05000366/LER-1979-037-03, /03L-0 on 790517:during Cold Shutdown,Technicians Inadvertently Set Isolation Trip Setpoint of Alarm Units 2G31-K603A&B for Leakage Flow of 134 Gallons/Minute. Caused by Incorrect Procedure.Procedure Revised

/03L-0 on 790517:during Cold Shutdown,Technicians Inadvertently Set Isolation Trip Setpoint of Alarm Units 2G31-K603A&B for Leakage Flow of 134 Gallons/Minute. Caused by Incorrect Procedure.Procedure Revised

ML19259C223
Person / Time
Site:	Hatch
Issue date:	06/01/1979
From:	Nix R GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19259C221	List: 05000366/LER-1979-037, Forwards LER 79-037/03L-0 05000366/LER-1979-037-03, /03L-0 on 790517:during Cold Shutdown,Technicians Inadvertently Set Isolation Trip Setpoint of Alarm Units 2G31-K603A&B for Leakage Flow of 134 Gallons/Minute. Caused by Incorrect Procedure.Procedure Revised
References
LER-79-037-03L, LER-79-37-3L, NUDOCS 7906140424
Download: ML19259C223 (1)

LER-1979-037, /03L-0 on 790517:during Cold Shutdown,Technicians Inadvertently Set Isolation Trip Setpoint of Alarm Units 2G31-K603A&B for Leakage Flow of 134 Gallons/Minute. Caused by Incorrect Procedure.Procedure Revised

Event date:
Report date:
3661979037R03 - NRC Website

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U. S. NUCLE AR REGULATORY COMMISSION NRC FORM 366 (7 771 LICENSEE EVENT REPORT CONTROL BLOCK: l l

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CON'T 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 7b REPORT D AT E 80 7

8 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I o l 2 l lDuring normal surveillance with the unit in cold shutdown, technicians performed HNP-2-3501 reactor water clean-up differential flow FT&C. Due to an error in the l o 13 l l procedure, the technicians inadvertently set the isolation trip setpoint of alarm j

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is s 79 GPM l

units 2G31-K603A&B for a leakage flow of 134 GPM. The tech spec limit o s

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3a). The plant was in condition 4 (cold shutdown) and the RWCU l

o s l (Table 3.3.2-2 item l

1017 ] ldif ferential flow system was not required to be operable. Public health and safety l

Iwas not affected.

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CODE TYPE N O.

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31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1110llThe formula for determination of leak flow on procedure HNP-2-3501 was stated as

" Leak Flow = Qi - (Q2 + Q3)".

It should have been " Leak Flow = Q1 - (Q9 + Q3)".

i i lWhere Qi = RWCU system inlet flow, Q7 - RWCU system return flow and Q3 = RWCU blow-l g,,7; l down flow to radwaste.

Procedures HNP-2-3501 and 5207 were revised and the FT6C was l

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ldone successfully.

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8 9 STA S

% POWE R oTHER STATUS Dis O RY DISCOVERY DESCRIPTION W@

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i 5 ACTIVITY CONTENT toCAisON oF RELE ASE RELE ASED of RELE ASE AMOUNT OF ACTivlTY [2_] h (Z,j@l N/A l

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1 6 PERSONstt ExPOSuEES NUMBE R TYPE DESC RIPTION I0l0 0lh W @l N/A l

t 7 PE RSOwE t iNau' RIES 2284 156 otSCRtPTiON@

l NuvB E R l0l0l0l@l N/A 1

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8 9 11 12 LOSS OF OR DAMAGE TO FACILITY M 790614 Oe/$14/

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ISSUEf@ DESCRIPTION 2 o 68 69 80 &

7 8 9 10 T. Nix, Supt. of M ntenance PHONE:

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