05000267/LER-1980-019-03, /03L-0:on 800327,operation in Degraded Mode of Limiting Condition 4.2.10 Occurred on Six Occasions & Reactor Dewpoint Limit of Limiting Condition 4.2.11 Was Exceeded Once.Caused by Problem W/Buffer Helium Sys

/03L-0:on 800327,operation in Degraded Mode of Limiting Condition 4.2.10 Occurred on Six Occasions & Reactor Dewpoint Limit of Limiting Condition 4.2.11 Was Exceeded Once.Caused by Problem W/Buffer Helium Sys

ML19309F835
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/25/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19309F830	List: 05000267/LER-1980-019, Forwards LER 80-019/03L-0 05000267/LER-1980-019-03, /03L-0:on 800327,operation in Degraded Mode of Limiting Condition 4.2.10 Occurred on Six Occasions & Reactor Dewpoint Limit of Limiting Condition 4.2.11 Was Exceeded Once.Caused by Problem W/Buffer Helium Sys
References
LER-80-019-03L, LER-80-19-3L, NUDOCS 8005010401
Download: ML19309F835 (1)

LER-1980-019, /03L-0:on 800327,operation in Degraded Mode of Limiting Condition 4.2.10 Occurred on Six Occasions & Reactor Dewpoint Limit of Limiting Condition 4.2.11 Was Exceeded Once.Caused by Problem W/Buffer Helium Sys

Event date:
Report date:
2671980019R03 - NRC Website

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NRC FORM 366 U.S. NUCLEAR RECn.TCRY COMMISSION 800 5010 LICENSEE EVENT REPORT CONTROL BLOCK: l l

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8 60 61 OOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 r

f EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l

Io l2l l During the period from March 27, 1980, through April 16, 1980, operation in a de-l [ol3l l graded mode of LCO 4.2.10 occurred on six separate occasions, and the reactor dew-1 l

I o 14 l l point limit of LCO 4.2.11 was exceeded once.

Reportable per Fort St. Vrain Technical i ITTT1 1 Specification AC 7.5.2(b)2.

No affect on public health and safety. Similar occur-l 10 l61 l rences reported in RO's 80-11, 79-53. 79-45. 79-43. 79-31. 79-30. 79-24. 79-01. 78-39.1 IoI7i l 78-37, 78-18, 78-16, 78-12, 78-01, 77-36, 77-13, 77-02, and 76-06.

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CODE TYPE NO.

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33 J4 35 36 31 40 43 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l i l 0 l l Prime cause of oxidant and moisture levels was problems with buffer helium system.

I g l Corrective action was reduction of reactor powe.- level, which reduced average core i

g l outlet temperature belou the limit.

In one case, the primary coolant oxidants were I

g ] reduced below the limit. No further corrective action is anticipated or required.

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7 8 9 80 SYN S 4 POWER OTHER STATUS IS O RY OtSCOVERY OESCRIPTtON lt 15 l l E l @ l Ol 4l 5lhl N/A l

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ACTIVITY CO TENT AMOUNT OF ACTIVITY @ l LOCATION OF RELEASE @

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7 8 9 tt 12 80 LOSS 08 OR DAMACE TO FACILITY TYPE

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