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

From kanterella
(Redirected from ML19210D366)
Jump to navigation Jump to search
/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

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 l0 l@l4 l1 l1 11 l1 [@l l

l@

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.

O e

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

j O 7 l

O 8

l' 80 DE CODE SUBC E COMPONENT CODE SUBC DE S

DE T R lU l@ l I @ @ @

l Al B @ W@ l z l@ lI lN lS O o 7

8 9

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

CODE TYPE NO.

h yg.gRO 1719 l l-l 10 18 7l M

l 01 31 lLl

[--j l0 l LE R a

_ 21 22 23 24 26 27 28 79 30 31 32 KEN A ON O 4 PLANT tET HOURS S8 iT D FOH b B.

SU PLIE MA FACTURER

- LG J@ll.J@

Lz_j@

izl@

i 01 01 Oi Oi U@

IN l@

LA]@

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-

[

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

l C l@]

QA Fire Protection Au it l

80 44 4S 46 12 o

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

NA l

NA

[)) @ [Zj@MES i c DESCRIPTION @

l PERSONNtt EXPOS NUMBER TYPE NA l t l 7 l l 0l Ol Ol@Lz_l@l PERSONNE t iN;uln'iES NA 130l

?39 j

NUMBE R

DESCRIPTION

lOlOl0l@l

~'

80 i n 7

8 9 11 12 TYPE ESC Pi ON NA L1J@l i 9 80 7

M 9 to NRC USE ONLY g

{hy NA J

iiiiiiiiiiiil:

ESCHIPTION IS'iUiEL 8l 68 09 go. ;

2 o 9NM-M

{

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.

O e

S 4

O