ML20244C367
| ML20244C367 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/20/1983 |
| From: | Rivenbark G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-51407, NUDOCS 8307070590 | |
| Download: ML20244C367 (64) | |
Text
_
- pw <- o. UNITED STATES -
C Aiven bctrk . ,
[
-3 3l NUCLEAR REGULATORY COMMISSION Wi&4 tNGTO N, O. C. 20555
%( [~/ $' o p 1
k ;of June 20,1983 , f Docket No. 50-366 '
i
. \
_bl LICENSEE: Lorgia Power Company FACILITY: Hatch Unit No. 2
SUBJECT:
SUMMARY
OF JUNE 1,1983 MEETIllG WITH GEORGIA POWER COMPAfiY (GPC) CONCERNING CRACKS IN HATCH UNIT 2 PIPING j i !
The NRC staff held the subject meeting with GPC representatives in Bethesda, Maryland. .GPC made a presentation to the staff in which it discusced its ,.
c4 evaluation and repair of cracks discovered in weld areas of the riatch Unit .
2 Rear: tor Heat Removcl and Recirculation systems piping. A copy of the q slides. used by GPC in its presentation is attached as Enclosure 1. A >
meeting attendance list is attached as Enclosure 2. '
(
?h duh'k ueorge Rivenbark, Project Manager r Operating Reactors Branch #4 7
Division of Licensing
Enclosures:
As stated ,
~
cc w/ enclosures:
See next page j i
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SUMMARY
DISTRIBUTION i ,
l
, licecsee: Georgia Power Company 1
- Copiec also se.nt to those people on service ('cc) list. for subject plant (s) .
9,..
Docket File -
NRC POR L PDR -
t ORS #4 Rdg. .
f <
Project Manager -GRivenback .
JStol z ,
EGrimes '(Emerg. Preparedness only)
'O
' EL D
.NSIC ELJordan, IE J . d!! Taylor !E ACRS ,(10)
NRC ' Meeting
Participants:
Cch^ng 11 Hun GJohnson WXoo ..
ASuslik- ,
OClark '
FWI tt BCr6wley AHerdt j P,0Liaw UHazel to n t
e 4
_ _ _ ____._______a_._.-____
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. AGENDA
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- as
'i< M_ ARCH UNIT'2 RFCIRC & RHR IGSCC Ai4ALYSES/ REPAIRS MEETING
/ Bethesda, Maryland.
-(r-( - ,
. June 1, I983 :
- 1) INTRG3UCTION 2)' NISERVICEINSPECTION o ,
'I 'A. SCOPE OF EXAMIrlATIONS
/ , B.
C.
RESULTS EXAMINATION METHODS VAL 10ATI0tl u
, 3) INVESTIGATION INTO THE CAUSE OF CRACKING' A. ' BACKGROUND
- 3. THE INVESTIGATION
,C .
SUMMARY
OF CAUSE OF CRACv,1NG INVESTIGATION '
y 1
< 4) AtlALYSES AND REPAIRS .
, 5) FUTURE'lilSPECTIONS l ;
6)- FUTURE . MODI FI CATIONS / RE PLACEMENTS .
7)'
SUMMARY
'AMD CONCLUSIONS 1
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,' SCOPE'0F EXAMIrlATIONS' {
, RECIRCULATIOff SYSTEli 1
- ASME CATEGORY B-F WELDS EXAMINED:
12" - 5 welds 28" ' - I wel d- y 1
Total - 6 welds
'l ASM CATEGORY B-J WELDS EXAMIflED:
---_E_ !
.4" -;4'. welds 1' 6" - 2 welds I
12" - 41 ' welds '
22" .16 welds 1 28" - 33 welds Total - 96 welcs [
' TOTAL. NUMBER OF RECIRCULATION SYSTEM UELDS EXAMINED:
102 'wel ds '!
l RHR SYSTEM' ASME CATEGORY B-F-WELD 3 EXAMIll_ED,: i 20" - I weld 24" - 2 welds ,
Total - 3 welds 11
'ASME CATEGORY B-J WELDS EXAMINED:
20" - 2 welds 24" - 6 welds Total - 8 welds TOTAL NUMGER OF RHR SYSTEM WELDS EXAMI? LED:
l 11 welds RWCU SYSTEM ASME CATEGORY B-F WELDS EXAMINED :
I 6" None , no t apolicable 1 Total - None , not applicable ASME CATEGORY 8-J WELDS EXAMINED:
6" - 5 welds Total - 5 welds TOTAL RWCU SYSTEM WELDS EXAMINED:
5 welds
., .s _ [
lp a. ,
' SCOPE OF EXAMINAT!0tlS (CONT.')
1 TOTAL NUMBER OF RECIRCULATION , RHR ; AND RWCU WELDS EXAMINED: a 118 welds *
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- This number equates to 85.5F. of all stainless steel welds in the Class 1 portions of the Recirculation, RHR, and RWCU systems !
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STAINLESS' STEEL PIPING UT EXAMINATION RESULTS H WELD SIGNIFICANT
' WELD-No. WELD TYPE FAB. SRI %C INDICATIONS % THRU-WALL (MAXY .{
~ RECIRCULATION SYSTEM-i 2B31-1RC-12AR-F-1 'BC-P ,FW 1.11 .065 None --
j
-2 Y-E' SW 1.44 .065 360* Inter. , Pipe Side 25%
-31 E-P' .SW 1.53 .065 .360*' Inter., Pips Side 10% ,
1
-4' P-SE FW l.30 .065 None --
SE-N. SN' -- -
.Not Examined ~ --
2B31-1RC-12AR-G-l' BC-P FW ~ 1.11 .075 None -- 1 l
-2 P-E' SW l'.46 .075 360 Inter., Pipe Side 14% I 1
-3 E-P SW 1.56 .075 360* Inter., Pipe Side 15% I i
-4 P-SE. ' FW 1.33 .075 None --
l 1
-5 SE-N- SW -- --
Not Examined --
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~ 2B31-1RC-12AR-H-1 Red-P FW 1.15 .075 None --
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-2 P-E SW 1.55 .075 360* Inter., Pipe Side 10.';
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-3 E-P SW 1.65 .060 360* Inter. , Pipe Side 300
-4 P-SE PJ 1.46 .060 None --
i
Not Examined -- l 2B31-lRC-12AR-J-l '
BC-P FW l.07 .065 None -- I
-2 P-E SW l.45 .b65 360* Inter.. Pipe side . 233
-3 E-P SW. 1.56 .065 360* Inter., Pipe Side 20%
-4 P-SE FW l.30 .065 360* Inter. , Pipe Side 28%
i
Not Examined --
l 2831-1RC-12AR-K-1 BC-P F'. ! 1.05 .070 None --
-2 P-E SW l.45 .070 360* Inter., Pipe Side 19 *,
-3 E-P SW l.45 .070 360* Inter. , Elbow Side 6%
i
~4 P-SE TW 1.27 .070 None --
Not Examined --
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'hy' l' 'i' i WELD' STONIFICANT.
h4 -i ' VELD'NO.' WELD TYPE FAB. SRI %C INDICATIONS' % THRU-WALLOtA.'d
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>., RECIRCllLATIOS SYSTDt - (Continued) 2831-lRC-12BRdA-1 BC-P FW 1.04 .060 Mone ---
i e , . g. .-2 -P-E SW 1.40 .060 None -~
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., -3 E-P. SW 1.44 .060 360* Inter., Pipe Side. 25%
-4. P-SE :FW 1.21 .060 None --
i
Mone --
L2B31-1RC-12BR-B-1 BC-P FW 1.06 .070 Eone, --
-2' .P-E SW 1. 4 4 ' - .070. 360 Inter., Pipe Side 26%
-3 E-? SW . 1.51 .070 360* Inter., Pipe / Elbow 22%
s Sides
-4 P-SE FW 1.26 .070 '360* Inter., Pipe Side 23%
None --
.t ,
- .2 B 31-1RC-12 B R-C-1 Red-P RJ 1.13 .065 None --
-2 P-E SW 1,53 .065 360* Inter. , Pipe Side 23%
-3 E-P SW 1.60 .060 360* In:er., Pipe Side 30%
-4 P-SE FW 1.38 .055 360* Inter. , Pipe Side 32%
-. None j
2831-1RC-12BR-D-1 BC-P FW 1.10 .060 None --
-2 P-E SW 1 44 .060 360* Inter. , Pipe Side 14%
-3 E-P SW 1.53 .060 360* Inter., Pipe Side 17%
1
-4 P-SE FW 1.31 .060 None --
{
None --
2B31-1RC-12BR-E-1 LC-P FW 1.11 .060 None --
'I
-2 P-F. SW 1.43 .060 None -- I 1
-3 E-P SW 1.49 .060 360* Enter., Pipe / Elbow 22% i Sides '
-3A P-P FW Not Calc. --
360* Inter., Pipe Side 21%
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WELD SIGNIFICANT WELD'NO. WELD TYPE FAB. SRI %C I:tDICATIO"5 % THRU-WALL (MAX h.ECTRCULAT10 S
- STEM . (Continued) h -4 '?-SE FW 1.29 .055 360* Inter., Pipe Side- 13%
j.
-5 ,
-- JNone. ,
2B31-1RC-22AM-1 ' C-P SW 1.16 .048 Parallel.to weld. 'C-42%.
Cap 53"L & 7 1/2"L P-14%
4 ,
Pipe 25 1/2"L & 9"L
-2 'P-CR SW 1.13 .056 Shallow indications in <
the RAZ called inside j geo me try . CPC to re--
examine next refueling outage.
j- -3 CR-P SW 1.07. .056 Shallow indications in --
the RAZ called inside geometry. GPC to re-examine next refueling -/
outage.
-4 -?-C SW 0.96 054 Parallel.to weld, Pipe '19t' '
60"L.
, 2B31-1RC-22BM-1 C-? SW 0.96 0'S ' Parallel to veld, Cap C-16%
25'1/2"L & 5 1/2"L, Pipe P-40%'
27"L. k 2 P-CR SW 1.13 .056 Shallow indications in ---
~
the RAZ called inside geometry. CPC to re-examine next refueling outage, i -3 CR-P SW 1.10 .056 Shallow indications in --
the HAZ called inside
. geometry. GPC to re- I examine next refueling outage. ~
-4 P-C SW 0.96 .043 360* Inter., Pipe / Cap P - 3 7 ';
S id e s C-300 2831-1RC-22AM-1BC-1 P-BC SU 0.98 .060 Shallow indications --
outside the HAZ. GPC to re-examine next refueling outage.
-1BC-2 P-RC SW 0.98 .060 Shallow indications --
outside the HAZ. GPC to re-examine next refueling outage.
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- WELD i SICMIFICANT '
. 's.-!. o WCLD NO. -
WELD "tPE- F/.B . SRI %C INDICATIONS' % THRU-WALL (MA.V
- ; RECIRCLtL ATION SYSTCt (Continued) , h-i 2831-1RC-22AM-3BC-1 P-BC SW '1.01 ,060 Shallow indications -- .
outside the HAZ. GPC to re-examine next refueling outage. L 3BC-2 .P-BC SW 1.01 .060 Shallow indications --
p.i. , outside the RAZ. CFC to re-examine next ,
refueling outage. )
2B31-1RC-22BM-13C-1 P-SC SW 1.01 .060 Shallow indications --
outside the RAZ, CPC to re-examine.next.
refueling outage.
1EC-2 P-BC SW 1.06 .060. None --
2B31-1RC-22BM-3BC-1 P-BC SW 1.03 .060. Shallow indications --
cutside'.the RAZ. CPC to te-examine next '
refueling outage. '
3BC-2 P-BC SW 1.02 060 Shallow indications --
outside the RAZ. GPC to re-examine next i refueling catage, 2031-1RC-28A-1 N-SE SW -- -
None --
2 SE-P FR 1.08 .045 Hone --
-3 P-E SW 1,46 .060 Parallel to weld,-Elbew 12T; '!
Side-5 1/4"L.
4 E-P SW 1.35 .060 360' Inter., Elbow Side 17T 1
-6 T-P SW 0.92 .062 Shallow indications in --
the FL\Z called inside -l+
geometrv. CPC to re-examine next refueling
. outage.
-7 P-E SU 1.30 .057 360 Inter., Pipe / Elbow P-3*
Sides E-4 l:
-8 E-V FW 1.03 .057 None --
-9 V-P FW 1.01 .045 None --
. . w.. .s :- ~ + r
_ _ _ - - . - __ ^
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, WELD WELD No. '
t' ELD TYPE SIGNI'IICANT FAB. SRI _%C _ INDICATIONS _ *: TH RU-WA LI. f!!.\ \
_ RECIRCULATION SYSTD1 (Continued) 4 2'd31- i r,C-2 8 A- 10 P-E SW l.46 056 Parallel to weld, ?ipe 10%
Side - 1 1/L"L
-11 E-?e FW l.03 t
.056 Mono --
-12 Pu-P FW l.13 .041 None --
1
-13 P-V FW 'l.03 .041 Mone --
-14 .V-E FW 1.07 .058 None. --
{
-15 E-P- SW l.40
.058 Shallow indications in --
the RAZ called inside geometry. GPC to re-examine next refueling outagd.
-16 P-T SU 1.25 .062 Shallow indications in --
the RAZ called inside g eome t r't . GPC to re- '
examine next refueling outage.
-1" T-C SW l.09 .062 None --
-18 CR-Red S'.' 1.0; .063 None --
2B31-1RC-283-1 li-S E SW -- --
Set Exaniaed --
0 3 P-E l, SW l.28 .060 360* Inter. , Pipe Side 15 ', j
-c E-? Su 1.21 l
.060 Shallow indications in --
the RAZ called inside l geomecry. CPC to re-l examine next refueling outage. _ -
-5 P-P 0.91 FW .045 Ncne --
-7 P-E SW 1.29 .057 360* Inter., Pipe Side 13l;
-8 E-V FW l.37 .057 160* Inter., Elbe'.' S iie 7'
-9 V-P 1.01 FU .045 Sone --
-10 P-E SW l.41 .056 360' Inter. , Pipe / Elbow P-197, j Sides E-20 !l, '
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WEi.D ' SIGNIFICANT C ' # '
WELD NO.~ !!' ELD TYPE FAB. '
' SRI ~%C I!!DICATIONS '
7: TMP.U-WALL D!A7 is;
- C RECIRCULATION SYSTCt'(Continued)' '
ll "
-11. C-Po FW l.02 .056 None --
,ic
- e -12 Pu-P FW l.13 .041 Mone --
!i !
'h -13 'P-V FW 1.03 .041 Shallow indications in --
the HAZ called inside I 4
geometry. CPC to re- y examine next refueling outage.
-14 V-E FW -1.05 .056 None --
-15 E-P SW l.32 .056 360* Inter., Elbow Side 23 *;
o
-16. P-T SW 1.24 .062 Shallow indications in --
the HAZ called inside geometry. GPC to re-examine next refueling outage.
-17 T-C SW 1.0S .062 Mone --
-18 C-Red SW 1.03' .063 Mene --
2831- lR C-l. AA-1 BC-C FS.'( ? ) -- -
None --
o
-4AB-1 BC-C FN(?) -- --
None --
-4BC-1 BC-C FW(?) -- --
None --
-4BD-1 BC-C FW(?) -- --
None --
2D31-1RC-6A-1 -P-FL FW(?) -- --
None --
-6B-1 P-FL FW(?) -- --
None --
]l
(
RHR SYSTCt j t
'2 E11-lRH R- 20-R S -1 T-P FW l.33 .062 Shallow indications in --
{
the HAZ called inside geometry. CPC to re-examine next refueling outage
-2 P-K F'i 1.61 .056 360* Inter. , Pipe Side 13 *; '
~3 C-P FW l.56 .056 360 Inter., Elbow Side 14.;
2 Ell lRRR-24A-k-10 P-C FW 2.57 .060 None --
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WELD SIGNIFICANT WELD MO. WELD TYPE FAB. SRI %C I'!DICATIOMS % THRtf-WALLO!AX RRR SYSTCt (Continued) 2 Ell-1RHR-24A-R-ll E-P FW l.69 .062 None --
-12 P-E FW l.70 .062 None --
i o E-T .FW l.74 .060 None- --
g
. 2 Ell-1R.HR-24B-R-10 P-E 'FW 2.58- .060 None --
-11 E-P FW 1.68 .062 . Parallel to weld, Elbow 13% i Side 1-5/8"L, 2-10 9/16"L. 13%
-12 'P-E FW l.70 .062 Shallow indications in --
the RAZ called inside geometry. GPC to re-e:: amine next refueling outage.
-13 Ee cW l.74 .060 None --
. 4 RWCU SYSTEM 2031-1RWCU-6-D-1 BC-P --
1.24 .064 Not Esamined --
-2' P-E --
1.92 .064 None --
j 1
-3 E-P --
1.82 .064 None -- I d
l
-4 P-P- --
1.22 .064 Not Examined --
j
-5 P-E --
1.80 .064- None --
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-6 E-P --
1.98 .064 None -- 1
-7 P-V --
1.63 .064 None --
-8 V-P --
1.58 .064 Not Examined --
-9 P-E --
'1.42 ' .064 Not Examined --
-10 E-P --
1.40 .064 Not Examined --
-11 P-P --
1.02 .064 Not Examined --
-12 P -i; .-- 1. 4 '. .064 Not Examined --
1.46 .064
-13 E-P --
Not Examined --
-14 P-E --
1.34 .064 Not Examined --
-15 E-P --
1.33 .056 Not Examined --
l-i L___________. - - _ _ _ _ _ - _ _ _ _ _ _
1 . E
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. , IIELD SIGNIFICANT 'I l C. e . '11 ELD MO. tJELD TYPE FAB. SRI- '%C
~UiDICATIONS '% THRU-WALL (MAXJ
)
' RUCU SYSTEM (Continued) ~ i
~16 .P-V --
~1.23 .045 Not E:<amined :--
j' . . ,.
}
j/ ^ 17-V-P --
1.31 .063- Not E:<amined --
i;
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-17A. PX-P --
1.30- .063 Not Eiamined -
1
-18 P-V ' -- 1.11- .061 Not E:<amined ,
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iKEY-BT - Field Wald CR - Cross IJ
.'SU - Shop Weld PX - Penetration -
.P' , Pipe. N - Nozzle Fu -' Pump E - Elbow j.
T - Tee SC - Branch Connection q.
' Red Reducer C - Cap V - Valve-
'i E:< ample : Under " Weld Type" column, P-E is the abbreviation for a pipe-to-elbow. -i weld.
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N' STRUCTURAL-INTEGRlTY ASSOCIATES
. 31$0 ALMACEN EXPWYJ SulTE 226 e SAN JOSE. CA 95t18 + (408) 978 8200'
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ASSOCIATES: i
, T L Gtneta i i$AS" P.C. RiccAnocLLA
'CAUSE OF CRACKING INVESTIGATION
. COMPARISON OF HATCH UNIT'2 WITH UNIT 1 ,
.l l
-AREA $ INVESTIGATED i
.e FABRICATION HISTORY .
i e STRESSES - APPLIED AND RESIDUAL- i i
e OPERATING HISTORY
- TIME / CYCLES
- WATER. CHEMISTRY 1
i e INSPECTION RESULTS ]
- CURRENT ISI
- BASELINE RADIOGRAPHY j l
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FABRICATION HISTORY e COUNTERBORE EFFECT e CARBON CONTENT OF PIPE MATERIAL e WELDING, WELD REPAIR, GRINDING -l 4
o FIELD STORAGE RECORDS I
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i . Stainless Steel Pipe Fabrication Information -
FABRI- WELD !
WELD- CATION WELD PROCEDURE FILM
- 4-
,, LINE - SIZE TYPE SHEET NUMBER SPEC. LOCATION
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- B31-1 RC-12 B R-A FW -
B-10 15GE 44194-0060 B31-1RC-12BR-A-2 SW R D-2-B4 8 102 44303-0029 B31-1RC-12BR-A-3 SW RD-2-B4 C 102 44303-0029- i B31-1 RC-12 B R-A-4 FW -
B 16GE 44194-0065
~ B31-1 R C-12 BR- A-5 . Comb. - - - -
, B31-1 R C-12 BR-B-1 FW -
B-11 15GE 44194-0061 >
B21-1RC-12BR-B-2 SW RD-2-B5 B 102 44303-0030 'l
' B31-1 RC-12 BR-B-3 SW RD-2-B5 C 102 44303-0030- 1 B31-1RC-12BR B-4. FW -
B-16 16GE 44194-0066 831-1RC-12BR-B-5 Comr. - - - -
B31-1RC-12BR-C-1 FW -
B-12 15GE 44194-0062 B31-1 R C-1~2 BR-C-2 SW R D-2-B8 B 102 44305-0033 B31-1RC '12BR-C-3 SW RD-2-38 C 102 44303-0030 B31-1 R C-12 B R-C-4 FW -
B-17 16GE 44194-0067&68 B31-1 RC-12 BR -C-5 Comb. - - - -
l B31-1RC-12BR-D-1 FW -
B-13 15G E 44194-0063 B31-1 RC-12 B R-D-2 SW R D-2-B6 B 102 44303-0031.
l 831-1 R C-12 B R-D-3 SW RD-2-B6 C 102 44303-0031 B31-1 RC-12 B R-D-4 FW -
B-18 16GE 44194-0069 B31-1RC-12BR-D-5 Comb. - -
B31-1 RC-12 B R-E-1 FW -
B-14 15G E 44194-0064 B31 1 RC-12BR-E-2 SW RD-2-B7 .B 102 44303-0032 B31-1RC-12BR-E-3 SW RD-2-B7 C 102 44303-0032 B31-1RC-12BR-E-4 FW. -
B-19 16GE 44194-00 0
- B31 -1 RC-12 BR-E-5 ComL - - - -
. ;J l
B31-1 RC-12 A R-F-1 FW -
A-10 15G E 44194-0020 B31 -l h C-12 A R-F-2 SW R D A 4 B 102 44303-0023 i B31 -I RC-12 A R-F-3 SW RD-2-A4 C 102 44303-0023 B31-1 RC-12 AR-F-4 FW -
A-15 16G E 44194-0029 i B31-1 R C-12 AR-F-5 Comb. - - -
831-1 RC-12 A R-G-1 FW -
A il .15 G E 44194-0022
- B31-1 RC-12 A R-G-2 SW R D A5 8 102 44303-0021- j B31 -1 RC-12 A R-G-3 SW R D A 5 C 102 44303-0021 ;
t331-1 R C-12 A R-G-4 FW -
A-1G 16GE 44194-0030 i B31-1 RC-12 A R-G-5 Comb. - - - -
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i JWELD. PREP DESIGNS-FOR HATCH' t c
. RECIRCULAT10N SYSTEM PIPING .
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1 WELD PREP'FOR UNIT 2-SHOP WELDS WELD PREP FOR UNIT. 2 SHOP WELDS
.i (SAW) -(RISER &' DISCHARGE PIPE) (GTAW, SMAW) -(END CAPS),
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- WELD PREP FOR UNIT 1 SHOP WELDS WELD PREP FOR UNIT 1 AN 2 FIELD WELDS
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SUMMARY
OF RECIRCULATION SYSTEM PIPING CARBON CONTENT DATA WELDS IN CATEGORY l HATCH UNIT 1 -.,.
HATCH UNIT 2 RISER M A NIF. SUC/DlS RISER M A NIF. SUC/ DIS ,
j
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<.035
.035 - 0.499 3 10 i
.05- 0.599 6 8 23 2 5 22 l
.06 - 0.699 2 8- 8- 24 8 .12 f
.07 .08 32 14 ,
40 16 31 40 16 34 l
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l WATER CHEMISTRY q
1 e AVERAGE CONDUCTIVITY LOWER IN UNIT 1 THROUGH 1981 I
1 i
e AVERAGE CONDUCTIVITY LOWER IN UNIT 2 IN 13 2 AND 1983 e ONLY MAJOR CHEMICAL TRANSIENT REPORTED IN UNIT 1
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1 Comparison of Baseline Radiography to Current Ultrasonic '
. Results for Unit 2 j
LINE - SIZE . INDICATION - SIZE REMARKS l
I 12 BR A-1 Nothing. Counterbore is 1/4" from -
root on pipe side. Branch i connection has counterbore' i 1" away. No grinding. j ut 1 12 BR A-2 Nothing. No grind!ng. Counterbore 1/4" from root edge of weld.
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12 BR A-3 25% just adjacent to Counterbore 7/16" from root root. Not in counter- J of weld. No grinding. Smooth bore. Low DAC ~40% transition on elbow side. .]
(pipe side). j i
12 BR A-4 Counterbore geometry Minor counterbore 3/8" from !!
(1/2" from weld root), root on pipe side. Smooth on safe end side.
12 BR B-1 Root geometry only. Minor counterbore 3/8" from j root on pipe side. Minor counterbore on branch 9/16" from root.
12 BR B-2 26% on pipe side ~1/S" Counterbore 3/8" on elbow, from root. 1/4" - 5/16" on pipe (no grinding). ]
Gradual counterbore, not sharp transition.
12 BR B-3 22% in pipe side and 21% Counterbore sometimes tapered j on elbow side. 1/16" sometimes sharp 7/16" to 1/4" from weld edge on elbow. from weld on pipe side. Gentle 1/2" from - weld on pipe - taper on elbow side. No grinding.
side. j 12 BR B-4 23% on pipe side. 3/4" Hand prepped. Possible evidence from root of weld. of repair. No real counterbore.
D AC ~85-40%. . No grinding after welding. Trans- .
Ition is in the 3/4" to 1" distance .
from weld root. 1 12 BR C-1 Root geometry only Minor counterbere 3/8" from root on pipe side. No counterbore on branch.
12 BR C-2 28% on pipe. side or 1/4" Counterbore 3/8" - 1/2" on pipe from toot of weld, side; 9/16" on elbow side. More gentle on elbow side. Elbow side may have been hand ground. No post weld grinding.
8 6) )
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Ultrasonic Indications For Each of the Stainless Steel Pipe Systems Number of Indications -
No. of Welds Localtion of Indication *
'l' Shop Field Weld System Welds Welds Root Counterbore HAZ Othert Riser 18/20 4 10 6 4/20 2 2 -!
i Enri Cap" 4/4 1 1 I
- 20"RHR 1/3 1 -
24" RHR 1/8 2 28" Recire (
7/15 1 2 6 ,
1/18 l-1-
i t Outside expected HAZ i
Number of ir.dications may exceed total of welds because of cracking in )
both H AZ's,
- Incomplete data 1
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STRESSES
- i. ~
t e NOMINAL STRESSES COMPARABLE o STRESS CONCENTRATION EFFECT OF COUNTERBORE-RESULTS IN 0,3 TO 0,6 INCREASE IN STRESS RULE INDEX I
e STRESS CYCLES PER YEAR AT TWO UNITS COMPARABLE e IGSCC DAMAGE INDEX RESULTS ON TWO SAMPLE WELDS - UNIT 2 HIGHER AT 4 YEARS THAN UNIT 1 AT 7 YEARS (CONSIDERING EFFECT OF COUNTERBORE) l l
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. _ _ _ _ _ _ - _ _ . - - - _ - _ - - - _ _ - - -- - _a
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SUMMARY
- OF ICSCC STRESS RU.LE INDICES !
FOR RECIRCULATION SYSTEM PIPING r 2
?
y a) Original Data ,
i HATCH UNIT 1 HATCH UNIT 2 SRI RISER M ANIF. . SUCIDIS RISER M ANIF. SUC/ DIS !
< 1.0 4 3 5 4 -1 i
1.0 - 1.2 11 12 15 10 11 17- j 1.2 - 1.5 18 12 21 13 1.5 - 1.8 11 1 9-
> 1.8 ,
1
. 40 - 16 31 40 16 34 j l
b) Adjusted for Counterbore Stress Concentration ;.
HATCH UNIT 1 .l HATCH UNIT 2
M ANIF. SUC/ DIS RISER M A NIF. SUC/ DIS RISER
< 1.0 4 3 5 f 1.0 -- 1.2 11 12 15 10 11 I
1.2 - 1,5 18 12 10 (Later) 1.5 - 1.8 11 1
> 1.8 20 40 16 31 40 16 34 i 11 W ,
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.s, dia ' 1 . SUMM ARY OF- PLANT: OPERATION AL CYCLES.
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- SCRAMS TO- HOT STANDBY ' COLD SHUTDOWNS o
1983: 4 ' 0-rl -
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- 1981 10 -5
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i : :,- q HATCH UNIT 2 -t i .)
> YEAR' S' CRAMS TO HOT STANDBY - - COLD- SHUTDOWNS .
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'1983 0 'I 7- 5 L1982 6 1 1981 12 5. l
.1980-8- 3 l 1979-
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q IGSCC Damage Index for a Relatively Lightly Loaded i High Carbon Riser Weld i a) No stress concentration in HA'Z, KT=1.0, SRI:1.09 1
b)- Stress concentration in HAZ. KT=2.4, SRI:1.44 -/ j
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. t __ _ - -- .____.:___- __ .-_ ___ ___-_____ -_ - __ ______________________,-_____ __
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l FRACTURE MECHANICS ANALYSIS h l 8 ACCEPTANCE CRITERIA BASED'ON ASME CODE SECTION XI, IWB-3640 (APPROVED BY MAIN COMMITTEE) O CRITERIA BASED ON NET SECTION COLLAPSE IHEORY WITH SAME DESIGN MARGINS AS CONSTRUCTIONS CODE I. UPPER bound IGSCC FLAW GROWTH CURVE USED (EPRI NP-2472 AND EPRI 2423-LD) e a
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' FLAW EVALUATION INPUTS j s
INPUT SOURCE WHERE USED -) 1 PRIMARY STRESS STRESS REPORT ALLOWABLE'a/T 1 STEADY STATE APPLIED STRESS REPORT PREDICTED a/T , 4 STRESS ALLOWABLE a/T ! CRACK GROWTH MODEL NDE REPORT PREDICTED a/T i
' CRACK GROWTH LAW EPRI REPORTS: PREDICTED a/T NP-2472.AND NP-2423-LD WELD RESIDUAL STRESS NUTECH STANDARD CURVES PREDICTED a/T (BASED ON SEVERAL EPRI REPORTS) l t
N l. 1
= _ _ _ _ _ _ - .
I
y n 7 i / 6 r 3 j l FLAW EVALUATION METHODOLOGY l i I - 8 SE' LECT' HIGHEST' APPLIED STRESS IN SIZE OF PIPING BEING EVALUATED l 8 USE ASME SECTION XI TABLES OR. SOURCE EQUATIONS TO DETERMINE END OF INSPECTION INTERVAL " ALLOWABLE"
] '
FLAW SIZE-8 DETERMINE FLAW SIZE AT BEGINNING OF CYCLE FROM UI DATA l' DETERMINE CRACK GROWTH USING UPPER BOUND CRACK GROWTH CURVE TO IDENTIFY " CALCULATED" END OF CYCLE FLAW SIZE 8 COMPARE " CALCULATED"'TO " ALLOWABLE"'CRACx' DEPTH AT ENo
/ OF CYCLE TO DETERMINE THE NEED'F0R REPAIR 4
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L PROPOSED TABLE IWB 38411 g
-ALLOWABLE END OF INSPECTION PERIOD !
SIZE FOR' CIRCUMFERENTIAL FLAWS NORMAL CONDITIONS Ratio of Length to Circumference (1) Pm + Pb 0.1 0.2 0.3 0.4. 0.5 or more
*
- Ratio of Flaw Depth toThickness (2) ]
1.5 (3) (3) (3) (3) (3) . 1.4 0.30 0.20 (3) (3) (3) 1.3 0.48 0.38 0.28 0.18 0.18 l 1.2 0.66 -0.56 0.46 0.36 0.26-1.1 0.73 0.63 0.53 0.43 0.33 1.0 0.75 0.70 0.60 0.50 0.40 0.9 0.75 0.75 0.66 0.56 0.46 0.8 0.75 0.75 0.72 0.62 0.52 0.7 0.75 0.75 0.75 0.68 0.58 { 0.6 0.75 0.75 0.75 0.73 0.63 (1) Pm = Primary Membrane Stress f Pb = Primary Bending Stress { Sm = ASME Code Design Stress at Temperature j (2) Crack Depth = a for a Surface Flaw ( 2a for a Subsurface Flaw l (3) IWB 3514 3 Standards Govern
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j. da/dt = 1.843 x 10-12K4.615 i Upper Bound .j / 3 l g .j r3 '30 .- j .f.
, . Lower Bound
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L l: t: f COMPARISON OF EPRI RECOMMENDED AXIAL RESIDUAL STRESS DISTRIBUTION j, AND DISTRIBUTION trt1LI7.ED IN ANALYSIS (t > 1.0 inch) i-I' t ! l EPRI _ _ _ _ _ _ +12 g n _._ l
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FRACTURE MECHANICS ANALYSIS ! FOR LIMITING FLAW SIZE CONCLUSIONS REGARDING NET SECTION COLLAPSE ANALYSIS i 9 NET SECTION COLLAPSE ANALYSIS GIVES CONSERVATIVE PREDICTION OF MARGIN AGAINST CRACK INSTABILITY FOR AUSTEN! TIC STAINLESS STEEL PIPES 8 FIELD DATA VERIFIES THAT PIPE RUPTURE NAS NOT OCCURRED FOR LARGE CRACKS IN STAINLESS STEEL, IN AGREEMENT WITH PREDICTIONS 8 TEARING MODULUS ANALYSIS FOR CIRCUMFERENTIAL CRACKS IN STAINLESS STEEL PIPE SHOWS NET SECTION COLLAPSE CRITERION IS CONSERVATIVE 6: 9 nut.ec
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i' iI f' % li; FLAW EVALUATION METHODOLOGY _ I FOR 12 INCH PIPE 8 SELECT HIGHEST APPLIED STRESS IN SIZE OF PIPING BEING EVALUATED (LOOP A, JOINT 13 - 14.9 KSI, 16.6 KSI S M AT 575'F) I FOR 360* INDICATIONS USE SOURCE EQUATIONS'FOR TABLE IWB-3641-1 (EPRI NP2472SY, VOL. If JULY 1982) O CALCULATE ALLOWABLE END OF CYCLE a/T a/T - .41 (NO CREDIT FOR POTENTIAL OVERLAY THICKNESS ADDED TO T) 0 DETERMINE a/T AT BEGINNING OF CYCLE 9 DETERMINE CRACK GROWTH USING UPPER BOUND CRACK GROWTH CURVE TO IDENTIFY " CALCULATED" END OF CYCLE CRACK DEPTH I COMPARE CALCULATED TO MAXIMUM ALLOWABLE CRACK DEPTH AT END OF CYCLE Q
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I r FLAW EVALUATION METHODOLOGY I' FOR LARGE OIAMETER PIPE 8 SELECT HIGHEST APPLIED STRESS IN SIZE OF PIPING BEING EVALUATED 8 USE TABLE IWB-3641-1 TO CALCULATE ALLOWABLE END OF CYCLE a/T a/T = .63 9 DETERMINE a/T AT BEGINNING OF CYCLE FROM ULTRASONIC DATA 4 DETERMINE CRACK GROWTH USING UPPER BOUND CRACK GROWTH CURVE TO IDENTIFY " CALCULATED" END OF CYCLE CRACK
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9 COMPARE CALCULATED TO MAXIMUM ALLOWABLE CRACK DEPTH AT 1 END OF CYCLE l
p ~ l' ') li FLAW EVALUATION METHODOLOGY l 4 DETERMINE ALLOWABLE CRACK SIZE t CALCULATE CRACK GROWTH 0 COMPARED PREDICTED AND ALLOWABLE CRACK SIZE
$ MAJOR EFFECT OF PIPE DIAMETER IS BUTT WELD AXIAL RESIDUAL STRESS DISTRIBUTION 8 CONCLUSIONS ;
REPAIR OF 12 INCH PIPE FLAWS
- MARGINAL ACCEPTABILITY FOR END CAP WELD FLAWS ACCEPTABLE FOR 24 INCH AND LARGER PIPE FLAWS i
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e e GENERAL CONSIDERATIONS REPAIR RECOMMENDATIONS . i 0 OCCUPATIONAL RADIATION EXPOSURE (MAN REM) 9 IMPACT ON OUTAGE SCHEDULE e REPAIR COST e IGSCC FLAW SIZING CAPABILITIES USING UT METHODS 9 POTENTIAL FOR UNDETECTED AXIAL CRACKS 4 POTENTIAL FOR WELb REPAIR EFFECTS ON NORMAL RESIDUAL STRESS PATTERNS 9 LEAK DETECTION SCHEME
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PRELIMINARY DESIGN OF OVERLAY REPAIR 0 DETERMINE RESIDUAL STRESS PATTERN OF WELD GEOMETRY WITH OVERLAY
- RESIDUAL STRESS PATTERN CALCULATED AT SMALL WELD OVERLAY INCREMENTS
- HATCH 2 OVERLAYS COMPARED WITH THOSE FOR DRESDEN 2 AND VERMONT YANKEE FOR CONSISTENCY 0 CALCULATE CRACK GROWTH WITH OVERLAY IN PLACE
- CRACK GROWTM WOULD BE VERY SMALL l
- FOR SIZING IT WAS ASSUMED THAT a/t WOULD INCREASE BY 0.1. WITH THIS ASSUMPTI0tl FOR 360 0 INDICATIONS, AN a/t OF .31 IS THE BREAK POINT FOR MINI VS.
STANDARD (GREATER THAN .31 SHOULD HAVE STANDARD OVERLAY TO ATTAIN ADDITIONAL STRUCTURAL CAPABILITY). O 1 l
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) l TECHNICAL BASIS FOR STANDARD OVERLAY DESIGN O AVERLAY APPLIED AS STRUCTURAL REINFORCEMENT TO RESTORE ORIGINAL PIPE SAFETY MARGINS IN ACCORDANCE WITH IWB-3640 0 IGSCC RESISTANT WELD METAL PROVIDES ULTIMATE b BARRIER TO FURTHER CRACK PROPAGATION O REDUCTION IN CRACK GROWTH IN ORIGINAL MATERIAL DUE TO FAVORABLE RESIDUA'L STRESS PATTERN
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TECHNICAL BASIS FOR MINI-0VERLAY DESIGN ; O FLAW INDICATION IN WELD IS ACCEPTABLE AS-IS, l BUT CRACK PROPAGATION TO UNACCEPTABLE SIZE l EXPECTED DURING INSPECTION INTERVAL e OVERLAY APPLIED ONLY TO PRODUCE FAVORABLE RESIDUAL STRESS PATTERN AND THUS ARREST FURTHER CRACK PROPAGATION, NOT FOR STRUCTURAL REINFORCEMENT
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L r 3 1 E WELD OVERLAY TEST-SERIES 8 A SERIES OF FULL SCALE MOCK-UP TESTS ON 12" PIPE O THEY INCLUDE THE FOLLOWING TESTS:
- 1) QUALIFICATION OF LAST PASS HEAT SINK WELD
- 2) TEST OF A " MINI" OVERLAY
- 3) TEST OF VARIOUS THICKNESS OVERLAYS J
e ALL TISTS WILL EMPLOY CURRENTLY PROVEN WELDING PROCEDURES AND PARAMETERS S SELECTED TESTS WILL HAVE THERMOCOUPLE AND/OR STRAIN
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MEASUREMENTS 9 TEST RESULTS WILL BE USED TO SUBSTANTIATE ANALYTICAL PREDICTIONS
W u .- RESIDUAL STRESS ANALYSIS )i OVERLAY APPLIED TO CRACKED PIPE WELD ; PROCEDURE 1 8 " WELDS" ANALYSIS'0F 12" SCH. 80 BUTT WELD TO GIVE RESIDUAL STRESS PATTERN. i 0 9 INTRODUCED 40% X 360 CRACK INTO ABOVE CASE -- STRESSES ALLOWED TO REDISTRIBUTE.' 0 " WELDS" ANALYSIS PERFORMED ON BOTH CRACKED AND UNCRACKED CASES WITH HATCH STANDARD OVERLAY. S RESULTED IN 4 RESIDUAL STRESS PATTERNS
- STD. BUTT WELD (A)
STD. BUTT WELD W/ CRACK (B)
- STO. BUTT WELD + OVERLAY (C)
- STD. BUTT WELD W/ CRACK + OVERLAY (D)
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I 9 RESULTS CRACK STRESS INTENSITY PATTERN KS I \/ I N A 48 B 34 C -39 D -20 0 RESIDUAL STRESS PATTERNS FOR CASES C AND D VERY SIMILAR -- ONLY DIFFERENCE IS AT FREE SURFACE OF CRACK 4 WELDS -ANALYS IS- PERFORMED FOR ' IHSI - 0F PRECRACKED
- PIPE SHOWS ESSENTIALLY NO CHANGE IN RESIDUAL STRESS PATTERN FROM THAT DETERMINED FOR UNCRACKED PIPE.
CONCLUSION 0 e OVERLAY PRODUCES COMPRESSIVE STRESSES IN 360 CRACKED PIPE. I l l ! I y b I
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I ( ) \ RECIRC AND RHR SYSTEM EFFECTS j j 0 STEADY STATE SECONDARY STRESS : i
- NO ASME CODE LIMIT i
- SIMILAR TO COLD SPRING AND OTHER WELDS 0 STRESS IS CALCULATED WITH PIPING MODEL IMPOSED DISPLACEMENTS ;
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- ACTUAL MEASURED SHRINKAGE 9 CALCULATED STRESS
- LOW HEAT INPUT; LOW SHRINKAGE
- BRUNSWICK HIGHEST STRESS 4. KSI M
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, SAMPLE CALCULATION:
- APPLY AN OVERLAY ON ALL 2, 3 AND 4 WELDS IN THE 12" RIZER-PIPING ASSUMPTIONS:
- HATCH UNIT 1 AND 2 SYSTEM STRESSES ARE THE SAME
- AXIAL WELD SHRINKAGE AT ALL OVERLAYS IS 0.0625" (BASED ON AVERAGE OF ACTUAL SHRINKAGES MEASURED AT BRUNSWICK)
RESULTS:
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- MAXIMUM STRESS 1.7 KSI
- JUNCTION OF END RIZER ON HEADER k n d l
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j i L- FUTURE INSPECTIONS l CONTINGENT UPON RADIATION LEVELS, THE FOLLOWING WELDS WILL BE EXAMINED OURING THE NEXT SCHEDULED MAINTENANCE /REFUELI?lG OUTAGE:
$ THE SIX (6) REMAINI?tG ASME CATEGORY B-F WELDS IN THE RECIRCULATION SYSTEM THAT WERE fl0T EXAMINED DURING THE 1983 MAINTENANCE /REFUELIf!G OUTAGE l' THE T,4EllTY-SIX (26) OVERLAY REPAIRED WELDS IN THE RECIRCULATION SYSTEM 4 THE ilINE (9) RECIRCULATION SYSTEM A:10 THREE (3) RHR SYSTEM WELDS HAVING INDICATIONS WHICH WERE NOT REPAIRED 9 .THE NINETEEN (19) WELDS HAVING INDICATIONS NOT INDICATIVE OF IGSCC OR NOT LOCATED IN THE HAZ 4 OtlE HUNDRED PERCENT (100k) 0F THE REMAINIflG STAINLESS STEEL RHR SYSTEM WELDS 1
9 FIFiY PERCENT (50%) 0F THE REMAINING 12" AilD 28" RECIRCULATION SYSTEM WELDS STAIflLESS STEEL WELDS IN OTHER SYSTEMS WILL BE EXAMINED IN ACCORDANCE WITH GUIDANCE OF ilUREG-0313, REV.1 AND GPC LETTER OF JUNE 29, 1981 i l ' l l l l
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FUTURE MODIFICATIONS / REPLACEMENTS l
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8 MODIFICATIONS AND/OR REPLACEMENTS ARE UNDER CONSIDERATION, { NO FIRM PLANS HAVE BEEN MADE j 8 BECAUSE NONCONFORMING MATERIAL IS UTILIZED AT HATCH UNIT 2, CPC HAS COMMITTED TO PERFORM ALGbENTED INSERVICE INSPECTION PER NUREG-0313, REV 1 GUIDANCE AS DISCUSSED IN THE GPC LETTER DATED JUNE 29, 1981 e WHEN REPLACEMENT IS REQUIRED, GPC WILL USE CONFORMING MATERIAL j AND PROCESSES IN ACCORDANCE WITH NUREG-0313, REV 1 GUIDANCE AS q DISCUSSED IN THE GPC LETTER DATED JUNE 29, 1981 l I 8 GPC FOR W D A TASK FORCE TO ADDRESS IGSCC AT THE TWO HATCH UNITS; THE TASK FORCE IS INVESTIGATING ALL AVAILABLE COUNTERE ASURES TO l IGSCC AND WILL RECOMNEND A SOLUTION FOR THE HATCH STAINLESS STEEL PIPE CRACKING PROBLEMS I i
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~. 3 LIST OF ATTENDEES Name Organization J. A. Edwards Georgia Power Company Len T. Gucwa Georgia Power Company Max Manry Georgia Power Company C. Y. Cheng NRC/MTEB P. C. Riccardella Structural Integrity A. J. Giannuzzi Structural Integrity M. R. Hum NRC/MTEB George Johnson NRC/MTEB W. H. Koo NRC/MTEB J. E. Charnley NUTECH J. E. Wilson TVA G. J. Pitz1 TVA Arthur Busiik NRC/RRAB Doug McCusker Georgia Power Company R. K. Godby Georgia Power Company Dick Clark NRC/0RB#2 Davis Ptcairn NUTECH J. M.rk Dvais Southern Company Services James M. Agold Southern Company Services M. Bel ford Southern Company Services Frank Witt NRC/CMEB B. R. Crowley NRC/R:II . A. P. Herdt NRC/R:II G. W. Rivenbark NRC/DL B. D. Liaw NRC/MTEB W. S. Hazel ton NRC/MTEB l
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