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


==A. INTRODUCTION==
==A. INTRODUCTION==
General Design Criterion
the IEEE Standards Committee on September 20. 107..
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.
                                                                                      It is an IEEE standard which prescribes design.


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.
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.


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


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.
====n.     ====


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.
==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.


The substantial number of changes in this revision has made it impractical to Indicate the changes with lines in the margin.
circuit overload prote. :ion devices) within the two leads of any one single-phase ;rcuit or the three leads ot any


==B. DISCUSSION==
==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
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.
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.
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.


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.
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.


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.!'*
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:
IEEE Std 317-1983 references other standards that contain valuable information.
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                         


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
===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


===7. USNRC REGULATORY ===
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
GUIDES The guides are Issued in the following ten broad divisions:
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
Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing
    *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."
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
Street, New York, New York 10017.                                   (also designated IEEE Std 336-1971 ).
8. Occupational Health lated accidents, or to provide guidance to applicants.
                                                              1.63.2}}
 
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}}


{{RG-Nav}}
{{RG-Nav}}

Latest revision as of 01:16, 20 March 2020

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)
To:
References
RG-1.063
Download: ML13350A357 (2)
v • d • e


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

n.

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


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