Regulatory Guide 1.73

Qualification Tests of Electric Valve Operations Installed Inside the Containment of Nuclear Power Plants

ML003740261
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Issue date:	01/31/1974
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RG-1.73
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anuary 1974 U.S. ATOMIC ENERGY COMMISSION

REGULATORY GUI DE

DIRECTORATE OF REGULATORY STANDARDS

REGULATORY GUIDE 1.73 QUALIFICATION TESTS OF ELECTRIC VALVE OPERATORS INSTALLED

INSIDE THE CONTAINMENT OF NUCLEAR POWER PLANTS

A. INTRODUCTION

demonstrate design adequacy for service within the containment of a nuclear power plant. The procedure Section Ill, "Design Control." of Appendix B, provides for testing under conditions simulating (I)

"Quality Assurance Criteria for Nuclear Power Plants those that would be imposed during and after a design and Fuel Reprocessing Plants," to 10 CFR Part 50, basis loss-of-coolant accident and (2) those occurring

"Licensing of Production and Utilization Facilities," during normal operating conditions.

requires that, where a test program is used to verify the adequacy of a specific design feature, it include suitable The standard specifies procedures for accomplishing qualification testing of a prototype unit under the most accelerated aging of components to simulate the effects adverse design conditions. This regulatory guide of long-term operation under normal operating describes a method acceptable to the Regulatory staff conditions. These effects include exposure to nuclear for complying with the Commission's regulations with radiation, temperature, pressure, humidity, and chemical regard to qualification testing of Class I electric valve sprays. The standard also includes procedures for operators for service within the containment of accomplishing accelerated aging due to wear under rated light-water-cooled and gas-cooled nuclear power plants load conditions for the estimated number of operating to assure that the valve operator design will meet its cycles over a 40-year period or for 500 operating cycles, performance requirements. The Advisory Committee on whichever is larger.

Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory positio

B. DISCUSSION

The procedures specified by IEEE Std 382-1972.

"IEEE Trial-Use Guide for Type Test of Class I Electric IEEE Std 382-1972, "IEEE Trial-Use Guide for Valve Operators for Nuclear Power Generating Type Testn of Class I Electric Valve Operators for Nuclear Power Generating Stations," dated April 10, Stations," 3 dated April 10, 1973, for conducting

1973,2 (also designated ANSI N41.6) was prepared by qualification tests of electric valve operators for service Subcommittee 2 , Equipment Qualification, of the IEEE inside the containment vessel of water-cooled and gas-cooled nuclear power plants are generally acceptable Joint Committee on Nuclear Power Standards of the Institute of Electrical and Electronics Engineers, Inc.

and provide an adequate basis for complying with the qualification testing requirements of Section III of (IEEE) and subsequently was approved by the IEEE

Appendix B to 10 CFR Part 50 to verify adequacy of Standards Committee on September 20, 1972. The design for service under design basis event conditions.

standard delineates specific procedures for the subject to the following:

qualification testing of Class I electric valve operators to

1. To the extent practicable, auxiliary equipment (e.g.,

limit switches) that is not integral with the valve

' As used in this regulatory guide, the team "qualification test" and the term "type test" as defined in IEEE Std 382-1972 are synonymous.

3Clpies may be obtained from the Institute of Electrical

'This regulatory guide applies only to the version of IEEE and Electronics Engineers, United Engineering Center, 345 East Std 382-1972 dated April 10. 1973. 47th Street, New York, N.Y. 10017.

USAEC REGULATORY GUIDES CWpm of published guides may be obtained by requmt indicting the divisions desled wo the US. Atomic Enrlgy Commission, Washington. D.C. 20545, Regulatory Guides am issued to dcwliba end make mailable to the public Attention: Director of Regulatory Standards. Comments and suggestions for gtuthods aceptable to the AEC Regulatory staff of Implementing specific parts of Improvements In these guides am encouraged end should be sent to the Secretary the Commlssion's regulations, to delineste techniques used by the staff in of the Commission. US. Atomic Energy Commission. Washington. D.C. 21645.

emvluating ipedlic problems or postulated eccidents, or to provide guidanc to Attention: Chief, Public Proceedlngs Staff.

epplimnts RegAstory Guides ae not substltutes for regulations and comnpliance wit them Is not required. Methods end solutions different from those at out In The uides am Issued in the following ten broad divisions:

to guides will be acceptable If they Provide a bstisfor the findings requisite to the Issuane or continuance of a permit or license by the Commission. 1. Power Reactois

6. Products

2. Research end Tes Reactors

7. Transportation

3. Fuels end Materials Facilities I. occupational Health Published u will be revised periodically. as eppropriate, to accommoddte 4. IEnvlronmental and Siting 9. Antitrust Review eomstnt end to rfslect new Informstion or experience. 5LMateriels and Plant Protection 1

0. General

operator mechanism but will be part of the installed Concentrations in Containment Following a Loss of valve operator assembly should be tested in accordance Coolant Accident," for BWRs and PWRs. An equivalent with the subject standard. source term (.e.,100% of the noble gases, 50% of the halogens, and 1% of the remaining solids developed from

2. The test sequence described in Section 4.5.2 of the maximum full-power operation of the core) should be standard should be used unless the anticipated actual used for HTGRs. The containment size should be taken service operating sequence for the valve operator is into account in each case. For exposed organic materials, expected to create a more severe operating condition calculations should take into account both beta and than described in Section 4.5.2. In such case, the actual gamma radiation.

service sequence should be used in the test.

3. To assure that the valve operator is tested under an 5. Qualification testing for gas-cooled reactor (HTGR)

environment of sufficient severity, the magnitude of the components should follow the written description in environmental conditions (e.g., temperature, pressure, Section 4 of IEEE Std 382-1972 through at least two radiation, humidity) that, simulate the conditions to environmental transients of the temperature profiles which the valve operator is expected to be exposed depicted in Figures 2 and 3 of IEEE Std 382-1972.

during and following a design basi's. accident (Section

4.4, second paragraph) should be based on conservative calculations. 6. Part I, Section 6, "Standard References," of IEEE Std 382-1972, dated April 10, 1972, lists additional

4. The radiological source term for qualification tests applicable IEEE Standards. The specific applicability or in a nuclear radiation environment should be based on acceptability of these referenced standards has been or the same source term used in Regulatory Guide 1.7 will be covered separately in other regulatory guides, (Safety Guide 7), "Control, of Combustible Gas where appropriate.

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