ML17207A569
| ML17207A569 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 10/30/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7911190087 | |
| Download: ML17207A569 (6) | |
Text
I
'-'KSLNWYMlitt)flLkIIP7; Central Files GOT 40 1979 PSB RDG ts MEMORANDUM FOR:
R. Reid, Chief Operating Reactors Branch 84 Division of Operating Reactors
'v FROM:
SUBJECT:
REFERENCES:
G. Lainas, Chief Plant Systems, Branch Division of Operating Reactors RE(UEST FOR ADDITIONAL INFORMATION-PURGE SYSTEM - ST.
LUCIE PLANT, UNIT 1.
Letter to R. Reid'from R. Uhrig, Purging," dated January 5, 1979 2.
Letter to R. Reid from R. Uhrig, Purging," dated February 1, 1979 CONTAINMElUT 1
"Containment "Containment 3.
Letter to R. Reid from R. Uhrig, "Containment
'urging," dated May 25, 1979 I
4.
Letter to R. Reid from R. Uhrig, "Containment Purging Status Report," dated August 20, 1979 Plant Name:
St. Lucie Plant, Unit 1
Docket No.:
50-335 Project Manager:
P. Erickson
,Review Status:
Awaiting Information With regard to the containment purge and vent system at St. Lucie Plant,.Unit 1, the licensee plans to justify unlimit4d purging (Reference
- 2).
The Plant Systems Branch, Section B, after haying reviewed the documents (References 1-4) filed by the licensee, has prepared.,the enclosed request for additional information.
Section A.is con'tinuing their review and will provide questions regarding the electrical and instrumentation aspects of containment purging in Ja'nuarP 1980.
T911190 Q3 G. Lainas, Chief Plant Systems Branch Division of Operating Reactors P
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OCT 30 579 Encl osurh:
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J. Kerrigan, X28729 cc w/enclosure:
D. Eisenhut B. Grimes M. Gammil1 L. t<ichols G. Lainas E.
Reeves E. Adensam P. Erickson D. Tondi Shum J. Kerrigan J.
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ENCLOSURE RE UEST FOR ADDITIONAL INFORMATION FOR CONTAINMENT PURGE SYSTEM Ahl~.
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 avai lability 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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