-67 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300