05000324/LER-1980-010, Supplemental LER 80-010/03L-1:on 800114,during Normal Plant operation,OD-1 Determined That Max Critical Power Ratio Was Below Tech Specs for Bundle 43-28.Caused by Problems W/Low Power Range Monitor & Core Flow Input.Power Redu

Supplemental LER 80-010/03L-1:on 800114,during Normal Plant operation,OD-1 Determined That Max Critical Power Ratio Was Below Tech Specs for Bundle 43-28.Caused by Problems W/Low Power Range Monitor & Core Flow Input.Power Reduced

ML19296D449
Person / Time
Site:	Brunswick
Issue date:	02/27/1980
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19296D444	List: 05000324/LER-1980-010, Supplemental LER 80-010/03L-1:on 800114,during Normal Plant operation,OD-1 Determined That Max Critical Power Ratio Was Below Tech Specs for Bundle 43-28.Caused by Problems W/Low Power Range Monitor & Core Flow Input.Power Redu
References
LER-80-010-03L, LER-80-10-3L, NUDOCS 8003040603
Download: ML19296D449 (2)

LER-1980-010, Supplemental LER 80-010/03L-1:on 800114,during Normal Plant operation,OD-1 Determined That Max Critical Power Ratio Was Below Tech Specs for Bundle 43-28.Caused by Problems W/Low Power Range Monitor & Core Flow Input.Power Reduced

Event date:
Report date:
3241980010R00 - NRC Website

text

NRC FORM 366

"DPMTE" REPORT:'~ PREVIOUS LICENSEE EVENT REPORT REPORT DATE 2-11-80 h CONTROL BLOCK: l l

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l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lNlClBlElpl 2l@l0l0l-l0l0l0l n l o l _ l n i n l@l 4 l 1 l 1 l ' l 1 l@l l

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7 8 9 LICENSEE CODE 14 15 LICENSE NUM8ER 2$

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8 60 61 COCK ET NUM6t R 6d 69 EVENT OATE 74 75 REPORT DATE 80 SOURCE EVENT DESCRIPTION AND PROSABLE CONSEQUENCES h ITTTI I outine normal plant operation, the nuclear engineer performed an OD-1 which determined]

Io1al l that MCPR was 1.281 for bundle 43-28, an 8x8R bundle.

The reportable limit for this l l parameter is <l.29.

Power was being slowly increased following a rod shuffle the 1

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I I night before.

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l Technical Specifications 3.2.3, 6.9.1.9b l

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80 DE CODE SU8C E COMPONENT CODE SL8 COD'E SU E

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10 11 12 13 18 19 20 SEQUENTI AL OCCURRENCE REPORT R EVISION LE R/Ro EVENT YE AR REPORT No.

CODE TYPE No.

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Gl0l8 0lh 33 34 35 36 37 40 di 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h

] The CPR problem was due to: a) the controlling LPRM had two levels bypassed; I

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li l j [ b) problems with the core flow input. Power was immediatelv reduced to brine MCPR i

[;Til I in specifications. The LPRM will be replaced and the inoperable jet pump input will g l be corrected during the next refueling outage. A " drive flow" vs. " core flow" corre-l lation has been inserted into the comouter to provide more representative indication l gl 80 7

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% PoWE R oTHER STATUS IS O RY DISCOVERY DESCRIPTION

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A TIVITY CO TENT RELEASED OF RELE ASE AMOUNT oF ACTIVITY LOCATION OF RELEASE W l 2 l h l Z l@l N/A l

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7 8 9 to 11 44 45 80 PERSONNEL EXPOSURES NUM8ER TYPE CESCRIPTroN I

FiTTl 10 l o l o l@l z l@l N/A

,ERSc~d'iN;u'4ES oESCRiPT cNh NuveER I

1010101@Lv/s i a 80 7

8 9 11 12 LOSS OF OR DAMAGE To FACILITY TYPE

DESCRIPTION

l I 7. I@l N/A i 9 80 7

8 9 to 03040 -

NRc usE ONev PU8ticiTY e

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N/A 2 o 68 89 80 T.

7 8 9 10 (919) 457-9521 2

A. C. Tollison, Jr.

PHONE:

NAME OF PREPARER e.

LER CONTINUATION - RO #2-80-10 Facility: BSEP Unit No. 2 Event Date: January 14, 1980 of core flow. Had the proper core flow been seen by the computer, it is believed that this event would not have exceeded any limits.

O N

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