05000325/LER-1980-086-03, /03L-0:on 801207,during Testing,Linear Heat Generation Rate Found at 13.359 kW/ft.OD-1 Performed & Rate Exceeded Limit.Apparently Caused by Low Power Range Monitor D Drifting W/Inlet Subcooling

/03L-0:on 801207,during Testing,Linear Heat Generation Rate Found at 13.359 kW/ft.OD-1 Performed & Rate Exceeded Limit.Apparently Caused by Low Power Range Monitor D Drifting W/Inlet Subcooling

ML20002C221
Person / Time
Site:	Brunswick
Issue date:	01/05/1981
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20002C220	List: 05000325/LER-1980-086, Forwards LER 80-086/03L-0 05000325/LER-1980-086-03, /03L-0:on 801207,during Testing,Linear Heat Generation Rate Found at 13.359 kW/ft.OD-1 Performed & Rate Exceeded Limit.Apparently Caused by Low Power Range Monitor D Drifting W/Inlet Subcooling
References
LER-80-086-03L-01, LER-80-86-3L-1, NUDOCS 8101090676
Download: ML20002C221 (2)

LER-1980-086, /03L-0:on 801207,during Testing,Linear Heat Generation Rate Found at 13.359 kW/ft.OD-1 Performed & Rate Exceeded Limit.Apparently Caused by Low Power Range Monitor D Drifting W/Inlet Subcooling

Event date:
Report date:
3251980086R03 - NRC Website

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60 61 DOCKET NuMSER 68 69 EVENT D ATg 74 75 REPORT DATE 80 EVENT DESCRIPTION AN9 PROBABLE CONSEQUENCES h l o 12 l l While performing the daily core performance parameter periodic test P-1. the nuclear l

10131lengineer noticed that the LHGR was 13.359 IGI/ft. As this was close to the limit of I

l o 14 ] l 13.4 E1/f t., he performed an OD-1 to improve the base distribution of the P-1 check.

I l o l s ] l Following the performance of the OD-1, another F-1 was done which gave an LHCR of l

l o is l l 13.493 IGJ/f t.

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g [than 13.4 EJ/ft. The control rod pattern was adjusted to reduce the LIICR at the 1

I l liaiting node and power was returne; to normal.

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a LER ATTACHMENT - RO NO. 1-80-96 Facility: BSEP Unit No. 1 Event Date:

12-7-80 It is believed that the cause was LPRM "D" drif ting coupled with inlet subcooling as a result of 4A feedwater heater being isolated due to tube leaks. The suspected drift in LPRM "D" could not be verified due to the small amount that the LHGR was exceeded.

The control rod pattern was changed to reduce the LHCR at the j

limiting node. 4A feedwater heater is currently being repaired during.a main.tenance outage.

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