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{{#Wiki_filter:_____U U.S. NUCLEAR REGULATORY  
{{#Wiki_filter:_____U
COMMISSION
  U.S. NUCLEAR REGULATORY COMMISSION                                                                                                               April 1975 REGULATORY GUIDE
April 1975 REGULATORY  
  OFFICE OF STANDARDS DEVELOPMENT
GUIDE OFFICE OF STANDARDS  
                                                                    REGULATORY GUIDE 1.94.
DEVELOPMENT
REGULATORY  
GUIDE 1.9


===4. QUALITY ASSURANCE ===
QUALITY ASSURANCE REQUIREMENTS FOR INSTALLATION,
REQUIREMENTS  
                              INSPECTION, AND TESTING OF STRUCTURAL CONCRETE AND
FOR INSTALLATION, INSPECTION, AND TESTING OF STRUCTURAL  
    STRUCTURAL STEEL DURING THE CONSTRUCTION PHASE OF NUCLEAR POWER PLANTS
CONCRETE AND STRUCTURAL  
STEEL DURING THE CONSTRUCTION  
PHASE OF NUCLEAR POWER PLANTS  


==A. INTRODUCTION==
==A. INTRODUCTION==
Appendix B, "Quality Assurance Criteria for Nuclear Power: Plants. and Fuel Reprocessing Plants." to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," establishes overall quality assurance require-mcnts for the design, construction, and operation of safety-related structures, systems, and components of nuclear power plants. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to quality assur-ance requirements for installation, inspection, and test-ing of structural concrete and structural steel during the construction phasc of nuclear puwer plants. ThLi guide applies to all types of nuclear power plants.
 
==C. REGULATORY POSITION==
Appendix B, "Quality Assurance Criteria for Nuclear                               The requirements and guidelines that ate included Power: Plants. and Fuel Reprocessing Plants." to 10 CFR                           in ANSI N45.2.5-1974 for installation, inspection, and Part 50, "Licensing of Production and Utilization                                 testing of structural concrete and structural steel during Facilities," establishes overall quality assurance require-                       the construction phase of nuclear power plants are mcnts for the design, construction, and operation of                               generally acceptable to the NRC sta,'f and provide safety-related structures, systems, and components of                             an adequate basis for complying with the pertinent nuclear power plants. This guide describes a method                               quality assurance requirements of Appendix B to 10
  acceptable to the NRC staff for complying with the                                 CFR Part 50. subject to the following:
  Commission's regulations with regard to quality assur- ance requirements for installation, inspection, and test-                               I. Subdivision 1.5 of ANSI N45.2.5-1974 states:
  ing of structural concrete and structural steel during the                         "Othet documents that are required to be included construction phasc of nuclear puwer plants. ThLi guide                             as a part of this standard are identified at the point applies to all types of nuclear power plants.                                     of reference and listed in Section 8 and the Appendix of this Standard." The specific applicability cr accepta-


==B. DISCUSSION==
==B. DISCUSSION==
Working Group N45.2.5 of tile American National Standards Committee N45, Reactor Plants and Their Maintenance, has prepared a standard that includes quality assurance requirements for installation, inspec-tion, and testing of structural concrete and structural steel during the construction phase of nuclear powcr plants. This standard was approved by Subcommittee N45-2, Nuclear Quality Assurance Standards, of the American National Standards Committee N45, and the full committee.
bility of documents listed in Section 8 has been covered separatcly in other regulatory guides. Other standards Working Group N45.2.5 of tile American National                               and codes listed in ANSI N45.2.5-1974 provide useful Standards Committee N45, Reactor Plants and Their                                 guidance for the installation, inspection, and testing of Maintenance, has prepared a standard that includes                                 structural concrete and structural steel. Prior to use of quality assurance requirements for installation, inspec-                           these other referenced codes and standards, however, tion, and testing of structural concrete and structural                           the suitability of the standard or code should be reviewed steel during the construction phase of nuclear powcr                               for the particular application under consideration.


It was subsequently approved and designated N45.2.5.19741 by the American National Standards Institute on July 8, 1974.[ANSI N45.2.S-1974. "Supplementary Quality Assurance Re-quirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants.- Copics may be obtained from the American Society of Mechanical Engineers.
plants. This standard was approved by Subcommittee N45-2, Nuclear Quality Assurance Standards, of the                                    2. Subdivision 2.1 of ANSI N45.2.5-1974 includes American National Standards Committee N45, and the                                general provisions for planning the installation, inspec- full committee. It was subsequently approved and                                   tion, and testing of structural concrete and structural designated N45.2.5.19741 by the American National                                 steel. In this regard the provisions of Subdivision 2.1 of Standards Institute on July 8, 1974.                                               ANSI N45.2.5'-1974 should be used in conjunction with Regulatory Guide 1.55, "Concrete Placement in Cate- gory I Structures."
    [ANSI N45.2.S-1974. "Supplementary Quality Assurance Re- quirements for Installation, Inspection, and Testing of Structural                     3. Subdivision 4.5 of ANSI N45.2.5-1974 provides, in Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants.- Copics may be obtained from the                             part, that inspection of concrete placement shall be American Society of Mechanical Engineers. 345 East 47th                            performed to verify the adequacy of concrete consolida- Street, New York. New York 10017.                                                  tion equipment and technique of operation. AC! 309-72, USNRC REGULATORY GUIDS                                        Comments should be sent to the Secretary of the Commi,sson. U.S. Nuclear Regulatory Guides are issued to describe and make available to the public            Regulatory Commrssron. Washington. 0 C 70.S. Attention Docketing and methods acceptable to the NRC staff of implementing specific parts of the            Seraice Section Commissoon t reguletons, to delineate techniques used by the staff in ewalu          The guides are issued in ha following teonbroad divsoions sling spectic problems or postulated accidents, or to provide guidance to applt cants Regulatory Guides ate not substitutes tfo regulations, and compliance          I  Power Reactots                      6  Products with thenm is not required. Methods and solutions difterent from those set out in    2  Research and Test Reactors          7  Ttansporilston the guides will be acceptable it they provide a basis for the findings requisite to  3  Fuels and Materials Facilities      a. Occupmrtonal Health the issuance or continuance of a permit or license by the Commission                4  Environmental and Siting            9  Antitrust Review S Comments and suggestion% lot impiovementin in these guides are etncou*aged at all times. and guides will he revised. a)Appropriate. to accomnrodate con.


345 East 47th Street, New York. New York 10017.C. REGULATORY
erants and to reflect new information or erperience However. comments on this guide. It received within about two months alfter its isluanc
POSITION The requirements and guidelines that ate included in ANSI N45.2.5-1974 for installation, inspection, and testing of structural concrete and structural steel during the construction phase of nuclear power plants are generally acceptable to the NRC sta,'f and provide an adequate basis for complying with the pertinent quality assurance requirements of Appendix B to 10 CFR Part 50. subject to the following:
I. Subdivision
1.5 of ANSI N45.2.5-1974 states: "Othet documents that are required to be included as a part of this standard are identified at the point of reference and listed in Section 8 and the Appendix of this Standard." The specific applicability cr accepta-bility of documents listed in Section 8 has been covered separatcly in other regulatory guides. Other standards and codes listed in ANSI N45.2.5-1974 provide useful guidance for the installation, inspection, and testing of structural concrete and structural steel. Prior to use of these other referenced codes and standards, however, the suitability of the standard or code should be reviewed for the particular application under consideration.


===2. Subdivision ===
====e. will be par====
2.1 of ANSI N45.2.5-1974 includes general provisions for planning the installation, inspec-tion, and testing of structural concrete and structural steel. In this regard the provisions of Subdivision
                                                                                      5 Melreils and Plant Protection      10. General Copies of published guides may be obtained by written request indiclting the divisions desired to the U.S, Nuclear Regulatory Commission. Washington, OC.
2.1 of ANSI N45.2.5'-1974 should be used in conjunction with Regulatory Guide 1.55, "Concrete Placement in Cate-gory I Structures."


===3. Subdivision ===
ticularly useful in evaluating the need for an eatly revision                        20%5, Attenlion. ODlector. Office of Standards Oevelopmrnt
4.5 of ANSI N45.2.5-1974 provides, in part, that inspection of concrete placement shall be performed to verify the adequacy of concrete consolida- tion equipment and technique of operation.


AC! 309-72, USNRC REGULATORY
"Recommended Practice for Consolidation of Con-               Division 2 as an approved Code and appropriate endorse.
GUIDS Comments should be sent to the Secretary of the Commi,sson.


U.S. Nuclear Regulatory Guides are issued to describe and make available to the public Regulatory Commrssron.
crete," should be used as a basis for determining tie          ment by the NRC staff.


Washington.
adequacy of tht. equipment for concrete consolidation


0 C 70.S. Attention Docketing and methods acceptable to the NRC staff of implementing specific parts of the Seraice Section Commissoon t reguletons, to delineate techniques used by the staff in ewalu The guides are issued in ha following teon broad divsoions sling spectic problems or postulated accidents, or to provide guidance to applt cants Regulatory Guides ate not substitutes tfo regulations, and compliance I Power Reactots 6 Products with thenm is not required.
==D. IMPLEMENTATION==
 
9i and of the technique of operation.
Methods and solutions difterent from those set out in 2 Research and Test Reactors 7 Ttansporilston the guides will be acceptable it they provide a basis for the findings requisite to 3 Fuels and Materials Facilities a. Occupmrtonal Health the issuance or continuance of a permit or license by the Commission
4 Environmental and Siting 9 Antitrust Review Comments and suggestion%
lot impiovementin in these guides are
5 Melreils and Plant Protection
10. General at all times. and guides will he revised. a) Appropriate.


to accomnrodate con.erants and to reflect new information or erperience However. comments on Copies of published guides may be obtained by written request indiclting the this guide. It received within about two months alfter its isluance.
4. Subdivision 4.10 of ANSI N45.2.S-1974 states:            The purpose of this section is to provide gbidance to applicants and licensees regarding the NRC staffs' plans
"Welded reinforcing bar splices shall be subject to the for utilizing this regulatory guide.


will be par divisions desired to the U.S, Nuclear Regulatory Commission.
requirements of Section 5.5, except that provisions of AWS D 12.1 shall apply." The provisions of Articles                Except in those cases in which the applicant proposes CC-4334 and CC-4330 of the "Proposed Standard Code            an acceptable alternative method for complying with the for Concrete Reactor Vessels and Containments" (Pro- specified portions of the Commission's regulations, the posed ASME Boiler and Pressure Code Section III,              method described herein will be used in the evaluation Division 2, through Committee Addenda 6)2 for testing of construction pzrnit submittals for applications dock- of welded reinforcing bar splices should be used as            eted after May 1, 1975. If an applicant whose applica.


Washington, OC.ticularly useful in evaluating the need for an eatly revision 20%5, Attenlion.
interim guidance pending issuance of ASME Section III          tion for a construction permit is docketed on or before May I, 1975 wishes to use this regulatory, guide in developing submittals for applications, the pertinent
  2 Copies m*,y bc obtained 'roi;1 The American Concrete        portions of the application will be evaluated on the basis Institute, P.O. Box 4754. Detroit, Michigan 48219.              of this guide.


ODlector.
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"Recommended Practice for Consolidation of Con-crete," should be used as a basis for determining tie adequacy of tht. equipment for concrete consolidation and of the technique of operation.
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===4. Subdivision ===
                J
4.10 of ANSI N45.2.S-1974 states: "Welded reinforcing bar splices shall be subject to the requirements of Section 5.5, except that provisions of AWS D 12.1 shall apply." The provisions of Articles CC-4334 and CC-4330 of the "Proposed Standard Code for Concrete Reactor Vessels and Containments" (Pro-posed ASME Boiler and Pressure Code Section III, Division 2, through Committee Addenda 6)2 for testing of welded reinforcing bar splices should be used as interim guidance pending issuance of ASME Section III 2 Copies bc obtained 'roi;1 The American Concrete Institute, P.O. Box 4754. Detroit, Michigan 48219.Division 2 as an approved Code and appropriate endorse.ment by the NRC staff.
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==D. IMPLEMENTATION==
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The purpose of this section is to provide gbidance to applicants and licensees regarding the NRC staffs' plans for utilizing this regulatory guide.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 in the evaluation of construction pzrnit submittals for applications dock-eted after May 1, 1975. If an applicant whose applica.tion for a construction permit is docketed on or before May I, 1975 wishes to use this regulatory, guide in developing submittals for applications, the pertinent portions of the application will be evaluated on the basis of this guide.9i ZZ 0<mC 00 0 0 z -'i 0-a 0 0 J 1.94-2}}
                                                        1.94-2}}


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Revision as of 10:14, 4 November 2019

Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants
ML13350A297
Person / Time
Issue date: 04/30/1975
From:
NRC/OSD
To:
References
RG-1.094
Download: ML13350A297 (2)
v • d • e


_____U

U.S. NUCLEAR REGULATORY COMMISSION April 1975 REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.94.

QUALITY ASSURANCE REQUIREMENTS FOR INSTALLATION,

INSPECTION, AND TESTING OF STRUCTURAL CONCRETE AND

STRUCTURAL STEEL DURING THE CONSTRUCTION PHASE OF NUCLEAR POWER PLANTS

A. INTRODUCTION

C. REGULATORY POSITION

Appendix B, "Quality Assurance Criteria for Nuclear The requirements and guidelines that ate included Power: Plants. and Fuel Reprocessing Plants." to 10 CFR in ANSI N45.2.5-1974 for installation, inspection, and Part 50, "Licensing of Production and Utilization testing of structural concrete and structural steel during Facilities," establishes overall quality assurance require- the construction phase of nuclear power plants are mcnts for the design, construction, and operation of generally acceptable to the NRC sta,'f and provide safety-related structures, systems, and components of an adequate basis for complying with the pertinent nuclear power plants. This guide describes a method quality assurance requirements of Appendix B to 10

acceptable to the NRC staff for complying with the CFR Part 50. subject to the following:

Commission's regulations with regard to quality assur- ance requirements for installation, inspection, and test- I. Subdivision 1.5 of ANSI N45.2.5-1974 states:

ing of structural concrete and structural steel during the "Othet documents that are required to be included construction phasc of nuclear puwer plants. ThLi guide as a part of this standard are identified at the point applies to all types of nuclear power plants. of reference and listed in Section 8 and the Appendix of this Standard." The specific applicability cr accepta-

B. DISCUSSION

bility of documents listed in Section 8 has been covered separatcly in other regulatory guides. Other standards Working Group N45.2.5 of tile American National and codes listed in ANSI N45.2.5-1974 provide useful Standards Committee N45, Reactor Plants and Their guidance for the installation, inspection, and testing of Maintenance, has prepared a standard that includes structural concrete and structural steel. Prior to use of quality assurance requirements for installation, inspec- these other referenced codes and standards, however, tion, and testing of structural concrete and structural the suitability of the standard or code should be reviewed steel during the construction phase of nuclear powcr for the particular application under consideration.

plants. This standard was approved by Subcommittee N45-2, Nuclear Quality Assurance Standards, of the 2. Subdivision 2.1 of ANSI N45.2.5-1974 includes American National Standards Committee N45, and the general provisions for planning the installation, inspec- full committee. It was subsequently approved and tion, and testing of structural concrete and structural designated N45.2.5.19741 by the American National steel. In this regard the provisions of Subdivision 2.1 of Standards Institute on July 8, 1974. ANSI N45.2.5'-1974 should be used in conjunction with Regulatory Guide 1.55, "Concrete Placement in Cate- gory I Structures."

[ANSI N45.2.S-1974. "Supplementary Quality Assurance Re- quirements for Installation, Inspection, and Testing of Structural 3. Subdivision 4.5 of ANSI N45.2.5-1974 provides, in Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants.- Copics may be obtained from the part, that inspection of concrete placement shall be American Society of Mechanical Engineers. 345 East 47th performed to verify the adequacy of concrete consolida- Street, New York. New York 10017. tion equipment and technique of operation. AC! 309-72, USNRC REGULATORY GUIDS Comments should be sent to the Secretary of the Commi,sson. U.S. Nuclear Regulatory Guides are issued to describe and make available to the public Regulatory Commrssron. Washington. 0 C 70.S. Attention Docketing and methods acceptable to the NRC staff of implementing specific parts of the Seraice Section Commissoon t reguletons, to delineate techniques used by the staff in ewalu The guides are issued in ha following teonbroad divsoions sling spectic problems or postulated accidents, or to provide guidance to applt cants Regulatory Guides ate not substitutes tfo regulations, and compliance I Power Reactots 6 Products with thenm is not required. Methods and solutions difterent from those set out in 2 Research and Test Reactors 7 Ttansporilston the guides will be acceptable it they provide a basis for the findings requisite to 3 Fuels and Materials Facilities a. Occupmrtonal Health the issuance or continuance of a permit or license by the Commission 4 Environmental and Siting 9 Antitrust Review S Comments and suggestion% lot impiovementin in these guides are etncou*aged at all times. and guides will he revised. a)Appropriate. to accomnrodate con.

erants and to reflect new information or erperience However. comments on this guide. It received within about two months alfter its isluanc

e. will be par

5 Melreils and Plant Protection 10. General Copies of published guides may be obtained by written request indiclting the divisions desired to the U.S, Nuclear Regulatory Commission. Washington, OC.

ticularly useful in evaluating the need for an eatly revision 20%5, Attenlion. ODlector. Office of Standards Oevelopmrnt

"Recommended Practice for Consolidation of Con- Division 2 as an approved Code and appropriate endorse.

crete," should be used as a basis for determining tie ment by the NRC staff.

adequacy of tht. equipment for concrete consolidation

D. IMPLEMENTATION

9i and of the technique of operation.

4. Subdivision 4.10 of ANSI N45.2.S-1974 states: The purpose of this section is to provide gbidance to applicants and licensees regarding the NRC staffs' plans

"Welded reinforcing bar splices shall be subject to the for utilizing this regulatory guide.

requirements of Section 5.5, except that provisions of AWS D 12.1 shall apply." The provisions of Articles Except in those cases in which the applicant proposes CC-4334 and CC-4330 of the "Proposed Standard Code an acceptable alternative method for complying with the for Concrete Reactor Vessels and Containments" (Pro- specified portions of the Commission's regulations, the posed ASME Boiler and Pressure Code Section III, method described herein will be used in the evaluation Division 2, through Committee Addenda 6)2 for testing of construction pzrnit submittals for applications dock- of welded reinforcing bar splices should be used as eted after May 1, 1975. If an applicant whose applica.

interim guidance pending issuance of ASME Section III tion for a construction permit is docketed on or before May I, 1975 wishes to use this regulatory, guide in developing submittals for applications, the pertinent

2 Copies m*,y bc obtained 'roi;1 The American Concrete portions of the application will be evaluated on the basis Institute, P.O. Box 4754. Detroit, Michigan 48219. of this guide.

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