ML20206J075
| ML20206J075 | |
| Person / Time | |
|---|---|
| Issue date: | 06/30/1986 |
| From: | Aggarwal S NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| References | |
| RTR-REGGD-1.063, TASK-EE-405-4, TASK-RE REGGD-01.063, REGGD-1.063, NUDOCS 8606260399 | |
| Download: ML20206J075 (6) | |
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t*0Q pa %q June 1986 p
4 U.S. NUCLEAR REGULATORY COMMISSION Division 1
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0FFICE OF NUCLEAR REGULATORY RESEARCH g
Task EE 405-4 e
.E DRAFT REGULATORY GUIDE AND VALUE/ IMPACT STATEMENT b.,,,*
Contact:
S. K. Aggarwal (301)443-7668 PROPOSED REVISION 3 TO REGULATORY GUIDE 1.63 ELECTRIC PENETRATION ASSEMBLIES IN CONTAINMENT STRUCTURES FOR NUCLEAR POWER PLANTS A.
INTRODUCTION s
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General Design Criterion 50, " Containment Design Basis,"'of Appendix A,
" General Design Criteria for Nuclear Power Plants," to 10 CFR'Part 50,
" Domestic Licensir.g of Production and Utilization Facilitie's," requires, in part,thatthereactorcontainmentstructure, including,h$netrations,be designed so that the containment structure can,.without exceeding the design leakage rate, accommodate the calculated preshure,7 emperature, and other t
environmental conditions resulting from anycloss 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 andFuelReprocessingPlants,"to(10CFRPart50establishesqualityassurance requirements for 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 the Commission's regulations for the design, constructiori, testing, qualification, installation, and external circuit protec-tion of electric penetration ' assemblies in containment structures of nuclear power plants.
Any informatiEn, collection activities mentioned in this draf t regulatory guide are contained:as requirements in 10 CFR Part 50, which provides the regulatory basis fori his guide.
The information collection requirements in 10 CFR Part 50 have been cleared under OMB Clearance No. 3150-0011.
This regulatory guide and the associated value/tmeact statement are being issued in draft fore to involve the public in the early stages of the development of a regulatory position in this area. They have not received complete staff review and do not represent an official N#C staff position.
Pubite coments are being solicited on both drafts, the guide (including any implementation schedule) and the value/ impact statev nt.
Coments on the value/ impact statement should be accompanied by supporting data. Written coments may be submitted to the Rules and Procedures Branch. DRR. ADrt. U.S. Nuclear Regulatory Comission. Washington DC 20555. Coment s may also be delivered to Room 4000. Maryland National Bank Building 7735 Old r.corgetown Road. Bethesda. "aryland from 8:15 a.m. to 5:00 p.s.
Copies of conr'ents received may be examined at the "RC Public Document Room.1717 H street arW.,
Washington. DC. Comments will be most helpful if received by August 25, 1986.
Eequests for single copies of draft guides (which may be reproduced) or for placement on an automatic distribution list for single copies of future draft guides in specific divisions should be apde in writing to the U.S. Nuclear Replatory Comission.
Washington DC 20555. Attention: Director. Division of Technt;;al Information and Document Control.
s 8606260399 860630 PDR REGGD 01.063 R PDR
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 requirements for the design, construction, testing, qualification, and installation of electric penetration assemblies in containment structures for stationary nuclear power generating stations.
Secticn 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 operating 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.
The 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 1E Power Systems and Equipment in Nuclear Power Generating Stations."*
IEEE Std 317-1983 references other standards that contain valuable infor-mation.
Those referenced standards not endorsed by a regulatory guide or incorporated into the regulations, if used, are to be used in a manner consis-tent 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 5tations," provides a method acceptable to the NRC staff for satis-fying the Commission's regulations witi, respect to the design, construction, testing, qualification, and installation of electric penetration assemblies in containment structures for nuclear power plants, subject to the following:
- Copies may be obtained from the Institute of Electrical and Electronics Engineers, 345 East 47th Street, New York, NY 10017.
2
The external circuit protection of electric penetration assemblies should
' meet the provisions of Section 5.4 of IEEE Std 741-1986, " Criteria for the Protection of Class 1E 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 staff's 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:
d 1.
Plants for which the construction permit is issued after the issue
'N date of the final guide, 2.
Plants for which the operating license application is docketed 6 months or more after the issue date of the final guide, 3.
Plants for which the applicant or licensee voluntarily commits to the provisions of this guide.
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VALUE/ IMPACT STATEMENT BACKGROUND IEEE 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 Regu-latory 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 satis-factorily resolved.
Issuance of this Proposed 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 guides.
i SUBSTANTIVE CHANGES AND THEIR VALUE/ IMPACT Regulatory Position C.1 in Revision 2 was modified in this Proposed Revi-sion 3 to include the appropriate requirements of IEEE Std 741-1986, which apply l
to external circuit protection of electric penetration assemblies.
Regulatory Positions C.2 to C.6 in Revision 2 were not included in this Proposed Revision 3 because they were incorporated in IEEE Std 317-1983 as follows:
Regulatory Position Number Section Number (Rev. 2 of this guide)
(IEEE Std 317-1983) 2 6.2.8(3)(a) 3 6.2.8(5) 4 6.2.3(2) 5 0.1.2.5(2) 6 2
Regulatory Position C.7 in Revision 2 was deleted because the applicability of referenced IEEE standards has been included under " Discussion" in this Pro-posed Revision 3.
j 4
VALUE This guide endorses the latest version of a national standard.
The guide also should enhance the licensing process.
IMPACT This regulatory guide does not impose any new requirements or costs on licensees or applicants.
Thus, no impact will result from issuance of this guide.
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UNITED STATES NUCL5AR REGULATORY COMMISSION
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