ML19319E541

RO 50-313/76-34:on 761201,valve SF-10 in Spent Fuel Cooling Sys Leaked.Caused by Crack in Heat Affected Zone of Valve SF-11.Valve SF-11 Will Be Replaced

ML19319E541
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/30/1976
From:	Mardis D ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19319E539	List: ML19319E538 ML19319E541
References
NUDOCS 8004110804
Download: ML19319E541 (4)

Text

.- --__ _ _ _ _ _ _ _ _

~

- - ' UCENSEE EVENT REPOP- '

CONTROL BLOCK:l l l l I I I (PLEAsE PRINT ALL REGUIRED INPORedATEDet)

I 6 1

' "" '

TAME LCENSE NUMBER .

1AIRl4lKl(Ill

'

10101-101010101o1-10101 141/ Ill/l/l 10131 7 89 , 14 15 25 26 30 31 32 CATEGORY Typt 50 COCKET NUMBER EVENT OATE REPOAT CATE

"

01CONil 7 "1B I I LL-J LLJ 1015101-10131'13I II I.2. l o t /1716 I I i 121 s 1o 1714 I 57 58 59 60 E1 68 69 74 75 + 80 EVENT DESCRIPTION 08 @dMoun 'rsvene- s17 tis" anwet f99 'fe 5Ph LEAWA6E' is/41 'museerEMED eM A uGLs 'n o A*zTt f4 M i 7 89 '

80 DE Ior VaEva v-io. A ,1s -reveruAx,- w asYe Atn no rexe rwa raus c asear . A 1rs -I.

7 89 80 DE IPMNFTRAer TEYT* of Tyr VALV6 Addf SF-10 YAlvf 37-fl RGvCALD A CR M rH TNT MrAri 7 89 '

80 h.lAFFECT1r*5 2dMf. n neman3Aur _vv m Att" AVAIL ABL G" . YAlyf ST = ll u r s t_ n G" l 7 89 80'-

BG farrueen. (s'o - sis /74 - 34) l 7 89 ' / '

= 80 CE CIDE COMPONENT CODE SUPPLE uauur n votafoN E IFl.Cl L5J 7 89 10 IVIAItIviElxl 12 LAJ l4131915I ty.]

11 17 43 44 47 48 CAUSE OESCRIPTION DE I N4 1 7 89 80 BE N19 I hve sr-ll uret ne asruics o . I

-

80 ji I-

's d  % POWEA OTHEA STATUS O COvEAY OrSCOVERY OESCASTCN i

7 8 LC 9 10 lol91' 12l I13~ u I LkJ l ua I 44 45 48 80 ACTMTV CONTENT RELEASEO OF RELEASE AMOUNT OF ACTMTV LOCATCN OF RELEASE

.. FTil. lyj lyj i un i I us . .. I 7 8 9 10 11 44 45 80

.

PERSONNEL EXPOSURES . ,,

3 NUMBER TYPE CEScapTON '

GE 1010101 1r] l v4 I 7 89 11 12 13 80 PERSONNEL INJUAIES NUMBER OESCAFTCN DE 1010101 l .NA l 7 89 11 12 80 OFFSITE CONSEQUENCES BB I WA I 7 89 4 80 LOSS OR OAMAGE TO FACIUTY TYPE DESCApTON '

7 89 10

$Y 80 PUBLICITY I

&I 7 89 WA

' ' '

I P 80 p}bl lACOITIONAL FACTOAS N#

8004110 h-o 7 89 I 80 81 '

i

"

NAuE M ar<n 6 krnn- ~ONd.....s4, 6 v - nu

_. . . . . . . . .. ... ... .

'

. ' ~fi~ nT . . . . . . -

. -

• O 3 .

. ',

s, .

.

.- . .

m>

'

- 1. Reportabic Occurrence Report No. 50-313/76-34

' 4 L

2. Report Date: 12/30/76 3. Occurrence Date: 12/1/76

-

4 Facility: Arkansas Nuclear One-Unit 1 Russellville, Arkansas i

S. Identification of Occurrence: .

Water leakage from valve in spent fuel cooling system.

'

-

.

6. Conditions Prior to Occurrence:

Steady-State Power X

,

Re~ actor Power 2542 MWth Hot Standby Net Output 829 Mwe Cold Shutdown Percent of Full Power 99  %

(A)

U Refueling Shutdown Load Changes During Routine Power Operation

-

Routine Startup Operation Routine Shutdown Qeration ,,

Other (specify) ,

, , . , ,

s ..

.

7. Description of Occurrence: ,

,

At 1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br /> on December 1,1976, leakage was discovered on a weld -

downstream of Valve SF-10 between the valve and a T-section. Cause of the leakage appeared to be a small crack in the weld. A dye-penetrant ,

j test of the T-section area revealed no penetrating cracks. It was then

• l thought that the Icakage may have come from above on Valve SF-11. A dye-penetrant test revealed a crack in the heat affected zone of Valve SF-11. ,

O

.

<

NSI4III-2, Rev. S Attachment "D" 5 October 1, 1976 Page 2 of 4

_

- --

-- -

e- . . . . . - - - . ~ . ,. ._. __ _. _

___ . . .

. .

,

, . m

. .

'

.* ,

• -, .

-

,

% .

,

Reportable Occurrence Report No. 50-313/76-34 4

8. Designation of Apparent Cause of Occurrence:

.

-

,

Design Procedure

.

'

Manufacture Unusual Service Condition Including Environmental ,

Installation /

Construction , Component Failure (See Failure Data) 5 Operator _

Other (specify) X

.

Unknown

.

-

.

I

.

9. Analysis of Occurrence:

'

Since the leakage was only a minute amo'unt and was contained in a controlled area, there was no hazard to the health.and safety of the public. 5 i

. . . , ,

.

. .

,

.

'

l

.

-

1 l

I

.

October 1, 1976 NSP-III-2, Rev. 5 Attachment "D" 5

% Page 3 Of 4

.

-- - -, ,- , - , - - - , - ,, - , , , - .-~.-,,- . - . . - - . -

.-- - . - _. _ .- . . . - -

. -- - .: .- 4 . - , , . ~ . . . . _ _ , , . . . , , ,

"

. ..

-n

. . . . ,,

• m - 3

.

.

.

'

u o .. .

'

S' _ _, P ~" .

4 1

. .

.

. ,

Reportable Occurrence Report No. 50-313/76-34 s 4

,,.

- .  ;

. ,.

4

10. Corrective Action: >

-

C'

. ..  ; -

.

After a dye-penetrant test was perfomed on the T-section area of f f, ' ' ,, .

-

Valve SF-10 and no penetrating cracks were found, a dye-penetrant' teg .i- -- - >

revealed a' crack in the body of Valve SF-11. Valve SF-11 will

be '

.. ,.

" ;

replaced. .

.> .

-

.

.. + ..>

. .e -

,

.

<

i

.'?.

- -

'

n p-j

• i

-

;

"

.

.

. t

1. .

t

'

.

.

~~

11. Failure Data:

.

NOIE I

s s

t

. . ., ,

l,

- -

.

.

. .

.

. i

,

.:

.

.

t

.

.

l l

October 1, 1976 NSP-III-2, Rev. 5 Attachinent "D" 5 i

% Page 4 of 4

. .

e

. - - - , . _ , , , , - ---,y-- ,- ,- , .- , _.----.-,y.,,.w-w. w, - - -, , , , _ - -

, y 7-_,--_,y ,._,ys,