Regulatory Guide 1.63

(Task Ee 405.4), Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants

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Issue date:	02/28/1987
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RG-1.063, Rev 3
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Revision 3'

February 1987 U.S. NUCLEAR REGULATORY COMMISSION

)REGULATORY GUiDE

OFFICE OF NUCLEAR REGULATORY RESEARCH

REGULATORY GUIDE 1.63 (Task EE 4054)

ELECTRIC PENETRATION ASSEMBLIES IN CONTAINMENT STRUCTURES

FOR NUCLEAR POWER PLANTS

A. INTRODUCTION

General Design Criterion 50, "Containment Design Basis,"

of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing of Pro duction and Utilization Facilities," requires, in part, that the reactor containment structure, including penetrations, be designed so that the containment structure can, without exceeding the design leakage rate, accommodate the calcul ated pressure, temperature, and other environmental condi tions resulting from any loss-of-coolant accident. Sec tion 50.49,

"Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants,"

of 10 CFR Part 50 specifies the qualification requirements.

Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50

establishes quality assurance requirements for design, construction, and operation of nuclear power plant struc tures, systems, and components. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations for the design, construction, testing, qualification, installation, and external circuit protection of electric penetration assemblies in containment structures of nuclear power plants.

The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.

Any information collection activities mentioned in this regulatory guide are contained as requirements in 10 CFR

Part 50, which provides the regulatory basis for this guide.

The information collection requirements in 10 CFR Part 50

have been cleared under OMB Clearance No. 3150-0011.

The substantial number of changes in this revision has made it impractical to Indicate the changes with lines in the margin.

B. DISCUSSION

IEEE Std 317-1983, "IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations,""

was prepared by a working group of Subcommittee 1, General Plant Criteria, of the Nuclear Power Engineering Committee of the Institute of Electrical and Electronics Engineers (IEEE) and was subsequently approved by the IEEE Standards Board on September 23, 1982. This standard prescribes require ments for the design, construction, testing, qualification, and installation of electric penetration assemblies in contain ment structures for stationary nuclear power generating stations.

Section 6.2.8(5) of IEEE Std 317-1983 requires that the duration of maximum short circuit current flow in test specimens of electric penetration assemblies be no less than

0.033 second. This duration is representative of the operat ing time of molded-case circuit breakers. System design may include use of other circuit breakers, which will result in durations longer than 0.033 second. Consideration should be given to modifying the test program to represent the duration of maximum short circuit current expected based on system design.

rhe external circuit protection of electric penetration assemblies is beyond the scope of IEEE Std 317-1983. This subject is covered by IEEE Std 741-1986, "Criteria for the Protection of Class IE Power Systems and Equipment in Nuclear Power Generating Stations.!'*

IEEE Std 317-1983 references other standards that contain valuable information. Those referenced standards not endorsed by a regulatory guide or incorporated into the

0e Copies may be obtained from the Institute of Electrical and Electronics Engineers, 345 East 47th Street, New York, NY 10017.

USNRC REGULATORY GUIDES

The guides are Issued in the following ten broad divisions:

Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing

1. Power Reactors

6. Products specific parts of the Commission's regulations, to delineate tech-

2. Research and Test Reactors

7. Transportation niques used by the staff in evaluating specific problems or postu-

3. Fuels and Materials Facilities

8. Occupational Health lated accidents, or to provide guidance to applicant

s. Regulatory

4. Environmental and Siting

9. Antitrust and Financial Review Guides are not substitutes for regulations, and compliance with

5. Materials and Plant Protection 10. General them Is not required. Methods and solutions different from those set out in the guides will be acceptable If they provide a basis for the findings requisite to the issuance or continuance of a permit or Copies of issued guides may be purchased from the Government license by the Commission.

Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of This guide was issued after consideration of comments received from Documents, U.S. Government Printing Office, Post Office Box the public. Comments and suggestions for improvements in these

37082, Washington, DC 20013-7082, telephone (202)275-2060 or guides are encouraged at all times, and guides will be revised, as

(202)275-2171.

appropriate, to accommodate comments and to reflect new Informa tion or experience.

Issued guides may also be purchased from the National Technical Written comments may be submitted to the Rules and Procedures information Service on a standing order basis. Details on this Branch, DRR.

ADM,

U.S. Nuclear Regulatory Commission, service may be obtained by writing NTIS. 5285 Port Royal Road.

Washington, DC 20555.

Springfield, VA 22161.

regulations, if used, are to be used in a manner consistent with current regulations.

C. REGULATORY POSITION

Conformance with the requirements of IEEE Std 317-1983,

"IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations," provides a method acceptable to the NRC staff for satisfying the Commission's regulations with respect to the design, construction, testing, qualification, and installa tion of electric penetration assemblies in containment structures for nuclear power plants, subject to the following:

The external circuit protection of electric penetration assemblies should meet the provi sions of Section 5.4 of IEEE Std 741-1986,

"Criteria for the Protection of Class I E Power Systems and Equipment in Nuclear Power Generating Stations."

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants and licensees regarding the NRC staffs plans for using this regulatory guide.

Except in those cases in which the applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the methods described herein will be used in the evaluation of the design, construction, testing, qualification, installation, and external circuit protection of electric penetration assemblies for nuclear power plants as follows:

I. Plants for which the construction permit is issued after February 28, 1987,

2. Plants for which the operating license application is docketed after August 28, 1987,

3. Plants for which the applicant or licensee voluntarily commits to the provisions of this guide.

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VALUE/IMPACT STATEMENT

BACKGROUND

IEEE i Std 317-1976,

"IEEE Standard for Electric Penetration Assemblies In Containment Structures for Nuclear Power Generating Stations," was approved by IEEE in September 1975. In July 1978, the NRC staff issued Revision 2 to Regulatory Guide 1.63, which endorsed IEEE Std 317-1976, subject to seven exceptions. Since then the staff has worked with IEEE in developing IEEE Std 317-1983. As a result of these efforts, the exceptions to IEEE Std 317-1976 have been satisfactorily resolved.

Issuance of this Revision 3 is consistent with the NRC

policy of evaluating the latest versions of national nuclear standards in terms of their suitability for endorsement by regulatory guides.

SUBSTANTIVE CHANGES AND THEIR VALUE/IMPACT

Regulatory Position C.1 in Revision 2 was modified in this Revision 3 to include the appropriate requirements of IEEE Std 741-1986, which apply to external circuit protec tion of electric penetration assemblies.

Regulatory Positions C.2 to C.6 in Revision 2 were not included in this Revision 3 because they were incorporated in IEEE Std 317-1983 as follows:

Regulatory Position Number (Rev. 2 of this guide)

2 3

4

5

6 Section Number (IEEE Std 317.1983)

6.2.8(3Xa)

6.2.8(5)

6.2.3(2)

D.1.2.5(2)

2 Regulatory Position C.7 in Revision 2 was deleted because the applicability of referenced IEEE standards has been included under "Discussion" in this Revision 3.

VALUE

This guide endorses the latest version of a national standard. The guide ahsr should enhance the licensing process.

IMPACT

This regulatory guide does not impose any new require ments or costs on licensees or applicants. Thus, no impact will result from issuance of this guide.

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