Regulatory Guide 1.116
| ML003739465 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1977 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| References | |
| RG-1.116 | |
| Download: ML003739465 (2) | |
U.S. NUCLEAR REGULATORY COMMISSION
Revision O-R19 Rune 1976 REGULATORY GUIDE
OFFICE OF STANDARDS DEVELOPMENT
REGULATORY GUIDE 1.116 (This page revised May 1977)
QUALITY ASSURANCE REQUIREMENTS FOR INSTALLATION, INSPECTION,
AND TESTING OF MECHANICAL EQUIPMENT AND SYSTEMS
A. INTRODUCTION
Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR
Part SO, "Licensing of Production and Utilization Facilities," establishes overall quality assurance require ments for the design, construction, and operation of sa7.ty-reiated 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 mechanical equipment and systems for water cooled and high-temperature gas-cooled nuclear power plants.*
B. DISCUSSION
Working Group N45-2.8 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 mechanical equipment and systems for water-cooled and high-temperature gas-cooled nuclear power plants. This standard was approved by Subcommittee N45-2, Nuclear Quality Assurance Stand ards, of the American National Standards Committee N45 and the full committee.
It was subsequently approved and designated N45.2.8-1975 1 by the American National Standards Institute on May 20. 1975.
NRC documents WASH 1309, "Guidance on Quality Assurance Requirements During the Construction Phase of Nuclear Power Plants," dated May 10, 1974 (Green
'ANSI
N45.2.8-1975,
"Supplementary Quality Assurance
"Requirements for Installation, Inspection, and Testingt of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants." Copies may be obtained from the American Society of Mechanical Engineers, 345 East 47th Street, New York, New York 10017.
Book, Revision 0) and WASH 1284, "Guidance on Quality Assurance Requirements During the uperations Phase of Nuclear Power Plants," dated October 26, 1973 (Orange Book, Revision 0) contain guidance on accept able methods of implementing portions of the quality assurance program. These documents are used by the NRC staff in the evaluation of applications for construc tion permits and operating licenses. WASH 1284 con tains extracts of proposed standard N45.2.8 (Draft 3, Rev. 2) and WASH 1309 contains proposed standard N45.2.8 (Draft 3. Rev. 3). ANSI N45.2.8-1975 reflects development from the proposed versions referenced in the above WASH documents to the final version approved by the American National Standards Institute.
No substantive changes have been made to NRC
guidance on quality assurance requirements for installa tion, inspection, and testing of water-cooled and high temperature gas-cooled nuclear power plant mechanical equipment from that previously provided.
It is important to consider the relationship of the quality assurance requirements included in Sections III
and X! of the ASME Boiler and Pressure Vessel Code with those included in ANSI N45.2.8-1975. Code-covered activities are primarily intended to assure the integrity of the pressure boundary of an item. Not all activities of safety importance are covered by the Code. The Code does not cover requirements to assure operability of components. Accordingly, activities of N45.2.8-1975 apply to Code components except for those activities addressed in the Code.
The applicability of N45.2.8-1975 and Sections III and XI of the ASME
Boiler and Pressure Vessel Code is addressed in Section
1.2 of ANSI N45.2,8-1975.
/
C. REGULATORY POISITION
The requirements for installation, inspection, and testing of mechanical equipment and systems of water cooled and high-temperature gas-cooled nuclear power USNRC REGULATORY GUIDES
Comments should be sent to the Secretary of the Commission, US -Nuclear Rego latory Commission Washington D.C.
20555, Attention: Docketing and Service Regulatory Guides are issued to describe and make available to the public methods Branch.
acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specific problems The guides are issued in the following ten broad divisions or postulated accidents, or to provide guidance to applicants.
Regulatory Guides ate not substitutes for regulations, and compliance with them is not required.
1. Power Reactors
6 Products Methods and solutions different from those set out in the guides will be accept.
2. Research andi Test Reactors
7. Transportation able if they provide a basis for the findings requisite to the issuance or continuance
3. Fuels and Materials Facilities
6. Occupational Health of a permit or license by the Commission.
4. Environmental and Siting
9. Antitrust Review
5. Materials and Plant Protection
10. General Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to Requests for single copies of issued guides (which may be reproduced) or for place reflect new information or experience, However the staff's consideration of com ment on an automatic distribution list for single copies of future guides in specific resots rece,,ed during the initial public comment period for this guide has resulted divisions should be made in writing to the US. Nuclear Regulatory Commission.
in the determination that there is no need for a revision at this time.
Washrngton D.C
20555, Attention Director. Division of Document Controi
- The Advisor" Committee on Reactor Saf'eguards has heetn consulted concerning this u*lde and has concurred in the regulatory position.
ýpants that are included in ANSI N45.2.8-1975 are 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 Ute following:
1. Subdivision 1.5 of ANSI N45.2.8-1975 states:
"Documents that are required to be included as a part of this standard are identified at the point of reference and described in Section 8 of this standard." The specific acceptability of these listed documents has been or will be covered separately in other regulatory guides or in Commission reu'-tions where appropriate.
2. Although ANSI N45.2.8-1975 is entitled "Supple mentary Quality Assurance Requirements for Installa tion, Inspection, and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants," the requirements included in the stand ard are considered to be applicable during the operations phase a. well as the construction phase and should be followed for those applicable operations phase activities that are comparable to activities occurring during the construction phase. In this regard, it should be noted that N45.2.8-1975 does not address radiological con siderations associated with installation, inspection, and testing of mechanical components in radioactively con taminated systems.
3. Section 5 of N45.2.8-1975 includes requirements for install *-
system inspections and tests. Individual subsections address preoperational tests, cold functional tests, and hot functional tests. Regulatory Guide 1.68,
"Preoperational and Initial Startup Test Programs .L.r- Water-Cooled Power Reactors," describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to preoperational and initial startup testing programs for water-cooled nuclear power plants 2 In this regard, the requirements of Section 5 of N45.2.8-1975 pertaining to preopera tional tests, cold functional tests, and hot functional tests should be used in conjunction with Regulatory Guide 1.68.
D. IMPLEMENTATION
The purpose of this section is to provide information to applicants regarding the NRC staff's plans for using this regulatory guide.
This guide reflects current NRC staff practice. There fore, except in those cases in which the applicant proposes an acceptable alternative method for com plying with specified portions of the Commission's regulations, the method described herein is being and will continue to be used in the evaluation of submittals for operating license or construction permit applications until this guide is revised as a result of suggestions from the public or additional staff review.
Although Regulatory Guide 1.68 pertains to preoperational and initial startup test programs for water-cooled nuclear power plants, it should be used as guidance in preparing preopera tional and initial startup test propams for high-temperature pa-cooled nuclear power plants.
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