Regulatory Guide 1.63: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
 
Line 1: Line 1:
{{Adams
{{Adams
| number = ML12298A128
| number = ML13350A357
| issue date = 07/31/1978
| issue date = 10/31/1973
| title = Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled 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 2
| document report number = RG-1.063
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 4
| page count = 2
}}
}}
{{#Wiki_filter:'0                          UNITED STATES
{{#Wiki_filter:Oc**btr 1973 Ni          U.S. ATOMIC ENERGY COMMISSION
o                NUCLEAR  REGULATORY COMMISSION
                                REGULATORY
    fWASHINGTON,                    D.  C. 20555 Z
                                DIRECTORATE OF REGULATORY STANDARDS)
                          July 18, 1978 REGULATORY GUIDE DISTRIBUTION LIST (DIVISION      1)
                                                                                                                              GUI DE
Regulatory Guide 1.63, Revision 2, "Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants,"
                                                              REGULATORY GUIDE 1.63 ELECTRIC PENETRATION ASSEMBLIES IN CONTAINMENT STRUCTURES
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.
                                        FOR WATER-COOLED NUCLEAR POWER PLANTS


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


Robert B. Minogue, rirector Office of Standards Development
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.


Revision 2 U.S. NUCLEAR REGULATORY COMMISSION                                                                                    July 1978 eREGULATORY GUIDE
of Production and Utilization Facilities" requires, in part, that the reactor containment structure, including penetrations, be designed so that the contai
                        '01          OFFICE OF STANDARDS DEVELOPMENT
                                                                      REGULATORY GUIDE 1.63 ELECTRIC PENETRATION ASSEMBLIES IN CONTAINMENT STRUCTURES
                                        FOR LIGHT-WATER-COOLED NUCLEAR POWER PLANTS


==A. INTRODUCTION==
====n.     ====
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==
==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
ment structure can, without exceeding the design leakage rate, accommodate the calculated pressure,                                          IEEE Std 317-1972, "IEEE Standard for I-lectriu"
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:
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
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.
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.


be designed to withstand, without loss of mechanical integrity, the maximum short-circuit. current v
circuit overload prote. :ion devices) within the two leads of any one single-phase ;rcuit or the three leads ot any
 
====s. time ====


==B. DISCUSSION==
==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
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.
 
* 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 hours.
 
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==
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).
circuit breakers)
  Engineers, Inc. (IEEE), and subsequently approved by
                                                                              The purpose of this section is'to provide informa-
       '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"
    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
                                                                                    desred 10 the (IS. Atomice Eneqy CowwnIuelort. Weshinaron, O.C:.70545.
       (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.
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.


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).
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:
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
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                         
1978.                                                                    after August 25, 1976.


* U. S. GOVERNMENT PRINTING OFFICE: 1978-720-387/234
===6. ProdvMt===
                                                                    1.63-2
                                                                                    2. Rwmrdch end Test Rsectl                7. Tras'ucrtef'on
                                                                                                                                          4
                                                                                    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


UNITED STATES
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
NUCLEAR REGULATORY COMMISSION
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
                                                                            A
    *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."
    WASHINGTON, D. C. 20555 POSTAGE AND FEES PAID
Street, New York, New York 10017.                                  (also designated IEEE Std 336-1971 ).
                                                      UNTIED STATES NUCLEAR
                                                              1.63.2}}
        OFFICIAL BUSINESS                            REGULATORY  COMMISSION
  PENALTY FOR PRIVATE USE, $300
                            119406002001 US NRC REGION I
                                            1 SN
                            GIFFICE OF INSPECTION & ENFORCE
                            R J EORES
                                                                            4
                            631 PARK AVENUE
                            REGION I
                            KING OF PRUSSIA      PA    19406
                                                                            4}}


{{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


Retrieved from "https://kanterella.com/w/index.php?title=Regulatory_Guide_1.63&oldid=2635182"