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{{Adams
{{Adams
| number = ML13350A297
| number = ML003740305
| issue date = 04/30/1975
| issue date = 04/30/1976
| title = Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants
| title = Rev 1 Quality Assurance Requirements for Installation, Inspection & Testing of Structural Concrete & Structural Steel During the Construction Phase of Nuclear Power Plants
| author name =  
| author name =  
| author affiliation = NRC/OSD
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.094
| document report number = RG-1.94, Rev 1
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 2
| page count = 2
}}
}}
{{#Wiki_filter:_____U
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION
  U.S. NUCLEAR REGULATORY COMMISSION                                                                                                               April 1975 REGULATORY GUIDE
Revision 1 April 1976 REGULATORY GUIDE  
  OFFICE OF STANDARDS DEVELOPMENT
OFFICE OF STANDARDS DEVELOPMENT  
                                                                    REGULATORY GUIDE 1.94.
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


QUALITY ASSURANCE REQUIREMENTS FOR INSTALLATION,
==A. INTRODUCTION==
                              INSPECTION, AND TESTING OF STRUCTURAL CONCRETE AND
Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR
    STRUCTURAL STEEL DURING THE CONSTRUCTION PHASE OF NUCLEAR POWER PLANTS
Part 50, "Licensing of Production and Utilization Facilities," establishes overall quality assurance require ments for the design, construction, and operation of safety-related structures, syste-ris, 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 phase of nuclear power plants. This guide applies to all types of nuclear power plants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.
 
==B. DISCUSSION==
Working Group N45.2.5 of the 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 power plants. This standard was approved by Subcommittee N45-2, Nuclear Quality Assurance Standards, of the American National Standards Committee N45, and the full committee.
 
It was subsequently approved and designated N45.2.5-19741 by the American National Standards Institute on July 8, 1974.
 
*Lines indicate substantive changes from previous issue.


==A. INTRODUCTION==
'ANSI N45.2.5-1974, "Supplementary Quality Assurance Re quirements for Installation, Inspection, and Testing of Struc tural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants." Copies may be obtained from
ý1'the Ame'ican Society of Mechanical Engineers, 345 East 47th Street, New York, New York 10017.


==C. REGULATORY POSITION==
==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
The requirements and guidelines that are 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 staff and provide an adequate basis for complying with the pertinent quality assurance requirements of Appendix B to 10 CFR Part  
  acceptable to the NRC staff for complying with the                                CFR Part 50. subject to the following:
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:
1. Subdivision 1.5 of ANSI N45.2.5-19.74 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-  
"Other 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 or acceptabil ity of documents listed in Section 8 has been covered separately 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.


==B. DISCUSSION==
2. Subdivision 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 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."
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.
3. Subdivision 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. ACI 309-72, USNRC REGULATORY GUIDES
Comments should be sent to the Secretary of the Commission. U.S. Nuclear Regulatory Commission. Washington, D.C. 20555. Attention: Docketing and Regulatory Guides are issued to describe and make available to the public Service Section.
 
methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evalu.


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."
The guides are issued in the following ten broad divisions Sting specific problems or postulated accidents. or to provide guidance to appli cants Regulatory Guides are not substitutes for regulations, and compliance  
    [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
===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
0 Occupational Health the issuance or continuance of a permit or license by the Commission
4. Environmental and Siting S Antitrust Review Comments and suggestions for improvements in these guides are encouraged
5 Materials and Plant Protection
10. General at all times. and guides will be revised, as appropriate, to accommodate com ments rnd 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


====e. will be par====
"Recommended Practice for Consolidation of Con crete," 2 should be used as a basis for determining the adequacy of the equipment for concrete consolidation and of the technique of operation.
                                                                                      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
4. Subdivision 4.10 of ANSI N45.2.5-1974 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." In addition, the provisions of Articles CC4334 and CC4330 of the "Code for Concrete Reactor Vessels and Containments" (ASME Boiler and Pressure Vessel Code, Section III, Division 2, 1975 Edition)3 for testing of welded reinforcing bar splices
2Copies may be obtained from The American Concrete Institute, P.O. Box 4754, Detroit, Michigan 48219.


"Recommended Practice for Consolidation of Con-                Division 2 as an approved Code and appropriate endorse.
3Copies may be obtained from the American Society of Mechanical Engineers, 345 East 47th Street, New York, N.Y.


crete," should be used as a basis for determining tie          ment by the NRC staff.
10017.


adequacy of tht. equipment for concrete consolidation
should be used as guidance pending endorsement of that Code by the NRC staff.


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
9i and of the technique of operation.
The purpose of this section is to provide information to applicants regarding the NRC staff's plans for using this regulatory guide.
 
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
Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used in the evaluation of construction permit applications docketed after October
  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.
15, 1976. The methods described herein will continue to be used until this guide is revised as a result of suggestions from the public or additional staff review.


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Latest revision as of 02:05, 17 January 2025

Rev 1 Quality Assurance Requirements for Installation, Inspection & Testing of Structural Concrete & Structural Steel During the Construction Phase of Nuclear Power Plants
ML003740305
Person / Time
Issue date: 04/30/1976
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.94, Rev 1
Download: ML003740305 (2)
v • d • e


U.S. NUCLEAR REGULATORY COMMISSION

Revision 1 April 1976 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

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 ments for the design, construction, and operation of safety-related structures, syste-ris, 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 phase of nuclear power plants. This guide applies to all types of nuclear power plants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.

B. DISCUSSION

Working Group N45.2.5 of the 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 power plants. This standard was approved by Subcommittee N45-2, Nuclear Quality Assurance Standards, of the American National Standards Committee N45, and the full committee.

It was subsequently approved and designated N45.2.5-19741 by the American National Standards Institute on July 8, 1974.

  • Lines indicate substantive changes from previous issue.

'ANSI N45.2.5-1974, "Supplementary Quality Assurance Re quirements for Installation, Inspection, and Testing of Struc tural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants." Copies may be obtained from

ý1'the Ame'ican Society of Mechanical Engineers, 345 East 47th Street, New York, New York 10017.

C. REGULATORY POSITION

The requirements and guidelines that are 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 staff 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:

1. Subdivision 1.5 of ANSI N45.2.5-19.74 states:

"Other 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 or acceptabil ity of documents listed in Section 8 has been covered separately 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 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 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 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. ACI 309-72, USNRC REGULATORY GUIDES

Comments should be sent to the Secretary of the Commission. U.S. Nuclear Regulatory Commission. Washington, D.C. 20555. Attention: Docketing and Regulatory Guides are issued to describe and make available to the public Service Section.

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 Sting 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

0 Occupational Health the issuance or continuance of a permit or license by the Commission

4. Environmental and Siting S Antitrust Review Comments and suggestions for improvements in these guides are encouraged

5 Materials and Plant Protection

10. General at all times. and guides will be revised, as appropriate, to accommodate com ments rnd 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

"Recommended Practice for Consolidation of Con crete," 2 should be used as a basis for determining the adequacy of the equipment for concrete consolidation and of the technique of operation.

4. Subdivision 4.10 of ANSI N45.2.5-1974 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." In addition, the provisions of Articles CC4334 and CC4330 of the "Code for Concrete Reactor Vessels and Containments" (ASME Boiler and Pressure Vessel Code,Section III, Division 2, 1975 Edition)3 for testing of welded reinforcing bar splices

2Copies may be obtained from The American Concrete Institute, P.O. Box 4754, Detroit, Michigan 48219.

3Copies may be obtained from the American Society of Mechanical Engineers, 345 East 47th Street, New York, N.Y.

10017.

should be used as guidance pending endorsement of that Code by the NRC staff.

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants regarding the NRC staff's plans for using this regulatory guide.

Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used in the evaluation of construction permit applications docketed after October

15, 1976. The methods described herein will continue to be used until this guide is revised as a result of suggestions from the public or additional staff review.

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