Regulatory Guide 2.3: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(11 intermediate revisions by the same user not shown)
Line 1: Line 1:
{{Adams
{{Adams
| number = ML003740129
| number = ML13350A249
| issue date = 07/30/1976
| issue date = 09/30/1975
| title = Revison 1, Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements for Use in Research Reactors
| title = Quality Verification for Plant-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-2.3, Rev 1
| document report number = RG-2.003
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 4
| page count = 2
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY  
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION                                                                                                           September 1975 REGULATORY GUIDE
COMMISSION  
  OFFICE OF STANDARDS DEVELOPMENT
Revision 1 REGULATORY  
                                                                    REGULATORY GUIDE 2.3 QUALITY VERIFICATION FOR PLATE-TYPE URANIUM-ALUMINUM
GUIDE July 1976 OFFICE OF STANDARDS  
                                        FUEL ELEMENTS FOR USE IN RESEARCH REACTORS
DEVELOPMENT  
REGULATORY  
GUIDE 2.3 QUALITY VERIFICATION  
FOR PLATE-TYPE  
URANIUM-ALUMINUM  
FUEL ELEMENTS FOR USE IN RESEARCH REACTORS  


==A. INTRODUCTION==
==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.
==C. REGULATORY POSITION==
Paragraph (aX7) of Section 50.34, "Contents of                                    The guidance contained in ANSI N398-1974. "Quality Applications; Technical Information," of 10 CFR Part                            Verification for Plate-Type Uranium-Aluminum Fuel
  50, "Licensing of Production and Utilization Facilities,"                        Elements."' is generally acceptable to Up NRC staff and requires that each applicant for a construction permit to                        provides an adequate basis fo rnplying with build a production or utilization facility include in its                        §50.34(a)(7) of 10 CFR Part ',-50 " h respect to preliminary safety analysis report a description of the                          establishing and executing a qiality ass ice program quality assurance program to be applied to the design,                          for verifying the quaUt-                                  Iof SSNate-type uranium- fabrication, construction, and testing of the structures,                        aluminum fuel elements ffu6'!,Vi irescarch reactors, systems, and components of the facility. This guide                             subject to the fullo1*0:.
  describes a method acceptable to the NRC staff for 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 , '*-4,arck*' 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.DISCUSeve    Np              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.


==B. DISCUSSION==
"Quality Control for Plate-Type Uranium-Al ,num                                                         
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.
==D. IMPLEMENTATION==
 
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.
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.
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                  el* and its Secretariat. 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. ANSI N402,              operating license applications for research reactors dock-
  "Quality              rance Program. Guidelines for Research                    oted after May 15, 1976.


or to provide guidance to appli cants. Regulatory Guides are not substitutes for regulations, and compliance
Reactors,"              ch is currently being developed under Subcommitte              ANS-15, is expected to provide overall guidance for establishing quality assurance programs for                                1
1. Power Reactors 6. Products with them is not required.
                                                                                          ('opies may be obtaineid rroni the American Nuclear research reactors.                                                                Society. 244 Fast O+/-Cidcn Avenue. Ilindale. Illinois 60521.


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
t USNRC REGULATORY GUIDES                                      Comments      should be sent to the Secretary o    the Commission.  U.S. Nuclear Regutatory Guides are issued to describe and mnake available to the public        Regulatory Commission.      Washington.    D.C. 20566. Attention. Docketing and methods acceptable to the NRC staff of Implementing specific parts                Service Section.
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  
Conmnmlssion's regulations. to delineate techniques used by the stalt in evslu      The guides are issued in the following ten broad divisions
5. Mi terials and Plant Protection  
"tOng specific problems or postulated accidents, or to provide guidance to appli cents. Regulatory Guides are not substitutes fot 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.              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 atill limes, and guides will tie revised. as appropriate. to accommodate corn mnits and to reflect new information or taperience. 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. Washington. D.C.
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.
Ilculaily uselul in evaluating the need for dn early evaision.                      20r%5. Attention: Director. Office of Standards Development.


Washington.
I


D C review. 20555. Attention Director.
referred tothe input ror 4 usee peaking tinmcs (the noise:                a stable pulser should. not shift by more. than. one
.lel .,afies iti'erselV with ..tle peukinig time). The main                channel over a 24.hou* periodfor a line voltage of 1!5V
  . ni.plil .htild be. a standard NIM' nmodule.                              - 10%, 50-65 Hz, and at constant room temperature.


Office of Standards Development The revision reflects comments received from the public and from additional staff review. C. REGULATORY
(Note: The .ADC drift and linearity specifications are At Loliting ratesgreater thanr" l 0" cps. problems            .closely ..re!ted to the overall . system%stability and
POSITION The guidance contained in ANSI N398-1974, "Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements,"**
.':.i' i als degraid* tion o1 t he energy resolution resulting in          lirearity operating Spec-fications described in Section
is generally acceptable to the NRC staff and provides an adequate basis for complying with paragraph
  .a loss of.counts in the. spectrum peaks begin to occur.                  C.S.)
50.34(a)(7)
    These.effecisare due to.the overlar' of portions of two ormnore pulses in. time and to bas.Žline fhuctuatio*s. The                  The .ADC should be capable of being DC coupled to
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:  
    . .agiiitudeof ihese effects can be minimized by the                    the main amplifier in order that BLR circuits can be inclusion of.th1e. folluwing features in the amplifier's              used. A digital = offset capability in the ADC is des-111-. (: a baseline restorer. (BLR) circuit at. the                   recommended.. (Note: In some systems the ADC is an
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.
-ampli*iir :outp.iu and _(2) pole-zero. cancelled ýcoupling                integral -part of a multichannel analyzer, a unit which
  "networks The. BLR circuit should be adjustable f.r.both                  also performs the .functions .of data storage, display, and i a d Inlig counting rateconditions.'
  I-ow                                                                    sometimes rrudimentary analysis.. These latter functions'
                                                                            are taken up in Part 2 of this serie


===2. Subdivision ===
====s. In multichannel====
2.1.5 of the standard requires that the total impurity content not exceed the equivalent
.5. Analog to Digital Converter (ADC)                                      analyzer systems, however, the. ADC function is usually specified separately.and canbe compared with the above (Systems I. 11.II!) The ADC should be capable of               recommendations.)
1 0 B content of 1.5 ppm on a weight basis relative to uranium. The NRC staff considers that an equivalent
  digitizing pulse :,mplitudes from the amplifier in the range of 0 to 10 volts in at least 4096 channels. The                          (Sysiemn I) For certain applications where energy fre.quency of the internal clock should be at least 50                  resolution is definitely not critical, all the ADC
1 0 B content up to 4.0 ppm on a weight basis relative to uranium is acceptable.
  "megidahcz to handle high. counting rates with nominal                    specifications above arc applicable with the exception ADC dead time losses. The integral nonlinearity should                  that a 1024 channel capacity with a 1024 digital offset be tle: than 0. 15% over the top 95% of full scale and the              may be adequate to provide a sufficiently small energy differential nonlinearity should be less than I.Wff over                interval per channel (keV/channel) to cover a limited the top 95% of full scale for semi-Gaussian pulses with                  energy range of interest. It should be emphasized,
"peaking times of I to usec.-These linearity specifications                however, that this choice may restrict the effective use are' n6t 'siringent. but arec adequate to enable                        of the system for other applications.


3. The procedure in Subdivision
"identificatiin.of unknown peaks which .may appear in a spectrum..                                                               6. Power Supplies The short-term zero channel arid gain drifts should                  (Systems 1,, II, .111) The system power supplies be < .01%/ 0 C and < .02%/0 C, respectively (the                        (detector high voltage, preamplifier, and NIM bin)
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.
    percentage refers to full scale), in the temperature range              should be capable of operating the system within the from 0&deg;. to 50'C. For long term stability, the peak from                  operating specifications listed in Section C.A when supplied with 115 volts (+/- 10%) at. 50 to 65 hertz (at
            ' NIM-Nuclear Instrument Module, see USAEC -Technical            constant room temperature), The detector bias power Information Document. Standard Nuclear Instrument Modules,           
* supply should have an adjustable output that is short Revision 3. TID-20893 (1969).                                          .circuait protected with automatic power restoration after
        .'.*'r    more details on BLR circuits see V. Radeka, "Effect      removal of the short. The maximum output voltage is
    -.of 'aseline Retoration' on Signal-to-Noise.     Ratio in Pulse        determined by detector requirements; 5 kilovolts is Amplitude Mcasuremernts,7 Rev. Sci. lnsir. 3 8.1 397 (1967).           sufficient for most. applications.


==D. IMPLEMENTATION==
5 .9-6}}
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}}


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

Latest revision as of 01:22, 20 March 2020

Quality Verification for Plant-Type Uranium-Aluminum Fuel Elements for Use in Research Reactors
ML13350A249
Person / Time
Issue date: 09/30/1975
From:
Office of Nuclear Regulatory Research
To:
References
RG-2.003
Download: ML13350A249 (2)


U.S. NUCLEAR REGULATORY COMMISSION September 1975 REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 2.3 QUALITY VERIFICATION FOR PLATE-TYPE URANIUM-ALUMINUM

FUEL ELEMENTS FOR USE IN RESEARCH REACTORS

A. INTRODUCTION

C. REGULATORY POSITION

Paragraph (aX7) of Section 50.34, "Contents of The guidance contained in ANSI N398-1974. "Quality Applications; Technical Information," of 10 CFR Part Verification for Plate-Type Uranium-Aluminum Fuel

50, "Licensing of Production and Utilization Facilities," Elements."' is generally acceptable to Up NRC staff and requires that each applicant for a construction permit to provides an adequate basis fo rnplying with build a production or utilization facility include in its §50.34(a)(7) of 10 CFR Part ',-50 " h respect to preliminary safety analysis report a description of the establishing and executing a qiality ass ice program quality assurance program to be applied to the design, for verifying the quaUt- Iof SSNate-type uranium- fabrication, construction, and testing of the structures, aluminum fuel elements ffu6'!,Vi irescarch reactors, systems, and components of the facility. This guide subject to the fullo1*0:.

describes a method acceptable to the NRC staff for 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 , '*-4,arck*' 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.DISCUSeve Np 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

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 el* and its Secretariat. 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. 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. Society. 244 Fast O+/-Cidcn Avenue. Ilindale. Illinois 60521.

t USNRC REGULATORY GUIDES Comments should be sent to the Secretary o the Commission. U.S. Nuclear Regutatory Guides are issued to describe and mnake available to the public Regulatory Commission. Washington. D.C. 20566. Attention. 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. 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. 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 atill limes, and guides will tie revised. as appropriate. to accommodate corn mnits and to reflect new information or taperience. 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. Washington. D.C.

Ilculaily uselul in evaluating the need for dn early evaision. 20r%5. Attention: Director. Office of Standards Development.

I

referred tothe input ror 4 usee peaking tinmcs (the noise: a stable pulser should. not shift by more. than. one

.lel .,afies iti'erselV with ..tle peukinig time). The main channel over a 24.hou* periodfor a line voltage of 1!5V

. ni.plil .htild be. a standard NIM' nmodule. - 10%, 50-65 Hz, and at constant room temperature.

(Note: The .ADC drift and linearity specifications are At Loliting ratesgreater thanr" l 0" cps. problems .closely ..re!ted to the overall . system%stability and

.':.i' i als degraid* tion o1 t he energy resolution resulting in lirearity operating Spec-fications described in Section

.a loss of.counts in the. spectrum peaks begin to occur. C.S.)

These.effecisare due to.the overlar' of portions of two ormnore pulses in. time and to bas.Žline fhuctuatio*s. The The .ADC should be capable of being DC coupled to

. .agiiitudeof ihese effects can be minimized by the the main amplifier in order that BLR circuits can be inclusion of.th1e. folluwing features in the amplifier's used. A digital = offset capability in the ADC is des-111-. (: a baseline restorer. (BLR) circuit at. the recommended.. (Note: In some systems the ADC is an

-ampli*iir :outp.iu and _(2) pole-zero. cancelled ýcoupling integral -part of a multichannel analyzer, a unit which

"networks The. BLR circuit should be adjustable f.r.both also performs the .functions .of data storage, display, and i a d Inlig counting rateconditions.'

I-ow sometimes rrudimentary analysis.. These latter functions'

are taken up in Part 2 of this serie

s. In multichannel

.5. Analog to Digital Converter (ADC) analyzer systems, however, the. ADC function is usually specified separately.and canbe compared with the above (Systems I. 11.II!) The ADC should be capable of recommendations.)

digitizing pulse :,mplitudes from the amplifier in the range of 0 to 10 volts in at least 4096 channels. The (Sysiemn I) For certain applications where energy fre.quency of the internal clock should be at least 50 resolution is definitely not critical, all the ADC

"megidahcz to handle high. counting rates with nominal specifications above arc applicable with the exception ADC dead time losses. The integral nonlinearity should that a 1024 channel capacity with a 1024 digital offset be tle: than 0. 15% over the top 95% of full scale and the may be adequate to provide a sufficiently small energy differential nonlinearity should be less than I.Wff over interval per channel (keV/channel) to cover a limited the top 95% of full scale for semi-Gaussian pulses with energy range of interest. It should be emphasized,

"peaking times of I to usec.-These linearity specifications however, that this choice may restrict the effective use are' n6t 'siringent. but arec adequate to enable of the system for other applications.

"identificatiin.of unknown peaks which .may appear in a spectrum.. 6. Power Supplies The short-term zero channel arid gain drifts should (Systems 1,, II, .111) The system power supplies be < .01%/ 0 C and < .02%/0 C, respectively (the (detector high voltage, preamplifier, and NIM bin)

percentage refers to full scale), in the temperature range should be capable of operating the system within the from 0°. to 50'C. For long term stability, the peak from operating specifications listed in Section C.A when supplied with 115 volts (+/- 10%) at. 50 to 65 hertz (at

' NIM-Nuclear Instrument Module, see USAEC -Technical constant room temperature), The detector bias power Information Document. Standard Nuclear Instrument Modules,

  • supply should have an adjustable output that is short Revision 3. TID-20893 (1969). .circuait protected with automatic power restoration after

.'.*'r more details on BLR circuits see V. Radeka, "Effect removal of the short. The maximum output voltage is

-.of 'aseline Retoration' on Signal-to-Noise. Ratio in Pulse determined by detector requirements; 5 kilovolts is Amplitude Mcasuremernts,7 Rev. Sci. lnsir. 3 8.1 397 (1967). sufficient for most. applications.

5 .9-6