Regulatory Guide 1.63

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

ML12298A128
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Issue date:	07/31/1978
From:	Office of Nuclear Regulatory Research
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RG-1.063, Rev 2
Download: ML12298A128 (4)

'0 UNITED STATES

o NUCLEAR REGULATORY COMMISSION

fWASHINGTON, D. C. 20555 Z

July 18, 1978 REGULATORY GUIDE DISTRIBUTION LIST (DIVISION 1)

Regulatory Guide 1.63, Revision 2, "Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants,"

transmitted herewith, describes a method acceptable to the NRC staff for complying with the Commission's regulations regarding mechanical, electrical, and test requirements for the design, qualification, con- struction, installation, and testing of electric penetration assemblies.

With reference to the provisions of Section D, "Implementation," of the guide, any purchase orders for electric penetration assemblies executed prior to the effective date of the guide that specify the provisions of either Revision 0 or Revision 1 of Regulatory Guide 1.63 need not be changed.

Robert B. Minogue, rirector Office of Standards Development

Revision 2 U.S. NUCLEAR REGULATORY COMMISSION July 1978 eREGULATORY GUIDE

'01 OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.63 ELECTRIC PENETRATION ASSEMBLIES IN CONTAINMENT STRUCTURES

FOR LIGHT-WATER-COOLED NUCLEAR POWER PLANTS

A. INTRODUCTION

by a working group of Subcommittee 1 (General Plant Criteria) of the Nuclear Power Engineering General Design Criterion 50, "Containment De- Committee of the Institute of Electrical and Elec- sign Basis," of Appendix A, "General Design tronics Engineers (IEEE) and was subsequently ap- Criteria for Nuclear Power Plants," to 10 CFR Part proved by the IEEE Standards Board on September 4,

50, "Domestic Licensing of Production and Utiliza- 1975. This IEEE standard prescribes design, qualifi- tion Facilities," requires, in part, that the reactor cation, construction, installation, and testing re- containment structure, including penetrations, be de- quirements for electric penetration assemblies in signed so that the containment structure can, without containment structures for light-water-cooled nuclear exceeding the design leakage rate, accommodate the power plants.

calculated pressure, temperature, and other environ- mental conditions resulting from any loss-of-coolant

C. REGULATORY POSITION

accident. Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Conformance with the requirements of IEEE Std Plants," to 10 CFR Part 50 establishes quality 317-1976, "IEEE Standard for Electric Penetration assurance requirements for the design, construction, Assemblies in Containment Structures for Nuclear and operation of nuclear power plant structures, Power Generating Stations," provides an acceptable systems, and components. This guide describes a method of complying with General Design Criterion method acceptable to the NRC staff for complying 50 of Appendix A and with Appendix B to 10 CFR

with General Design Criterion 50 of Appendix A and Part 50 with respect to mechanical, electrical, and with Appendix B with respect to the mechanical, test requirements for the design, qualification, con- electrical, and test requirements for the design, struction, installation, and testing of electric penetra- qualification, construction, installation, and testing tion assemblies in containment structures for light- of electric penetration assemblies in containment water-cooled nuclear power plants, subject to the structures of light-water-cooled nuclear power plants. following:

The Advisory Committee on Reactor Safeguards was consulted regarding this guide and concurred in the 1. Section 4.2.4 should be supplemented by the following: The electric penetration assembly should regulatory positions.

be designed to withstand, without loss of mechanical integrity, the maximum short-circuit. current v

B. DISCUSSION

conditions that could occur given single random IEEE Std 317-1976,1 "IEEE Standard for Electric failures of circuit overload protection devices. The Penetration Assemblies in Containment Structures for circuit overload protection system should conform to Nuclear Power Generating Stations," was prepared the criteria of IEEE Std 279-1971,' "Criteria for Protection Systems for Nuclear Power Generating

• Lines indicate substantive changes from previous issue. Stations," (also designated ANSI N42.7-1972).

Copies may be obtained from the Institute of Electrical and

2. The maximum short-circuit current assessed at Electronics Engineers, United Engineering Center, 345 East the penetration assembly should be consistent with

47th Street, New York, New York 10017. the criteria used in establishing the interrupting USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission, US. Nuclear Regu- 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 are 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 and Test Reactors 7. Transportation able if they provide a basis for the findings requisite to the issuance or continuance 3 Fuels and Materials Facilities

8. Occupational Health

4. Environmental and Siting 9. Antitrust Review of a permit or license by the Commison. 5. Materials and Plant Protection 10. General Comments and suggestions for improvements in these guides are encouraged at all Requests for single copaies of issued guides (whkih may be reproduced) or for place times, and guides will be revised, as appropriate, to accommodate comments and ment on an automatic distribution list for single copies of future guides in specific to reflect new information or experience. This guide was revised as a result of divisions should be made in writing to the US. Nuclear Regulatory Commission, substantive comments received from the public and additional staff review. Washington, D.C. 20555, Attention: Director, Division of Document Control.

capability of the protective device associated with the The test voltages for the above shall be based on penetration assembly conductors. Accordingly, the the voltage rating of the conductor in accordance provisions of Section 4.2.4 pertaining to the rated with the following table:

short-circuit current for alternating-current circuits should be modified as follows:

Rated Voltage (V) x/r Ratio 2 Conductor Rated Voltage (V)

300 and 600

Impulse 4 Voltage (V) 4

300 1000

600 >8 5000 60,000

1000 8000 95,000

5000 15,000 95,000

8000 >15 5. The 500-hour aging time at minimum aging

15000 temperature of Section 6.3.3 is a printing error 5 and

3. The provisions of Section 4.2.4 pertaining to should be changed to 5000 hours0.0579 days <br />1.389 hours <br />0.00827 weeks <br />0.0019 months <br />.

the duration of the maximum short-circuit current are 6. The definition of "Double Aperture Seal" in representative of circuits protected by molded-case Section 2 is a printing error I and should be changed circuit breakers but are not representative of circuits as follows: "Two single aperture seals in series."

using other air circuit breakers. The provisions per- taining to the duration of the maximum short-circuit 7. The specific applicability or acceptability of the current should be modified as follows: codes, standards, and guides referenced in Section 3 will be covered separately in other regulatory guides, Service Classification Duration(s) where appropriate.

Low-voltage power and 0.033 (for molded-case control circuit breakers)

0.066 (for other air

D. IMPLEMENTATION

circuit breakers)

The purpose of this section is'to provide informa-

4.3 Section 6.4.4, "Dielectric-Strength Test," tion to applicants regarding the NRC staff's plans for should be supplemented, for qualification testing using this regulatory guide. Except in those cases in only, by the following: which the applicant proposes an acceptable alterna- tive method for complying with specified portions of

(3) Each medium-voltage power conductor shall the Commission's regulations, the*method described be given an impulse withstand test by applying a herein will be used in the evaluation of submittals for

1.2 x 50 tts impulse voltage test series consisting of construction permit applications docketed after three positive and three negative impulse voltages. If August 31, 1978.

flashover occurs on only one test during any group of three consecutive tests, three more shall be made. If If an applicant wishes to use this regulatory guide no flashover occurs in the second group of tests, the in developing submittals for applications docketed on flashover in the first group shall be considered as a or before August 31, 1978, the pertinent portions of random flashover and the equipment shall be consid- the application will be evaluated on the basis of this ered as having passed the test. guide.

2 Values based on data of ANSI C37.010-1972, "Application Guide for AC High-Voltage Circuit Breakers Rated on a 4 Values based on data of ANSI C37.20-1969, "Switchgear Symmetrical Current Basis." Assemblies Including Metal-Enclosed Bus" (1974 Consolidated Edition dated September 3, 1974).

I This additional staff position, not contained in Revision 1, was included in a letter to the Division 1 distribution, dated February 5 This printing error was corrected in printings of the standard

1978. after August 25, 1976.

• U. S. GOVERNMENT PRINTING OFFICE: 1978-720-387/234

1.63-2

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