ML19210C788
| ML19210C788 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/05/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 7911200107 | |
| Download: ML19210C788 (3) | |
Text
Thkb en necog'o, UNITED STATES E
NUCLEAR REGULATORY COMMISSION g
3 "-
.; j WASHINGTON, D. C. 20555 November 5, 1979 Docket No.
50-335
.Dr. Robert E. Uhrig Vice President Florida Power & Light Company Advanced Systems & Technology P. O. Box 529100 Miami, Florida 33152
Dear Dr. Uhrig:
By letter dated January 5, February 1, May 25, and August 20,1979, you provided information on containment purging and venting system for St.
Lucie, Unit No. 1.
To continue our review of this issue, please pro-vide your response within 45 days to the enclosed questions.
Sincerely, f
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
Request for Additional Information cc: w/ enclosure See next page
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Floriaa Power & Light Company cc:
Robert Lowenstein, Esquire Lowenstein, Newnan, Reis & Axelrad 1025 Connecticut Avenue, N.W.
Washington, D. C.
20036 Norman A. Coll, Esquire ficCarthy, Steel, Hector & Davis 14th Floor, First National Bank Building Miami, Florida 33131 Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Bldg.
Tallahassee, Florida 32304 Indian River Junior College Library 3209 Virginia Avenue Fort Pierce, Florida 33450 13/3 J50 t
I
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION FOR CONTAINMENT PURGE SYSTEM AND
-CONTAINMENT VENTING SYSTEM FOR ST. LUCIE PLANT, UNIT 1
~ ~ ~ '
DOCKET NO. 50-335 1.
With regard to the containment purge and venting system, provide the following information:
a.
Discuss the provisions made to ensure that : isolation valve closure will not be prevented by debris which could poten-tially become entrained in the escaping air and steam.
b.
Discuss the provisions made for testing the availability of the isolation function and the leakage rate of the isolation valves, individually, during reactor operation.
c.
Specify the amount of containment atmosphere released through the purge and vent isolation valves for a spectrum of break sizes during the maximum time allowed for them to close in your Technical Specifications.
d.
Provide an analysis to demonstrate the acceptability of the provisions made to protect structures and safety-related equipment; e.g., fans, filters, and ductwork, located beyond the purge system isolation valves against loss of function from the environment created by the escaping air and steam, e.
For the containment purge isolation valves, specify the differential pressure across the valve for which the maximum leak rate occurs.
Provide test results (e.g.,
from vendor tests of leakage rate versus valve differential pressure) which support your conclusion.
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