Regulatory Guide 1.89
| ML012880422 | |
| Person / Time | |
|---|---|
| Issue date: | 11/30/1974 |
| From: | US Atomic Energy Commission (AEC) |
| To: | US Atomic Energy Commission (AEC) |
| References | |
| RG-1.089 | |
| Download: ML012880422 (2) | |
U.S. ATOMIC ENERGY COMMIS
REGULAI
DIRECTORATE OF REGULATOR"
REGULATORY
QUALIFICATION OF C
FOR NUCLEAR P
A. INTRODUCTION
Criterion III, "Design Control," of Appendix B,
"Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50,
"Licensing of Production and Utilization Facilities,"
requires that design control measures provide for veri fying the adequacy of a specific design feature by design reviews, by calculational methods, or by suitable qualifi cation testing of a prototype unit under the most adverse conditions. This regulatory guide describes a method acceptable to the Regulatory staff for com plying with the Commission's regulations with regard to design verification of Class IE equipment for service in light-water-cooled and gas-cooled nuclear power plants.
B. DISCUSSION
IEEE Std 323-1974, "IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Sta tions,"' dated February 28, 1974, was prepared by Sub committee 2, Equipment Qualification, of the Nuclear Power Engineering Committee of the Institute of Elec trical and Electronics Engineers, Inc., (IEEE) and sub sequently was approved by the IEEE Standards Board on December 13, 1973. The standard describes basic procedures for qualifying Class IE equipment and inter faces that are to be used in nuclear power plants and components or equipment of any interface whose failure could adversely affect any class IE equipment.
The requirements delineated include principles, pro cedures, and methods of qualification which, when satisfied, will confirm the adequacy of the equipment design for the performance of Class IE functions under normal, abnormal, design-basis-event, post-design-basis event, and containment-test conditions.
November 1974 SION
"ORY
GUIDE
V STANDARDS
GUIDE 1.89 LASS IE EQUIPMENT
OWER PLANTS
C. REGULATORY POSITION
The procedures described in IEEE Std 323-1974,
"IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations,"' dated February
28, 1974, for qualifying Class IE equipment for service in light-water-cooled and gas-cooled nuclear power plants are generally acceptable and provide an adequate basis for complying with design verification requirements of Criterion III of Appendix B to 10 CFR Part 50 to verify adequacy of design under the most adverse design condi tions subject to the following:
1. Reference is made in IEEE Std 323-1974, Sections 2,
6.3.2(5), and 6.3.5, to IEEE Std 344-1971, "Guide for Seismic Qualification of Class I Electric Equipment for Nuclear Power Generating Stations." The specific appli cability or acceptability of IEEE Std 344 will be covered separately in other regulatory guides, where appropriate.
2. The radiological source term for qualification tests in a nuclear radiation environment should be based on the same source term as that used in Regulatory Guide 1.7 (Safety Guide 7, 3/10/71) for BWRs and PWRs. An equivalent source term (i.e., 100% of the noble gases,
50% of the halogens, and 1% of the remaining solids developed from maximum full-power operation of the core) should be used for HTGRs. The containment size should be taken into account in each case. For exposed organic materials, calculations should take into account both beta and gamma radiation.
' Copies may be obtained from the Institute of Electrical and Electronics Engineers, Inc., United Engineering Center, 345 East
47th Street, New York, New York 10017.
USAEC REGULATORY GUIDES
Copies of published guides may be obtained by request indicating the divisions desired to the U.S.
Atomic Energy Commission, Washington, D.C. 20545, Regulatory Guides are issued to describe and make available to the public Attention: Director of Regulatory Standards. Comments and suggestions for methods acceptable to the AEC Regulatory staff of implementing specific parts of improvements in these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques
.sed by the staff in of the Commission, U.S. Atomic Energy Commission, Washington, D.C. 20545, evaluating specific problems or postulated accidents, or to provide guidance to Attention: Docketing and Service Section.
'pplicants. Regulatory Guides are not substitutes for regulations and compliance ith them is not required. Methods and solutions different from those set out in The guides are issued in the following ten broad divisions:
"a guides will be acceptable if they provide a basis for the findings requisite to
"e issuance or ontinuance of a permit or license by the Commission.
1. Power Reactors
6. Products
2. Research and Test Reactors
7. Transportation
3. Fuels and Materials Facilities
8. Occupational Health Published guides will be revised periodically, as appropriate, to accommodate
4. Environmental and Siting
9. Antitrust Review comments and to reflect new information or experience.
5. Materials and Plant Protection
10. General E*-!CLOSUUE
its
.2'
4
-
D. IMPLEMENTATION
The purpose of this section is to provide information to applicants and licensees regarding the Regulatory staff's plans for utilizing this regulatory guide.
This guide reflects current regulatory 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, this guide will be used by the Regulatory staff in evaluating all construction permit applications for which the issue date of the Safety Evaluation Report (SER) is July 1, 1974, or after.
For those construction permit applications for which an SER was issued prior to July 1, 1974, the Regulatory staff may, subsequent to issuance of the construction permit (or operating license), reevaluate the Safety Analysis Report on a case-by-case basis to assure that acceptable methods for qualification of Class IE equip ment have been specified in purchase orders executed for such equipment on or after November 15, 1974.
1.89-2