ML19210D366

LER 79-087/03L-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

ML19210D366
Person / Time
Site:	Hatch
Issue date:	11/19/1979
From:	Coggin C GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19210D363	List: ML19210D362 ML19210D366
References
LER-79-087-03L-01, LER-79-87-3L-1, NUDOCS 7911260362
Download: ML19210D366 (2)

Text

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

- LICENSEE EVENT REPORT CONTROL DLOCK: l l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INf ORMATION) i 6 lo lil l Gl A l E l I l H l 1 l@l 010 l 0 j 0 l 0 l 0 l 0101010 l023 l@l4 26 l1LICENSE l1 11TYPE l1JO[@lS1 CAT l l@

58 14 IS LICENSE NUMBEH 7 8 9 LICENSEE CODE CON'T lolil 7 8 3 E lLl@l015l0101013l211 l@l 1 101214 l 719 l@l1 11 11 9171 60 St DOCAET Nuit0E R 68 G9 EVENT DATE 74 75 HEPORT D AT E 80 EVENT DCSCRIPTION AND PRO 8 ABLE CONSEQUENCES h l 10121 During steady state power operation a routine QA audit revealed that water level in 270, 000 gal. as l iO l3 l l one fire water storage tank had dropped below Tech Specs limit of At worst case the water level dropped) 0 4 Iset forth in Technical Specifications 3.13.2-B.

In the event of a fire, water tank no. I was available i p iT1 l 7% below the required minimum.

The water i O e I and emergency intertie to the plant service water could have been made.

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

j O 7 l

80 O 8 l' COMPONENT CODE SUBC DE S DE DE CODE SUBC E O o l Al B @ W@ l z l@ lI lN lS T R lU l@ l I @ @ @

18 19 20 9 10 11 12 13 REVISION 7 8 OCCURRENCE REPORT SEQUENTfAL TYPE NO.

REPORT NO. CODE LE R EVENT YE AR 1719 l l-l 10 18 7l M l 01 31 lLl [--j l0 l h yg.gRO a

24 26 27 28 79 30 31 32

_ 21 22 23 FOH b B. SU PLIE MA FACTURER S8 iT D U@ IN l@ LA]@ ICl31110lg ON O 4 PLANT tET HOURS KEN A Lz_j@ izl@ i 01 01 Oi Oi -

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34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h

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li lO l l Upon iiivestigation, it was discovered that although the level readinos had been mon-j i i l itored and recorded _ regularly on a daily basis, the procedure requiring the surveil-In order to prevent recur i

, , l lance did not specify the respective acceptance criteria.

l

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

1-1050 " Daily Surveillance Checks" which (continued 3ij4i DISCO RY DISCOVERY DESCRIPTION 32

% POWER OTHER STATUS STA S QA Fire Protection Au it l Iiis]' W

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4S 46 80 ACTIVITY COArENT LOCATION OF RELEASE RELE ASED OF RELEASE AMOUNT OF ACTIVITY NA l NA i c l

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PERSONNtt EXPOS NUMBER TYPE DESCRIPTION @ l NA l t l 7 l l 0l Ol Ol@Lz_l@l"

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NUMBE R DESCRIPTION NA 130l ?39 7

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80 TYPE ESC Pi ON NA i 9 L1J@lto 80 7 M 9 NRC USE ONLY ESCHIPTION g {hy iiiiiiiiiiiil:

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2 o IS'iUiEL 8l 68 09 7 8 9 to C. l. Coqnin, Supt. Plt, Ena. Serv, pnone; 9NM-M {

NAME OF PHEPAHEH .

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

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