ML19323B933

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RO 80-26:on 800508,preliminary Calculations of Reactor Coolant Pressure/Temp Relations Indicated That Resultant Dose at Site Boundary Was Higher than FSAR Requirements But Below Tech Spec Limits.Complete Rept Will Be Provided
ML19323B933
Person / Time
Site: Rancho Seco
Issue date: 05/08/1980
From: Coward G
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
References
NUDOCS 8005140434
Download: ML19323B933 (1)


Text

8005140kN L

SACRAf/EfdTO f/UtilCIPAl', UTILITY DISTRICT D 6201 S Street Box 15810. Sacramento California 95813; (916) 452 3211 May 8, 1980 t

i Hr. R. H. Engelken, Director

)

Region V Office of inspection (,

Enforcement U. S. Nuclear Regulatory Commission 4

1990 North California Boulevard Walnut Creek Plaza, Suite 202 Walnut Creek, California S4396 s

.Re: Operating License DPR-54 Docket No. 50-312 Reportable Occurrence 80-26 (Immediate Notification)

Dear Mr. Engelken:

In accordance with Technical Specifications for Rancho Seco Nuclear Generating Station, Section 6.9.4.l(h), the Sacramento Municipal Utility District is notifying you of a reportable occurrence.

This event was dis-cussed with Mr. D. Sternberg of your office today.

The TMI corrective actions require the re. actor coolant pressure /

temperature relations to be 500F subcooled.

During an OTSG rupture, the

. requirement delays the depressurization of the primary system to se.condary system pressure and results in a slightly greater reactor coolant mass flow to the secondary system and eventually to the environment.

Preliminary calculations indicate the resultant dose at the site boundary to be higher than stated in the FSAR but below the limit established in the Technical Specifications Section 3.1.4.-

A complete repo,rt will be sent to you withln 14 days.

Sincerely yours,

,A h

G. A. Coward Acting Plant Superintendent Rancho Seco Nuclear Generating Station Unit 1 RWC:Jr Y

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