Regulatory Guide 1.63
| ML13350A357 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1973 |
| From: | US Atomic Energy Commission (AEC) |
| To: | |
| References | |
| RG-1.063 | |
| Download: ML13350A357 (2) | |
1973Ni U.S. ATOMIC ENERGY COMMISSION
REGULATORY
GUIDIRECTORATE
OF REGULATORY
STANDARDS)
REGULATORY
GUIDE 1.63ELECTRIC
PENETRATION
ASSEMBLIES
IN CONTAINMENT
STRUCTURES
FOR WATER-COOLED
NUCLEAR POWER PLANTSDE
A. INTRODUCTION
General Design Criterion 50, "Containment DesignBasis," of Appendix A, "General Design Criteria forNuclear Power Plants,"
to IOCFR Part 50, "Licensing of Production and Utilization Facilities"
requires, inpart, that the reactor containment structure, including penetrations, be designed so that the contain.ment structure can, without exceeding the designleakage rate, accommodate the calculated pressure, temperature, and other environmental conditions resulting from any loss-of-coolant accident.
Appendix Bto Part 50, "Quality Assurance Criteria for NuclearPower Plants and Fuel Reprocessing Plants,"
establishes quality assurance requirements for the design,construction, and operation of nuclear power plantstructures, systems, and components.
This guidedescribes an acceptable method of complying withAppendix B and Criterion
56 of Appendix A withrespect to the mechanical, electrical, and testrequirements for the design, construction, andinstallation of electric penetration assemblies incontainment structures for water-cooled nuclear powerplants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and hasconcurred in the regulatory position.
B. DISCUSSION
IEEE Std 317-1972,' "IEEE Standard for ElectricPenetration Assemblies in Containment Structures forNuclear Power Generating Stations,"
was prepared bythe Joint Committee on Nuclear Power Standards (currently designated the Nuclear Power Engineering Committee)
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, NewYork 10017.the IEEE Standards Committee on September
20. 107..It is an IEEE standard which prescribes design.construction, installation, and testing requirements forelectric penetration assemblies in containment structiltes for water-cooled nuclear power plants.C. REGULATORY
POSITIONIEEE Std 317-1972,
"IEEE Standard for I-lectriu"
Penetration Assemblies in Containment Structures t'mNuclear Power Generating Stations,"
provides anacceptable method of complying with Appendix B andGeneral Design Criterion
50 of Appendix A to 10 CFRPart 50 with respect to mechanical, electrical and testrequirements for the design, constnhction, andinstallation of electric penetration assemblies incontainment structures for water-cooled nuclear powerplants, subject to the following:
1. Section 4 should be supplemented as follows:
Theelectric penetration assembly should be designed towithstand, withou! loss of mechanical integrity, themaximum possible fault current vs. time conditiins (which could occur because of single random failures ofcircuit overload prote. :ion devices)
within the two leadsof any one single-phase
- rcuit or the three leads ot anyone 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 conformito the criteria of IEEE Std 279-1971,'
"Criteria forProtection Systems for Nuclear Power Generating Stations"
(also designated ANSI N42.7-1972).
2. The maximum containment pressure to he specified in accordance with Section 4.3 should be construed asbeing synonymous with maximum containment internalIJSAIC REGULATORY
GUIDES Clol"e Of pcAIIshad guitars nmey be 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,,u In, thene quida we encouragd and should be sent to the Secret trythe 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:
Chtlef, PubiticPoed'pSa eWlon". Regultory Guides we not euberltittee for regulations end cot tolleftes wft% thetm is tot reciuited.
Meth"d end aolutions different fromt those sat out let The Sp18w swe heued It, the folIaongr ten broaid d~IvItont:
thes Odaw esll be aeet I"e If they twold a bash for If* flndlnge reqJw~te tote'swat an antnuenos o al permil t Mrtemoe by the Comwtlecl0.
1. poyean Rewant 6. ProdvMt2. Rwmrdch end Test Rsectl 7. Tras'ucrtef'on
2. F uok and Materilst Faclyiftl S. oeccutlorttHalt01h Puld~ihaed gudes selti be reelsed porkiscldtly.
tOon4etCoeidt
4. Ertvlrommentot ndS~lIng g. Antit,,nl R~vvwwco11¶oitI
and to reflect Mtee lntonntlaon orexperience.
S. Meenlals end Imamt Pratetikon tO. Ge"wal pressure as defined in footnote I to Article NE3000 ofSection III of the ASME Boiler and Pressure Vessel Code(Summer 1972 Addenda).
23. The specific applicability or acceptability of thecodes, standards, and guides referenced in Section 3 willhe covered separately in other regulatory guides, whereappropriate.ma) be obtined from the American Society ofMechanical Engineers, United Enginering Center, 345 EWst 47thStreet, New York, New York 10017.4. Section 8 shoula be tupplemented as follows:
Thequality assurance requirements for the design,construction, installation, and testing of electricpenetration assemblies shaU be in accordance with therequirements set forth in ANSI N45.2.1971,
2 "QualityAssurance Program Requirements for Nuclear PowerPlants,"
and ANSI N45.2.4.1972!'
2 Inspection, and Testing Requirements furInstrumentation and Electric Equipment During theConstruction of Nuclear Power Generating Stations."
(also designated IEEE Std 336-1971
).1.63.2