ML20100K835
| ML20100K835 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/05/1984 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| NLS-84-502, NUDOCS 8412110304 | |
| Download: ML20100K835 (13) | |
Text
U 1.
y Carolina Power & Light Company SERIAL: NLS-84-502 DEC 0 51984 Director of Nuclear Reactor Regulation Attention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing
. United States. Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT UNIT 1 DOCKET NO. 50-325 - LICENSE NO. DPR-71 IGSCC INSPECTION RESULTS
Dear Mr. Vassallo:
By letter dated October 9, _1984 (Serial No. NLS-84-436), Carolina Power. &
i Light Company (CP&L) apprised you of the Company's plans for. performing i
inspections for IGSCC on Brunswick Unit 1 during the November 1984 outage.
The inspections described in that letter have been completed. This report contains the results of the UT inspections of ASME Code Class I stainless steel weld joints 4" and. greater. It also describes the corrective actions taken and provides a basis for continued operation of Unit I until the refueling outage presently scheduled to begin on March 31, 1985.
Inspection Program t
UT ' inspections were performed by General Electric Company (GE). Examination teams were divided into a master / slave arrangement. The master-directing the examination was_ located outside-the drywell and communicated with the slave
-with headsets. Both slave and master were.provided with duplicate oscilloscope displays. The slave performed the actual scanning under the direction of the master.
The " masters" were Level II or Level III personnel qualified per IEB 83-02 and graduates of-the 40-hour EPRI course on IGSCC which was under the review of an NRC representative. The " slaves" were Level I/II personnel qualified per IEB 83-02 (except for the length of cracked pipe on which the proficiency demonstration was performed which was limited by the availability of cracked opecimens). 'The Level II slaves who were graduates of the 40-hour EPRI course on IGSCC were deemed qualified to scan without further demonstration. Other Level I/II slaves were required to demonstrate scanning ability on a Nine-Mile Point Plant pipe sample containing known areas of IGSCC. Sizing was performed by Level III inspectors who had successfully completed the EPRI sizing course.
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. Details of.the methods used for the ultrasonic inspections are listed below:
. Calibration was establishedjfrom calibration holes only. This provides, higher sensitivity than using calibration notches.
Scanning' sensitivity. was a minimum of 6 d3,above calibration or
^
sufficient gain to present a 10 to 20 percent noise level.
Scanning speed was sufficiently slow to ensure careful observation of the reflected ultrasonic signals.- In no case was it permitted to exceed 3"/second.
.A scanning overlap of 50 percent for each~ successive scan was used in lieu of the~ code-required 10 percent overlap.
Applicable welds were examined from six directions--two perpendicular,
-~
four parallel. Additionally, during the scans, the search unit was oscillated i 30*.
The pipe-to-pipe and pipe-to-elbow welds were examined from both sides. Other welds were accessible for examination from one-
. side only.
Inspections were performed using a single-element, 2.25 MHz transducer ~
and a Krautkramer-Branson USIP-11 ultrasonic flaw detector.
Relevant reflectors originating in RAZ or base metal were-recorded regardless of amplitude.
The IGSCC sizing was performed by EPRI-qualified. Level III personnel using a Krautkramer-Branson USK-7 ultrasonic flaw detector along with specially-designed transducers and wedges. The transducers used were 5.0 MHz, broad.
band, and highly. damped (on the' order of 1.5 cycles). The wedges used were Jone or.nore of the following angles:
45' shear, 50' refracted longitudinal, 52' shear, and a 70* refracted longitudinal which was used for either : the -70-70 or 70* " creeping wave" technique.
The sizing methods used were those taught ~at EPRI and are considered to be
" state-of-the-art".
These methods include the Satellite Pulse Observation
' Technique (SPOT), Pulse Arrival Time Technique (PATT), dB drop method,:and 70*
~
creeping wave technique.. One or more of the preceding methods were used for-sizing, and a description of the specific method (s) used is recorded on the examination / evaluation data sheet for each indication.
IGSCC indications that were detected are listed in Table 1.
Those welds that were accessible for UT inspection from one side only are also listed in Table 2.
'For the purposes of recording data, the weld centerline was determined to be the midpoint of the weld cap. This provided a repeatable reference point for successive examinations. The Level III inspectors who evaluated the data
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Mr.LD. B. V wamilo.
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-adjusted the transducer. position relative to the centerline for the plotting if the: radiographs' revealed an offset weld cap..In addition, where'
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i indications were recorded, a' weld crown profile'was taken and thickness:
readings taken in five locations'in the indication area (i.e., the base metali away from the weld, the base metal adjacent to the weld. crown on both sides, and on the. weld crown centerline).
The~ indications'were plotted using the UTfdata, thickness measurements, weld crown ' profile, and radiographs to determine the crack. location..-The ICSCC
. indications were sized by a Level III, EPRI-qualified sizer. using the various t'echniques taught in the EPRI courses..
The three weld joints listed below were found'during'the current inspections-Jto contain IGSCC' indications-which were not detected'during the inspections performed in January 1983 by Southwest Research Institute (SWRI).
1-B3 2-RE CIRC-12"-AR-A4
. SWRI-identified no recordable indications. - GE only identified the IGSCC indication which was in a weld repair area.
1-B32-RE CIRC-12"-AR-B4 SWRI identified a discrete, nonrelevant ' indication between 8" and 9" circumferentially, with a maximum amplitude of 125 percent DAC. This was identified as a root geometry condition.' GE identified IG3CC at 34.75" circumferentially and a discrete 100% DAC indication at 24" circumferential1y. After reviewing the radiographs and employing-crack tip diff raction techniques, it was determined to be a localized root geometry condition.
1-B32-RECIRC-12"-BR-F4 SWRI identified no recordable indications from the pipe side.' GE identified two areas containing IGSCC.
The differences between the SWRI and GE results can be largely attributed to the greater sensitivity of the GE calibration and scanning techniques. SWRI established reference sensitivity using the 1/2 T-hole for calibration and scanned at 6 dB.
GE established reference sensitivity.using the 3/4 T-hole and also a separate DAC for scanning at 1 1/2 V-path.
In two of the three welds, GE scanned at +10 dB over reference. The GE scanning was performed with more sensitivity than the SWRI by a factor-of two.
In addition, the
- IGSCC was located near areas of root or counterbore geometry.
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Mr. D. B. Vassallo '
Disposition of Indications A flawed pipe analysis was performed in accordance with ASME Code,Section XI, Article lWB-3640, for weld joint 1-B3 2-RE CIRC-28"-B 12.
The overlay repair The designs are based on through-wall cracks with the measured lengths.
design thicknesses are adequate to satisfy Article IWB-3640. The design and installation of the overlay repairs were performed in accordance with Generic Letter 84-11.
Tables 3, 4, and 5 provide summary information on the design of overlays.
As indicated in Table 1, a total of 11 welds required weld overlay.
During the overlay process, stainless steel overlay material was inadvertently applied on top of the Inconel safe-end extension to safe-end weld on the A4 and B4 weld overlays. This was detected by liquid penetrant examination of the first overlay layer. The stainless steel weld overlay was removed by controlled machining, and the base material received a liquid penetrant examination to confirm removal of the cracking. The area was etched to confirm removal of stainless steel material and establish the location of the edge of the inconel weld. The excavated area was weld-repaired with Inconel, followed by a liquid penetrant examination. The stainlese steel overlay was then completed using a modified design which maintained a minimum required distance from the Inconel weld repair material.
Two piping spool pieces were replaced with 316 Nuclear Grade material as shown in Figure 1.
Removal of the exterior spool piece allowed inspection of the containment penetration interior weld which was not previously accessible.
A liquid penetrant inspection was performed on this weld and revealed indications. The joint was repaired by an overlay applied to the inside diameter of the pipe.
Weepage was discovered on the 1-B32-RECIRC-4"-A10 weld joint which is located on the recirculation pump discharge valve bypass line. The pinhole was located on the weldolet. side of the weld. This weld is not inspectable by means of UT due to the geom'etry of the weldolet. The indication was excavated and weld-repaired, followed by a liquid penetrant inspection. The weld joint was subsequently repaired by weld overlay.
Additionally, weld joints 1-G31-RWCU-6"-7 and 1-G31-RWCU-6"-10 had weld blowouts. Weld joint 1-G31-RWCU-6"-7 also had a linear indication which was weeping and detected prior to initiation of weld overlay. The linear indication did not appear to have the characteristics typical of IGSCC. The location of the indication was not coincident with the location of the IGSCC indication. The area was excavated and weld-repaired, followed by a liquid penetrant examination. Three other blowouts on 1-G31-RWCU-6"-7 were observed during the overlay process. They were in locations where there were no recordable indications. The blowout on 1-G31-RWCU-6"-10 was not in a location of IGSCC indications, nor in a location of other recordable indications.
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Mr. D,:B. Vncasilo.
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' Overlay examinations were performed in accordance with Article 5 of ASME Section V.and included PT, and UT examinations. For UT, as a minimum, 0* and 45* examinations were performed. Calibration for the O' examination was-established by setting the response from the 1/16" diameter end-drilled hole 3
- at the clad interface to 50 percent full screen height. To meet ALARA objectives, >this : examination served for both the weld overlay integrity and bond examinations. Additionally, a 45* shear wave transducer was calibrated by adjusting the response from the 1/16" diameter end-drilled ' hole at the clad interface to 80 percent full screen height and the overlay was scanned in four directions. An attempt to scan Section XI examination volume was performed using a 45' shear wave-transducer._ Calibration'for this examination was made by adjusting the response from an axial machined ID notch in the overlay calibration standard to 80 percent full screen height.
Due to the low signal-to-noise ratio, low-level' indications were not seen. _The acceptance criteria of Section III, Article NB-5000 was used.
^ On the first ultrasonic test on the overlay for weld 1-B22-RECIRC-12"-AR-B4, a lack of fusion indication was detected in the first layer of the overlay. The indication was detected using a 0*, dual-element transducer. The indication was 2.375" long and approximately 0.2" wide with.a maximum amplitude of 100 percent DAC. This was evaluated by NUTECH Engineers and found to be acceptable. The videotape of the welding process was reviewed and no cause-for the abnormality was identified.
A hydrostatic test in accordance with ASME Section XI has been performed successfully on the isolatable RWCU piping. The 1-B32-RECIRC-4"-A10 joint cannot be isolated from the reactor; therefore, an in-service leak test will be performed at normal operating -pressure and temperature. The in-service leak test pressure is approximately 20 psi less than the hydrcstatic test pressure at operating temperature. The small difference in test pressures and the nondestructive examination performed on the overlays will give adequate assurance of the integrity of the overlays.
Compensatory Actions The following special surveillance measures have been implemented at the Brunswick plant:
1.
Plant shutdown shall be initiated for inspection and corrective action shall be taken when any leakage detection system 8.ndicates, within any period of 24' hours, an increase in the rate of unidentified leakage in excess of 2 gpm or its equivalent, whichever occurs first. For sump level monitoring systems with fixed-measurement interval method, the level shall be monitored at 4-hour intervals or less.
l 2.
At least one of the leakage measurement instruments associated with each sump shall be operable, and the outage time for inoperable instruments shall be limited to' 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or an orderly shutdown will be immediately initiated.
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,Mr. D. B. Vtcoollo~
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- 3. -
A visual examination for leakage of the reactor coolant piping shall be performed during each plant outage in which the containment is deinerted.
l,
-if such an inspection has not been made in the previous 9:2 days.. The examination shall be performed consistent with the requirements of IWA-5241 and IWA-5242 of the 1980 Edition of Section XI of the ASME Boiler and Pressure Vessel Code.. The system boundary. subject to this i
examination sha11'contain the susceptible welds inside the primary containment.
.These special surveillance measures are consistent with those given in
, to Generic Letter 84-11 and with CP&L's ALARA program.
Conclusion Carolina Power & Light Company has completed inspections of ASME Code Class l e stainless steel weld joints 4" and greater in diameter. For those welds found' i
to contain IGSCC, a conservative analysis has been nerformed to determine appropriate corrective action. ' Repairs have been completed on 11 affected welds, _ and an analysis on the remaining weld with IGSCC shows that it will remain structurally sound until the next planned outage. In addition.
existing stringent leak detection surveillance measures will remain in effect at Brunswick. Since 1) coeprehensive inspections have been performed on
[
susceptible piping, 2) conservative repairs and analyses were performed on I
welds containing IGSCC indications, and 3) enhanced surveillance requirements
-for drywell leakage detection will remain in effect, CP&L believes that start-up and. continued operation of Brunswick Unit I until. March 31, 1985 is justified and will not adversely affect the health and safety of the public.
Details of the weld overlay designs and our plans for future disposition of.
the unrepaired indication will be submitted prior to the next Brunswick Unit 1 outage. Should you have any questions regarding this submittal, please-contact Mr. S. R. Zimmerman at (919) 836-6242.
i Yours very truly, t
~C7,;;. ;-. 1--
t gq,A. B.
er - Vice' President Nuclear Engineering & Licensing ABC/JSD/af (914JSD) 4:
1 Enclosures cc:
Mr. D. O. Myers (NRC-BNP)
Mr. J. P. O'Reilly (NRC-RII)
Mr. M. Grotenhuis (NRC) r
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' TABLE 1 BRUNSWICd UNIT 1 IGSCC INDICATION SLMMARY._
Ti440VGH-LOCAT10N SIDE-WELD NO.'
ORIENTATION LENGTH WALL DEPTH FROM REF.-
0F WELD DISPOSITION 1-G31-RWCU-6"-4 Circumferential 1.25" 10 Percent 13.1" Elbow Repair 1-G314tWCU-6" - Circumferential.
2.75" 31 Percert 14.0"
' Elbow Repair.
I-G31-RWCU-6"-7 Circumferential 3.0"4 81 Percent 16.5" Elbow Repair 1-G31-RWCU-6"-8 Circumferential 1.125" 23 Percent 6.25" Pipe Repair Circumferential 1.125" 19 Percent 4.875"
. Elbow Repale I-G314tWCU-6"-10 Circumferential 2.75" 14 Percent 8.25" Elbow Repair.
1-G31-RWCU-6" Circumferential 4.25" 24 Percent
,8.0" Pipe Replaced Circumferential 5.0" 27 Percert 7,4.0" Elbow Replaced 1-G31-RWCU-6"-16 Circumferential 2.375" 16 Percent 13.0" Upstream Replaced Pipe
.1-G31-RWCU-6"-17 Circumferentf al/Axlal
-1.1" 35 Percert 0.6" Elbow Replaced Circumferential 1.0" 40 Percent 13.5" Elbow Replaced 1-G31-RWCU-6"-19 '
Circumferential 0.4" 12 Percert 17.4" Elbow Replaced Circumferential 0.375" 18 Percent 15.7" Elbow Replaced 1-832-REC lRC-12"-AR-A4 Circumferential 1.6" 19 Percert 30.2" Pipe Repair 1-832-REC lRC-12"-AR-82 Circumferential 2.0" 20 Percent 25.5" Pipe Repair I-832-REC lRC-12"-AR-84 Circumferential 1.0" 45 Percert 34.75" Pipe Repair 1-032-RECIRC-12"-BR-F4 Circumferential 0.5" 23 Percent 3"
Pipe Repair Circumferential 4.0" 9 Percert 20.0" Pipe
' Repair 1-832-RECIRC-28"-B-12
-Circumferential 2.5" 10 Percent 23.0" Pipe Flawed Pipe Analysis 1-G31-RWCU-PENETR-X14 Circumferential 2.0" N/A 0
Pipe Repair Circumferential 5.5" N/A 0
Pipe Repa le I-832-REC IRC-4"-A 10 Pinhole Leak 0.06" 100 Percert 0.5" From TDC Weldolet Repair' Round (914JSD/mf)
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+1 TABLE 2 :
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~ BRUNSWICK 1 WEI.DS ' ACCESSIBIE FROM ONE SIDE ONLY
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WELD NO. '
. TYPE:
i 1-B32-RECIRC-28"-A-2 Pipe to Safe-end*
Elbow to Valve 1-832-RECIRC-28"-A-8 r
1-832-RECIRC-28"-A-9
. Valve to Pipe.
'l-832-RECIRC-28"-A-9BC -
Branch Connection _
1-B32-RECIRC-28"-A-11 '
Elbow to Pump.
' l-B3 2-RE CIRC-28"- A-12 Pump'to Pipe
' l-B32-RECIRC-28"-A-12BC Br'anch Connection 1-B32-RECIRC-28"-A-13 Pipe to' Valve 1-B32-RECIRC-28"-A-15BC Branch. Connection 1-B32-RECIRC-28"-B-2 Pipe to Safe-end*
11-B32-RE CIRC-28"-B-9 Valve to Pipe 1-B32-RECIRC-28"-B-9BC Branch Connection 1-B32-RECIRC-28"-B-11 Elbow to Pump 1-B32-RECIRC-28"-B-12 Pump to Pipe
~~
1-B32-RECIRC-28"-B-12BC Branch Connection 1-B32-RECIRC-28"-B-13 Pipe to Valve 1-B32-RECIRC-28"-B-14 Valve to Elbow 1-532-RECIRC-28"-B-15BC Branch Connection 1-B3 2-RECIRC-28"-B Tee to Cross 1-B3 2-RE CIRC-22"-AM-1 Valve to Pipe 1-B32-RECIRC-22"-AM-2 Valve to Pipe 1-832-RECIRC-22"-AM-3 Pipe to Valve 1-B32-RECIRC-22"-AM-3BCA
- Branch Connection 1-B32-RECIRC-22"-AM-3BCB Branch Connection
' l-B32-RECIRC-22"-ANF4
-Cross to Pipe 1-B32-RE CIRC-22"-AM-5 Cross to Pipe 1-B32-RECIRC-22"-AM 5BCA
- Branch Connection 1-B32-RECIRC-22"-AM-5BCB
. Branch Connection 1-832-RECIRC-22"-BM-1BCA Branch. connection
> 1-B3 2-RE CIRC-22"-BM-1 BCB Branch Connection 1-B32-RECIRC-22"-BM-2 Cross to Pipe 1-B32-RECIRC-22"-BM-3 Cross to Pipe pNC
.1-B32-RECIRC-22"-BM-3BC Branch Connection-1-B32-RECIRC-22"-BM-4BC Branch Connection 1-B32-RE CIRC-22"-BM-5 Pipe to Valve -
~
b 1-B32-RECIRC-12"-AR-Al Sweepolet to Pipe t
1-B32-RECIRC-12"-AR-A4 Pipe to Safe-end Extension
- g 1-B32-RECIRC-12"-AR-B1
- Sweepolet to Pipe 1-B32-RECIRC-12"-AR-B4 Pipe to' Safe-end Extension *
<l-1-B32-RECIRC-12"-AR-C1 Reducer to Pipe
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1-B3 2-RECIRC-12"-AR-C4 Pipe to Safe-end Extension
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- Conforming Material (914JSD/mf) -
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TABLE 2 (Cont'd)
BRUNSWICK 1 WELDS ACCESSIBLE FROM ONE SIDE ONLY WELD NO.
TYPE 1-B3 2-RE CIRC-12"-AR-D1 Sweepolet to Pipe 1-B32-RE CIRC-12"- AR-D4 Pipe to Safe-end Extension
- l-B32-RECIRC-12"-AR-E l Sweepolet to Pipe 1-B'
?ECIRC-12"-AR-E4 Pipe to Safe-end Extension
- l-B3 2-RECIRC-12"-B R-F1 Sweepolet to Pipe
' l-B32-RE CIRC-12"-BR-F4 Pipe to Safe-end Extension
- 1-B3 2-RE CIRC-12"-B R-G1 Sweepolet to Pipe 1-B3 2-RE CIRC-12"-BR-G4 Pipe to Safe-end Extension
- l-B3 2-RE CIRC-12"-BR-H1 Reducer to Pipe 1-B32-RE CIRC-12"-BR-H4 Pipe to Safe-end Extension
- 1-B3 2-RE CIRC-12"-B R-J 1 Sweepolet to Pipe 1-B32-RE CIRC-12"-BR-J4 Pipe to Safe-end Extension
- 1-B32-RECIRC-12"-B R-K 1 Sweepolet to Pipe 1-B32-RE CIRC-12"-BR-K4 Pipe to Safe-end Extension
- l-B32-RECIRC-4"-BYPASS-Al Weldolet to Pipe 1-B32-RECIRC-4"-BYPASS-A10 Pipe to Weldolet 1-B3 2-RECIRC-4"-BYPASS-B1 Weldolet to Pipe 1-B3 2-RE CIRC-4"-BYPASS-B10 Pipe to Weldolet 1-E l l-RHR-24"-A-DIS CHARGE-12 Valve to Tee 1-Ell-RHR-24"-B-DISCHARGE-13 Valve to Tee 1-E l l-RHR-20"-A-SUCTIO N-1 Tee to Pipe 1-Ell-RHR-20"-A-SUCTION-1BC Pipe to Weldolet 1-Ell-RHR-20"-A-SUCTION-2 Pipe to Valve 1-G31-RWCU-6"-SUCTION-1 Weldolet to Pipe 1-G31-RWCU-6"-SUCTION-2 Pipe to Valve 1-G31-RWCU-6"-SUCTION-3 Valve to Pipe 1-G31-RWCU-6"-SUCTION-12 Pipe to Valve 1-G31-RWCU-6"-SUCTION-13 Valve to Pipe 1-C31-RWCU-6"-SUCTION-16 Pipe to Penetration 1-G31-RWCU-6"-SUCTION-17 Pipe to Penetration
~
1-G31-RWCU-6"-SUCTION-19 Pipe to Valve 1-G31-RWCU-4"-DISCHARGE-2 Valve to Pipe 1-G31-RWCU-4"-DISCHARGE-3 Pipe to Valve Inconci Butter Examination 1-B3 2-RE CIRC-28"-Al Nozzle to rafe-end*
l-B3 2-RECIRC-12"- AR-E6 Safe-end to Nozzle 1-B3 2-RE CIRC-12"-BR-J 6 Safe-end to Nozzle 1-Bil-JPI-N8A Nozzle to Safe-end*
- Conforming Material (914JSD/mf)
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TABUE 3 i
BRUNSWICK 1-
SUMMARY
OF TOTAL STRESSES g
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MAXIMUM STRESS (PSI)
TOTAL STRESS (PSQ DEAD CRACK WOL'
' WELD ID WEIGHT THERMAL -SEISMIC PRESSURE GROWTH DESIGN 1-B32-RECIRC-12"-AR-A4 -
311-4494 3823 7015 11820-11149 1-B32-RECIRC-12"-AR-84 591 14745 3108 7015 12351 10714 1-B32-RECIRC-12"-AR-B2 409 3235 1985 7015 10659 9409 1-B32-RECIRC-12"-BR-F4
-323 2250 1534 7015 9588 8872 1-B32-RECIRC-28"-B-12 868 870 3053 6928 8666 10849 1-G31-RWCU-PENETR-X14 2159 10310 6495 4000 16469 12654 i
1-G31-RWCU-6"-10 561 2483 3322 4000 7044 7883 1-G31-RWCU-6"-8 366 4954 3560 4009 9320
'7926 1-G31-RWCU-6"-7 593 3718 913 4000 8311 5506 1-G31-RWCU-6"-6 483 3318 1074 4000 7801 5557-1-G31-RWCU-6"-4 572 2537 1837 4000 7109 6409 t
L (914JSD/mf) i L-
L
. TABLE 4 BRUNSWICK 1 OVERALY DESIGN THICKNESS VS AS-BUILD THICKNESS WELD #'
OVERLAY DESIGN THICKNESS OVERLAY AS-BUILT THICKNE,SS_-
- 1-832-RECIRC-12"-BR-F4 0.19~
0.290 1-G31-RWCU-6"-8 0.185 0.189 1-G31-RWCU-6"-6 0.18 0.473 1-G31-RWCU-6'-10
.0.17 0.215 1-B32-RECIRC-12"-AR-A4 0.19 0.351 1-B32-RECIRC-12"-AR-B4 0.19 0.262 1-B32-RECIRC-12"-AR-B2 0.19 0.205 j.
'l-G31-RWCU-6"-7
'O.17 0.252 1-G31-RWCU-6" 0.16 0.217 1-G32-RWCU-PENETR-X14 0.25
'NA MIN 1
L (914JSD/mf)
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TAB' E 5 BRUNSWICK 1 WELD SHRINKAGE DATA-WELD NO.
SHRINKAGE 1-G31-RWCU-6"-4.
0.1755" 1-G31-RWCU-6"-6
~
0.219" i
1-G31-RWCU-6"-7 0.306" 1-G31-RWCU-6"-8 0.205" 1-G31-RWCU-6"-10 0.231" 1-532-RECIRC-AR-A4 0.1755" 4
1-B32-RECIRC-AR-B2 0.248" 1-B32-RECIRC-AR-B4-0.106" 1-832-RECIRC-BR-F4 0.093" 1
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(914JSD/mf)
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