Regulatory Guide 2.3: Difference between revisions

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{{Adams
{{Adams
| number = ML13350A249
| number = ML003740129
| issue date = 09/30/1975
| issue date = 07/30/1976
| title = Quality Verification for Plant-Type Uranium-Aluminum Fuel Elements for Use in Research Reactors
| title = Revison 1, Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements for Use in Research Reactors
| 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-2.003
| document report number = RG-2.3, Rev 1
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 2
| page count = 4
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY  
{{#Wiki_filter:U.S. NUCLEAR REGULATORY  
COMMISSION
COMMISSION  
September
Revision 1 REGULATORY  
1975 REGULATORY  
GUIDE July 1976 OFFICE OF STANDARDS  
GUIDE OFFICE OF STANDARDS  
DEVELOPMENT  
DEVELOPMENT
REGULATORY  
REGULATORY  
GUIDE 2.3 QUALITY VERIFICATION  
GUIDE 2.3 QUALITY VERIFICATION  
FOR PLATE-TYPE  
FOR PLATE-TYPE  
URANIUM-ALUMINUM
URANIUM-ALUMINUM  
FUEL ELEMENTS FOR USE IN RESEARCH REACTORS  
FUEL ELEMENTS FOR USE IN RESEARCH REACTORS  


==A. INTRODUCTION==
==A. INTRODUCTION==
Paragraph (aX7) of Section 50.34, "Contents of Applications;
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 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.
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 C. REGULATORY
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.
POSITION The guidance contained in ANSI N398-1974. "Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements."'
is generally acceptable to Up NRC staff and provides an adequate basis fo rnplying with§50.34(a)(7)
of 10 CFR Part ',-50 " h respect to establishing and executing a qiality ass ice program for verifying the quaUt- Iof SSNate-type uranium-aluminum fuel elements ffu6'!,Vi irescarch reactors, subject to the fullo1*0:.
establishing and executing a quality assurance program Instead of,-t. deAr"ptitOiven in Section i.4.9 of for verifying the quality of plate-type uraniuni- the standard ,
actor should be defined as a aluminum fuel elements used in research reactors, nuclear tor a used for scientific, engineering, or.DISCUSSIONi nd is designed to operate at a thermal a.DISCUS Np eve megawatt or less or a level of 10 Work Group ANS-I 5.2 of Subcommittee ANS-1.5 c .. or less if it does not contain a circulating loop.Research Reactors, of the American Nuclear Society .r core in which fuel experiments are conduc-Standards Committee has revised the American Na liquid fuel loading, or an experimental facility in Standards Institute (ANSI) Standard NS. 96 core in excess of 16 square inches in cross section."Quality Control for Plate-Type Uranium-Al ,num


==D. IMPLEMENTATION==
==B. DISCUSSION==
Fuel Elements." The revised standard pro ui for the- establishment and execution f a gram The purpose of this section is to provide information designed to verify the quality of plat e nium- to applicants and licensees regarding the NRC staff's aluminum fuel elements for use in researcih rs. The plans for utilizing this regulatory guide.revised standard was approved by the American National Standards Committee N search Reactors, Reactor Except in those -cases in which the applicant Physics and Radiation and its Secretariat.
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.


It proposes an acceptable alternative method for*was subsequently a )p designated ANSI complying, with the specified portions of the N398-1974 by; oI ber 19, 1974. Commission's regulations, the method described herein will be used by the NRC staff in the It sl'ou e ogni that ANSI N398-1974 covers, evaluation of submittals for construction permit or only on i f quality assurance.
The revised standard was approved by the American National Standards Committee N17, Research Reactors, Reactor Physics and Radiation Shielding, and its Secretariat.


ANSI N402, operating license applications for research reactors dock-"Quality rance Program. Guidelines for Research oted after May 15, 1976.Reactors," ch is currently being developed under Subcommitte ANS-15, is expected to provide overall guidance for establishing quality assurance programs for 1 ('opies may be obtaineid rroni the American Nuclear research reactors.
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.


Society. 244 Fast O+/-Cidcn Avenue. Ilindale.
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.


Illinois 6052
USNRC REGULATORY
GUIDES Comments should be sent to the Secretary of the Commission.


===1. USNRC REGULATORY ===
U.S Nuclear Regulatory Guides are issued to describe and make available to the public Regulatory Commission.
GUIDES Comments should be sent to the Secretary o t the Commission.
 
U.S. Nuclear Regutatory Guides are issued to describe and mnake available to the public Regulatory Commission.


Washington.
Washington.


D.C. 20566. Attention.
D.C 20586. Attention Docieting and methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations.
 
Docketing and methods acceptable to the NRC staff of Implementing specific parts Service Section.Conmnmlssion's regulations.


to delineate techniques used by the stalt in evslu The guides are issued in the following ten broad divisions"tOng specific problems or postulated accidents, or to provide guidance to appli cents. Regulatory Guides are not substitutes fot 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.


and compliance  
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 difletent from those set out In 2. Research end Teot Reactors 7. Transportation the guides will be acceptable if they provide a basis for the findings requisite to 3. Fuels and Materials Factlities B. Occupational Health the issuance Or conttnuanc.e of a permit or license by the Commission.
1. Power Reactors 6. Products with them is not required.


4, Envirortmental and Siting 9. Antitrust Review Comments and suggestions tor impa~vements in these guides are encouraged S. Materials and Plant Protection t0. General at ill limes, and guides will tie revised. as appropriate.
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.


to accommodate corn mnits and to reflect new information or taperience.
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.


However. comments on Copies of published guides may be obtllned by written request indiclting the this guide. it received within about two monthi, after its issuance, will be pap divisions desired to the U.S Nuclear Regulatory Commission.
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.
Washington.


D.C.Ilculaily uselul in evaluating the need for dn early evaision.
D C review. 20555. Attention Director.


20r%5. Attention:  
Office of Standards Development The revision reflects comments received from the public and from additional staff review. C. REGULATORY
Director.
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.


Office of Standards Development.
===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.


I
3. The procedure in Subdivision
referred tothe input ror 4 usee peaking tinmcs (the noise:.lel .,afies iti'erselV
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.
with ..tle peukinig time). The main.ni. plil .htild be. a standard NIM' n module.At Loliting ratesgreater thanr" l 0" cps. problems.':.i' i als tion o1 t he energy resolution resulting in.a loss of.counts in the. spectrum peaks begin to occur.These.effecisare due to.the overlar' of portions of two ormnore pulses in. time and to bas.line The..agiiitude of ihese effects can be minimized by the inclusion of.th1e. folluwing features in the amplifier's des-111-.  
(: a baseline restorer. (BLR) circuit at. the
:outp.iu and _(2) pole-zero.


cancelled
==D. IMPLEMENTATION==
ý coupling" networks The. BLR circuit should be adjustable f.r.both I-ow i a d Inlig counting rateconditions.'
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
.5. Analog to Digital Converter (ADC)(Systems I. 11. II!) The ADC should be capable of digitizing pulse :,mplitudes from the amplifier in the range of 0 to 10 volts in at least 4096 channels.
1, 1976.2.3-3 UNITED STATES NUCLEAR REGULATORY
 
COMMISSION
The fre.quency of the internal clock should be at least 50" megidahcz to handle high. counting rates with nominal ADC dead time losses. The integral nonlinearity should be tle: than 0. 15% over the top 95% of full scale and the differential nonlinearity should be less than I.Wff over the top 95% of full scale for semi-Gaussian pulses with" peaking times of I to usec.-These linearity specifications are' n6t 'siringent.
WASHINGTON, D. C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 POSTAGE AND FEES PAID UNITED STATES NUCLEAR REGULATORY
 
COMMISSION}}
but arec adequate to enable" identificatiin.of unknown peaks which .may appear in a spectrum..
The short-term zero channel arid gain drifts should be < .01%/0 C and < .02%/0 C, respectively (the percentage refers to full scale), in the temperature range from 0&deg;. to 50'C. For long term stability, the peak from' NIM-Nuclear Instrument Module, see USAEC -Technical Information Document.
 
Standard Nuclear Instrument Modules, Revision 3. TID-20893
(1969)..' more details on BLR circuits see V. Radeka, "Effect.-of 'aseline Retoration'
on Signal-to-Noise.
 
Ratio in Pulse Amplitude Mcasuremernts,7 Rev. Sci. lnsir.3 8.1 397 (1967).a stable pulser should. not shift by more. than. one channel over a periodfor a line voltage of 1!5V-10%, 50-65 Hz, and at constant room temperature.(Note: The .ADC drift and linearity specifications are.closely ..re!ted to the overall .system% stability and lirearity operating Spec-fications described in Section C.S.)The .ADC should be capable of being DC coupled to the main amplifier in order that BLR circuits can be used. A digital = offset capability in the ADC is recommended.. (Note: In some systems the ADC is an integral -part of a multichannel analyzer, a unit which also performs the .functions .of data storage, display, and sometimes rrudimentary analysis..
These latter functions'
are taken up in Part 2 of this series. In multichannel analyzer systems, however, the. ADC function is usually specified separately.and canbe compared with the above recommendations.)(Sysiemn I) For certain applications where energy resolution is definitely not critical, all the ADC specifications above arc applicable with the exception that a 1024 channel capacity with a 1024 digital offset may be adequate to provide a sufficiently small energy interval per channel (keV/channel)
to cover a limited energy range of interest.
 
It should be emphasized, however, that this choice may restrict the effective use of the system for other applications.
 
6. Power Supplies (Systems 1,, II, .111) The system power supplies (detector high voltage, preamplifier, and NIM bin)should be capable of operating the system within the operating specifications listed in Section C.A when supplied with 115 volts (+/- 10%) at. 50 to 65 hertz (at constant room temperature), The detector bias power* supply should have an adjustable output that is short.circuait protected with automatic power restoration after removal of the short. The maximum output voltage is determined by detector requirements;
5 kilovolts is sufficient for most. applications.
 
5 .9-6}}


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

Revision as of 17:56, 31 August 2018

Revison 1, Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements for Use in Research Reactors
ML003740129
Person / Time
Issue date: 07/30/1976
From:
Office of Nuclear Regulatory Research
To:
References
RG-2.3, Rev 1
Download: ML003740129 (4)


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

COMMISSION

WASHINGTON, D. C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 POSTAGE AND FEES PAID UNITED STATES NUCLEAR REGULATORY

COMMISSION