ML19210C562
| ML19210C562 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/30/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7911190115 | |
| Download: ML19210C562 (3) | |
Text
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OCT 3 01979 MEMORANDUM FOR:
R. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors FROM:
G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - CONTAINMENT PURGE SYSTEM - RANCHO SECO NUCLEAR GENERATING STATION (TAC 10206)
REFERENCES :
1.
Letter to R. Reid from J. Mattimoe, dated January 4,1979 2.
Letter to R. Reid from J. Mattimoe, dated June 15, 1979 Plant Name: Rancho Seco Nuclear Generating Station Docket No. : 50-312 Project Manager:
D. Garner Review Status: Awaiting Information With regard to the containment purge and vent system at Rancho Seco Nuclear Generating Station, the licensee plans to justify unlimited purging (Reference 1). The Plant Systems Branch, Section B, after having reviewed the documents (References 1 and 2), filed by the licensee, has prepared the encloseo request for additional information.
Section A is continuing their review and will provide questions regarding the electrical and instrumentation aspects of containment purging in January 1980.
G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
Enclosure:
As stated 1354 148 I
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7911190
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.o 0 ^!:79 R. Reid Contacts:
J. Kerrigan, X28129 D. Shum, X27058 cc w/ enclosure:
D. Eisenhut B. Grimes W. Gamill L. Nichols G. Lainas E. Reeves E. Adensam D. Garner D. Tondi D. Shum J. Kerrigan J. T. Beard G. Knighton V.
S'.onan F. Wi tt J. Zudans R. Scholl 1354 149
ENCLOSURE
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REQUEST FOR ADDITIONAL INFORMATION FOR CONTAINMENT PURGE SYSTEM AND CONTAINMINT VENTING SYSTEM FOR RANCHO SECO NUCLEAR. GENERATING STATION DOCKET NO. 50-312 1.
With regard to the containment purge and venting system (i.e.,
both the 66" purge lines and the 12" vent lines), 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 closure time allowed in your Technical Specifications.
d.
Provide an analysis to demonstrate the acceptability of the provisions made to protect strucrues 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.
f.
Provide an analysis of the reduction in the containment pressure resulting from the partial loss of containment atmosphere during the accident for ECCS backpmssure determi nation.
2.
Provide a schematic drawing of your vent and purge system.
1354 150
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