Regulatory Guide 1.63

Electric Penetration Assemblies in Containment Structures for Water-Cooled Nuclear Power Plants

ML13350A357
Person / Time
Issue date:	10/31/1973
From:	US Atomic Energy Commission (AEC)
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References
RG-1.063
Download: ML13350A357 (2)

1973 Ni U.S. ATOMIC ENERGY COMMISSION

REGULATORY

GUI DIRECTORATE

OF REGULATORY

STANDARDS)

REGULATORY

GUIDE 1.63 ELECTRIC PENETRATION

ASSEMBLIES

IN CONTAINMENT

STRUCTURES

FOR WATER-COOLED

NUCLEAR POWER PLANTS DE

A. INTRODUCTION

General Design Criterion 50, "Containment Design Basis," of Appendix A, "General Design Criteria for Nuclear Power Plants," to IOCFR Part 50, "Licensing of Production and Utilization Facilities" requires, in part, that the reactor containment structure, including penetrations, be designed so that the contain.ment structure can, without exceeding the design leakage rate, accommodate the calculated pressure, temperature, and other environmental conditions resulting from any loss-of-coolant accident.

Appendix B to Part 50, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," establishes quality assurance requirements for the design, construction, and operation of nuclear power plant structures, systems, and components.

This guide describes an acceptable method of complying with Appendix B and Criterion

56 of Appendix A with respect to the mechanical, electrical, and test requirements for the design, construction, and installation of electric penetration assemblies in containment structures for water-cooled nuclear power plants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.

B. DISCUSSION

IEEE Std 3 1 7-1 9 7 2 ,' "IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations," was prepared by the Joint Committee on Nuclear Power Standards (currently designated the Nuclear Power Engineering Committee)

of the Institute of Electrical and Electronics Engineers, Inc. (IEEE), and subsequently approved by'Copies may be obtained from the Institute of Electrical and Electronics Engineers, 345 East 47th Street, New York, New York 10017.the IEEE Standards Committee on September

20. 107..It is an IEEE standard which prescribes design.construction, installation, and testing requirements for electric penetration assemblies in containment structiltes for water-cooled nuclear power plants.C. REGULATORY

POSITION IEEE Std 317-1972, "IEEE Standard for I-lectriu" Penetration Assemblies in Containment Structures t'm Nuclear Power Generating Stations," provides an acceptable method of complying with Appendix B and General Design Criterion 50 of Appendix A to 10 CFR Part 50 with respect to mechanical, electrical and test requirements for the design, constnhction, and installation of electric penetration assemblies in containment structures for water-cooled nuclear power plants, subject to the following:

1. Section 4 should be supplemented as follows: The electric penetration assembly should be designed to withstand, withou! loss of mechanical integrity, the maximum possible fault current vs. time conditiins (which could occur because of single random failures of circuit overload prote. :ion devices) within the two leads of any one single-phase

rcuit or the three leads ot any one three.phase circuit. Incorporating adequate sell-fusing characteristics within the penetration conductors themselves constitutes an acceptable design approach.Where self-fusing characteristics are not incorporated, the circuit overload protection system should conformi to the criteria of IEEE Std 279-1971,' "Criteria for Protection Systems for Nuclear Power Generating Stations" (also designated ANSI N42.7-1972).

2. The maximum containment pressure to he specified in accordance with Section 4.3 should be construed as being synonymous with maximum containment internal IJSAIC REGULATORY

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Meth"d end aolutions different fromt those sat out let The Sp18w swe heued It, the folIaongr ten broaid d~IvItont:

thes Odaw esll be aeet I"e If they twold a bash for If* flndlnge reqJw~te to te'swat an antnuenos o al permil t Mrtemoe by the Comwtlecl0.

1. poyean Rewant 6. ProdvMt 2. Rwmrdch end Test Rsectl 7. Tras'ucrtef'on

2. F uok and Materilst Faclyiftl S. oeccutlorttHalt01h Puld~ihaed gudes selti be reelsed porkiscldtly.

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and to reflect Mtee lntonntlaon orexperience.

S. Meenlals end Imamt Pratetikon tO. Ge"wal pressure as defined in footnote I to Article NE3000 of Section III of the ASME Boiler and Pressure Vessel Code (Summer 1972 Addenda).2 3. The specific applicability or acceptability of the codes, standards, and guides referenced in Section 3 will he covered separately in other regulatory guides, where appropriate.ma) be obtined from the American Society of Mechanical Engineers, United Enginering Center, 345 EWst 47th Street, New York, New York 10017.4. Section 8 shoula be tupplemented as follows: The quality assurance requirements for the design, construction, installation, and testing of electric penetration assemblies shaU be in accordance with the requirements set forth in ANSI N45.2.1971, 2 "Quality Assurance Program Requirements for Nuclear Power Plants," and ANSI N45.2.4.1972!'

2 Inspection, and Testing Requirements fur Instrumentation and Electric Equipment During the Construction of Nuclear Power Generating Stations." (also designated IEEE Std 336-1971 ).1.63.2