05000321/LER-1980-080-03, /03T-0:on 800706,w/reactor in Hot Standby & Reactor Water Cleanup in Normal Operation,Water Found Coming from Cleanup Line Insulation,Due to Crack in Heat Affected Zone of Spool Piece.Cause Unknown.Piece Replaced: Difference between revisions

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{{Adams
#REDIRECT [[05000321/LER-1980-080-03, Water Found Leaking from Insulation on Reactor Water Cleanup Return Line.Caused by Crack in Heat Affected Zone of Stainless Steel Spool Piece on Common Return to Reactor Vessel Due to Stress Corrosion]]
| number = ML19321A142
| issue date = 07/17/1980
| title = /03T-0:on 800706,w/reactor in Hot Standby & Reactor Water Cleanup in Normal Operation,Water Found Coming from Cleanup Line Insulation,Due to Crack in Heat Affected Zone of Spool Piece.Cause Unknown.Piece Replaced
| author name = Coggin C
| author affiliation = GEORGIA POWER CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| docket = 05000321
| license number =
| contact person =
| document report number = LER-80-080-03T, LER-80-80-3T, NUDOCS 8007220519
| package number = ML19321A139
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 2
}}
{{LER
| Title = /03T-0:on 800706,w/reactor in Hot Standby & Reactor Water Cleanup in Normal Operation,Water Found Coming from Cleanup Line Insulation,Due to Crack in Heat Affected Zone of Spool Piece.Cause Unknown.Piece Replaced
| Plant =
| Reporting criterion =
| Power level =
| Mode =
| Docket = 05000321
| LER year = 1980
| LER number = 80
| LER revision = 3
| Event date =
| Report date =
| ENS =
| abstract =
}}
 
=text=
{{#Wiki_filter:" " " ^ " " " * " ^ " ' " " " * * *
,RC F ORM 3c6
/ 77)
LICENSEE EVENT HEPORT y
CONT ROL PLOCK: l l
l l
l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INf'ORMATIOfJ) i o
? II I _l_Gl Al El Il.1l 1 l@[ 0 l 0 l -l 0 l 0 l 0 l 0 l 0 l - l 0 l 0 l@l 4 l 1 l 1 l 1 l 1 l@l l
l@
LICENSFE CODL 14 15 LICENSE NUYBlet 2S 7ti LICENSE TYPE 40 bl L A I bd CONN
~R
[",% LLJ@l 0i S i 0l 0 l 0l 312 l i 1@l 017101 c l a 1 d@l 0 l 7 l i 171 s 101@
O 8
00 61 DOCKET NUMBEH M
W LVENT DATE
/4 72 HEPOHT DATE H0 EVENT DESCRIPTtON ANO PRODADLE CONSEQUENCES h 012 l IWith the reactor in 110 t Standby and_RWCU in normal operation, water was 1 0131 l f ound to be c o1r in g from insulation on RUCU return line.
Investigation l
n l4 ; l revealed a crack in the heat affected zone of a stainless steel spool l
on the common return to the reactor vessel.
Another crack was l
;o is] [ piece j o i3 ; jdiscovered in the middle of the 6" spool piece.
There was no effect l
l 0 l 71 l on public health and safety.
This is not a repetitive occurrence.
l I
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'^"de' SusCEE COMPONENT CODE SUBC D'E S C DE CO l Cl Gl@ [E]@ l X l@ lP lI lP lE [X lX l@ l Bl@ W @
O g 7
8 9
10 tt 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LE R/RO EVENT YEAR AEPORT NO.
CODE TYPE N O.
O REPORT l8 l0 l l-j l 0l 8l 0l l/]
lOl3l lTl l--l l0 l
,,,, 21 22 23 24 26 27 2G 29 30 31 32 KEN ACT N ON PLANT SETH HOURS SB IT O F OF 4 B.
SU LIE MAN FACTURER
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36 3
40 41 42 44 47 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h cause of the crack is unknown at this time.
The spool piece was
_j li l0 l l The l3l3ll removed and will be sent off-site for analysis.
A new spool piece installed.
An i'pdate report will be written when the results of l
g was g,g3gl testing are complete.
l I
I114 I I 7
8 9 ST S
*4 POWER OTHER STATUS ISCO RY DISCOVERY DESCRIPTION NA l
l B l@l Operator Observation l
.l1151 I dh l0 l0 l8 l@l
* liiviTY CO0 TENT e
RELE ASED OF RELEASE AMO''NT OF ACTIVITY LOCATION OF RE LE ASE l
NA l
l NA 1 6 l d @ [Z_j@l PERSONNEL E xPOSUF ES NUP.4Rf H DESCHtPTION l._1.,.12 l l 9 9 4 h [ TYPE _ _.jhl l
Z NA PtnSONNE L iN;u'r?its NUMRT H
 
==DESCRIPTION==
l q 0[ q@l NA I,
80 7
9 11 12 LOSS Of OR DAMAGE TO FACILITY l
TYPE DESCHIP110N Ii I o I L_3hl NA 7
Y 9 30 NRC USE ONt Y PUBL ICIT Y r
1%SUF n@DE SCniPilON Ltj l
NA l
[J l l l l l l l l l l l 2
? o ca oo
: 80. :
80 4 ggy,g,$n gg o 2 c. t. Conain - supt. rit. nna. serv.
mamm
,mose,
 
x J
^
LER #:
50-321/1980-080 Licensee:
Georgia' Power Company h3.
Facility Name:
Edwin I.
llatch Docket #:
50-321
 
=Narrative=
Report for LER 50-321/1980-080 On July 6,
1980, with the Unit I reactor at 8% power in Hot Standby for llPCI testing, the Operations Department discovered water leaking from the RWCU common return line to the reactor vessel.
Investigation revealed a crack running along the heat affected zone and turning out into the stainless steel (A312-304) spool piece about one inch.
A second crack was observed in the middle of the 6"
spool pie::. about one inch in length at approximately the same position on the pipe.
The spool piece was removed and replaced with one of the same material.
The weld prep. and final welds were inspected via dye-penetrant examination.
No indications were found during D-P' examination.
Our Arc.hitect/ Engineer recommended performing a
X-ray examination during our next refueling outage.
This has been included in our ISI schedule for the Unit I
rafueling outage.
A hydrostatic pressure test was O" were performed ct 1.1 times the operating pressure and no leaks observed.
This is not a repetitive occurrence.
There c
was no affect on public health or. saf ety as a result of this i.' c i d e n t.
t e
(
) -
LJ
,m.
}}
 
{{LER-Nav}}

Latest revision as of 02:14, 18 September 2025