ML19210D148

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LER 79-086/03L-0:on 791027,secondary Containment Violated by Simultaneous Opening of Airlock Doors Between Reactor Bldg & Radwaste Bldg.Caused Y Design Deficiency.Interlocking Scheme Under Review
ML19210D148
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 11/13/1979
From: Baxley S
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19210D139 List:
References
LER-79-086-03L-01, LER-79-86-3L-1, NUDOCS 7911200587
Download: ML19210D148 (1)


Text

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LICENSEE E\7EhT ftEPORT CONTROL t3LOCM l l l l l l l (PLEASE PRIN's OR TYPE ALL REOUtaEO INTOnMATION) 1 6 lo l1l8 9l G l A 7

l E l I l H l141 l@l LICENSEE CODE 15 0 l 0 l 0 l LICENSE 0 l 0 NUMBEH l 0 l 0 l0 l0 l0 l0 25 l@l426 l1 l1 11 l1 l@l57 C Al T 68l@

LICENSE TY PE JO CON'T 7

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S uRCE l60L l@l 01510101013 61 DOCK E T NUY8ER I P 11 68 l@l1 69 10 l2171719 l@l1 11 kVENT DATE 74 75 l ll DATE REPORT 31 719l@ 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h Io l2 I l During normal plant operation, secondary containment was momentarily violated when  ;

0 3 l personnel simultaneously opened the reactor building to radwaste building airlock  ;

O 4 l doors. This event occurred again 10-31-79 when personnel simultaneously opened the l lO ls t t reactor building to turbine building airlock doors. Secondary containment integrity ;

j o is i l was demonstrated per HNP-1-3653 Standby Gas Treatment System Operability Section "G", ,

o 7 I to comply with Technical Specification 4.7.C.2. This is a repetitive occurrence; see ; i o a i LER 79-68 and LER 79-74.

There were no effects on public health or safety. l 80 7 8 9 C DE CODE SUSC E COMPONENT CODE SUSCODE S DE 7

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,. SEQUENTI AL OCCURRENCE REPORT REVISION LER EVENT YEAR REPORT NO. CODE TYPE NO.

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_ 21 22 23 24 26 27 28 29 30 31 32 TAK N A TO ON PLANT TH HOURS 22 S B !T D FOR1 8. SU PLI MANUFACTURER l F l@l34F l@

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h ji lO; [ The cause of this event was design deficiency. The doors were opened simultaneous 1v. I g,jij l The present design of the interlock system will not prevent this. A review of the I i

, 2 l present airlock interlocking scheme is under review as stated in LER 79-68 and LER l 3 3 [ 79-74. i ,

i 4 1 1 7 8 9 80 ST S  % POWER OTHER STATUS blS OV RY DISCOVERY DESCRIPTION I 2 I s ] [_fj@ l 0 l 9 l 3 l@l N/A l [A_J@l Personnel Observation l ACTivlTY CO TENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELE ASE li 168 l9 U @ l ZI@ N/A l N/A I 7 10 11 44 45 80 PERSONNEL EXPOSunES NUVSE R TYFE DESCRIPTION 11 l 71 l 01 01 Ol@ Z l@l N/A l PERSONNE L INJURIES -

Nuvstn DESCniPriON@ t1 z., [ 7L 7,'i/ J W l8 01 7 9 0 0l@l 11 12 N/A 80 l

LOSS OF On DAMAGE TO FACILITY TYPE DE SCRIP TION ==

i o lZl@l 'N/A 791120058 7 l 7 8 9 10 80 2 o I<;SUEf@DESCRIPilON QL l N/A  ! i j  ; ;;  ;  ; ; ; ll 7 8 9 to 68 69 80 E NAME OF PREPAFTEft *

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  • O U PHON E: 912-367-7781 2,

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