Regulatory Guide 1.94

Rev 1 Quality Assurance Requirements for Installation, Inspection & Testing of Structural Concrete & Structural Steel During the Construction Phase of Nuclear Power Plants

ML003740305
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Issue date:	04/30/1976
From:	Office of Nuclear Regulatory Research
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RG-1.94, Rev 1
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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 2 Copies may be obtained from The American Concrete Institute, P.O. Box 4754, Detroit, Michigan 48219. 3 Copies 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.(n. 0 W Z z 0 0 U) 0 LIn Cni O0 D Un) UN wL 0 ~> th Z ou -J . 0 Z LA 0I W z z