ML19210C633
| ML19210C633 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/02/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7911190266 | |
| Download: ML19210C633 (3) | |
Text
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UNITED STATES y*
j NUCLEAR REGULATORY COMMISSION
.. E WASHINGTON, D. C. 20555 2
NOV 2 1979 MEMORANDUM FOR:
T. Ippolito, Chief Operating Reactors Branch 13 Division of Operating Reactors FROM:
G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - CONTAINMENT PURGE SYSTEM - COOPER NUCLEAR STATION (TAC 10182)
REFERENCE:
1.
Internal Memorandum for T. Ippolito from G. Lainas, dated August 31, 1979 On Septenter li,1979, members of the P1 ant Systems Branch (PSB) met with representa.;ives of Nebraska Public Power District in Bethesda, Maryland, to discuss the issue of containment purging during normal opera tion. The licensee, at that time, requested further clarifi-cation on some of the PSB, Section B, questions (Enclosure 1 to Reference 1). To provide this clarification, PSB, Section B, has modified our request for additional infomation (enclosed).
The PSB Section A (EI&C) is currently reviewing the licensee's information provided at their Septenter 12, 1979 meeting.
w G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
Enclosure:
As stated Contacts :
J. Xerrigan, X28129 D. Shum, X27058 gj,j;g jg cc:
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1 T. Ippolito NOV 2 ;s73 cc w/ enclosure:
D. Eisenhut B. Grimes W. Gammi11 L. Nichols G. Lainas E. Reeves E. Adensam V. Rooney D. Tondi D. Shum J. T. Beard G. Knighton V. Noonan F. Wi tt J. Zudans R. Scholl 13S} _[3.._.
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ENCLOSURE s
RE00EST FOR ADDITIONAL INFORMATION FOR CONTAINMENT PURGE SYSTEM AND a
CONTAINMENT VENTING SYSTEM FOR COOPER NUCLEAR STATION DOCXET NO. 50-298 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 ft.nc. tion 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 break sizes during the maximum closure time allowed in your Technical Specifications.
d.
Provide an analysis to demonstrate the acceptat'ility 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.
136; 12 h
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