ML19319A650
| ML19319A650 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/14/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 7911190547 | |
| Download: ML19319A650 (3) | |
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ATTN: Mr. William O. ParkeriJr.'
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WWe/are~ currently reviewing y[our submittal of June 8.;1978 in regard GC e
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KEQUEST FOR-ADDfTTONAL VNFORMATXON
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AND EVALUATION OF GCONEE UNIT 1 PROPOSED TECHNICAL SPECIFICATION STEAM GENERATOR TUBE LEAKAGE RATE LIMIT INCREASE Steam generator tube primary-to-secondary leakage gives an indication that the reactor coolant pressure boundary has been breached.
The. technical specification steam generator tube leakage rate limit is the last line of defense against unacceptable tube degradation.
In the event that abnormally degraded tubes develop through wall cracks during normal operation, the primary to secondary leak rate limit will ensure that any leaking tube has an adecuate margin of safety to witnstand the loads imposed during normal operation and postulated accidents.
To establish a leak rate limit that retains an adequate margin of safety _ against tube failure it is necessary to know the burst pressures and leak rates associated with various types of throu;n wall defe::s.
The primary to seccndary leak rate limit under normal operating cressure should be less than the leak rate determined tneoretically or experimentally for the most limiting single defect.
To date no theoretical or experimental leak rate data has been submitted for Babccck and Wilcox (5&W) steam generators.
Furthermore, the only tube' burst cata whi:n nas been suomitted for S&W steam generator. tubes (Attachment E to Dece.mber 15, 1977 Letter Addressed to Mr. E. Case 1
from Mr. W. Farker, Jr.) did not include results for any through wall defects.
Inerefore, 'a proter assessment of tne proposed leak rate limit cannot be mace.
The current 0.3 GFM leak rate limit was conservatively established based on leak rate and tube burst cata subr.itted by otner vendors; however, nis data may not be fully applicaole to E&W steam generator tubes.
Proper. assessment of the leak rate limit for the Oconee B&W steam generaters will require review of leak rate and tube burst data for postulated defects.
In particular tnis data should be made available for defect geometries resembling the " erosion" and circumferential fatigue cracks which have been observed in the Oconee steam generators.
The defects s'nould be manufactured td resemble observed tube degradation as accurately as possible.
Circumferential cracks should preferably be introduced by a fatigue mechanism since mechanically machinec or electric di,cht ege machined (EDM) cracks are not as tight as fatigue 4
cracks and f.end to overestimate leak rates.
Burst and leak tests should be condusted in an environment aporoximating real operating conditions as nearly 4s practicable.
In particular tnese tests should be conducted at the actual operating temperature.
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' Duke Power Company cc:
Mr.' William L. Porter Duke Pcaer Co.mpany P. O. Box 2178 422 South Church Street Charlotte, North ' Carolina 28242 J. Michae. McGarry, III, Esquire DeBevoise & Liberman 700 Shoreham Building 806-15th Street, NW.,
Washington, D.C.
20005 Oconee Public Library 201 South Spring Street Walhalla, South Carolina 29591 e
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