ML19296D983

From kanterella
Jump to navigation Jump to search
Forwards Request for Addl Info Re Containment Purge & Vent Sys.Discussion Should Be Provided Re Provisions Made to Ensure That Isolation Valve Closure Will Not Be Prevented by Debris Which Could Become Entrained in Escaping Air
ML19296D983
Person / Time
Site: Crystal River 
Issue date: 02/29/1980
From: Reid R
Office of Nuclear Reactor Regulation
To: Hancock J
FLORIDA POWER CORP.
References
NUDOCS 8003140008
Download: ML19296D983 (3)


Text

. -.

~

?

p.' **cci g

A, UNITED STt TES y7e g

NUCLEAR REGULATORY COMMISSION

')")('-p WASHING TO N. D. C. 20555 e

' ' %,...../

February 29, 1980 Docket No. 50-302 Mr. J. A. Hancock Director, Nuclear Operations Florida Power Corporation P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733

Dear Mr. Hancock:

We have reviewed your submittal of January 10, 1979, regarding the containment purge and vent system at Crystal River Unit No. 3 and have determined that the additional infonnation identified in the enclosure is necessary to continue our review.

Please provide this information within 30 days of receipt of this letter.

/

Sincerely,

,k

' l 0 'r Robert W. Reid, Chief Operating Reactors Branch #a Division of Operating Reactors

Enclosure:

Request for Additional Information cc w/ enclosure:

See next page 600a no oo3

. Flcrica Power Corporation cc: fir. L. A. Brandimore Vice. President and General g,

Counsel P. O. Box 14042 St. Petersburg, Flc,ri da 33733 Mr. Robert B. Borsun Babcock & Wilcox f;uclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 J

Crystal River Public Library Crystal River, Florida 32629 Mr. Jack Shreve Office of the.Public Counsel Room 4, Holland Building Tallahassee, Florida 32304

Enclosure REQUEST FOR ADDITIONAL

~

INFORMATION FOR CONTAINMENT PURGE AND VENT SYSTEM FOR CRYSTAL RIVER HUCLEAR

^

GENERATING PLANT, UNIT 3 DOCKET NO. 50-302 1.

With regard to the containment purge and vent system, provide the following information:

a.

Discuss the provisions made to ensure that isolation valve closure will nct be prev.ited by debris which could potentially 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 specified for them to clcse in your technical s peci fi cati ons.

d.

Provide an analysis to demonstrate the acceptability of the provisions made to protect structures and safety-related equipment, e.g., fans,

filters, and cuctwork, located beyond the purge system isolation valves against loss of function from the environment created by the escaping air and steam.

e.

Provide an analysis of the reduction in the containment pressure resulting fror the partial loss of containment atmosphere during the accident for.ECCS backpressure determination.

f.

Specify the allowable leak rates of the purge and ver.t isolation valves for the spectrum of design basis pressures and flows against which the valves raust close.

_