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)

Oc**btr 1973 Ni U.S. ATOMIC ENERGY COMMISSION

REGULATORY

DIRECTORATE OF REGULATORY STANDARDS)

GUI DE

REGULATORY GUIDE 1.63 ELECTRIC PENETRATION ASSEMBLIES IN CONTAINMENT STRUCTURES

FOR WATER-COOLED NUCLEAR POWER PLANTS

A. INTRODUCTION

the IEEE Standards Committee on September 20. 107..

It is an IEEE standard which prescribes design.

General Design Criterion 50, "Containment Design construction, installation, and testing requirements for Basis," of Appendix A, "General Design Criteria for electric penetration assemblies in containment structiltes Nuclear Power Plants," to IOCFR Part 50, "Licensing for water-cooled nuclear power plants.

of Production and Utilization Facilities" requires, in part, that the reactor containment structure, including penetrations, be designed so that the contai

C. REGULATORY POSITION

ment structure can, without exceeding the design leakage rate, accommodate the calculated pressure, IEEE Std 317-1972, "IEEE Standard for I-lectriu"

temperature, and other environmental conditions Penetration Assemblies in Containment Structures t'm resulting from any loss-of-coolant accident. Appendix B Nuclear Power Generating Stations," provides an to Part 50, "Quality Assurance Criteria for Nuclear acceptable method of complying with Appendix B and Power Plants and Fuel Reprocessing Plants," establishes General Design Criterion 50 of Appendix A to 10 CFR

quality assurance requirements for the design, Part 50 with respect to mechanical, electrical and test construction, and operation of nuclear power plant requirements for the design, constnhction, and structures, systems, and components. This guide installation of electric penetration assemblies in describes an acceptable method of complying with containment structures for water-cooled nuclear power Appendix B and Criterion 56 of Appendix A with plants, subject to the following:

respect to the mechanical, electrical, and test requirements for the design, construction, and

1. Section 4 should be supplemented as follows: The installation of electric penetration assemblies in electric penetration assembly should be designed to containment structures for water-cooled nuclear power plants. The Advisory Committee on Reactor Safeguards withstand, withou! loss of mechanical integrity, the has been consulted concerning this guide and has maximum possible fault current vs. time conditiins (which could occur because of single random failures of concurred in the regulatory position.

circuit overload prote. :ion devices) within the two leads of any one single-phase ;rcuit or the three leads ot any

B. DISCUSSION

one three.phase circuit. Incorporating adequate sell- fusing characteristics within the penetration conductors IEEE Std 3 17 -1 9 7 2 ,' "IEEE Standard for Electric themselves constitutes an acceptable design approach.

Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations," was prepared by Where self-fusing characteristics are not incorporated, the Joint Committee on Nuclear Power Standards the circuit overload protection system should conformi to the criteria of IEEE Std 279-1971,' "Criteria for (currently designated the Nuclear Power Engineering Protection Systems for Nuclear Power Generating Committee) of the Institute of Electrical and Electronics Stations" (also designated ANSI N42.7-1972).

Engineers, Inc. (IEEE), and subsequently approved by

'Copies may be obtained from the Institute of Electrical 2. The maximum containment pressure to he specified and Electronics Engineers, 345 East 47th Street, New York, New in accordance with Section 4.3 should be construed as York 10017. being synonymous with maximum containment internal IJSAIC REGULATORY GUIDES Clol"e Of pcAIIshad guitars nmeybe obtainted by ,emteet indleeting the divil,,0"

desred 10 the (IS. Atomice Eneqy CowwnIuelort. Weshinaron, O.C:.70545.

Rtegltory rpuldsO we Iteuad to 611W~lbe end Make W014bile to the pujbdi Attenttn: Olteclor 04 Regulutory standards, Comnwtnts end 'vwrnt.O"' to'

,nothede eeorptubl to the ARC Repuiitoc eteft of Imoluemyenting .Oecdfk taws, of ttvpt Row,,uIn,thenequida we encouragd and should be sent to the Secret try the C0110ft,001a's tagujietlon. to delinseattechniques woodtby ft lefaitt In of the Comenlasion, U~.SAt=m~ E e,'p Cowerisl.on, Washirngion, OZC.2M645.

snluallre wepefle owobtems or postuleted eceldint,, of to proelde guldenixt to Attention: Chtlef, PubiticPoed'pSa eWlon". Regultory Guides we not euberltittee for regulations end cot tolleftes wft% thetmis tot reciuited. Meth"d end aolutions different fromt those sat out let The Sp18w sweheued It, the folIaongr ten broaid d~IvItont:

thesOdaw esll be aeet I"e If they twold a bash for If* flndlnge reqJw~te to anantnuenos o al permil t Mrtemoe te'swat by the Comwtlecl0. 1. poyean Rewant

6. ProdvMt

2. Rwmrdch end Test Rsectl 7. Tras'ucrtef'on

2. Fuok and Materilst Faclyiftl S. oeccutlorttHalt01h Puld~ihaed gudes seltibe reelsed porkiscldtly. tOon4etCoeidt 4. Ertvlrommentot ndS~lIng g. Antit,,nl R~vvww co11¶oitI and to reflect Mtee lntonntlaonorexperience. S. Meenlals end ImamtPratetikon tO. Ge"wal

pressure as defined in footnote I to Article NE3000 of 4. Section 8 shoula be tupplemented as follows: The Section III of the ASME Boiler and Pressure Vessel Code quality assurance requirements for the design, (Summer 1972 Addenda). 2 construction, installation, and testing of electric penetration assemblies shaU be in accordance with the

3. The specific applicability or acceptability of the 2 requirements set forth in ANSI N45.2.1971, "Quality codes, standards, and guides referenced in Section 3 will Assurance Program Requirements for Nuclear Power he covered separately in other regulatory guides, where Plants," and ANSI N45.2.4.1972!' 2 "ln.*hillation, appropriate. Inspection, and Testing Requirements fur

• Copies ma) be obtined from the American Society of Instrumentation and Electric Equipment During the Mechanical Engineers, United Enginering Center, 345 EWst 47th Construction of Nuclear Power Generating Stations."

Street, New York, New York 10017. (also designated IEEE Std 336-1971 ).

1.63.2