05000321/LER-1979-087-03, /03L-0:on 791024,water Level in Fire Water Storage Tank Dropped Below Tech Specs Limit.Caused by Unspecified Acceptance Criteria in Surveillance Procedure.Requirement Incorporated in Daily Surveillance Checks

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/03L-0:on 791024,water Level in Fire Water Storage Tank Dropped Below Tech Specs Limit.Caused by Unspecified Acceptance Criteria in Surveillance Procedure.Requirement Incorporated in Daily Surveillance Checks
ML19210D366
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 11/19/1979
From: Coggin C
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19210D363 List:
References
LER-79-087-03L-01, LER-79-87-3L-1, NUDOCS 7911260362
Download: ML19210D366 (2)


LER-1979-087, /03L-0:on 791024,water Level in Fire Water Storage Tank Dropped Below Tech Specs Limit.Caused by Unspecified Acceptance Criteria in Surveillance Procedure.Requirement Incorporated in Daily Surveillance Checks
Event date:
Report date:
3211979087R03 - NRC Website

text

U. S. NUCLE AR REGULATORY COMA IS NRC FORM 366 (7 77)

LICENSEE EVENT REPORT CONTROL DLOCK: l l

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23 26 LICENSE TYPE JO S1 CAT 58 7

8 9 LICENSEE CODE 14 IS LICENSE NUMBEH lolil 3 E lLl@l015l0101013l211 l@l 1 101214 l 719 l@l1 11 11 9171 CON'T 68 G9 EVENT DATE 74 75 HEPORT D AT E 80 60 St DOCAET Nuit0E R 7

8 EVENT DCSCRIPTION AND PRO 8 ABLE CONSEQUENCES h During steady state power operation a routine QA audit revealed that water level in l

10121 270, 000 gal. as l

iO l3 l l one fire water storage tank had dropped below Tech Specs limit of Iset forth in Technical Specifications 3.13.2-B.

At worst case the water level dropped) 0 4 In the event of a fire, water tank no. I was available i p iT1 l 7% below the required minimum.

The water i

I and emergency intertie to the plant service water could have been made.

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] supply system serves both units. This is a non-repetitive occurrence.

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10 11 12 13 18 19 20 REVISION SEQUENTfAL OCCURRENCE REPORT EVENT YE AR REPORT NO.

CODE TYPE NO.

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ICl31110lg 33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h li lO l l Upon iiivestigation, it was discovered that although the level readinos had been mon-

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l itored and recorded _ regularly on a daily basis, the procedure requiring the surveil-j i i In order to prevent recur i

l lance did not specify the respective acceptance criteria.

j rence, this requirement and associated acceptance criteria was incorporated in HNP l

,;3; 1-1050 " Daily Surveillance Checks" which (continued 3ij4i STA S

% POWER OTHER STATUS DISCO RY DISCOVERY DESCRIPTION 32 Iiis] W @ l1 0l0l@l NA l

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QA Fire Protection Au it l

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COArENT ACTIVITY LOCATION OF RELEASE RELE ASED OF RELEASE AMOUNT OF ACTIVITY l

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7 8 9 to C. l. Coqnin, Supt. Plt, Ena. Serv, pnone; NAME OF PHEPAHEH

Georgia Power Company Plant E. I. Hatch Baxley, Georgia 31513 Cause Description and Corrective Actionsgoverns the performance of short frequency surveillance requirements for the unit.

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