ML20096C893

Proposed Tech Specs,Adding Surveillance Requirement to Incorporate Steam Generator post-leak Exam Program

ML20096C893
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/23/1984
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20096C882	List: ML20096C879 ML20096C890 ML20096C893
References
NUDOCS 8409050435
Download: ML20096C893 (3)

Text

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Fo'rt St. Vrain #1-

-( . Technical Specifications Amendment No.

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Page 5.3-22 l Specification ~ SR 5.3.12 -

Steam- Generator Tube Leaks l- Surveillance

-l Following each steam generator tube leak, specimens from l the accessible subheader tube ' connected to tiie leaking l inaccessible tube (s) shall be metallographically examined.

-l The results of this examination shall be compared to the l results.from the specimens of all previous tube leaks.

l A study shall be performed to evaluate the size and l elevation of all tube leaks to determine if a cause or l trend in the degradation of the tubes can be identified.

l Following each steam generator tube leak study, the l Nuclear Regulatory Commission shall be notified as to the f

l estimated size and elevation of the leaks as well as the l results of the metallographic and engineering analyses l performed that may identify the mechanism that caused the l leak to occur.

l Basis for Specification SR 5.3.12 l The surveillance. plan outlined above is considered l adequate to evaluate steam generator tube integrity and l assure that the consequences of postulated tube leaks l remain within the limits analyzed in the FSAR (see Section l 14.5).

8409050435 840823 PDR ADOCK 05000267 P PDR

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l' ATTACHMENT 2 SIGNIFICANT HAZARDS CONSIDERATIONS

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SIGNIFICANT HAZARDS CONSIDERATIONS I. EVALUATION SR 5.3.12~

Thn addition of this surveillance requirement will assure that L the appropriate examination, analysis, and Nuclear Regulatory Commission notification requirements, as committed in P-84028,.

will be performed .following any future tube leaks. The described program is considered. adequate to monitor steam i generator tube integrity and maintain the consequences of postulated tube leaks within the limits analyzed in the FSAR.

II. CONCLUSION Based on the above evaluation, it is concluded that operation of Fort St. Vrain in accordance with the proposed changes will not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident form any accident previously evaluated, or .(3) involve a significant-reduction in any margin of safety.

Therefore, these changes will not increase the risk to the health and safety of the public nor do they involve any significant hazards considerations.

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