ML20211A163
| ML20211A163 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/30/1986 |
| From: | Covill D, Croneberger D, Miller R, Ostrowski R, Tira Patterson GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20211A156 | List: |
| References | |
| 2631H, GL-84-11, TR-039, TR-039-R00, TR-39, TR-39-R, NUDOCS 8610150007 | |
| Download: ML20211A163 (26) | |
Text
.
0YSTER CREEK CYCLE 11R OITTAGE IGSCC ACTIVITIES TR-039 Rev. O AlmiORS s
9 Z Z - 8/.
D. Covill - E4]/ME
&' f-9$-86 R.Oftrowski-SPP APPROVALS M
R. L. Miller - Materials Eng. Mgr.
h 77P 9-93 86 T.
. Patterson - Mgr. Spec. Proc. 4 Programs 0-Y~06 l
M p
D. K.eCroneber r - Director Eng. 4 Design 2
A w-n R'
Keatdn - Director Quslity Assurance I
h.ar i hhl R. F. Wilson'- Director Technidal Functions (Significant Impact Review)
Gy01$pokk
') p )k P
263111
V TR-039 Rev. O Page 2 ABSTRACT This report describes the Cycle 11R outage activities related to the BWR IGSCC issue. We examined 151 butt welds in the Recirculation, Shutdown Cooling, Reactor Water Cleanup, Core Spray, and Isolation Condenser systems and 18 structural weld overlays in the Isolation Condenser system outside the drywell for IGSCC. Four butt welds contained indications with the characteristics of IGSCC. Three (two Recirculation system and one in the Isolation Condenser system outside the drywell) required weld overlay repair; one Recirculation system weld was analyzed and found to be acceptable for continued operation without repair. The existing 18 overlaid welds in the Isolation Condenser system contained no indications of IGSCC in the overlays or outer 25% of the original pipe wall.
IHSI was effectively applied to 64 Recirculation system welds. All were examined for-IGSCC after IHSI.
l l
I i
l 2631H l
TR-039 Rev. O Page 3
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TABLE OF CONTENTS PAGE 1.0 Introduction 1
2.0 IGSCC Examinations and Results 6
3.0 Disposition of Weldments Containing IGSCC Indications 9
4.0 Induction Heating Stress Improvement (IHSI) 11 5.0 Conclusions 12 6.0 Future Actions 13 7.0 References 14 8.0 Tables 15 9.0 Figures 21 Total Effective Pages 26
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5 TR-039 Rev. O Page 4
1.0 INTRODUCTION
1.1 Purpose This document describes GPUN's Cycle 11R outage activities relating to the BWR intergranular stress corrosion cracking (IGSCC) issue. Activities that occurred were augmented inspections of stainless steel piping for IGSCC, induction heating stress improvement (IHSI) of Recirculation system welds, and weld overlay repairs.
1.2 Background
In 1984, the NRC issued Generic Letter 84-11 [1]. This document provided NRC recommendations for performing examination of welds in stainless steel piping in systems generically susceptible to developing IGSCC. The NRC provided recommendations for sampling, examination methods, personnel
- - qualifications, and dispositioning weldments found to contain IGSCC indications.
GPUN responded to Generic Letter 84-11 via TDR 571 [2]. We committed to complying with the NRC's recommendation during the Cycle 11R outage. This document provides the information identifying that we have fulfilled our commitment.
1.3 Examinations for IGSCC 1.3.1 Examination Methods The primary method of examination was ultrasonic testing (UT) using procedures and equipment demonstrated effective in both the detection and sizing of IGSCC.
2631H t
TR-039 Rev. O Page 5 r
1.3.2 Examiner Qualifications
' Operators and examiners were qualified before performing
]
examinations in cccordance with the requalification guidelines established in the NRC/BWROG/EPRI meeting held in September 1985. Only those individuals on the EPRI NDE Center " Registry of Qualified Individuals" performed examinations and reviews.
d 1.3.3 Systems in Scope Welds were examined in the Recirculation, Core Spray, Reactor Water Cleanup, Shutdown Cooling, and Isolation l
Condenser (inside and outside drywell) systems.
1 1.3.4 Sample Size A total of 151 butt welds and 18 structural weld overlays (applied during the last outage to the Isolation Condenser system outside the drywell) were f
exanined. One hundred percent of the welds treated with IHSI (64 Recirculation system) were examined after 4
I IHSI. Details are provided in Table 1.
i.3.5 Examination Results Four welds contained indications having the UT signal characteristics of IGSCC. Three (NG-C-9A, NG-C-17 and NG-C-23) were in the "C" loop of the Recirculation system (26-inch diameter), and one (NE-i-27) was in the Isolation Condenser system outside the drysell in the "A" steam supply line (12-inch diameter).
4 J
2631H
5 TR-039 Rev. 0 Page 6 1.4. Disposition of Indications Welds NG-C-17, NG-C-23, and NE-1-27 were repaired with a'
~
standard design weld overlay. Weld NG-C-9A was evaluated to the requirements of the ASME Code Section XI, sub-section IWB-3640 and found to be acceptable for continued service without repair.
1.5 IHSI IHSI was effectively applied to 64 welds in the Recirculation system (26-inch diameter).
2.0 IGSCC EXAMINATIONS AND RESULTS 2.1 Iny duction
'tals section describes the IGSCC augmented inspection program and results of examinations performed during the Cycle 11R outage. Described are the examination methods, personnel
.__ _... qualifications, extent of examinations, and results. This program fulfilled our commitment to the requirements of Generic Letter 84-11.
2.2 Examination Methods Stainless steel piping system welds were examined by ultrasonic (UT) and, in some cases, radiographic testing (RT) was used to supplement the (Tr.
Manual and automated (If examination procedures were qualified at the EPRI NDE Center. These procedures rely on the 45 degree shear wave examination as the primary detection technique.
2631H
s TR-039 Rev. O Page 7 Geometric considerations of the weld bead width related to base
^
materlil thickness in some cases required the use of manual 60 degree shear wave as a supplemental detection examination.
Sizing after verification of IGSCC was performed by manual (fr.
Various EPRI-taught and industry-accepted techniques were utilized.
The equipment utilized for the automated (fr detection examination was the GE-SMART System. The AIARA I Scanner (track and arm) with (fr Transducer Skewing capabilities allowed accurate location determination by use of X, Y, and Z coordinates. The data aquisition system was the Ultra Image III. The data output from this system was a floppy disc, video
- - cassette recording of the "A" scan, and computer printout of essential variables supplemented by hand written calibration and data sheets.
Examination of structural weld overlays was performed using manual (fr techniques and were demonstrated effective in detecting IGSCC in the overlay and the outer 25% of the original pipe wall.
l 2.3 Personnel Qualifications tir was performed by personnel qualified to the NRC/EPRI/BWROG Coordination Plan for Training and Qualification Activities of 2631H l
5--
TR-039 Rev. O Page 8 NDE Personnel effectiv"e September 1, 1985. The September 1,
~
1985 pian revision includes,requalification requirements for IGSCC detection.
2.4 GPUN Review EPRI-qualified GPUN personnel, and GPUN-approved contractors who were also EPRI-qualified, performed reviews of all procedures, personnel certifications, data packages, and concurred with all data analysis performed by the contractor.
2.5 Sampling Plan The sampling plan for performing examinations for IGSCC was as identified in TDR 571 which was our response to Generic Letter 84-11. Details are provided in Table 1.
In summary, in each system, we examined at least 20% of those welds previously inspected to IE Bulletin 82-03 [3], but no less than 2, and 20%
-of those welds not previously inspected, but no less than 4.
In the Recirculation system, we examined 100% of the welds that were treated with IHSI (64) plus 3 welds not treated.
In addition, in the Isolation Condenser system outside the drywell, we examined all 18 structural weld overlays deposited during the 10R outage [4]. The detection of an IGSCC indication in one butt weld in the Isolation Condenser System outside the drywell required an additional sample of butt welds equal to the first sample (20). Since we strongly suspected that this may have been an instance of mischaracterization of examination da.a taken during inspections performed in the 10R 2631H
5 l
4 TR-039 Rev. 0 Page 9 outage (i.e., NE-1-27 was dispositioned as containing underc6t)', we concentrated our second set of examinations on welds which were similarly dispositioned in the 10R outage.
2.6 Examination Results Four welds con.tained indications having the UT signal characteristics of IGSCC. Three, NG-C-23, NG-C-17, and NG-C-9A, were in the Recirculation system. The indications in NG-C-23 were detected before and after IHSI with no change in the UT signal characteristics after IHSI. NG-C-9A and NG-C-17 were inspected after IHSI only. The fourth weld containing IGSCC indications was weld NE-1-27 which is located in the Isolation Condenser system outside the drywell;. this weld was examined as part of the 84-11 inspection commitment (TDR 571).
-- - -No indications were detected in the overlays or the outer 25%
of the original pipe wall in any of the 18 overlays on the Isolation Condenser system piping outside the drywell.
3.0 DISPOSITION OF WELDMENI'S CONTAINING IGSCC INDICATIONS 3.1 Introduction This section describes the actions taken to disposition the weldments identified by examination as containing the UT signal characteristics of IGSCC. The two actions described are weld overlay repair and analytical evaluation for continued service without repair.
3.2 Weld Overlay Repairs Recirculation system welds NG-C-17 and NG-C-23 and Isolation Condenser weld NE-1-27 were weld overlay repaired. The 2631H
I TR-039 Rev. O Page 10 overlays were designed assuming that a 360' through-wall crack existed a't each location. The resultant minimum design thickness provides adequate margin against plastic collapse when evauated to the requirements of IWB-3642 of the ASME B6PV Code (1983 through Winter 1985 Addends)Section XI. The width of the overlays are sufficient to enable ultrasonic examination of the overlay and outer 25% of the pipe wall in accordance with the current, accepted methods. Since the overlays were deposited using the automated gas tungsten arc method, only primary stresses were included in the design input.
Conservative values of shrinkage stresses from previously applied overlays were included in the design for Isolation Condenser weld NE-1-27. Details of the designs are provided in Tables 3, 4, and 5 and Figures 3, 4, and 5.
The overlays were deposited using the automated GTAW process with 308L bare wire. The welding arc was visually monitored throughout welding. The original pipe surface and final overlay surface were liquid penetrant examined. The measurements to confirm minimum design thickness included the first layer that contained an average ferrite number of 8 or higher with no single reading less than 5.
Following completion of the overlay welding, each was ultrasonically examined using the current, EPRI-taught, industry-accepted methods.
3.3 Use-As-Is The indication in Recirculation system weld NG-C-9A (18%
s through-wall, 2.9% of circumference) was evaluated for
C TR-039 Rev. O Page 11 continued service assuming both as-welded and as-IHSI'd residua 1 stress patterns. The results showed that the indication was acceptable for continued service without repair for at least one 18 month operating cycle when evaluated to the criteria of IWB-3640 of ASME Code (1983 through Winter 1985 Addenda)Section XI, Tables IWB-3641-5 and 6.
The evaluation was performed assuming that the weld was deposited using the shielded-metal arc process.
As-IHSI-treated, we do not expect further substantial crack growth to the point where repair action would be required.
This will be confirmed by future examinations (see Section 6.0).
4.0 INDUCTION HEATING STRESS IMPROVEMENT (IHSI) 4.1 Introduction
-- - ~ Biis section describes the implementation of IHSI on the Recirculation system during the cycle 11R outage.
4.2 Extent Of the 89 welds in the Recirculation system, we treated 64.
Vertical welds were treated without forced water flow. The welds not treated were the 20 safe-end welds that were overlaid for corrosion resistance during initial construction [5] and the 5 Recirculation pump casing-to-suction elbow welds. The pump casings and suction elbows are cast 316 stainless steel approximately one inch thick. We did not treat these 25 welds since there is currently no adequate means of nondestructively examining them following IHSI. Additionally, cast materials i
w 2631H
TR-039 Rev. O Page 12 have been inherently resistant to IGSCC. We expect to have an adequafe NDE method available for implementation in a future outage.
The essential parameters (such as time, temperature, and heating zone width) were consistent with those used throughout the industry and endorsed by EPRI. A post-IHSI review of each weld package resulted in the conclusion that all 64 received an effective treatment. NUTECH was the IHSI contractor.
4.3 Nondestructive Examination We initially examined 14 welds in the Recirculation system before IHSI, 12 of which were to be treated. One weld (NG-C-23) contained IGSCC indications. We then implemented IHSI and examined all 64 welds after IHSI. The ultrasonic response from the indications in NG-C-23 did not change following IHSI; the depth of the indications required weld overlay repair. Weld NG-C-9A, which was not examined before IHSI, contained one indication of IGSCC; this weld was evaluated and found to be acceptable for continued service without repair. Weld NG-C-17, which was not examined before IHSI, contained indications requiring weld overlay repair.
5.0 CONCLUSION
S 1.
Our augmented inspection program fulfilled our commitment to the requirements of Generic Letter 84-11, including the requirements for extent of examinations, examination methods, and personnel and procedural qualifications.
s 2631H
TR-039 Rev. O Page 13 2.
Of the four weldments,found to contain indications with UT signals characteristic of IGSCC, three were repaired with standard weld overlays and one was analytically determined to be acceptable as-IIISI-treated for continued service without repair. These weldments are acceptable for continued service.
3.
The 18 structural weld overlays on the Isolation Condenser i
system piping outside the drywell deposited during the last (Cycle 10R) outage were examined; no IGSCC indications were detected in the overlays or the outer 25% of the pipe walls.
These everlays are acceptable for continued service.
4.
IHSI treatment of 64 Recirculation system welds was effectively perforned. The likelihood of initiation of IGSCC in uncracked weldments and further growth of shallow, undetected IGSCC has been substantially reduced, if not eliminated.
6.0 RmRE ACTIONS The NRC has issued a draft Revision 2 to NUREG-0313(6] and a draft implementing generic letter [7J. These documents address the IGSCC issue and include the NRC's position and recommendations regarding long-term actions. We expect that the two documents will be released well before the cycle 12R outage begins (currently scheduled for April 1988).
Implementation of mitigating actions, such as stress improvement techniques and hydrogen water chemistry, and future inspection plans are currently under evaluation and will be described in our response to the Generic Letter implementing NUREG-0313 Rev. 2, when issued.
263111
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l-l TR-039 Rev. 0 l
Page 14
7.0 REFERENCES
1.
" Inspections of BWR Stainless Steel Piping (Generic Letter l
84-11)",USNRC, April 19, 1984.
2.
" Reactor Coolant System Inspections for IGSCC - Cycle 11R Outage", TDR 571 Rev. 1, GPUN, March 26, 1986.
l 3.
" Stress Corrosion Cracking in Thick-Wall, large-Diameter, l
Stainless Steel, Recircualtien System Piping at BWR Power Plants", IE Bulletin No. 82-03, Rev. 1, USNRC, October 28, 1982.
l 4
" Isolation Condenser System Piping Cracked Welds-Repair and l
Failure Analysis", TDR 580 Rev. 2, GPUN, November 5, 1985.
l S.
Oyster Creek FSAR Amendments 29, 35, 36, 37, 40, 43, and 47.
6.
" Technical Report on bhterial Selection and Processina Guidelines for BWR Coolant Pressure Boundary Piping",
NUREG-0313 Draft Revision 2, W.S. Hazelton, USNRC, June 1986.
7.
"NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping i
1 (Generic Letter 86-
)", Draft,USNRC.
l I
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2631H t
Rsv. 0 Pcga 15 l
8.0 TABLES I
i 1.
Cycle 11R Outage IGSCC Examinations l
2.
IGSCC Indications 3.
NG-C-17 Overlay Design Tabulation 4.
NG-C-23 Overlay Design Tabulation 5.
NE-1-27 Overlay Design Tabulation l
l 1
i l
l l
l 263111 1
_--____-.----..__---.-___-----__.--_-__.y Tab 12 1 OYSTE3 CREEK C]CLE IIR DUTAE ICSCC EEAMINATIQg5 l
$0T CVCLE Ile INSPECTI0ms umINSPECT-PREV.
PeEV.
. OVERLAY PI sePI PIPE TOTAL ABLE INSPECTED INSPECTED REPAIRED NO NO PI RPI SISIQt SIE WCLQS WELDStil W LDS W LDS
_ WELDS litSI litil itis 1 litil QLR TOTAL RESuLTS l
1 Reg 1rculation 26 39 IS 31 43 c
I 2
2stsa/Al 36138/Al 0
67 3 W/IGSCC peactor Water 6
50 7
8 35 0
2 8
0 0
0 10 0 W/IGSCC CltA! w Shutoown 14 14 0
2 12 0
2 4
0 0
0 6
0 W/IGSCC Cooline i
Cere a
e,9 7
3 59 0
2 14 0
0 0
16 0 W/ICSCC
- Sora, 6
_i 4
0 0
0 0
0 0
0 0
0 0 W/IGSCC Isolation 10 54 14 19 21 0
4 8
0 0
0 12 0 W/IGSCC t
Condenser fI1 l
Isolation a
58 0
51(2) 0 7
17 0
0 0
7 24 0 W/ICSCC Condenser (0) 10 13 0
13(31 0
1 3
0 0
0 1
4 0 W/IGSCC 12 54 0
54(4) 0 9
17 0
0 0
9 26 1 W/IGSCC 16 9
0 9(5) 0 1
3 0
0 0
1 4
0 W/IGSCC IQT_ALS _
.397 _ _ _1 L __
._l'/4 -._
179 la.
st 3h 23 3h
__13
_lg ___tpf1GZC meten Abbreviations It uninspectable by uT I
- Inboard of second isolation valve.
23 5 Welds installed in 10R Outage not included in llR 0
- Outboard of second isolation valve.
Sampling Base for initial inspections.
OLR
- Overlay repaired
- 3) I weld - same as Note 2.
- Previously inspected.
43 7 Welds - same as note 2.
- seot previously inspected.
53 3 Welds - same as Isote 2.
INSI
- IMSI applied this outage, no INSI - IMSI not applied this outage.
B/A
- Welds inspected bef' ore and af ter INSI (all IMSI'd welds inspected after INSI).
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Tabit 2 IGSCC In0! CATIONS PIPE WELD Sv5 TEM DIasETte tin.)
gwegg LOCATIQu arstatpTIoss Recirculation 26 hG-C-23
'C' toop Pipe-to-elbow weld. 2 indications. 1-2.g*
long x 15% through-wall 1-1.25" lens x 55% through-wall, circumferential orientation. Indications on pipe side of l
weld.
I 26 NG-C-17
'C' toop valve-to-stpe weld. 4 circumferential indications, max. through-wall of 29t; I amial indication. 14% through-wall x l=
long. All 5 on pipe side of weld.
26 NG-C-9A
'C' toop Pipe-to-elbow weld. 1 indication. 2.2*
long u lat through-wall, circunt'erential orientation. Indication on elbow side of weld.
l Isolation Condenser 12 NE-1-27
'A' Supply Pipe-to-elbow weld. 360* intermittent.
Outside man. through-wall of 281, circumfer-Drywell enttal. On both sides of weld.
I asial indication 1.5" long on pipe side of weld.
.? N R 4*
C-L4 P-* O < -
N l
l l
TR-039 Rsv. c
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Page :.8 k
eeeeeeeeeeeeeeee....eeeeeeeeeeeeeeeeeeeeeeeeee.....eeeeee...
e PLANT ID OYSTER CREEK e
WELD ID: NG - C - 17 e
PIPE THICKNESS = 1.10 INCH e
P!PE DIAMETER = 26.00 INCH e
PRIMARY STRESSES:
6.h0 KS!
PRESSURE
=
DEAD WEIGHT MEMBRANE = 0.10 KS!
e e
DEAD WE!GHT BENDING = 0.57 KS!
0.03 KS!
e SE!SMIC MEMBRANE
=
e SE!SMIC SENDING
= 1.10 KS!
= 16.90 KS!
e e
e e
PB(KSI)
_PM+PE epi +PR *
..I.
PM SH 3SM e
WOT T+WOT (KS!)
ACTUAL CALC (ACTUAL)
(CALC) e e
_4...
- 0.350 0.759 4.996 1.301 14.170 0.373 0.378
+
e e
e PRIMARY STRESS RATIOS (ADJUSTED):
PM/SM = 0.296 e
(PM + PB)/SM = 0.373 e
e e
e e
MIN! MUM REQUIRED WELD OVERLAY THICKNESS = 0.350 INCH e
MINIMUM REQUIRED WELD OVERLAY WIDTH
= 3.80 INCH e
e e,eeeeeeeeeeeeeeeeeeeeeeee***eee**ese********eeeeee*o*e.*****
Table 3
'I b
Bt-039 Rev. O i
Page 19
- n***************************************************
PLANT ids OYSTER CREEK WELD ids NG - U - 20
\\
+
PIPE THICKNESS = Q.98 INCH PIPE DIAMETER = 26.00 INCH PRIMARY STRESSES:
6.16 KSI a
PRESSURE DEAD WEIGHT MEMBRANE =
0.05 KSI
=
0.91 KSI DEAD WEIGHT BCNDING 0.05 KSI SEIGMIC MEMBRANE
=
1.35 KSI SEISMIC BENDING
=
16.90 KSI
=
SM a
n m
PB(KSI)
- I-_
PM T+WOT (KSI)
ACTUAL CALC (ACTUAL)
(CALC)
WOT 0.310 0.760 4.696 1.693 14.558 0.378 0.080, PRIMARY STRESS RATIOS (ADJUSTED):
0.278 PM/SM
=
(PM + PB)/SM = 0.378 MINIMUM REQUIRED WELD OVERLAY THICKNESS
- O.310 INCH
= 3.60 INCH MINIMUM REQUIRED WELD OVERLAY WIDTH
- g*w*At***4**N**d**>***##*#######**#U#**####8##*****#"**
5 Table 4 S
,.y_-
5 TR-039 R:v. O Page 20 as*****sss***s*** ssassast*****ssasssssssssssantasts:Isssssssssagess s
s s
PLANT ID: 0YSTER CREEK s
MLD IDI NE-1-27 8
PIPE THICKNESS = 0 69 INCH PIPE DIAMETER = 12 75 INCH PRIMARY STRESSES:
PRESSURE
= 5 80 KS!
DEAD WEIGHT MEMBRANE = 0.00 KSI DEAD WIGHT DENDING = 0.32 KSI s
SEISMIC MEMBRANE
= 0.00 KS!
8 SEISMIC SENDING
= !.65 KSI SM
= 16.90 KS!
3 a
3 PB (KSI)
.25128
.2512B SM 3SM I.
PM WOT T+WOT (KSI)
ACTUAL CALC (ACTUAL) (CALC) g g
3 0 205 0.770 4.610 1 484 13.789 0.361 0.363 3
y PRIMARY STRESS RATIOS (ADJUSTED) s PM/SM
= 0.273 (PMfPB)/SM = 0.361 8
MINIMUM REQUIRED WELD DVERLAY THICKNESS = 0.205 INCH s
= 2.1 INCH MINIMUM REQUIRED WELD OVERLAY WIDTH SAFETY FACTOR WHEN INCLUDING THERMAL AND SHRINKAGE STRESS
= 3.019 s
s sass **sts***********ss**********ss*****sss****************sts****sses Table 5
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,,,,,-.-,--__.,-a----*'-wm-witw=-----w-'
i TR-039 Rev. O Page 21 9.0 FIGURES 1.
Location of IGSCC Indications - Recirculation Loop
'C'.
2.
'A' Supply line, Weld Overlay Locations 3.
NG-C-17 Overlay Design 4.
NG-C-23 Overlay Design 5.
NE-1-27 Overlay Design
=6 eGD 9 s FG O
2631H
1 RECIRCULATION LOOP "C" TR-039 Rev. O Page 22 NG-C-23 (Overlay)
L
,i-P- - NG-C-9 A (Use-As-Is) g J
/
... '... 's 1
N NG-C-17
\\
(Overlay)
LOCATION OF IGSCC INDICATIONS FIGURE 1 i
..___..__.,.__,._...__.,__,....___.____.[_._,,,_,m,
.. o..
s
- (
TR-039 Rtv. 0 Page 23
.g
~
hh 3S 3s 55 m
II
=
==
- I bb
/
0 y
9 n.
9
\\
4-'*
22
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+g' 30 vv m m k k E b
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- os
- +
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A A,
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6 1%
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Y4 9
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4 1
FIGURE 2
' A Supply Line, Weld Overlay Locations s
w e
a e
e 4
e 3
gs
-,.-_,+y,,
y---
r w--,r.,
m-
5 TR-039 R:iv. O Page 24 WELD OVERLAY DESIGN OYSTER CREEK - RECIRCULATION PIPING l
- -- "W" M I N p WELD "W i " M I N ---+
- -- C R O W N WIDTH E
l I
0.D.
o 4
sn x
L "T " M I N L FIRST VALVE PIPE LAYER f
l.D.
PIPE SIZE WALL THK. I "T" MIN "Wi" "W"
N G-C-17 26"
- 1. ! O 0.350 1.90 1.90~
I l
NOTES:
- 1) APPLY OVERLAY PER G.E. SPECIFICATION PSOYP22S, REV. 2. MODIFIED TO DIMENSIONS SHOWN.
210! MENS 10NS AND 0.D. CONTOURS ARE THOSE RECEIVED FROM SITE MEASUREMENTS.
- 3) MINIMUM SLOPE AT EACH END : 1:1 WIDTH TO THI CKN ESS.
t Figure 3 s
==
v w
m e
=w e
,ywwe w
i4-er==-w+---
=
e
- + - - -
w-
- - - - - - + - -
s-
j TR-039 Rcy. O Page 25 l
WELD OVERLAY DESIGN OYSTER CREEK - RECIRCULATION P! PING c
"W" M I N
=
WELD I
~"W i " M I N
- -CROWN
- "Wi" M I N I
WlOTH y\\\\ l O.0.
E n
x ELBOW I
. "T " M I N b F!RST
/
P!PE LAYER
- 1.D.
C WELD PIPE TO ELBOW WELD NO. I PIPE SIZE WALL THK.
T " M I N } "W i "
"W" N G - C -2 3,,_
i, ;,2 6 ",,,,, _ _ _ _0. 9 8 0.31 1.8 i 4.85 l
NOTES:
- 1) APPLY OVERLAY PER G.E. SPECIFICATION P50YP225, REV. 2, MODIFIED TO DIMENSIONS SHOWN.
- 2) O!MENSIONS AND O.D. CONTOURS ARE THOSE RECEIVED FROM SITE MEASUREMENTS.
j
- 3) MINIMUM SLOPE AT E ACH END : I:l WIDTH TO THICKNESS.
Figure 4 l
,w
--.--y-.w, m.
7 r-----y
TR-039 Rev. 0 WED OVERI.AY DESIGN Page 26 OYSTER CREEK - ISOLATION CONDENSER PIPING WED NO. NE-1-27 "W"M!N.
=
=
WELD "W1."u:N.
"W1" MIN.
CROWN
=
=
WIDTH 1
-FlRST
,/_
y i
////////// \\
N1 u LAYER 0.D.
4 x
U o
j W%
"T"um.
ELBOW l
PlPE T WELD
- ~~ ~
PlPE TO ELBOW WELD NO.
P!PE SIZE WALL THK.
"T"uw "Wi" "W"
NE-l-27 12" 0.687 0.205 1.05 3.40 1
i NOTES: 1) Apply overlay per G.E. Specification P50YP225, Rev. 2, modified to dimensions shown.
l
- 2) Dimensions and 0.D. contours are those received from I
site measurements.
- 3) Minimum slope at each end = 1:1 width to thickness.
Figure 5 i
s
~
- * ~ -
3--
--._-s.
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