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
Download: ML003740305 (2)

Revision 1 U.S. NUCLEAR REGULATORY COMMISSION 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

C. REGULATORY POSITION

Appendix B, "Quality Assurance Criteria for Nuclear The requirements and guidelines that are included in Power Plants and Fuel Reprocessing Plants," to 10 CFR 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 ments for the design, construction, and operation of generally acceptable to the NRC staff and provide an safety-related structures, syste-ris, and components of adequate basis for complying with the pertinent quality nuclear power plants. This guide describes a method assurance requirements of Appendix B to 10 CFR Part acceptable to the NRC staff for complying with the 50, subject to the following:

Commission's regulations with regard to quality assur ance requirements for installation, inspection, and test ing of structural concrete and structural steel during the 1. Subdivision 1.5 of ANSI N45.2.5-19.74 states:

construction phase of nuclear power plants. This guide "Other documents that are required to be included as a applies to all types of nuclear power plants. The part of this standard are identified at the point of Advisory Committee on Reactor Safeguards has been reference and listed in Section 8 and the Appendix of consulted concerning this guide and has concurred in the this Standard." The specific applicability or acceptabil regulatory position. ity of documents listed in Section 8 has been covered separately in other regulatory guide

B. DISCUSSION

and codes listed in ANSI N45.2.5-1974 provide useful Working Group N45.2.5 of the American National guidance for the installation, inspection, and testing of Standards Committee N45, Reactor Plants and Their structural concrete and structural steel. Prior to use of Maintenance, has prepared a standard that includes these other referenced codes and standards, however, the quality assurance requirements for installation, inspec suitability of the standard or code should be reviewed tion, and testing of structural concrete and structural for the particular application under consideration.

steel during the construction phase of nuclear power 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 ANSI N45.2.5-1974 should be used in conjunction with Standards Institute on July 8, 1974.

Regulatory Guide 1.55, "Concrete Placement in Cate

• Lines indicate substantive changes from previous issue. gory I Structures."

'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 3. Subdivision 4.5 of ANSI N45.2.5-1974 provides, Phase of Nuclear Power Plants." Copies may be obtained from in part, that inspection of concrete placement shall be

ý1'the Ame'ican 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. 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 should be used as guidance pending endorsement of that crete," 2 should be used as a basis for determining the Code by the NRC staff.

adequacy of the equipment for concrete consolidation and of the technique of operation.

D. IMPLEMENTATION

4. Subdivision 4.10 of ANSI N45.2.5-1974 states:

"Welded reinforcing bar splices shall be-subject to the The purpose of this section is to provide information requirements of Section 5.5, except that provisions of to applicants regarding the NRC staff's plans for using AWS D 12.1 shall apply." In addition, the provisions of this regulatory guide.

Articles CC4334 and CC4330 of the "Code for Concrete Reactor Vessels and Containments" (ASME Boiler and Except in those cases in which the applicant proposes Pressure Vessel Code,Section III, Division 2, 1975 an acceptable alternative method for complying with Edition) 3 for testing of welded reinforcing bar splices specified portions of the Commission's regulations, the method described herein will be used in the evaluation of

2 Copies may be obtained from The American Concrete Institute, construction permit applications docketed after October

3 P.O. Box 4754, Detroit, Michigan 48219. 15, 1976. The methods described herein will continue to Copies may be obtained from the American Society of be used until this guide is revised as a result of Mechanical Engineers, 345 East 47th Street, New York, N.Y.

10017. suggestions from the public or additional staff review.

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