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{{#Wiki_filter:Revision I 12/28/72 U.S. ATOMIC ENERGY COMMISSION.REGULATORY
{{#Wiki_filter:Revision I
GUIDE DIRECTORATE  
                                                                                                                                                        12/28/72
OF REGULATORY  
                              .REGULATORY GUIDE
STANDARDS REGULATORY  
                                U.S. ATOMIC ENERGY COMMISSION
GUIDE 1.15 TESTING OF REINFORCING  
                                DIRECTORATE OF REGULATORY STANDARDS
BARS FOR CATEGORY I CONCRETE STRUCTURES'
                                                                  REGULATORY GUIDE 1.15 TESTING OF REINFORCING BARS FOR CATEGORY I
                                                              CONCRETE STRUCTURES'


==A. INTRODUCTION==
==A. INTRODUCTION==
General Design Criterion I of Appendix A it) 10 ClFR Part 50, "General Design Criteria for Nuclear Power Plants," requires that structures, systems and components important to safety be designed.
specimens indicates that the tensile and yield strengths of the full diameter bars may be lower than the ValIe.,,
        General Design Criterion I of Appendix A it) 10                               that ate obtained using reduced diameter -pcinieis. The ClFR Part 50, "General Design Criteria for Nuclear                                   variatinns are generally greater in bar size, No. 14 and Power Plants," requires that structures, systems and                                 larger. Thus, the evaluation of the desigii margin tit components important to safety be designed. fabricated.                              safety in the slrticture may not be conservative if it is erected, and tested to quality standards commensurate                                based upon test results obtained from teduced diameter with the importance of the safety function to be                                    specimens.


fabricated.
performed. This guide describes an acceptable method for implementing this criterion with regard to tests and                                     ASTM A-615-72 requires only one tension test inspections of reinforcing bars for Category I concrete                             specimen per heat if all bars from a single heat differ in structures. 2 The Advisory Committee on Reactor                                     size by less than three designation numbers: only two Safeguards has been consulted concerning this guide and                               specimens are required in other cases. Because each heat has concurred in the regulatory position.                                             may contain from 50 to 250 tons of steel, the fraction of the reinforcing bars that are tested may vary by a
 
erected, and tested to quality standards commensurate with the importance of the safety function to be performed.
 
This guide describes an acceptable method for implementing this criterion with regard to tests and inspections of reinforcing bars for Category I concrete structures.
 
2 The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.


==B. DISCUSSION==
==B. DISCUSSION==
The tensile strength of concrete structures important to safety depends upon reinforcing bars imbedded in the concrete.
factor of 5. A more consistent basis for sampling can he obtained by choosing the test specimens on the basis ,,1 The tensile strength of concrete structures                                  the number of reinforcing bars or the weight of important to safety depends upon reinforcing bars                                    reinforcing.
 
The contribution of the concrete to the tensile strength of the structure is minimal and :hus generally disregarded.
 
The tensile strength of reinforcing bars is usually tested in accordance with ASTM A-615-72. "Standard Specification for Deformed Billet-Steel Bars for Concrete Reinforcement", American Society for Testing and Materials.
 
This specification permits the tensile test specimens to be either of full bar diameter or of a reduced diameter.
 
Comparison of test data obtained with both full bar diameter and reduced diameter This guide is a revision of former Safety Guide IS. As such, it is applicable to water-cooled nuclear power reactors.tSt'ructures, systems, and components of a nuclear power plant are designated as Category I if they are designed to withstand the effects of the Safe Shutdown Earthquake (SSE)and remain functional.
 
See Safety Guide 29, "Seismic Design Classification." specimens indicates that the tensile and yield strengths of the full diameter bars may be lower than the ValIe.,, that ate obtained using reduced diameter -pcinieis.
 
The variatinns are generally greater in bar size, No. 14 and larger. Thus, the evaluation of the desigii margin tit safety in the slrticture may not be conservative if it is based upon test results obtained from teduced diameter specimens.
 
ASTM A-615-72 requires only one tension test specimen per heat if all bars from a single heat differ in size by less than three designation numbers: only two specimens are required in other cases. Because each heat may contain from 50 to 250 tons of steel, the fraction of the reinforcing bars that are tested may vary by a factor of 5. A more consistent basis for sampling can he obtained by choosing the test specimens on the basis ,,1 the number of reinforcing bars or the weight of reinforcing.
 
Special chemistry requirements have occasionally been placed on somne reinforcing bars. and checks should be made that any such requirements are being met.Since some mechanical splice configurations may require deformations that exceed the minlimum requirements set forth in ASTM A-615-72.
 
it is impertant to inspect the deformations it) assute that they will permit a reliable mechanical splice to le made.C. REGULATORY
POSITION I. Yield Strength and Tensile Strength Tests Reinforcing bars used for concrete structures important to safety should be tested to verify their yield strength and tensile strength -,3 follows: USAEC REGULATORY
GUIDES Copies of published guides may be obtained by request ndicating the divisions desired to the US. Atomic Energy Commission, Washington.
 
O.C. 20545.Regulatory GAides ate issued to describe and mrAke available to the public Attention:
Director of Regulato'y Standards.
 
Comrents and suggestions to'methods accptrible to the AEC Regulatory staff of implementing specific pars of irrtIOVeMOInts in these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques used by the staff in of the Commission.


US. Atomic Energy Commission.
imbedded in the concrete. The contribution of the concrete to the tensile strength of the structure is Special chemistry requirements have occasionally minimal and :hus generally disregarded. The tensile been placed on somne reinforcing bars. and checks should strength of reinforcing bars is usually tested in be made that any such requirements are being met.


Washington, D.C. 20545, evaluating uJlecific problems or postulated accidents, or to provide guidance to Attention;
accordance            with      ASTM          A-615-72.          "Standard Specification for Deformed Billet-Steel Bars for                                            Since some mechanical splice configurations may Concrete Reinforcement", American Society for Testing                                require deformations that exceed the minlimum and Materials. This specification permits the tensile test                            requirements set forth in ASTM A-615-72. it is specimens to be either of full bar diameter or of a                                  impertant to inspect the deformations it) assute that reduced diameter. Comparison of test data obtained                                    they will permit a reliable mechanical splice to le made.
Chief. Public Proceedings Stall.applicantls.


Regulatory Guides are not substitutes for regulations and compliance with them is not required.
with both full bar diameter and reduced diameter


Methods and solutions different from those set Out in The guides are issued in the following ten broad diwvrions.
==C. REGULATORY POSITION==
This guide is a revision of former Safety Guide IS. As such, it is applicable to water-cooled nuclear power reactors.                              I.    Yield Strength and Tensile Strength Tests tSt'ructures, systems, and components of a nuclear power Reinforcing bars used for concrete structures plant are designated as Category I if they are designed to withstand the effects of the Safe Shutdown Earthquake (SSE)                          important to safety should be tested to verify their yield and remain functional. See Safety Guide 29, "Seismic Design                          strength and tensile strength -,3 follows:
Classification."
                      USAEC REGULATORY GUIDES                                      Copies of published guides may be obtained by request ndicating the divisions desired to the US. Atomic Energy Commission, Washington. O.C. 20545.


the guides will be acceptable it they provide a basis for the findings requitet, to the issuance or continuance of a permit or license by the Commission.
Regulatory GAides ate issued to describe and mrAke available to the public          Attention: Director of Regulato'y Standards. Comrents and suggestions to'
methods accptrible to the AEC Regulatory staff of implementing specific pars of    irrtIOVeMOInts in these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques used by the staff in          of the Commission. US. Atomic Energy Commission. Washington, D.C. 20545, evaluating uJlecific problems or postulated accidents, or to provide guidance to    Attention; Chief. Public Proceedings Stall.


1. Power Reactors 6. Product i 2. Research and lest Reacro's 7. Trans~oo'ttinn
applicantls. Regulatory Guides are not substitutes for regulations and compliance with them is not required. Methods and solutions different from those setOut in    The guides are issued in the following ten broad diwvrions.
3. Fuels and Materials Facilitm 8, Occupational Health Puhshrhed guides will lie revised periodically, as appropriae.


to accommodate
the guides will be acceptable it they provide a basis for the findings requitet, to the issuance or continuance of a permit or license by the Commission.                  1. Power Reactors                       
4. Environmentat ard Siting 9. A',:Irust Review comments and to reflect new inlormation or eaperience.


S. Materials and Plant Protection t0. General aI, At Iea, one fiui-diamele, specimeni hom eacht 11r sliv Should le tested Cor each 50 torns or 'ftrctioli thefico" of reinforcing baOrs that aie prodticed ornm eachand tised il Category I sitrutllures.
===6. Product    i===
                                                                                      2.   Research and lest Reacro's            7. Trans~oo'ttinn
                                                                                      3. Fuels and Materials Facilitm        8, Occupational Health Puhshrhed guides will lie revised periodically, as appropriae. to accommodate        4.  Environmentat ard Siting              9.  A',:Irust Review comments and to reflect new inlormation or eaperience.                                S. Materials and Plant Protection        t


V. The le"I procedures should he in acckirdance wit hi .I\STN'I A-370-0,S. -StIand1rd MtIhods arid Definitioms I*oI" Mechanical Tesit ing of Steel Ploducls." American Society o'Or leSling iand c. The jsnc itandards should be in acc' ord:unce wi III ASTNI A. 1.5-72. "St:adaid Speciflica:ion for Dcl'Otned lillc-Steel iais for Conrrrcie
===0. General===


====k. inmerceent ====
aI, At Iea, one fiui-diamele, specimeni hom eacht                        or ColostruLtor, lhe reinforing liatr cliet!li
.'ric:ri Socieiy I'Or resting:nmid .Nhiefials.


ifrcludinw Srupplemient:1l Requiremuer (S-I). using ftill sectioh s ite harý a,%, d. anry material properly such is yield-It'in l.tIII- Io-[Onsile.streI)-thI
====s. ty shoultjd he====
ratio. ducilily.
  *. sliv Should le tested Cor each 50 torns or 'ftrctioli
11r                                                                              controlled toI lie extent required to achieve lhe desled thefico" of reinforcing baOrs that aie prodticed ornm each                      material prrperty, :and conflriratI                        .ry ltslit- i sh1o1h.d he Ie*, and tised il Category I sitrutllures.                                       perforrmined.


weldabilitv ,M 4,lhj.'i .',imdLIar )lo)pety is relied upon hV the designer or ColostruLtor, lhe reinforing liatr cliet!lis.ty shoultjd he controlled toI lie extent required to achieve lhe desled material prrperty, :and conflriratI .ry ltslit- i sh1o1h.d he perforrmined.
V. The le"I procedures should he in acckirdance wit hi .I\STN'I      A-370-0,S.          -StIand1rd    MtIhods arid            2.    Deformation I nspections Definitioms I*oI"Mechanical Tesiting of Steel Ploducls."
American Society o'Or          leSling iand i*aterials.                                 Del'irniitions on lhe reinforc:ing hais should tic c. The            jsnc              itandards should be in                inspected            to   assure    their        compliance          wihl  AS'IM
acc'ord:unce        wi III      ASTNI          A. 1.5-72.   "St:adaid          A.6 Ii-72 and wiili the licensee's specifieatLions pertinent Speciflica:ion for Dcl'Otned lillc-Steel                        iais for        to bonding and other purposes which are dependem on Conrrrcie                               


2. Deformation I nspections Del'irniitions on lhe reinforc:ing hais should tic inspected to assure their compliance wihl AS'IM A.6 Ii-72 and wiili the licensee's specifieatLions pertinent to bonding and other purposes which are dependem on lite def.or iniI t ion ch .ract erisi.sA.3
====k. inmerceent====
3 ,' ld c.q ija (iI' d cl'o fi n allj I i ,t,,t fo r N.l lic.ing w ill h ,.e der 'n r: I ,s t te'd 1% lht tensile cests o(i ilhic st l .ic', See SaI'.ty (.uid, "Mc.t.hnicul (Cadweld)  
                                    .'ric:ri        Socieiy I'Or resting        lite def.or iniI t ion ch .ract erisi.sA.3
Splices in Reinf6:i1,'
:nmid .Nhiefials.      ifrcludinw Srupplemient:1l Requiremuer (S-I). using ftill sectioh s ,*'" ite harý a,%,      *olled.                                                     d cl'o fi n allj Ii ,t,,t fo r N.llic.ing   w ill h ,.e
liars of C'atcrory I (oncre te Sirt ic. ti.S." I. I -2.}}
                                                                                      3 ,'ld c.q ija *.y (iI'
      d. M\ier*, anry material properly such is yield- der 'n r: t I te'd     ,s lht tensile cests o(i ilhic nect-mi*.;, st l .ic',See
                                                                                                        1%
  It'in l.tIII-Io-[Onsile.streI)-thI ratio. ducilily. weldabilitv                SaI'.ty (.uid, i*t. "Mc.t.hnicul (Cadweld) Splices in Reinf6:i1,'
,M 4,lhj.'i .',imdLIar )lo)pety is relied upon hV the designer                  liars of C'atcrory I (oncre te Sirtic. ti.S."
                                                                        I. I -2.}}


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Latest revision as of 11:12, 4 November 2019

Testing of Reinforcing Bars for Category I Concrete Structures
ML13350A368
Person / Time
Issue date: 12/28/1972
From:
US Atomic Energy Commission (AEC)
To:
References
RG-1.015, Rev. 1
Download: ML13350A368 (2)


Revision I

12/28/72

.REGULATORY GUIDE

U.S. ATOMIC ENERGY COMMISSION

DIRECTORATE OF REGULATORY STANDARDS

REGULATORY GUIDE 1.15 TESTING OF REINFORCING BARS FOR CATEGORY I

CONCRETE STRUCTURES'

A. INTRODUCTION

specimens indicates that the tensile and yield strengths of the full diameter bars may be lower than the ValIe.,,

General Design Criterion I of Appendix A it) 10 that ate obtained using reduced diameter -pcinieis. The ClFR Part 50, "General Design Criteria for Nuclear variatinns are generally greater in bar size, No. 14 and Power Plants," requires that structures, systems and larger. Thus, the evaluation of the desigii margin tit components important to safety be designed. fabricated. safety in the slrticture may not be conservative if it is erected, and tested to quality standards commensurate based upon test results obtained from teduced diameter with the importance of the safety function to be specimens.

performed. This guide describes an acceptable method for implementing this criterion with regard to tests and ASTM A-615-72 requires only one tension test inspections of reinforcing bars for Category I concrete specimen per heat if all bars from a single heat differ in structures. 2 The Advisory Committee on Reactor size by less than three designation numbers: only two Safeguards has been consulted concerning this guide and specimens are required in other cases. Because each heat has concurred in the regulatory position. may contain from 50 to 250 tons of steel, the fraction of the reinforcing bars that are tested may vary by a

B. DISCUSSION

factor of 5. A more consistent basis for sampling can he obtained by choosing the test specimens on the basis ,,1 The tensile strength of concrete structures the number of reinforcing bars or the weight of important to safety depends upon reinforcing bars reinforcing.

imbedded in the concrete. The contribution of the concrete to the tensile strength of the structure is Special chemistry requirements have occasionally minimal and :hus generally disregarded. The tensile been placed on somne reinforcing bars. and checks should strength of reinforcing bars is usually tested in be made that any such requirements are being met.

accordance with ASTM A-615-72. "Standard Specification for Deformed Billet-Steel Bars for Since some mechanical splice configurations may Concrete Reinforcement", American Society for Testing require deformations that exceed the minlimum and Materials. This specification permits the tensile test requirements set forth in ASTM A-615-72. it is specimens to be either of full bar diameter or of a impertant to inspect the deformations it) assute that reduced diameter. Comparison of test data obtained they will permit a reliable mechanical splice to le made.

with both full bar diameter and reduced diameter

C. REGULATORY POSITION

This guide is a revision of former Safety Guide IS. As such, it is applicable to water-cooled nuclear power reactors. I. Yield Strength and Tensile Strength Tests tSt'ructures, systems, and components of a nuclear power Reinforcing bars used for concrete structures plant are designated as Category I if they are designed to withstand the effects of the Safe Shutdown Earthquake (SSE) important to safety should be tested to verify their yield and remain functional. See Safety Guide 29, "Seismic Design strength and tensile strength -,3 follows:

Classification."

USAEC REGULATORY GUIDES Copies of published guides may be obtained by request ndicating the divisions desired to the US. Atomic Energy Commission, Washington. O.C. 20545.

Regulatory GAides ate issued to describe and mrAke available to the public Attention: Director of Regulato'y Standards. Comrents and suggestions to'

methods accptrible to the AEC Regulatory staff of implementing specific pars of irrtIOVeMOInts in these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques used by the staff in of the Commission. US. Atomic Energy Commission. Washington, D.C. 20545, evaluating uJlecific problems or postulated accidents, or to provide guidance to Attention; Chief. Public Proceedings Stall.

applicantls. Regulatory Guides are not substitutes for regulations and compliance with them is not required. Methods and solutions different from those setOut in The guides are issued in the following ten broad diwvrions.

the guides will be acceptable it they provide a basis for the findings requitet, to the issuance or continuance of a permit or license by the Commission. 1. Power Reactors

6. Product i

2. Research and lest Reacro's 7. Trans~oo'ttinn

3. Fuels and Materials Facilitm 8, Occupational Health Puhshrhed guides will lie revised periodically, as appropriae. to accommodate 4. Environmentat ard Siting 9. A',:Irust Review comments and to reflect new inlormation or eaperience. S. Materials and Plant Protection t

0. General

aI, At Iea, one fiui-diamele, specimeni hom eacht or ColostruLtor, lhe reinforing liatr cliet!li

s. ty shoultjd he

  • . sliv Should le tested Cor each 50 torns or 'ftrctioli

11r controlled toI lie extent required to achieve lhe desled thefico" of reinforcing baOrs that aie prodticed ornm each material prrperty, :and conflriratI .ry ltslit- i sh1o1h.d he Ie*, and tised il Category I sitrutllures. perforrmined.

V. The le"I procedures should he in acckirdance wit hi .I\STN'I A-370-0,S. -StIand1rd MtIhods arid 2. Deformation I nspections Definitioms I*oI"Mechanical Tesiting of Steel Ploducls."

American Society o'Or leSling iand i*aterials. Del'irniitions on lhe reinforc:ing hais should tic c. The jsnc itandards should be in inspected to assure their compliance wihl AS'IM

acc'ord:unce wi III ASTNI A. 1.5-72. "St:adaid A.6 Ii-72 and wiili the licensee's specifieatLions pertinent Speciflica:ion for Dcl'Otned lillc-Steel iais for to bonding and other purposes which are dependem on Conrrrcie

k. inmerceent

.'ric:ri Socieiy I'Or resting lite def.or iniI t ion ch .ract erisi.sA.3

nmid .Nhiefials. ifrcludinw Srupplemient:1l Requiremuer (S-I). using ftill sectioh s ,*'" ite harý a,%, *olled. d cl'o fi n allj Ii ,t,,t fo r N.llic.ing w ill h ,.e

3 ,'ld c.q ija *.y (iI'

d. M\ier*, anry material properly such is yield- der 'n r: t I te'd ,s lht tensile cests o(i ilhic nect-mi*.;, st l .ic',See

1%

It'in l.tIII-Io-[Onsile.streI)-thI ratio. ducilily. weldabilitv SaI'.ty (.uid, i*t. "Mc.t.hnicul (Cadweld) Splices in Reinf6:i1,'

,M 4,lhj.'i .',imdLIar )lo)pety is relied upon hV the designer liars of C'atcrory I (oncre te Sirtic. ti.S."

I. I -2.