ML19274E680

LER 79-017/01T-0 on 790327:radiation Leakage Exceeded Limit for Single Containment Isolation Valve.Replacement of Faulty AO-2-1601-60 Shaft Seals Should Solve Problem.Suppl Rept Will Be Issued If Further Leaks Found

ML19274E680
Person / Time
Site:	Dresden
Issue date:	04/09/1979
From:	Parcell M COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17173A749	List: ML17173A747 ML19274E680
References
LER-79-017-01T, LER-79-17-1T, NUDOCS 7904170166
Download: ML19274E680 (2)

Text

LICENSEE EVLfJ i HEt'OHT

, CON?OL ULOCK: W l l l o

h (PLi' ASE PRINT OR TYPC ALL RLOUinED INF ORMATION) o 1 lI lL lD lR lS

h[ 0 l 0 l -l 0 l 0 l 0 l 0 l 0 l - l 0 l 0 ]@l 4 l 1 l1 l! l Mlj@l$7 _

l@

7 8 9 LICEt6EE CODE 14 l '.* LICdf I PAMoL H /> M LICONOL l O t LATb3 CON'T

[ 0j_1]

7 8

[nN l I'l@[0 l 5 0UUCKET t,J 01 l0 l0 ]?

fauY LE H 3 l7 l@]0l3l2l7l7l9l@l0l4l0l9l7l9 h 03 t+ ) LVENT DATE /4 M HEFOHT DA TE 6)

EVENT DESCRIPTION AND FROBABLE CONSEGUENCES h l 0 l 2 l l Measured leakage of volume bounded by containuent isolation valves A0-?-1601-23,"4,60.l

,g ;3 ; ; 61, 62 t, 63 was 1660 SCFH. This exceeds the T.S. limits for single contalument isola j

[gl,,; l tion valve allovable leakage, total for tectable penetrations and isolat ion valves and [

nuximum allowable Containment leak rate. The leakage was into the secondary contain- l l o in ] l nent and resulted in no danger to public health and safety. Similar eventr- 50-237/ l

76-10 & 50-249/76-16. l 0 8 l )

CU 7 8 9 SYSTEM CAUSE C AUS E COYP. VALVE CODE CODE SUJCCDE COVPONENT CODE SUSCODE SUCCODE Inlpl 8

is 9

ol@ [EJh l X lh lV l A l L lV lE lX lh [Bjh [Dj h 10 11 12, 13 13 19 21.,

7

'E QUE NTI AL OCCU n n E N CE REPORT REVISION LE R/PO EVENTYEAH HEPOR I NO. CODE TYPE N O.

hRE T 7l9l l-l 23 l 0 l1 l 7 l ]/] l0l1l lTl 30 l- [0]

_ 21 22 24 26 27 2J 29 31 32 ACTION FUTURE EFFECT SHU T uo.*tN ATT AC HY E N T NPR D-4 PRIME COMP. COYPONENT TAKEN ACilUN ON PLANT YETHGD HOURS SUEYtTTED FOHU SUB. SUrPLIEH VtNUFACTURER

[Zj@lh M

Ih IJ) Z l@ W@ [ 0l 0l 0l 0l lY lQ l Y[g ]g Pl 3l 4 0l{

34 M 31 40 41 42 43 44 47 CAUSE DESCRIPTICN AND CORRECTIVE ACTIONS i o l Leakage identified from A0-2-1601-60 shaft seals. Seals will be repaired and the valveq g,y,y ; retested prior to startup. If other sources of leakage are identified, a suppler ental l

,,  ; report will be submitted. A0-2-1601-60: 18" rubbar seated butterfly valve, model No.l 11131 l l i 4 l l 7 8 9 80 F ACILITY METHOD OF STATUS  % POWER OTHEH STATUS DiSCOV E HY DISCOVERY DESCRIPTION i s @j@ l 0 l 0 l 0 l@l N/A l l45Bl@l46Local leak rate testine l 7 8 9 to 12 11 44 80 ACTIVITY CONTENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE

[071 [z j @ l z l@l N/A I l N/A l 7 8 9 10 11 44 45 60 PERSOreNEL EX POSURES NUVP*R DESCRIPTION l i l 71 10 10 0l@lTYPE @l 1 l N/A l 7 8 9 11 12 13 BC FERSONNE L INJURIES NUV8ER C ESCRIPTION li la8l 91010 0l@l N/A l 7 11 12 80 LOSS OF OR DAYAGE TO FACILtTY TYPE DESCHIPTION '

lil91 Lzj@l N/A l 7 8 9 to 80 n y' f 3 7 9 0 4 17 0 1 cm, "S' '

12 i n l dSuf @otSCHiPTiON@

l IIIIIIl!IIIIl' 7 8 9 10 68 69 80 5 NAME OF FREPARER PHONE:

e ATTACilMEtiT TO LICf."SEE EVE::T REPORT 79-017/01T-0 COM:10:GlEAI.TH EDISON COMPA:;Y ( C',' f.)

DHESDEN UNIT 2 (II.DHS 2)

DOCKET # 030-237 The measured leakage of a local leak rate test of the volume bounded by containment isolation valves AO-2-1601-23, 24, 60, 61, 62 & 63 was 1660 SCFil. This leak rate is in excesu of t he allowable Icak rate for a con-tainment Isolation valve (29. 38 SCFil) , the t otal for testable penetra-tions And isolation valves (176.29 SCFH) and maximum containment leak rate (783.5 SCFil) (T.S. 4.7.A.2.e). Lenkage was identified from the shaft seals of AO-2-1601-60 which ir an 18" rubber seated butterfly valve. Since this leakage is into the secondary containment and is within the capacity of the standby gas treatment system (4000 CFM),

thin event presented no danger to public health and safety.

The shaft s.als will be repaired prior to unit startup and the volume retested. If 1t is determined that all the excess leakage was not through the A0-2-1601-60 shaft seals, a supp1 mental report will be submitted.

e f ** *

. . - -