05000313/LER-1979-005, /03L-0:on 800716,during Power Operation,One Small Primary to Secondary Leak Developed in Tube 74-1 of Steam Generator E24A.Cause of Failure Believed Similar to Defective Tubes Reported in LER 79-005/03L-0

From kanterella
Revision as of 11:36, 24 December 2024 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
/03L-0:on 800716,during Power Operation,One Small Primary to Secondary Leak Developed in Tube 74-1 of Steam Generator E24A.Cause of Failure Believed Similar to Defective Tubes Reported in LER 79-005/03L-0
ML19344B061
Person / Time
Site: Arkansas Nuclear 
Issue date: 08/15/1980
From: Shively C
ARKANSAS POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19344B060 List:
References
LER-80-026-03L-01, LER-80-26-3L-1, NUDOCS 8008250508
Download: ML19344B061 (1)


LER-1979-005, /03L-0:on 800716,during Power Operation,One Small Primary to Secondary Leak Developed in Tube 74-1 of Steam Generator E24A.Cause of Failure Believed Similar to Defective Tubes Reported in LER 79-005/03L-0
Event date:
Report date:
3131979005R00 - NRC Website

text

,a V

~

i NRC FORM 366 U. S. NUCLE AR REGULATORY COMMISSION (7 77)

LICENSEE EVENT REPORT EXHIBIT A CONTROL 8 LOCK: l l l l l l lh IPLE ASE PRINT OR TYPE ALL REQUIRED INFORMATION) l Al R l A l Nl 0 l 1lg]50l0 l -l0 l0 l 0l 0} 0 l-l 0 l0 ]g l1 l 1l1 l 1lgl l lg O i 9

LICENsit CODE 44 1

LICENst NuwetH 25 26 uttNst evet JG b3 CAT 6e 7

8 CON'T l' % [l:_j@l015 p l0 l 0 ]311 131@l 0 ! 7l1 l 618101@l0 l 8111 SI 8101@

O i F

S to 61 00C8tET Nuuggn 68 69 EVENT DATE 34 FS HEPOR10 ATE 80 EVENT DESCRIPTION AND PROSABLE CONSEQUENCES h LO_12) I During Power operation, a small primary to secondary leak developed, i

O 3 1,c inaar,+na ky nn incenn en nr +ko rnnannen, ve riu-pump nyk,nct i

tradiation monitor indication.

Leakage was verified to be from Steam i

O a Generator, E24A, by chemical analysis of the secondary system activity.

g IOisi I 10161 IThe RCS l enkrate l imit per T.

S.

3.

1 6.

1 and the secondarv system i

l activity limit per T. S. 3.10 were not exceeded. An orderly unit shut-l O,

109IIdnwn was er ectit ed. There were nn similnr nceurrences.

Pennrtable ner I

T.'& 6. 12". 3. 2" d svsite causs CAvss C D..

v COO 4 CCCE sueCODE COMPONE NT Cout

%urcoat muliCODE I Cl c l@ l..FJ@ L,2.c_J G.,IH I Tl El X l Cl H l@ [F_J@ [2_j @

o e

,o m

.o (g n,a EVE NT vE A84 R E POR T O E

1

@fggi l 8 I 01

[--J 1 0 1 2 1 61 y

l 013 I [Lj

[--j J

_2n 27 23 24 26 27 7e

.w a

si 32 T Ast N A TO PLA T WET wouns 22 se T O FOm SUN LDJ@L.21@ l^l@

L.AJ@

l 0l3 l 6 lT l [N jg

]g g

lBjd&hTUR[$lg R

wA l

33 34 3s 36 33 40 40_

gg gj gg 47 CAUSE DESCR.PTION AND CORRECflVE ACTIONS 27 m lFollowing unit shutdown, testing identified leaker to be tube 74-1.

Testi g ;ing also revealed tube 140-68 to have an extremely small amount of leak-i m lage. A sampling of tubes around each leaker 6 all of the "open lane" r

l tubes were Eddy Current Inspected. Tube 78-62 was identified to have a

, 3 E ' 61 % thruwall OD d efec t.

Cause of failure is believed to be similar i

',Mgrypreviously identified def tim tubes reported by LER 50-313/ S-005.

a theNr 2MN " ice-i li is I

@ l Il I kl3 tgW'Wfe Ipfg i

A!TiviTv CO'" TINT so 36 RELE Asf D 08 p*LE ASE AwouNT OF ACTIVITY toca re li lc l [Gj @ [NJ@l 17_7 curies, Pred. Xh-133[ Primary to Seconlos pitgAstary to Condenser tg nasON 'El en.OsEs At mos.

fauu6fp TYPE OfsCRoPT*ON l 1101 0l@[E j@l Maintenance / Inspection - 16.8 MAN-REM g

i i

' n sO,.Na',uu'4 s_

=

et>CaiericNh uveta 8101010 l@l NA l

7 8 9 11 12

'35c' " * '"'f,'O, ' " " @

T i sC.

l.,Hj@[_ Sten-Genevn tnr Tube Leak l

')

euousTv OtsC..,nON @

NHC USE ONLY issue 0@L Sews Rel ea se l'YJ 1 IfIlll1ilt!!l 2

  • Chris N. Shively Nh%b3M NAVE or PREPARER

,g oy,;

8 008250 pog