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

ML13350A297
Person / Time
Issue date:	04/30/1975
From:	NRC/OSD
To:
References
RG-1.094
Download: ML13350A297 (2)

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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

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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