05000348/LER-1979-009-03, /03L-0 on 790216:during Plant Startup W/Reactor & Steam Generator Controls Manual & Steam Dumps in Automatic, Steam Dumps Occurred.Temp Average Reduced to 538 F.Personnel Reinstructed

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/03L-0 on 790216:during Plant Startup W/Reactor & Steam Generator Controls Manual & Steam Dumps in Automatic, Steam Dumps Occurred.Temp Average Reduced to 538 F.Personnel Reinstructed
ML19283B774
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 03/14/1979
From: Hairston W
ALABAMA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19283B767 List:
References
LER-79-009-03L, LER-79-9-3L, NUDOCS 7903190286
Download: ML19283B774 (1)


LER-1979-009, /03L-0 on 790216:during Plant Startup W/Reactor & Steam Generator Controls Manual & Steam Dumps in Automatic, Steam Dumps Occurred.Temp Average Reduced to 538 F.Personnel Reinstructed
Event date:
Report date:
3481979009R03 - NRC Website

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NRC FORM 36G (7-77)

LICENSEE EVENT REPORT CONTROL BLOCK: l l

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8 60 61 OOCKET NUMB ER 68 69 EVENT OATE 74 75 REPORT DAT E 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l C l 2 l l At 2303.on 2-16-79 while conducting a plant S/U with ret tor and steam generator l

10l3ll controls in manual and the steam dumps in auto on the pressure controller, excessive l

1014 l l0Pening of the steam dumps occurred causing a reduction in Tavg to 538 F.

Tech. Spec.[

1015 l3.1.1.5 requires RCS temp. to be 541 F or greater.

Steam dumps were turned off and j

t I avg was restored to greater than 541 F at 2308 on 2-16-79.

Action statement require-l T

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l 0 l 7 l lments of Tech. Spec. 3.1.1.5 were met.

Health / safety of public not affected.

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40 46 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l t l 0 l lTavg decrease occurred because excessive valve opening resulted from incorrect setpointl jon the steam dump pressure controller. Steam dumps were turned off and Tavg was t

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l i 12 I Irestored to greater than 541 F at 2308 on 2-16-79.

Operations personnel will be l

,, ; 3 g l instructed regarding the potential for reoccurrence with pressure controller setpoints i,,4ggless than 1005 psig. Also, a design change has been requested to prevent controller l

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'ST2ES sPowER OTHER STATUS 015 O RY DISCOVERY DESCRIPTION NA l

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l i l 5 l (_CJh l Ol 0l 8 l@l A DVITY CO TENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE l

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8 9 10 11 44 45 80 PERSONNEL EXPOSURES l 0 l 0 l 0 l@l Z l@ DESCRIPTION

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NUMBER TYPE l

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,E RSON~ d'l~2u'4 E S DESCniPTiONh NuveER li IR I lo I o l o l@l NA 7

8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE

DESCRIPTION

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7 8 9 to 80 ISSUE @L"SCRiPnO~@

7903190276 NRC USE ONW dl i

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t NAME OF PREPARERW. G. Hairston. IIT pu o E: