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| {{Adams | | {{Adams |
| | number = ML12160A492 | | | number = ML003740129 |
| | issue date = 05/21/2013 | | | issue date = 07/30/1976 |
| | title = (Draft Was Issued as DG-2005, Dated March 2012), Quality Verification for Plate Type Uranium Aluminum Fuel Elements for Use in Research and Test Reactors, Revision 2 | | | title = Revison 1, Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements for Use in Research Reactors |
| | author name = Wertz G | | | author name = |
| | author affiliation = NRC/NRR/DPR | | | author affiliation = NRC/RES |
| | addressee name = | | | addressee name = |
| | addressee affiliation = | | | addressee affiliation = |
| | docket = | | | docket = |
| | license number = | | | license number = |
| | contact person = Bayssie M | | | contact person = |
| | case reference number = DG-2005
| | | document report number = RG-2.3, Rev 1 |
| | document report number = RG 2.3, Rev. 2 | |
| | package number = ML12160A480
| |
| | document type = Regulatory Guide | | | document type = Regulatory Guide |
| | page count = 4 | | | page count = 4 |
| }} | | }} |
| {{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION May 2013 OFFICE OF NUCLEAR REGULATORY RESEARCH Revision 2 REGULATORY GUIDE | | {{#Wiki_filter:U.S. NUCLEAR REGULATORY |
| Written suggestions regarding this guide or development of new guides may be submitted through the NRCs public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/contactus.html. Electronic copies of this regulatory guide, previous versions of this guide, and other recently issued guides are available through the NRCs public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/. The regulatory guide is also available through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under ADAMS Accession No. ML12160A492. The regulatory analysis may be found in ADAMS under Accession No. ML12160A494 and the staff responses to the public comments on DG-2005 may be found under ADAMS Accession No. ML12160A496.
| | COMMISSION |
| | Revision 1 REGULATORY |
| | GUIDE July 1976 OFFICE OF STANDARDS |
| | DEVELOPMENT |
| | REGULATORY |
| | GUIDE 2.3 QUALITY VERIFICATION |
| | FOR PLATE-TYPE |
| | URANIUM-ALUMINUM |
| | FUEL ELEMENTS FOR USE IN RESEARCH REACTORS |
|
| |
|
| REGULATORY GUIDE 2.3 (Draft was issued as DG-2005, dated March 2012)
| | ==A. INTRODUCTION== |
| QUALITY VERIFICATION FOR PLATE-TYPE URANIUM-ALUMINUM FUEL ELEMENTS FOR USE IN RESEARCH AND TEST REACTORS
| | Paragraph (a)(7) of 9 50.34, "Contents of Applications: |
| | Technical Information," of 10 CFR Part 50, "Licensing of Production and Utilization Facilities," requires that each applicant for a construction permit to build a production or utilization facility include in its Preliminary Safety Analysis Report (PSAR) a description of the quality assurance program to be applied to the design, fabrication, construction, and testing of the structures, systems, and components of the facility. |
| | |
| | This guide describes a method acceptable to the NRC staff for establishing and executing a quality assurance program for verifying the quality of plate-type uranium-aluminum fuel elements used in research reactors. |
| | |
| | ==B. DISCUSSION== |
| | Work Group ANS-15.2 of Subcommittee ANS-15, Research Reactors, of the American Nuclear Society Standards Committee has revised the American National Standards Institute (ANSI) Standard N8.1-1967, "Quality Control for Plate-Type Uranium-Aluminum Fuel Elements." The revised standard provides guidelines for establishing and executing a program designed to verify the quality of plate-type uranium-aluminum fuel elements for use in research reactors. |
|
| |
|
| ==A. INTRODUCTION==
| | The revised standard was approved by the American National Standards Committee N17, Research Reactors, Reactor Physics and Radiation Shielding, and its Secretariat. |
| Purpose This guide provides guidance that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for complying with the Commissions regulations on establishing and executing a quality assurance program for verifying the quality of plate-type uranium-aluminum fuel elements used in research and test reactors (RTRs).
| |
| Applicable Rules and Regulations Title 10, Section 50.34(a) (7), of the Code of Federal Regulations (10 CFR Part 50) (Ref. 1), requires each applicant for a construction permit to build a production or utilization facility to describe in its preliminary safety analysis report the quality assurance program that will be applied to the design, fabrication, construction, and testing of the facilitys structures, systems, and components. Title 10, Section 52.11, of the Code of Federal Regulations (10 CFR Part 52) (Ref. 2), requires information collection.
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| Related Guidance
| | It was subsequently approved and designated ANSI N398-1974 by ANSI on November 19, 1974. It should be recognized that ANSI N398-1974 covers only one limited aspect of quality assurance. |
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| |
|
| Regulatory Guide 2.5, Quality Assurance Program Requirements for Research and Test Reactors, (Ref. 3) contains methods that the NRC staff finds acceptable for complying with the Commission s regulations on the overall quality assurance program requirements for RTRs.
| | ANSI N402, "Quality Assurance Program Guide lines for Research Reactors," which is currently being developed under Subcommittee ANS-15, is expected to provide overall guidance for establishing quality assurance programs for research reactors. |
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|
| Purpose of Regulatory Guides
| | USNRC REGULATORY |
| | GUIDES Comments should be sent to the Secretary of the Commission. |
|
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|
| The NRC issues regulatory guides to describe to the public methods that the staff considers acceptable for use in implementing specific parts of the agency s regulations, to explain techniques that the staff uses in evaluating specific problems or postulated accidents, and to provide guidance to Rev. 2 of RG 2.3, Page 2 applicants. Regulatory guides are not substitutes for regulations and compliance with them is not required. Methods and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission.
| | U.S Nuclear Regulatory Guides are issued to describe and make available to the public Regulatory Commission. |
|
| |
|
| Paperwork Reduction Act This regulatory guide contains information collection requirements covered by 10 CFR Part 50 and 10 CFR Part 52 that the Office of Management and Budget (OMB) approved under OMB control number 3150-0011 and 3150-0151, respectively. The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number.
| | Washington. |
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| |
|
| ==B. DISCUSSION==
| | D.C 20586. Attention Docieting and methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations. |
| Reason for Revision
| |
|
| |
|
| Revision 1 to Regulatory Guide 2.3, issued in July 1976, endorsed the guidance provided in the American National Standards Institute (ANSI) N398-1974, Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements." It was subsequently approved and designated ANSI N398-1974 by ANSI on November 19, 1974 and covers only one limited aspect of quality assurance. ANSI N398-1974 has been superseded and is no longer supported by the NRC staff. Revision 2 to Regulatory Guide 2.3 refers to the guidance in ANSI/ANS-15.2-1999, Quality Control for Plate-Type Uranium-Aluminum Fuel Elements (Ref. 4).
| | to delineate techniques used by the staff in evalu The guides are issued in the following ten broad divisions ating specific problems or postulated accidents. |
| Background The NRC initially issued Regulatory Guide 2.3 in 1975 to provide guidance concerning procedures that the staff considered acceptable for complying with the agencys regulatory requirements in 10 CFR 50.34(a) (7). The original guide endorsed specific safety standards to provide guidelines for establishing and executing a program designed to verify the quality of plate-type uranium-aluminum fuel elements for use in research reactors. The American Nuclear Society (ANS) Subcommittee on the Operation of Research Reactors (ANS-15) rewrote ANSI N398-1974, issued it as ANSI/ANS-15.2-1999, and subsequently reaffirmed the standard in March 2009. The NRC staff believes that the foreword to ANSI/ANS-15.2-1999 (R2009) has several important assumptions about its use. Harmonization with International Standards The International Atomic Energy Agency (IAEA) has established a series of safety standards constituting a high level of safety for protecting people and the environment. Relative to this regulatory guide, IAEA Safety Requirements publication NS-R-4, Safety at Research Reactors (Ref. 5), provides quality assurance requirements in sections 4.5-4.13, as part of an overall system of management and verification controls. While the NRC has an interest in facilitating the harmonization of standards used domestically and internationally, the NRC does not specifically endorse NS-R-4, and is only acknowledging that it may be useful as a reference for general information. The NRC could consider the use of the international standard in a licensing action following adequate justification and technical review.
| |
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|
| Rev. 2 of RG 2.3, Page 3 Documents Discussed in Staff Regulatory Guidance This regulatory guide endorses the use of one or more codes or standards developed by external organizations, and other third party guidance documents. These codes, standards and third party guidance documents may contain references to other codes, standards or third party guidance documents (secondary references). If a secondary reference has itself been incorporated by reference into NRC regulations as a requirement, then licensees and applicants must comply with that standard as set forth in the regulation. If the secondary reference has been endorsed in a regulatory guide as an acceptable approach for meeting an NRC requirement, then the standard constitutes a method acceptable to the NRC staff for meeting that regulatory requirement as described in the specific regulatory guide. If the secondary reference has neither been incorporated by reference into NRC regulations nor endorsed in a regulatory guide, then the secondary reference is neither a legally-binding requirement nor a generic NRC approval as an acceptable approach for meeting an NRC requirement. However, licensees and applicants may consider and use the information in the secondary reference, if appropriately justified and consistent with current regulatory practice, consistent with applicable NRC requirements such as 10 CFR 50.59. C. STAFF REGULATORY GUIDANCE The NRC staff finds ANSI/ANS-15.2-1999 (R2009), Quality Control for Plate-Type Uranium-Aluminum Fuel Elements, provides an acceptable method for complying with the requirements in 10 CFR 50.34(a)(7) in regard to establishing and executing a quality assurance program for verifying the quality of plate-type uranium-aluminum fuel elements for use in RTRs, subject to the following condition:
| | or to provide guidance to appli cants. Regulatory Guides are not substitutes for regulations, and compliance |
| (1) ANSI/ANS-15.2-1999 (R2009), Section 13.4, Verification of Fuel Element Assembly Dimensions, requires a verification of items
| | 1. Power Reactors 6. Products with them is not required. |
| 1-6, with item 6 designated functional fit. The NRC staff considers item 6 a desired test, but not required.
| |
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|
| ==D. IMPLEMENTATION==
| | Methods and solutions different from those set out in 2. Research and Test Reactors 7. Transportation the guides will be acceptable if they provide a basis for the findings requisite to 3. Fuels and Materials Facilities |
| The purpose of this section is to provide information to applicants and licensees regarding the NRCs plans for using this regulatory guide. The regulatory position held in this guidance demonstrates the method that the NRC staff finds acceptable for an applicant or licensee to meet the requirements of the underlying NRC regulations. Methods or solutions that differ from those described in this regulatory guide may be deemed acceptable if they provide sufficient basis and information for the NRC staff to verify that the proposed alternative demonstrates compliance with the appropriate NRC regulations.
| | 8. Occupational Health the issuance or continuance of a permit or license by the Commission. |
|
| |
|
| Current licensees may continue to use guidance the NRC found acceptable for complying with the identified regulations as long as their current licensing basis remains unchanged. The imposition of the guidance in this regulatory guide is not a backfit, as that term is defined in 10 CFR 50.109, Backfitting, because non-power reactor licensees are not included within the scope of entities protected by the Backfit Rule.
| | 4. Environmental and Siting 9. Antitrust Review Comments and suggestions for improvements in these guides are encouraged |
| | 5. Mi terials and Plant Protection |
| | 10. General at all times, and guides will be revised, as appropriate, to accommodate com ments and to reflect new information or experience. |
|
| |
|
| Rev. 2 of RG 2.3, Page4 REFERENCES
| | This guide was revised as a Copies of published guides may be obtained by written request indicating the result of substantive comments received from the public and additional staff divisions desired to the U.S Nuclear Regulatory Commission. |
| 1 1. 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, U.S. Nuclear Regulatory Commission, Washington, DC.
| |
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| |
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| 2. 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants, U.S. Nuclear Regulatory Commission, Washington, DC.
| | Washington. |
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| 3. Regulatory Guide 2.5, Quality Assurance Program Requirements for Research and Test Reactors, U.S. Nuclear Regulatory Commission, Washington, DC.
| | D C review. 20555. Attention Director. |
|
| |
|
| 4. ANSI/ANS-15.2-1999 (R2009), Quality Control for Plate-Type Uranium-Aluminum Fuel Elements, American Nuclear Society, La Grange Park, IL.
| | Office of Standards Development The revision reflects comments received from the public and from additional staff review. C. REGULATORY |
| | POSITION The guidance contained in ANSI N398-1974, "Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements,"** |
| | is generally acceptable to the NRC staff and provides an adequate basis for complying with paragraph |
| | 50.34(a)(7) |
| | of 10 CFR Part 50 with respect to establishing and executing a quality assurance program for verifying the quality of plate-type uranium-aluminum fuel elements for use in research reactors, subject to the following: |
| | 1. For the purpose of this guide, a research reactor should be defined as a nuclear reactor that is used for scientific, engineering, or training purposes and is designed to operate at a thermal power level of 1 megawatt or less or a level of 10 megawatts or less if it does not contain a circulating loop through the core in which fuel experiments are conducted, a liquid fuel loading, or an experimental facility in the core in excess of 16 square inches in cross section. |
|
| |
|
| 2 5. Safety Requirements, NS-R-4, Safety at Research Reactors, September, 2005, International Atomic Energy Agency, Vienna, Austria. | | ===2. Subdivision === |
| | 2.1.5 of the standard requires that the total impurity content not exceed the equivalent |
| | 1 0 B content of 1.5 ppm on a weight basis relative to uranium. The NRC staff considers that an equivalent |
| | 1 0 B content up to 4.0 ppm on a weight basis relative to uranium is acceptable. |
|
| |
|
| 3 | | 3. The procedure in Subdivision |
| 1 Publicly available NRC published documents are available electronically through the NRC Library on the NRCs public Web site at: http://www.nrc.gov/reading-rm/doc-collections/. The documents can also be viewed on-line or printed for a fee in the NRCs Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD; the mailing address is USNRC PDR, Washington, DC 20555; telephone 301-415-4737 or (800) 397-4209; fax (301) 415-3548; and e-mail pdr.resource@nrc.gov. 2 Copies of American Nuclear Society (ANS) standards may be purchased from the ANS Web site (http://www.new.ans.org/store/) ; or by writing to: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526, U.S.A., Telephone 800-323-3044. | | 7.2.1 requires that the blister test consist of heating each completed fuel plate in an air-atmosphere furnace at 932 0 F (-10OF, +20 0 F) for a minimum of 30 minutes. The NRC staff considers that a temperature in the range 932 0 F to 1015 0 F for a minimum of 30 minutes is acceptable for the test. 4. Section 14.1 of the standard requires the polyethylene bag used for shipping to be at least 0.010 in. thick. A thickness of at least 0.006 in. is considered acceptable. |
|
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| 3 Copies of International Atomic Energy Agency (IAEA) documents may be obtained through their Web site: WWW.IAEA.Org/ or by writing the International Atomic Energy Agency P.O. Box 100 Wagramer Strasse 5, A-1400 Vienna, Austria. Telephone (+431) 2600-0, Fax (+431) 2600-7, or E-Mail at Official.Mail@IAEA.Org}}
| | ==D. IMPLEMENTATION== |
| | The purpose of this section is to provide information to applicants regarding the NRC staff's plans for utilizing this regulatory guide. *Lines indicate substantive change from previous issue. **Copies may be obtained from the American Nuclear Society, 244 East Ogden Avenue, Hinsdale, Illinois 60521.2.3-2 Except in those cases in which the applicant proposes an acceptable alternative method for complying with the specified portions of the Commission's regulations, the method described herein will be used by the NRC staff in the evaluation of submittals for research reactor construction permit or operating license applications docketed after September |
| | 1, 1976.2.3-3 UNITED STATES NUCLEAR REGULATORY |
| | COMMISSION |
| | WASHINGTON, D. C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 POSTAGE AND FEES PAID UNITED STATES NUCLEAR REGULATORY |
| | COMMISSION}} |
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| {{RG-Nav}} | | {{RG-Nav}} |
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U.S. NUCLEAR REGULATORY
COMMISSION
Revision 1 REGULATORY
GUIDE July 1976 OFFICE OF STANDARDS
DEVELOPMENT
REGULATORY
GUIDE 2.3 QUALITY VERIFICATION
FOR PLATE-TYPE
URANIUM-ALUMINUM
FUEL ELEMENTS FOR USE IN RESEARCH REACTORS
A. INTRODUCTION
Paragraph (a)(7) of 9 50.34, "Contents of Applications:
Technical Information," of 10 CFR Part 50, "Licensing of Production and Utilization Facilities," requires that each applicant for a construction permit to build a production or utilization facility include in its Preliminary Safety Analysis Report (PSAR) a description of the quality assurance program to be applied to the design, fabrication, construction, and testing of the structures, systems, and components of the facility.
This guide describes a method acceptable to the NRC staff for establishing and executing a quality assurance program for verifying the quality of plate-type uranium-aluminum fuel elements used in research reactors.
B. DISCUSSION
Work Group ANS-15.2 of Subcommittee ANS-15, Research Reactors, of the American Nuclear Society Standards Committee has revised the American National Standards Institute (ANSI) Standard N8.1-1967, "Quality Control for Plate-Type Uranium-Aluminum Fuel Elements." The revised standard provides guidelines for establishing and executing a program designed to verify the quality of plate-type uranium-aluminum fuel elements for use in research reactors.
The revised standard was approved by the American National Standards Committee N17, Research Reactors, Reactor Physics and Radiation Shielding, and its Secretariat.
It was subsequently approved and designated ANSI N398-1974 by ANSI on November 19, 1974. It should be recognized that ANSI N398-1974 covers only one limited aspect of quality assurance.
ANSI N402, "Quality Assurance Program Guide lines for Research Reactors," which is currently being developed under Subcommittee ANS-15, is expected to provide overall guidance for establishing quality assurance programs for research reactors.
USNRC REGULATORY
GUIDES Comments should be sent to the Secretary of the Commission.
U.S Nuclear Regulatory Guides are issued to describe and make available to the public Regulatory Commission.
Washington.
D.C 20586. Attention Docieting and methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations.
to delineate techniques used by the staff in evalu The guides are issued in the following ten broad divisions ating specific problems or postulated accidents.
or to provide guidance to appli cants. Regulatory Guides are not substitutes for regulations, and compliance
1. Power Reactors 6. Products with them is not required.
Methods and solutions different from those set out in 2. Research and Test Reactors 7. Transportation the guides will be acceptable if they provide a basis for the findings requisite to 3. Fuels and Materials Facilities
8. Occupational Health the issuance or continuance of a permit or license by the Commission.
4. Environmental and Siting 9. Antitrust Review Comments and suggestions for improvements in these guides are encouraged
5. Mi terials and Plant Protection
10. General at all times, and guides will be revised, as appropriate, to accommodate com ments and to reflect new information or experience.
This guide was revised as a Copies of published guides may be obtained by written request indicating the result of substantive comments received from the public and additional staff divisions desired to the U.S Nuclear Regulatory Commission.
Washington.
D C review. 20555. Attention Director.
Office of Standards Development The revision reflects comments received from the public and from additional staff review. C. REGULATORY
POSITION The guidance contained in ANSI N398-1974, "Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements,"**
is generally acceptable to the NRC staff and provides an adequate basis for complying with paragraph
50.34(a)(7)
of 10 CFR Part 50 with respect to establishing and executing a quality assurance program for verifying the quality of plate-type uranium-aluminum fuel elements for use in research reactors, subject to the following:
1. For the purpose of this guide, a research reactor should be defined as a nuclear reactor that is used for scientific, engineering, or training purposes and is designed to operate at a thermal power level of 1 megawatt or less or a level of 10 megawatts or less if it does not contain a circulating loop through the core in which fuel experiments are conducted, a liquid fuel loading, or an experimental facility in the core in excess of 16 square inches in cross section.
2. Subdivision
2.1.5 of the standard requires that the total impurity content not exceed the equivalent
1 0 B content of 1.5 ppm on a weight basis relative to uranium. The NRC staff considers that an equivalent
1 0 B content up to 4.0 ppm on a weight basis relative to uranium is acceptable.
3. The procedure in Subdivision
7.2.1 requires that the blister test consist of heating each completed fuel plate in an air-atmosphere furnace at 932 0 F (-10OF, +20 0 F) for a minimum of 30 minutes. The NRC staff considers that a temperature in the range 932 0 F to 1015 0 F for a minimum of 30 minutes is acceptable for the test. 4. Section 14.1 of the standard requires the polyethylene bag used for shipping to be at least 0.010 in. thick. A thickness of at least 0.006 in. is considered acceptable.
D. IMPLEMENTATION
The purpose of this section is to provide information to applicants regarding the NRC staff's plans for utilizing this regulatory guide. *Lines indicate substantive change from previous issue. **Copies may be obtained from the American Nuclear Society, 244 East Ogden Avenue, Hinsdale, Illinois 60521.2.3-2 Except in those cases in which the applicant proposes an acceptable alternative method for complying with the specified portions of the Commission's regulations, the method described herein will be used by the NRC staff in the evaluation of submittals for research reactor construction permit or operating license applications docketed after September
1, 1976.2.3-3 UNITED STATES NUCLEAR REGULATORY
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