Regulatory Guide 1.15: Difference between revisions
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{{#Wiki_filter:Revision | {{#Wiki_filter:Revision I | ||
12/28/72 | |||
.REGULATORY GUIDE | |||
OF REGULATORY | U.S. ATOMIC ENERGY COMMISSION | ||
STANDARDS | DIRECTORATE OF REGULATORY STANDARDS | ||
REGULATORY | REGULATORY GUIDE 1.15 TESTING OF REINFORCING BARS FOR CATEGORY I | ||
GUIDE 1. | CONCRETE STRUCTURES' | ||
BARS FOR CATEGORY | |||
STRUCTURES' | |||
==A. INTRODUCTION== | ==A. INTRODUCTION== | ||
General Design Criterion I of Appendix A it) | specimens indicates that the tensile and yield strengths of the full diameter bars may be lower than the ValIe.,, | ||
requires that structures, systems | 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 | |||
This guide describes an acceptable | |||
2 | |||
==B. DISCUSSION== | ==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 | |||
of | |||
===6. Product i=== | |||
A | 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 | |||
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 | 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.}} | |||
{{RG-Nav}} | {{RG-Nav}} |
Latest revision as of 10:12, 4 November 2019
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.