Regulatory Guide 1.63: Difference between revisions

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{{Adams
{{Adams
| number = ML12298A128
| number = ML003740219
| issue date = 07/31/1978
| issue date = 02/28/1987
| title = Electric Penetration Assemblies in Containment Structures for Light-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 = NRC/RES
| author affiliation = NRC/RES
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, Rev 3
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 4
| page count = 4
}}
}}
{{#Wiki_filter:'0 UNITED STATES o NUCLEAR REGULATORY
{{#Wiki_filter:Revision 3' February 1987 U.S. NUCLEAR REGULATORY  
COMMISSION
COMMISSION)REGULATORY
fWASHINGTON, D. C. 20555 Z July 18, 1978 REGULATORY
GUiDE OFFICE OF NUCLEAR REGULATORY
GUIDE DISTRIBUTION
RESEARCH REGULATORY  
LIST (DIVISION
GUIDE 1.63 (Task EE 4054) ELECTRIC PENETRATION  
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  
ASSEMBLIES  
IN CONTAINMENT  
IN CONTAINMENT  
STRUCTURES
STRUCTURES  
FOR LIGHT-WATER-COOLED
FOR NUCLEAR POWER PLANTS  
NUCLEAR POWER PLANTS  


==A. INTRODUCTION==
==A. INTRODUCTION==
General Design Criterion  
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.
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, "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.
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 a method acceptable to the NRC staff for complying with General Design 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.
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.
 
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 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  
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)
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  
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  
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.
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).
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.
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
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.
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  
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.!'*
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)
IEEE Std 317-1983 references other standards that contain valuable information.
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:
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
Director, Division of Document Control.


capability of the protective device associated with the penetration assembly conductors.
===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.


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.
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.


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)
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.
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 hours.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.
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==
==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
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
3, 1974).5 This printing error was corrected in printings of the standard after August 25, 1976.* U. S. GOVERNMENT
STATEMEN
PRINTING OFFICE: 1978-720-387/234
 
4 1.63-2 UNITED STATES NUCLEAR REGULATORY  
==T. BACKGROUND==
COMMISSION
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
WASHINGTON, D. C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 POSTAGE AND FEES PAID UNTIED STATES NUCLEAR REGULATORY
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.
COMMISSION
 
A4 119406002001
Since then the staff has worked with IEEE in developing IEEE Std 317-1983.
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}}
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}}
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Revision as of 03:33, 21 September 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)


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