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 = ML13350A357
| number = ML12298A128
| issue date = 10/31/1973
| issue date = 07/31/1978
| title = Electric Penetration Assemblies in Containment Structures for Water-Cooled Nuclear Power Plants
| title = Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled 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 2
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 2
| page count = 4
}}
}}
{{#Wiki_filter:Oc**btr 1973 Ni U.S. ATOMIC ENERGY COMMISSION
{{#Wiki_filter:'0
REGULATORY GUI
UNITED STATES
DIRECTORATE OF REGULATORY STANDARDS)
o NUCLEAR
REGULATORY COMMISSION
fWASHINGTON,
D.
 
C.
 
20555 Z
July 18, 1978 REGULATORY GUIDE DISTRIBUTION LIST (DIVISION 1)
Regulatory Guide 1.63, Revision 2, "Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants,"
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.
 
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.
 
Robert B. Minogue, rirector Office of Standards Development
 
Revision 2 July 1978 U.S. NUCLEAR REGULATORY COMMISSION
eREGULATORY GUIDE
'01 OFFICE OF STANDARDS DEVELOPMENT
REGULATORY GUIDE 1.63 ELECTRIC PENETRATION ASSEMBLIES IN CONTAINMENT STRUCTURES
REGULATORY GUIDE 1.63 ELECTRIC PENETRATION ASSEMBLIES IN CONTAINMENT STRUCTURES
FOR WATER-COOLED NUCLEAR POWER PLANTS
FOR LIGHT-WATER-COOLED NUCLEAR POWER PLANTS
DE


==A. INTRODUCTION==
==A. INTRODUCTION==
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.
General Design Criterion 50, "Containment De- sign Basis," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part
50, "Domestic Licensing of Production and Utiliza- tion Facilities," requires, in part, that the reactor containment structure, including penetrations, be de- signed so that the containment structure can, without exceeding the design leakage rate, accommodate the calculated pressure, temperature, and other environ- mental conditions resulting from any loss-of-coolant accident. Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,"
to
10 CFR Part 50 establishes quality assurance requirements for the design, construction, and operation of nuclear power plant structures, systems, and components. This guide describes a method acceptable to the NRC staff for complying with General Design Criterion 50 of Appendix A and with Appendix B with respect to the mechanical, electrical, and test requirements for the design, qualification, construction, installation, and testing of electric penetration assemblies in containment structures of light-water-cooled nuclear power plants.


ment structure can, without exceeding the design leakage rate, accommodate the calculated pressure, temperature, and other environmental conditions resulting from any loss-of-coolant acciden
The Advisory Committee on Reactor Safeguards was consulted regarding this guide and concurred in the regulatory positions.


====t. Appendix B====
==B. DISCUSSION==
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.
IEEE Std 317-1976,1 "IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations," was prepared
* Lines indicate substantive changes from previous issue.


This guide describes an acceptable method of complying with Appendix B and Criterion 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.
Copies may be obtained from the Institute of Electrical and Electronics Engineers, United Engineering Center, 345 East
47th Street, New York, New York 10017.


==B. DISCUSSION==
by a working group of Subcommittee 1 (General Plant Criteria) of the Nuclear Power Engineering Committee of the Institute of Electrical and Elec- tronics Engineers (IEEE) and was subsequently ap- proved by the IEEE Standards Board on September 4,
IEEE Std 3 17-1 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) of the Institute of Electrical and Electronics Engineers, Inc. (IEEE), and subsequently approved by
1975. This IEEE standard prescribes design, qualifi- cation, construction, installation, and testing re- quirements for electric penetration assemblies in containment structures for light-water-cooled nuclear power plants.
'Copies may be obtained from the Institute of Electrical and Electronics Engineers, 345 East 47th Street, New York, New York 10017.
 
==C. REGULATORY POSITION==
Conformance with the requirements of IEEE Std
317-1976, "IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations," provides an acceptable method of complying with General Design Criterion
50 of Appendix A and with Appendix B to 10 CFR
Part 50 with respect to mechanical, electrical, and test requirements for the design, qualification, con- struction, installation, and testing of electric penetra- tion assemblies in containment structures for light- water-cooled nuclear power plants, subject to the following:
1. Section 4.2.4 should be supplemented by the following: The electric penetration assembly should be designed to withstand, without loss of mechanical integrity, the maximum short-circuit. current vs. time conditions that could occur given single random failures of circuit overload protection devices. The circuit overload protection system should conform to the criteria of IEEE Std 279-1971,'
"Criteria for Protection Systems for Nuclear Power Generating Stations," (also designated ANSI N42.7-1972).
2. The maximum short-circuit current assessed at the penetration assembly should be consistent with 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,  


the IEEE Standards Committee on September 20. 107..
===1. Power Reactors ===
It is an IEEE
6. Products Methods and solutions different from those set out in the guides will be accept-
standard which prescribes design.
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


construction, installation, and testing requirements for electric penetration assemblies in containment structiltes for water-cooled nuclear power plants.
===8. Occupational Health===
4. Environmental and Siting
9. Antitrust Review of a permit or license by the Commison.


==C. REGULATORY POSITION==
5. Materials and Plant Protection
IEEE Std 317-1972, "IEEE Standard for I-lectriu"
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.
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:
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,'
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.
"Criteria for Protection 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 as being synonymous with maximum containment internal IJSAIC REGULATORY GUIDES
Washington, D.C.
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'
20555, Attention:  
,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.
Director, Division of Document Control.


to delinseat techniques woodt by ft lefaitt In of the Comenlasion, U~.S
capability of the protective device associated with the penetration assembly conductors. Accordingly, the provisions of Section 4.2.4 pertaining to the rated short-circuit current for alternating-current circuits should be modified as follows:
At=m~ E e,'p Cowerisl.on, Washirngion, OZC. 2M645.
The test voltages for the above shall be based on the voltage rating of the conductor in accordance with the following table:
Rated Voltage (V)
300
600
1000
5000
8000
15000
x/r Ratio 2
>8
>15 Conductor Rated Voltage (V)
300 and 600
1000
5000
8000
15,000
Impulse 4 Voltage (V)
60,000
95,000
95,000
4
3. The provisions of Section 4.2.4 pertaining to the duration of the maximum short-circuit current are representative of circuits protected by molded-case circuit breakers but are not representative of circuits using other air circuit breakers. The provisions per- taining to the duration of the maximum short-circuit current should be modified as follows:
Service Classification Low-voltage power and control Duration(s)
0.033 (for molded-case circuit breakers)
0.066 (for other air circuit breakers)
4.3 Section 6.4.4, "Dielectric-Strength Test,"
should be supplemented, for qualification testing only, by the following:
(3) Each medium-voltage power conductor shall be given an impulse withstand test by applying a
1.2 x 50 tts impulse voltage test series consisting of three positive and three negative impulse voltages. If flashover occurs on only one test during any group of three consecutive tests, three more shall be made. If no flashover occurs in the second group of tests, the flashover in the first group shall be considered as a random flashover and the equipment shall be consid- ered as having passed the test.


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:
2 Values based on data of ANSI C37.010-1972, "Application Guide for AC High-Voltage Circuit Breakers Rated on a Symmetrical Current Basis."
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.
I This additional staff position, not contained in Revision 1, was included in a letter to the Division 1 distribution, dated February
1978.


===1. poyean Rewant ===
5. The 500-hour aging time at minimum aging temperature of Section 6.3.3 is a printing error 5 and should be changed to 5000 hours.


===6. ProdvMt===
6. The definition of "Double Aperture Seal" in Section 2 is a printing error I and should be changed as follows: "Two single aperture seals in series."
2. Rwmrdch end Test Rsectl
7. The specific applicability or acceptability of the codes, standards, and guides referenced in Section 3 will be covered separately in other regulatory guides, where appropriate.
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~vvww co11¶oitI and to reflect Mtee lntonntlaon orexperience.


S. Meenlals end Imamt Pratetikon tO. Ge"wal
==D. IMPLEMENTATION==
The purpose of this section is'to provide informa- tion to applicants regarding the NRC staff's plans for using this regulatory guide. Except in those cases in which the applicant proposes an acceptable alterna- tive method for complying with specified portions of the Commission's regulations, the* method described herein will be used in the evaluation of submittals for construction permit applications docketed after August 31, 1978.


pressure as defined in footnote I to Article NE3000 of Section III of the ASME Boiler and Pressure Vessel Code (Summer 1972 Addenda). 2
If an applicant wishes to use this regulatory guide in developing submittals for applications docketed on or before August 31, 1978, the pertinent portions of the application will be evaluated on the basis of this guide.
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.
4 Values based on data of ANSI C37.20-1969, "Switchgear Assemblies Including Metal-Enclosed Bus" (1974 Consolidated Edition dated September 3, 1974).
5 This printing error was corrected in printings of the standard after August 25, 1976.


*Copies ma)
* U. S. GOVERNMENT PRINTING OFFICE:
be obtined from the American Society of Mechanical Engineers, United Enginering Center, 345 EWst 47th Street, New York, New York 10017.
1978-720-387/234
4
1.63-2


4.
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C.


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,"
20555 OFFICIAL BUSINESS
and ANSI
PENALTY FOR PRIVATE USE, $300
N45.2.4.1972!' 2 "ln.*hillation, Inspection, and Testing Requirements fur Instrumentation and Electric Equipment During the Construction of Nuclear Power Generating Stations."
POSTAGE AND FEES PAID
(also designated IEEE Std 336-1971 ).
UNTIED STATES
1.63.2}}
NUCLEAR
REGULATORY
COMMISSION
A
119406002001
1 SN
US NRC REGION I
GIFFICE OF INSPECTION & ENFORCE
R J
EORES
631 PARK
AVENUE
REGION I
KING
OF PRUSSIA
PA
19406
4
4}}


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

Revision as of 21:38, 11 January 2025

Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants
ML12298A128
Person / Time
Issue date: 07/31/1978
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.063, Rev 2
Download: ML12298A128 (4)
v • d • e


'0

UNITED STATES

o NUCLEAR

REGULATORY COMMISSION

fWASHINGTON,

D.

C.

20555 Z

July 18, 1978 REGULATORY GUIDE DISTRIBUTION LIST (DIVISION 1)

Regulatory Guide 1.63, Revision 2, "Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants,"

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.

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.

Robert B. Minogue, rirector Office of Standards Development

Revision 2 July 1978 U.S. NUCLEAR REGULATORY COMMISSION

eREGULATORY GUIDE

'01 OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.63 ELECTRIC PENETRATION ASSEMBLIES IN CONTAINMENT STRUCTURES

FOR LIGHT-WATER-COOLED NUCLEAR POWER PLANTS

A. INTRODUCTION

General Design Criterion 50, "Containment De- sign Basis," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing of Production and Utiliza- tion Facilities," requires, in part, that the reactor containment structure, including penetrations, be de- signed so that the containment structure can, without exceeding the design leakage rate, accommodate the calculated pressure, temperature, and other environ- mental conditions resulting from any loss-of-coolant accident. Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,"

to

10 CFR Part 50 establishes quality assurance requirements for the design, construction, and operation of nuclear power plant structures, systems, and components. This guide describes a method acceptable to the NRC staff for complying with General Design Criterion 50 of Appendix A and with Appendix B with respect to the mechanical, electrical, and test requirements for the design, qualification, construction, installation, and testing of electric penetration assemblies in containment structures of light-water-cooled nuclear power plants.

The Advisory Committee on Reactor Safeguards was consulted regarding this guide and concurred in the regulatory positions.

B. DISCUSSION

IEEE Std 317-1976,1 "IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations," was prepared

  • Lines indicate substantive changes from previous issue.

Copies may be obtained from the Institute of Electrical and Electronics Engineers, United Engineering Center, 345 East

47th Street, New York, New York 10017.

by a working group of Subcommittee 1 (General Plant Criteria) of the Nuclear Power Engineering Committee of the Institute of Electrical and Elec- tronics Engineers (IEEE) and was subsequently ap- proved by the IEEE Standards Board on September 4,

1975. This IEEE standard prescribes design, qualifi- cation, construction, installation, and testing re- quirements for electric penetration assemblies in containment structures for light-water-cooled nuclear power plants.

C. REGULATORY POSITION

Conformance with the requirements of IEEE Std 317-1976, "IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations," provides an acceptable method of complying with General Design Criterion 50 of Appendix A and with Appendix B to 10 CFR Part 50 with respect to mechanical, electrical, and test requirements for the design, qualification, con- struction, installation, and testing of electric penetra- tion assemblies in containment structures for light- water-cooled nuclear power plants, subject to the following:

1. Section 4.2.4 should be supplemented by the following: The electric penetration assembly should be designed to withstand, without loss of mechanical integrity, the maximum short-circuit. current vs. time conditions that could occur given single random failures of circuit overload protection devices. The circuit overload protection system should conform to the criteria of IEEE Std 279-1971,'

"Criteria for Protection Systems for Nuclear Power Generating Stations," (also designated ANSI N42.7-1972).

2. The maximum short-circuit current assessed at the penetration assembly should be consistent with 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 penetration assembly conductors. Accordingly, the provisions of Section 4.2.4 pertaining to the rated short-circuit current for alternating-current circuits should be modified as follows:

The test voltages for the above shall be based on the voltage rating of the conductor in accordance with the following table:

Rated Voltage (V)

300

600

1000

5000

8000

15000

x/r Ratio 2

>8

>15 Conductor Rated Voltage (V)

300 and 600

1000

5000

8000

15,000

Impulse 4 Voltage (V)

60,000

95,000

95,000

4

3. The provisions of Section 4.2.4 pertaining to the duration of the maximum short-circuit current are representative of circuits protected by molded-case circuit breakers but are not representative of circuits using other air circuit breakers. The provisions per- taining to the duration of the maximum short-circuit current should be modified as follows:

Service Classification Low-voltage power and control Duration(s)

0.033 (for molded-case circuit breakers)

0.066 (for other air circuit breakers)

4.3 Section 6.4.4, "Dielectric-Strength Test,"

should be supplemented, for qualification testing only, by the following:

(3) Each medium-voltage power conductor shall be given an impulse withstand test by applying a

1.2 x 50 tts impulse voltage test series consisting of three positive and three negative impulse voltages. If flashover occurs on only one test during any group of three consecutive tests, three more shall be made. If no flashover occurs in the second group of tests, the flashover in the first group shall be considered as a random flashover and the equipment shall be consid- ered as having passed the test.

2 Values based on data of ANSI C37.010-1972, "Application Guide for AC High-Voltage Circuit Breakers Rated on a Symmetrical Current Basis."

I This additional staff position, not contained in Revision 1, was included in a letter to the Division 1 distribution, dated February

1978.

5. The 500-hour aging time at minimum aging temperature of Section 6.3.3 is a printing error 5 and should be changed to 5000 hours0.0579 days <br />1.389 hours <br />0.00827 weeks <br />0.0019 months <br />.

6. The definition of "Double Aperture Seal" in Section 2 is a printing error I and should be changed as follows: "Two single aperture seals in series."

7. The specific applicability or acceptability of the codes, standards, and guides referenced in Section 3 will be covered separately in other regulatory guides, where appropriate.

D. IMPLEMENTATION

The purpose of this section is'to provide informa- tion to applicants regarding the NRC staff's plans for using this regulatory guide. Except in those cases in which the applicant proposes an acceptable alterna- tive method for complying with specified portions of the Commission's regulations, the* method described herein will be used in the evaluation of submittals for construction permit applications docketed after August 31, 1978.

If an applicant wishes to use this regulatory guide in developing submittals for applications docketed on or before August 31, 1978, the pertinent portions of the application will be evaluated on the basis of this guide.

4 Values based on data of ANSI C37.20-1969, "Switchgear Assemblies Including Metal-Enclosed Bus" (1974 Consolidated Edition dated September 3, 1974).

5 This printing error was corrected in printings of the standard after August 25, 1976.

  • U. S. GOVERNMENT PRINTING OFFICE:

1978-720-387/234

4

1.63-2

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C.

20555 OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

POSTAGE AND FEES PAID

UNTIED STATES

NUCLEAR

REGULATORY

COMMISSION

A

119406002001

1 SN

US NRC REGION I

GIFFICE OF INSPECTION & ENFORCE

R J

EORES

631 PARK

AVENUE

REGION I

KING

OF PRUSSIA

PA

19406

4

4


Retrieved from "https://kanterella.com/w/index.php?title=Regulatory_Guide_1.63&oldid=5249580"