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{{Adams
{{Adams
| number = ML13350A357
| number = ML003740219
| issue date = 10/31/1973
| issue date = 02/28/1987
| title = Electric Penetration Assemblies in Containment Structures for Water-Cooled Nuclear Power Plants
| title = (Task Ee 405.4), Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants
| author name =  
| author name =  
| author affiliation = US Atomic Energy Commission (AEC)
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.063
| document report number = RG-1.063, Rev 3
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 2
| page count = 4
}}
}}
{{#Wiki_filter:1973 Ni U.S. ATOMIC ENERGY COMMISSION
{{#Wiki_filter:Revision 3' February 1987 U.S. NUCLEAR REGULATORY
REGULATORY  
COMMISSION)REGULATORY  
GUI DIRECTORATE
GUiDE OFFICE OF NUCLEAR REGULATORY  
OF REGULATORY  
RESEARCH REGULATORY  
STANDARDS)
GUIDE 1.63 (Task EE 4054) ELECTRIC PENETRATION  
REGULATORY  
GUIDE 1.63 ELECTRIC PENETRATION  
ASSEMBLIES  
ASSEMBLIES  
IN CONTAINMENT  
IN CONTAINMENT  
STRUCTURES
STRUCTURES  
FOR WATER-COOLED
FOR NUCLEAR POWER PLANTS  
NUCLEAR POWER PLANTS DE


==A. INTRODUCTION==
==A. INTRODUCTION==
General Design Criterion  
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.
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.


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.
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.


This guide describes an acceptable method of complying with Appendix B and Criterion
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.
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.
 
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==
==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)
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
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
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
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  
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.
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:
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.
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).
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.
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
 
GUIDES Clol"e Of pcAIIshad guitars nmey be obtainted by ,emteet indleeting the divil,,0" desred 10 the (IS. Atomice Eneqy CowwnIuelort.
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 1001
 
===7. 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 applicants.
 
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.K 1.63-2 VALUE/IMPACT
STATEMEN
 
==T. 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.


Weshinaron, O.C:. 70545.Rtegltory rpuldsO we Iteuad to 611W~lbe end Make W014bile to the pujbdi Attenttn:
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 guide
Olteclor 04 Regulutory standards, Comnwtnts end 'vwrnt.O"'
to',nothede eeorptubl to the ARC Repuiitoc eteft of Imoluemyenting .Oecdfk taws, of ttvpt Row,,u In, thene quida we encouragd and should be sent to the Secret try the C0110ft,001a's tagujietlon.


to delinseat techniques woodt by ft lefaitt In of the Comenlasion, U~.S At=m~ E e,'p Cowerisl.on, Washirngion, OZC. 2M645.snluallre wepefle owobtems or postuleted eceldint,, of to proelde guldenixt to Attention:
====s. SUBSTANTIVE ====
Chtlef, PubiticPoed'pSa eWlon". Regultory Guides we not euberltittee for regulations end cot tolleftes wft% thetm is tot reciuited.
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.


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


1. poyean Rewant 6. ProdvMt 2. Rwmrdch end Test Rsectl 7. Tras'ucrtef'on
The guide ahsr should enhance the licensing process.
2. F uok and Materilst Faclyiftl S. oeccutlorttHalt01h Puld~ihaed gudes selti be reelsed porkiscldtly.


tOon4etCoeidt
IMPACT This regulatory guide does not impose any new require ments or costs on licensees or applicants.
4. Ertvlrommentot ndS~lIng g. Antit,,nl R~vvww co11¶oitI
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!'
Thus, no impact will result from issuance of this guide.1.63-3 UNITED STATES NUCLEAR REGULATORY
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}}
COMMISSION
WASHINGTON, D.C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 j IltgT CL.A l" POSTAGIS Pli PAW UINRC WA K.D.C.  FIRMIT No. 0-7 I'l I%K}}


{{RG-Nav}}
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Revision as of 17:49, 31 August 2018

(Task Ee 405.4), Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants
ML003740219
Person / Time
Issue date: 02/28/1987
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.063, Rev 3
Download: ML003740219 (4)
v • d • e


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 1001

7. 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 applicants.

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.K 1.63-2 VALUE/IMPACT

STATEMEN

T. 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 guide

s. 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.1.63-3 UNITED STATES NUCLEAR REGULATORY

COMMISSION

WASHINGTON, D.C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 j IltgT CL.A l" POSTAGIS Pli PAW UINRC WA K.D.C. FIRMIT No. 0-7 I'l I%K


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