Regulatory Guide 1.94
| ML13350A297 | |
| Person / Time | |
|---|---|
| Issue date: | 04/30/1975 |
| From: | NRC/OSD |
| To: | |
| References | |
| RG-1.094 | |
| Download: ML13350A297 (2) | |
_____U U.S. NUCLEAR REGULATORY
COMMISSION
April 1975 REGULATORY
GUIDE OFFICE OF STANDARDS
DEVELOPMENT
REGULATORY
GUIDE 1.9
4. 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-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.
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.
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.
345 East 47th Street, New York. New York 10017.C. REGULATORY
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
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.
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.
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.
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.
will be par 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 S
"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.
4. Subdivision
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.
D. IMPLEMENTATION
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