ML20056F889
| ML20056F889 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/23/1993 |
| From: | Axline J, Jonathan Brown, Froehlich C PACIFIC NUCLEAR SYSTEMS, INC. |
| To: | |
| Shared Package | |
| ML20056F868 | List: |
| References | |
| COE-301-200, COE-301-200-R01, COE-301-200-R1, NUDOCS 9308310271 | |
| Download: ML20056F889 (142) | |
Text
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EVALUATION AND DISPOSITION OF IGBCC-SUSCEPTIBLE WELDMENTS AT i i QUAD CITIES NUCLEAR POWER STATION UNIT 2 ! 1993 OUTAGE i i Prepared for: I commonwealth Edison Company f Prepared by:
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Pacific Nuclear Systems, Inc. l I t Reviewed by: Issued by: ; L
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.jW. Axline, P.E. J. A. Brown, P.E. gf Project Engineer Project Manager i Approved by:- !
M\2hH. Froehlich, P.E. Date: M 3 ! I j Er gineering Manager ., i V ! OPACIFIC ! NtJELEAR. ' 9308310271 930827 "i ' PDR P ADDCK 05000265 p > PDR fi ;
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REVISION CONTROL SHEET J TITLE: Evaluation and Disposition of IGSCC- DOCUMENT FILE NUMBER: XCE042.0255 Susceptible Weldments at Quad Cities Nuclear Power Station Unit 2 - 1993 _-Outage (COE 301200) i John K. Miwa / Consultant Il f( i NAME/ TITLE INITIALS i Carl H. Froehlich / Staf' Engineer ' On File NAME/ TITLE INITIALS , James W. Axline / Staff Engineer NAMEAITLE INITIALS i NAME/ TITLE INITIALS AFFICTID Doc. PREPARED ACCURACY CRffUuA l PAGEIS) REV. SY/DATE CHECK BYCATE CHECK BY/DATE REMARKS ev e 0 JKM 8/8/93 CHF 8/7/93 CHF 8/7/93 Irmeel issue. I 1.1 - 1.8 0 (Signetre e - file) ;
- 2.1 - 2.3 0 3.1 - 3.6 0 l 4.1 - 4.5 0 i
5,55,9 o ; 6.1 & 6.2 0 7.1 & 7.2 0 , e A.0 - A.46 0 B.0 - B.39 0 d C.O. C.6 0 D.0 - D.6 0 , 5 2-5 3 II unm ! pp 1 R*me.d per Chant corernente pp , Page 1 of 1 I 11
@PACIF E :
NUELE6 R. !
CERTIFICATION BY REGISTERED PROFESSIONAL ENGINEER '! t
.; I hereby certify that this' document and the calculations contained herein were prepared by j me or under my direct supervision, and to the best of my knowledge are correct and complete.
I further certify that, to the best of my knowledge, design margins required by the ; original Code of Construction have not been reduced as a result of the activities addressed i herein. I am a duly Registered Professional
- Engineer under the laws of the State of California and am competent to review this i document. I Certified by: !
_ + No.27862 5
- 113tl94 W
C. H. Froehlich, P.E. 4 ClV\l
-x'0F Cfdg gf Registered Professional Engineer f
' State of California t Registration No. C 027862 '
Date: _ 8/24/93 : b i 1 COE-301-200 Revision 1 iii OPACIFIE i NUCLEAR. t t
}
TABLE OF CONTENTS Pace LIST OF TABLES V LIST OF FIGURES vi
1.0 INTRODUCTION
1.1 2.0 OVERLAY DESCRIPTION 2.1 3.0 EVALUATION CRITERIA 3.1 3.1 Weld Overlay Repair Evaluation 3.1 3.2 Evaluation of Sustained Stresses at 3.2 Unflawed Locations 4.0 STRESSES 4.1 4.1 Primary Stresses 4.1 4.2 Secondary Stresses 4.1 4.3 Sustained Stress Evaluation at Unflawed 4.2 Weld Locations 5.0 EVALUATION HETHODS AND RESULTS 5.1 5.1 Weld Overlay Repair Evaluation 5.1 5.2 Weld 02B-59 Discussion 5.2 6.0
SUMMARY
AND CONCLUSIONS 6.1
7.0 REFERENCES
7.1 APPENDIX A - Comparison and Description of A.0 Flawed Weldments with As-Built Overlay Dimensions APPENDIX B - Weld Overlay Design Drawings B.O APPENDIX C - Sustained Stresses at Unflawed Weld C.0 Locations APPENDIX D - Evaluation of Weld 02J-S3 Overlay D.0 Boat Sample COE-301-200 iv P/4CIFIC Revision O NUELEAR.
LIST OF TABLES Number Title Pace 1.0-1 Quad Cities Unit 2 - Weld Overlay Repair 1.8 and Flawed Pipe Evaluation I!istory Summary 3.1-1 Expanded Allowable End-of-Evaluation 3.3 Period Flaw Depth-to-Thickness Ratios for Circumferential Flaws in Base Metal or GTAW Weldments During Normal Operating Conditions 3.1-2 Leakage Barrier Repair Criteria for 3.4 Axial Flaws 4.1-1 Quad Cities Unit 2 - Applied Stresses for 4.4 Weld Overlay Repair Evaluations 5.1-1 Quad Cities Unit 2 - Circumferentially Flawed 5.4 Overlay-Repaired Welds - Pipe and Weld Overlay Repair Geometry Details 5.1-2 Quad Cities Unit 2 - Circumferentially Flawed 5.5 Overlay-Repaired Welds - Flaw Geometry Details 5.1-3 Quad Cities Unit 2 - Circumferentially Flawed 5.6 Overlay-Repaired Welds - Predicted vs. Allowable Flaw Depth Ratios 5.1-4 Quad Cities Unit 2 - Axially Flawed overlay- 5.7 Repaired Welds - Pipe and Weld Overlay Repair Geometry Details 5.1-5 Quad Cities Unit 2 - Axially Flawed Overlay- 5.8 Repaired Welds - Flaw Geometry Details 5.1-6 Quad Cities Unit 2 - Axially Flawed Overlay- 5.9 Repaired Welds - Predicted vs. Allowable Remaining Ligament Thickness COE-301-200 v hpff{lpl{ Revision NUELE/4R.
l t LIST OF FIGURES Number Title Pace 1.0-1 Quad Cities Unit 2 - Flawed Weld Locations - 1.6 Reactor Recirculation System Loop "A" 1.0-2 Quad Cities Unit 2 - Flawed Weld Locations - 1.7 Reactor Recirculation System Loop "B" and Shutdown Cooling System 3.1-1 Source Equations for Allowable End-of- 3.5 Evaluation Period Flaw Depth-to-Thickness Ratios for Circumferential Flaws 4.2-1 Weld Overlay Shrinkage Analysis Model 4.5
~.
COE-301-200 vi @ PACIFIC Revision 0 NUCLEAR.
1.0 INTRODUCTION
This report summarizes analyses performed by Pacific Nuclear (formerly NUTECH) for evaluation of indications in the Reactor Recirculation and Shutdown Cooling systems at Commonwealth Edison's Quad Cities Nuclear Power Station Unit 2 at the end of its 1993 outage. Since 1983, ultrasonic (UT) examinations of the welds in these systems, as well as the Reactor Water Clean-Up system, have identified flaws judged to be Intergranular Stress Corrosion Cracking (IGSCC). There are currently thirty-seven flawed weldments at Quad Cities Unit 2 including one flawed weld identified and repaired during the 1993 outage. One flawed weldment was replaced in 1983 and three overlay-repaired weldments were replaced in 1990. In addition, two weldments originally identified as flawed in 1983 are now believed to be tinflawed. The locations of all the currently flawed welds and two welds which received " load balancing" overlay repairs are shown in Figures 1.0-1 and 1.0-2. A summary of the overlay application, flawed pipe evaluation, and spool piece replacement history at Quad Cities Unit 2 is shown in Table 1.0-1 and is briefly described below. Appendix A presents descriptions of the IGSCC indications at Quad Cities Unit 2. i This report includes the sustained stress evaluations performed by Pacific Nuclear of unflawed and unrepaired IGSCC-susceptible piping that has had or may receive Stress Improvement (SI). l COE-301-200 1.1 hpg{lpl{ ] Revision 0 NUELEAR. i
02R6 (1983) Outace Twenty-three Reactor Recirculation, Shutdown Cooling, and Reactor Water Clean-Up system welds were identified as having flaws during the 1983 outage. Of these welds, nine were repaired with " engineered" weld overlay repairs, one weld (125-S27) was replaced, and the remaining thirteen were found to be acceptable for continued service based upon flawed pipe criteria. The i nine overlay-repaired welds were built-up to " standard" weld overlay repairs during the 1986 outage. Of the thirteen unrepaired welds, two welds (02AS S6 and 02BS-F14) have since been recharacterized as not having IGSCC; weld 02A-S10 was repaired during the 1986 outage with a
" standard" weld overlay repair which experienced significant fabrication defects which were repaired {
during the 1988 outage, but was eventually replaced { during the 1990 outage; two welds (02AS-S4 and 10S-F5) were repaired with " leakage barrier" (" design") weld overlay repairs during the 1985 outage and later built-up to " standard" weld overlay repairs durint; the 1986 outage; weld 02M-S3 was repaired with an " engineered" weld overlay repair during the 1985 outage and later built-up to a " standard" weld overlay repair during the 1986 outage; weld 02B-S9 was repaired with a " standard" weld overlay repair during the 1986 outage; two welds (02D-S3 and 02M-S4) were repaired with " standard" weld overlay repairs during the 1988 outage; and the remaining four welds were repaired with " standard" weld overlay repairs during the 1990 outage. The weld overlay repair designs and flawed pipe evaluations performed during the 1983 outage at Quad Cities Unit 2 are described in NUTECH Document No. COM-75-002 (Reference 1). COE-301-200 Revision 0 1.2 PACIFIE NUELEAR.
l 1 i
~1 02R7 (1985) outane Two Reactor Recirculation system welds (02E-F6A and 02M-F7) were identified as containing flaws and were repaired with " engineered" weld overlay repairs. Both of these welds were built-up to " standard" weld overlay repairs during the 1986 outage.
The weld overlay repair designs and flawed pipe evaluations performed during the 1985 outage at Quad Cities Unit 2 are described in NUTECH Document No. CEC-20-013 (Reference 2). l O2R8 (1986) Outace Flaws were detected in five additional Reactor l Recirculation system welds. Four of these welds were , repaired with " standard" weld overlay repairs. The remaining weld (02BD-F8) was evaluated during the 1986 and 1988 outages using flawed pipe criteria and found to be acceptable for continued service. This last weld was i repaired with a " standard" weld overlay repair during the i 1990 outage. ! i The design of weld overlay repairs and evaluations of l built-up weld overlay repairs and flawed welds performed during the 1986 outage are described in NUTECH Document No. CEC-73-203 (Reference 3). 1 COE-301-200 1.3 PACIFIC Revision O NUCLEAR. l
02R9 (1988) Outace Twelve new Reactor Recirculation and Reactor Water Clean-Up system welds were identified as having flaws. Eleven were repaired with " standard" weld overlay repairs. Two ; of these repaired welds (12S-S24 and 12S-F26AR) were replaced during the 1990 outage. The remaining veld I (02AD-S6) was evaluated using flawed pipe criteria and j found to be acceptable for continued service. This last ! weld was later repaired with a " standard" weld overlay repair during the 1990 outage. In addition to the
" standard" weld overlay repairs on the eleven flawed welds, two unflawed welds (02C-S4 and 02H-S4) received
" load leveling" standard weld overlay repairs to reduce (balance) overlay repair axial shrinkage stresses at other unflawed weldments in the Reactor Recirculation system.
The evaluation of the flawed welds and weld overlay repairs applied during the 1988 outage are described in ' SIA Document No. SIR-88-018 (Reference 4). , 02R10 (1990) Outace No new IGSCC flaws were identified during the 1990 outage. However, one weld (02J-S3) which received a
" standard" weld overlay repair during the 1988 outage was thought to have significant IGSCC growth into the weld overlay repair. A boat sample taken from this weld conclusively demonstrated that this cracking was arrested at the pipe wall-to-weld overlay repair interface (see Appendix D).
An overall evaluation of the veld overlay repairs applied ' through the Quad Cities Unit 2 1990 outage is documented ' in NUTECH Document No. XCL-42-252 (Reference 5). COE-301-200 1.4 @ PACIFIC Revision 0 NUELEAR.
02R11 (1992) Outace i No volumetric ultrasonic examinations of the Reactor Recirculation and Shutdown Cooling system veldments were performed during the 1992 outage. 02R12 (1993) Outace 1 One flawed weld (02C-F7) was identified during this l outage and given a " standard" weld overlay repair. The purpose of this report is to demonstrate that all the Quad Cities Unit 2 flawed weldments meet the requirements of NUREG-0313, Revision 2 (Reference 6) at the end of the 1993 outage. Section 2.0 presents a general description of the implementation requirements used during application of weld overlay repairs at Quad Cities Unit 2. Sections 3.0 and 4.0 provide the evaluation criteria and stresses used in the analysis of overlay repairs. The evaluation methods and results are given in Section 5.0. Sections 6.0 and 7.0 present a summary of conclusions and the references used in the evaluation. Appendix A contains a comparison and description of the flawed weldments identified since the Quad Cities Unit 2 1983 ontage. The current as-built dimensions for all the Quad Cities Unit 2 overlays are also presented in' Appendix A. Appendix B contains the design drawings for all the current overlays. Appendix C presents the sustained stress magnitudes for all unflawed and unrepaired IGSCC-susceptible welds outside of NUREG-0313 ISI Inspection Category "A". Appendix D provides Commonwealth Edison Company's evaluation of the boat sampla extracted from weld 02J-S3 during the 1990 outage. COE-301-200 1.5 Revision @ PACIFIC NUCLEAR.
02t453 C2L;53 02t-53 02 53 C2 53 D Q M MT MT D 02rtS4- 02L-54 02K 54
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02AD-55 02A5 59
- to GSCC " LOAD LEVELIr#T WOA k " to CSCC SINCE 1988 c.
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! ! *** AEPLACED DUAItG 199L 001 AGE C2A5-512 C2 AS-F 14 Figure 1.0-1 OUAD CITIES UNIT 2 FLAWED WELD LOCATIONS REACTOR RECIRCULATION SYSTEM LOOP "A" (Reference 7)
COE-301-200 1.6 @ PACIFIC Revision NUELFAR.
C2 -53 C2 -53 C2E;53 D2D 53 02; 5} C255'I2 C?G-54 (i 1] - 1] (- q l] 4U2 54*
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02E-F 5A 02B 59x - _ _ C2D-F6 _ C2CJ7 0 l l 105J1
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02SD-55 C2B5 F? - _ C2BD FE
- ND GSCC - ~LDAD L EVEL:tG WD;
' ( " ND GSCC SINCE 1988 OUT AGE 105 r" I d 0225-512 C2954 wa Figure 1.0-2 OUAD CITIES UNIT 2 FLAWED WELD LOCATIONS REACTOR RECIRCULATION SYSTEM LOOP "B" AND SHUTDOWN COOLING SYSTEM (Reference 7)
COE-301-200 1.7 PACIFIC Revision 0 NUCLFAR. I
Table 1.0-1 l OUAD CITIES UNIT 2 WELD OVERLAY REPAIR AND FLAWED PIPE EVALUATION HISTORY
SUMMARY
19&3 1985 1986 1988 199D 1992 1993 CD (C2R6) (C2R7) (C2RB) (C2R9) (C2R10) (C2R11) (C2R12) OUTACE OUTACE CUTACE OUTAGE OUTACE OUTACE OUTACE C2D-53 FPE iPE FPE STD C2D-F6 ENCR BUS C2F-F6 ENCR BUS C2G 53 ENCR BUS C2J-F6 ENCR BUS C?m-53 FPE ENCR BUS C2M-54 FPE FPE FPE STD C2AS-54 FPE LS BUS C2AS-56 FPE FPE FPE (1) 02AS-59 ENCR BUS C2AS-512 FPE FPE FPE FPE STD C2AS-F14 FPE FPE FPE FPE STD C2 AD- F 12 FPE FPE FPE FPE STD 02BS-53 ENCR BUS f C2BS F7 ENCR BUS N C2BS-512 FPE RGO RCO FPE STD 0 02BS-F14 FPE FPE RGO (1) T C2BD 56 ENCR BUS C2A-51D FPE FPE STD (2) RE PL ACE D I C2B-59 FPE FPE STD N 1CS-F1 ENGR BUS S 105-75 FPE LS BUS P 125 527 REPLACED E C2E-F6A ENCR BUS C C2H-F7 ENCR BUS T C2C-53 STD l E C2K-53 STD D C2K-54 5TD 02BS F2 $70 C2BD-F8 FPE FPE STD 125-524 STD REPLACED 125-F26AR STD REPLACED 02E-53 STD 02F-53 f STD i C2C-54 STD 02H-53 STD C2J 53 STD (3) 02J-54 STD C2K-F6 STD C2L-53 STD 02L-54 STD 02AD-56 FPE STD 02C-54 LL C2H-S4 LL 02C-77 STD { ABBPFVIATIowS: FPE - Flowed Pipe Evaluation Performed ENCR " Engineered" Overley Applied STD " Standard" Weld Overley Applied BUS - Built-up to "Stancard" Overley RCO - Root Cecmetry only LB " Leet.eDe Barrier" overley Applied LL - unflowed, " Load Leveling" overlay A; plied ICTES: (1) - No ICSCC reported. ' (2) - Fabrication defects from 1986 outage repaired. (3) - Scat sanctes extracted, sonually repaired, and one sa:!itional CTAW Layer applied. J coE-3oi-2co l nevision 1.8 @PAElFIC NUELEAR.
)
i i I 2.0 OVERLAY DESCRIPTION At the end of the 1993 outage, a total of thirty-nine overlays exist at Quad Cities Unit 2. Thirty-seven c. these overlays are " standard" overlay repairs and two have been applied as
" load leveling" overlays using " standard" overlay repair designs.
All of the overlays were made by increasing the pipe wall thickness through the deposition of weld metal 360" around and - to either side of the existing veld. The weld-deposited band provides additional wall thickness to restore the original Code safety margin. Because of waterbacking, the welding process produces a strong compressive residual stress pattern 4 on the inside portion of the pipe wall (as discussed in Reference 8) thereby preventing further crack growth. The deposited weld metal is either Type 308L or Type 309L with controlled delta ferrite content so as to be resistant to the propagation of IGSCC. The overlay design drawings are presented in Appendix B while the current as-built information for all overlays is in Appendix A. l The application of an overlay causes a small amount of axial shrinkage underneath the overlay. These shrinkages cause additional stresses at other locations in the piping system and their effect must be evaluated. The as-measured shrinkages compiled from work packages for each overlay are shown in Appendix A. The nondestructive examination (NDE) requirements for each overlay applied at Quad Cities Unit 2 consisted of the following: COE-301-200 2.1 @P/4EIFIC Revision 0 NUCLE /4R.
- 1. Surface examination of the existing pipe surface by the
; liquid penetrant testing (PT) technique in accordance with ASME Section XI. All PT indications were repaired prior to application of the weld overlay. Acceptable repair methods were as follows:
- a. For indications which are the result of geometric conditions (e.g., overlap, undercut, grinding marks, and scratches), the indications were removed by grinding prior to weld overlay application. No welding of the ground cavity was required.
For any linear indication, regardless of length, and b b. for any rounded indication in the region of the original weld heat-affected zone.(HAZ), the indications were weld repaired after removal. After repairs, the existing pipe surface was re-PT examined and re-repaired, if required, until found acceptable.
- 2. Delta ferrite content measurement of the first layer of new overlays or the first layer to increase the length of an existing overlay.
- 3. Enhanced visual examination of the first overlay layer for evidence of IGSCC flaws for new and built-up overlays (discoloration, porosity, etc.).
- 4. Surface examination of the completed overlay by the PT technique using methods in accordance with ASME Sections V and XI. All PT indications were reported to CECO for
^
resolution. ' COE-301-200 2.2 P/4CIFIC Revision 0 NUELE/4R.
- 5. Volumetric examination of the completed overlay and part :
of the original pipe wall by the ultrasonic testing (UT) technique developed by EPRI. All UT examinations were performed by EPRI-qualified examiners. 1 i I COE-301-200 Revision 0 2.3 @P/4ElFIE NUELE/4R.
i 3.0 EVALUATION CRITERIA 3.1 Weld Overlav Repair Evaluation All " standard" weld overlay repairs at Quad Cities Unit 2 were designed to meet the requirements of NUREG-0313. The following criteria were used by Pacific Nuclear to design / evaluate all of the weld overlay repairs listed in Appendix A:
- 1. For welds with circumferential flaws, the circumferential flaw depth was assumed to equal the greater of 100% of the original pipe wall thickness or the depth associated with the smallest remaining ligament by a conservative 360' length.
- 2. For welds with axial flaws, the axial flaw depth was assumed to be 100% of the original pipe wall thickness with a length equal to the greater of 1.5 times the pipewall thickness or its measured length. If an axial flaw was drawn up into the overlay due to a steam blow-out, the actual flaw Fepth was used.
- 3. Credit was taken for the first layer if the delta ferrite content was at least 7.5 FN. If the ferrite content was below this value, any circumferential or axial flaws were assumed to extend through the first layer.
- 4. A bounding under-the-overlay fatigue crack growth of 0.005 inch was used in the overlay design. This was established based on analyses performed by Pacific Nuclear in References 1, 2, and 3 using a conservative crack growth correlation derived from data presented in Reference 9.
COE-301-200 Revision 0 3.1 @PMEIFIE NUELEAR.
- 5. For circumferential flaws, the weld overl2.y repair strength for a combination of dead weight, internal pressure, and seismic stresses was compared to the net section plastic collapse criteria of ASME Section XI, Table IWB-3641-1 (Reference 10). Because this table has an arbitrary cut-off point at a stress ratio of 0.6, Pacific Nuclear has developed an expanded version (Table 3.1-1) based upon the source equations shown in Figure I 3.1-1.
4
- 6. For axial flaws, the weld overlay repair was compared to
" leakage barrier" weld overlay repair criteria presented in Table 3.1-2 from NUTECH Document COM-76-001 (Reference 11).
3.2 Evaluation of Sustained Stresses at Unflawed Locations As part of CECO's IGSCC mitigation program, various IGSCC-
- susceptible piping velds at Quad Cities Unit 2 have been mitigated by the Induction Heating Stress Improvement (IHSI) ,
process or the Mechanical Stress I=provement Process (MSIP). Other susceptible welds may be considered for future stress improvement (SI) mitigation. Because tha effectiveness of SI treatment is related to the applied stress acting on a weldment, it is recommended in Supplement 1 to Generic Letter 88-01 (Reference 12) that the service or sustained stress (unintensified internal pressure + dead weight + thermal expansion + weld overlay shrinkage stresses) for weldments receiving SI treatment be evaluated. The sustained stresses for unflawed and unrepaired welds outside of NUREG-0313 ISI Inspection Category "A" in various susceptible systems are tabulated in Appendix C. COE-301-200 3.2 P/4ElFIE Revision 0 NUELE/4R.
i i l Table 3.1-1 EXPANDED ALLOWABLE END-OF-EVALUATION PERIOD FLAW DEPTH-TO-THICKNESS RATIOS FOR CIRCUMFERENTIAL FLAWS IN BASE METAL OR GTAW WELDMENTS DURING NOPRAL OPERATING CONDITIONS (see Note 1) RATIO OF FLAW LENGTH (L) TO PIPE CIRCUMFERENCE (Note 3) STRESS ' RATIO (Note 2) 0.0 0.1 0.2 0.3 0.4 20.5 1.5 (4) (4) (4) (4) (4) (4) 1.4 0.75 0.40 0.21 0.15 (4) (4)- 1.3 0.75 0.75 0.39 0.27 0.22 0.19 1.2 0.75 0.75 0.56 0.40 0.32 0.27 1.1 0.75 0.75 0.73 0.51 0.42 0.34 1.0 0.75 0.75 0.75 0.63 0.51 0.41 O.9 0.75 0.75 0.75 0.73 0.59 0.47 0.8 0.75 0.75 0.75 0.75 0.68 0.53 0.7 0.75 0.75 0.75 0.75 0.75 0.58 0.6 0.75 0.75 0.75 0.75 0.75 0.63
- 0. Sc5) 0.75 0.75 0.75 0.75 0.75 0.68 0 . 4 c5) 0.75 0.75 0.75 0.75 0.75 0.73 50.36(5' O.75 0.75 0.75 0.75 0.75 0.75 NOTES:
(1) Flaw Depth = "a" for a surface flaw or
*2a" for a subsurface flaw.
"t" = nominal thickness.
Linear interpolation is permissible. (2) Stress Ratio = ( P + P,) /S, where: P. = primary longitudinal membrane stress (P s 0.55 ). P. = primary bending stress. S. = allowable design stress intensity in accordance with ASME Section III (Reference 13). (3) Circumference based upon nominal pipe diameter; "L" = end-of-evaluation period flaw length. (4) IWB-3524.3 shall be used.
~.
(5) Derived using source eTaations (Figure 3.1-1). COE-301-200 3.3 P/4EIFIC Revision 0 NUELE/4R.
Table 3.1-2 LEAKAGE BARRIER REPAIR CRITERIA FOR AXIAL FLAWS (Reference 11) STRESS NONDIMENSIONAL FLAW LENGTH (Note 2) RATIO (Note 1) 0.00 0.25 0.50 1.00 ;t 2.00 1.00 .. ( 3 ) (3) (3) (3)~ (3) 0.95 (4) (4) (3) -(3) (3) 0.90 (4) (4) (4) (3) (3). 0.80 (4) (4) (4) (4) ( 3 ) -~ 0.70 (4) (4) (4) (4) (3)- 0.60 (4) (4) (4) (4) (3) 0.50 (4) (4) (4) (4) (3}' 50.40 (4) (4) (4) (4) (3) ETIS: (1) Stress Ratio = (P
- OD)/(2
- t
- S.)
where: P = maximum pressure for normal operating conditions. f OD = nominal outside diameter of pipe. t = nominal thickness. S. = allowable design stress intensity in accordance with ASME Section III (Reference 13). (2) Nondimensional Flaw Length = M where R = Nominal radius of pipe. L = end-of-evaluation period flaw length. (3) IhT-3640 shall be used. (4) Only a
- Leakage Barrier
- weld overlay repair is required j (t a 0.125*). i l
1 j I i COE-301-200 Revision 0 3.4 @PAEIFIC NUELEAR. , i l
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N --> I , .- . CROSS-SECTION FLOW STRESS APPUED STRESS * (PARTWALLWPG) 6 J FOR 8 + $ < 18 0*: ju-0^ " !
=
2 (radians) i SF(SR) - 0.5 1x (2 sin -
"t sin 0) =0 '
i t FOR 6 + $ > 18 0*: ' i x(E6 ") l i p= t (radians) l 2" t SF (SR) - 0.5 1x (2 - ") t sin =0 I i I Figure 3.1-1 l l SOURCE EOUATIONS FOR ALLOWABLE END-OF-EVALUATION PERIOD l FLAW DEPTH-TO-THICKNESS RATIOS FOR CIRCUMFEREN'iIAL FLAWS -- i l' COE-301-200 3.5 R9EIFit Revision 0 NUELFAR.
where: i 1.= nalf-crack angle (radians) L,= total circumferential crack length S= neutral axis location angle (radians) a= flaw depth (inches) t= pipe thickness (inches) OD = outside pipe diameter (inches) R= mean pipe radius (inches) = (OD - t) / 2 S= allowable design stress intensity P, = primary longitudinal menbrane stress (50.5S) P= primary bending stress P, = unconcentrated expansion stress For Base Metal and For SMAW and SAW GTAW Weldments: Weldments: SR = P" + D^b M(P +P P
+ JL)
Sm SF SR = S, SF = 2.77 SF = 2.77 x 1.449 = 4.018 For SMAW Weldments: For SAW Weldments: M= 1.0 when OD 5 24" M= 1.08 when OD 5 24" M= 1.0 + 0.01(OD - 24) M= when OD > 24" 1.08 + 0.009(OD - 24) when OD > 24" l Figure 3.1-1 SOURCE EOUATIONS FOR ALLOWABLE END-OF-EVALUATION PERIOD FLAW DEPTH-TO-THICKNESS RATIOS FOR CIRCUMFERENTIAL FLAWS (Concluded) COE-301-200 3.6 PACIFIC Revision 0 NUELE/4R. i l
4.0 STRESSES As discussed in Section 3.0, various stress combinations are used in evalu2 ting weld overlay repairs and sustained stresses acting on unflawed and unrepaired welds. This section presents the stresses acting on the welds discussed in this report. 4.1 Primary Stresses Primary stresses include the effects of deadweight, internal pressure, and seismic loads. The design pressure ci 1,250 psi was obtained from IMPELL, Sargent & Lundy, and Pacific Nuclear piping system analyses (References 14 through 19). The deadweight and seismic stresses applied to each weld were also obtained from these references. The magnitudes of these stresses acting on weld overlay repairs are shown in Table 4.1-1. The magnitudes of these stresses used in the sustained stress evaluation of unflawed and unrepaired welds are shown in Appendix C. 4.2 Secondary Stresses Secondary stresses include the following:
- 1. Thermal Stresses The piping system differential thermal expansion stresses used in the sustained stress evaluations presented in this report were obtained from IMPELL, Sargent & Lundy, and Pacific Nuclear piping system analyses (References 14 through 19).
COE-301-200 4.1 Revision 0
@ PACIFIC NUELFAR. :
- 2. Weld overlay Shrinkage-Induced Stresses Each veld overlay causes a small amount of axial shrinkage underneath the overlay. This shrinkage primarily induces bending stresses at other locations in the piping system. These shrinkage-induced stresses are calculated using the Pacific Nuclear computer program PISTAR (Reference 20). Figure 4.2-1 presents the piping model used. This model in ludes the Reactor Recirculation, Residual Heat Removal (Low Pressure Coolant Injection and Shutdown Cooling), and Reactor Water Clean-Up systems inside the drywell. The actual as-built shrinkages as presented in Appendix A are used in the analysis. The resulting shrinkage stresses are included in the sustained stress evaluations presented in this report.
4.3 Sustained Stress Evaluation at Unflawed Weld Locations As discussed in Section 3.2, sustained stresses at unflawed and unrepaired weld locations outside of NUREG-0313 ISI Inspection Category "A" should be evaluated. This c'aluation is limitnd to the following susceptible systems lisied in CECO's response to Generic Letter 88-01 for Quad Cities Unit 2: A) Ma'.ator Recirculation B) Shutdown Cooling C) Low Pressure Coolant Injection (LPCI) D) Core Spray E) Reactor Water Clean-Up (RWCU) F) Jet Pump Instrumentation Nozzles G) Head Vent Nozzle H) Spare Nozzles ' t COE-301-200 4.2 Revision 0 m
'sirPREIFIE NUELEAR. :
The sustained stress level at a weld location consists of
.unintensified internal pressure, dead weight, thermal expansion and weld overlay-induced shrinkege stresses.
Initially, a review was made of piping systems that do not presently have weld overlay repairs. This was done to determine if the original design code compliance of these systems could be used to verify that the sustained stress limits were met. It was realized that a general statement to this effect cannot be made for plants designed under USAS B31.1.0 because the design allowables are not related to S,. Furthermore, stress intensification factors used in the design make such an evaluation incompatible with the requirements of NUREG-0313. The sustained stresses were, therefore, calculated on a system unique basis for the susceptible systems listed above. The jet pump instrumentation, head vent, and spare nozzles are affected by internal pressure only and, therefore, are not addressed in this document. The RWCU system currently contains only NUREG-0313 ISI Category "A" weldments, therefore, it is not further addressed in this document. The sustained stresses for the welda in the remaining systems are presented in Appendix C. 1
)
i I 1 l CCE-301-200 4,3 l Revision 0 hpA{lpg{ l NUELEAR. ! l 1
Table 4.1-1 OUAD CITIES UNIT 2 APPLIED STRESSES FOR WELD OVERLAY REPAIR EVALUATIONS DESIGN PRESSURE DEADWEIGHT SEISMIC TOTAL WELD PIPE WALL STRESS STRESS STRESS OVERLAY ID TNK. ( t,,) (P) (OW) (DBE) S T RE S S'" (inches) (psi) (psi) (psi) (psi) 02C-53 0.653 6102 3 72 590 70 % C2C-54* 0.690 5 775 516 1106 7397 02C- F 7 0.687 4642 397 1850 6389 02D 53 0.669 5956 213 841 7010 C2D-F6 0.595 6696 475 2604 9775 02E-$3 0.656 6074 109 1030 7213 C2E-F6A 0.653 6102 342 2354 8798 C2F-53 0.661 6027 23 1202 7252 C2F-F6 0.590 6753 736 3452 10941 020-53 0.662 6019 186 1511 7716 ' C2G-54 0.711 5940 240 805 6985 02M-53 0.684 5825 120 1170 7115 C2H-54" 0.680 5859 156 1287 7302 C2J-53 0.826 4824 73 1C33 5930 C2J-54 0.651 6001 96 744 6841 C2J-F6 0.648 6149 274 2317 8740 C2K-53 0.664 6001 91 1231 7323 C2K-54 0.673 5921 24 689 6634 02K-F6 0.603 6608 418 3292 10318 C2L-53 0.664 6001 112 1557 7670 02L-54 0.678 5974 149 1119 7242 C2M 53 0.662 6019 240 1272 7531 C2M-54 0.684 5825 180 1048 7053 C2M-F7 0.5 70 6991 647 3532 11170 C2B-59 1.184 5802 0 4 5806 02AD 56 1.432 6110 360 6 73 7143 C2AD-F12 1.377 6448 528 1825 8501 02AS-54 1.425 6141 182 354 6677 C2AS-59 1.263 6415 228 400 7043 C2AS-S12 1.387 6308 156 848 7312 C2AS-F14 1.360 6*34 204 1180 7818 02sD-56 1.420 6158 432 549 7139 C2sD-F8 1.455 6263 255 435 6953 02BS-F2 1.393 6281 110 359 6750 0285-53 1.418 6171 302 234 6707 C2BS-F7 1.250 7000 324 455 7779 02BS-512 1.417 6175 168 342 6685 105-F1 1.016 6152 912 3090 10154 105-F5 1.021 6122 333 390 6845 NOTESs (1) Total Overlay Strees = P + DW + 00E. (2) Unflawed weld. COE-301-200 4.4 Revision 0 hpfy{jpl{ NUCLEAR.
i N e r- - - m '
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( d:: 4 DNY- - I g / 5
v c N i I f Figure 4.2-1 WELD OVERLAY SHRINKAGE ANALYSIS MODEL - COE-301-200 4.5 ! Revision 0 w A PA EIFIC : NUCLEAR. i I
I i 5.0 EVALUATION METHODS AND RESULTS This section contains the evaluation methods and results utilized to assess the acceptability of the overlay-repaired weldments at Quad Cities Unit 2. 5.1 Weld Overlav Repair Evaluation Tables 5.1-1 and 5.1-2 present the pipe, weld overlay repair, and flaw geometry details needed to calculate the applied stress and flaw depth ratios for all the circumferential1y flawed overlay-repaired welds at Quad Cities Unit 2. Applied stresses are found in Table 4.1-1. Table 5.1-3 presents a comparison of predicted flaw depth ratios due to applied loads versus the allowable flaw depth ratios for the circumferential flaws detailed in Table 5.1-2. As discussed in Section 3.1, the allowable flaw depth ratios shown were determined from Table 3.1-1. As a result, all the weld overlay repairs presented in Table 5.1-1 meet NUREG-0313, Revision 2
" standard" overlay requirements.
Tables 5.1-4 and 5.1-5 show the pipe and flaw geometric details needed to determine predicted and allowable " leakage barrier" remaining ligament thicknesses for all the overlay-repaired welds at Quad Cities Unit 2. Table 5.1-6 presents a comparison of predicted remaining ligament thicknesses for the weldments given in Table 5.1-4 with allowable remaining ligament thicknesses determined using the " leakage barrier" criteria presented in Table 3.1-2. COE-301-200 5.1 Revision 0 PM EIFIE NUELEAR. I
reportable indications" in this weldment. Therefore, Pacific Nuclear's modified weld overlay repair evaluation approach appears to be overly conservative for this weldment. _Accordingly, Pacific Nuclear believes that the following
~ approach should be utilized for this weldment:
a = 1.184" + 0.005" = 1.189" t = 1.184" + (0.514" - 0.113") = 1.585" a/t = 1.189"/1.585" = 0.75 Therefore, weld 02B-S9 is acceptable per NUREG-0313 and ASME Section XI acceptance criteria. 5.3 Weld 02C-F7 Discussion One flawed weld (02C-F7) was identified during this outage and given a " standard" weld overlay repair. The delta ferrite measurement for the first layer was greater than the required 7.5 FN at all locations as indicated in Table 5.1-1. The finished thickness of the overlay was 0.406" as indicated in Table 5.1-1. The effect of the 02C-F7 overlay on the deadweight and stiffness of the piping system is negligible. The additional weight of the overlay is less than 1/4 of a pipe diameter (< 20 lbs.) and the thickened overlay section is less than 4" wide on a riser that is over 17 feet long. The effect of the 02C-F7 overlay shrinkage upon pipe supports and whip restraints is also negligible. The maximum piping displacement from this overlay is approximately 0.14" which is within normal pipe support tolerances for gaps / clearances. Thus pipe support travel and restraint clearances will not require modification. COE- 3 01-2 00 Revision 1 5.3 @P/4CIFIE NUELE/4R.
5.2 Weld 02B-S9 Discussion Weld 02B-S9 received a " standard" weld overlay repair during the 1986 outage. Because the primary stress load combination acting on this weld is low, this overlay had a conservative design thickness of 0.38" based upon a design pipe wall thickness of 0.979". The minimum as-built overlay thickness for this weld, excluding the low ferrite content first layer, is 0.401" (see the Reference 3 NUTECH report). Since the 1986 outage, Facific Nuclear has conservatively modified its approach for the evaluation of weld overlav repairs. As shown in Tables 5.1-1 and 5.1-2, this modified approach now bases the evaluation flaw depth on the as-built thickness of the flawed pipe wall and any low ferrite content layers. For weld 02B-S9, the critical as-built pipe wall thickness is 1.184", the low ferrite content first layer thickness is 0.113", and the total weld overlay repair thickness is 0.514". Using a balance-of-plant life fatigue crack growth depth of 0.005" results in the following: a (flaw depth) = 1.184" + 0.113" + 0.005" = 1.302"" t (thickness) = 1.184" + 0.514" = 1.698" a/t = 1.302"/1.698" 77 This value is slightly greater than the Table 3.1-1 maximum allowable a/t value of 0.75 for a flawed component having an applied stress ratio of only 0.24. A review of the 1988 outage volumetric ultrasonic examination (UT) results for this weldment (Appendix A) show that all detectable circumferential indications are below the low ferrite content first layer. The 1990 and 1993 outage ' volumetric UT examinations (also in Appendix A) found "no COE-301-200 5.2 @ PACIFIC Revision 1 NUELEAR.
i Table 5.1-1 OUAD CITIES UNIT 2 CIRCUMFERENTIALLY FLAWED OVERLAY-REPAIRED WELDS PIPE AND WELD OVERLAY REPAIR GEOMETRY DETAILS MAXIRJN MIN. TOTAL LOW FW 1si WELO P E TMK. (t,) THK. (t ) ( t.) THK (t )* gp g ) (inches) (inches) (inches) 02C-s3 12.750 0.653 0.355 N/A 1.005 02C-54* 12.750 0.690 0.343 N/A 1.033 C2C F7 12.750 0.684 0.406 N/A 1.090 02D 53 12.750 0.669 0.293 N/A 0.962 02D F6 12.750 0.595 0.329 N/A 0.924 C2E-53 12.750 0.656 0.351 N/A 1.007 02E-F6A 12.750 0.653 0.314 N/A 0.967 C2F-s3 12.750 0.661 0.303 N/A 0.964 02F-F6 12.750 0.590 0.355 N/A 0.945 02G-53 12.750 0.662 0.307 N/A 0.969 C2G-54 12.750 0.711 0.253 N/A 0.964 C2H 53 12.750 0.684 0.326 N/A 1.0?0 02 H - 54'* 12.750 0.680 0.313 h/A 0.993 02J-s3 12.750 0.826 0.378 N/A 1.204 02J-54 12.750 0.651 0.280 N/A 0.931 02J-F6 12.750 0.648 0.372 N/A 1.020 02K-s3 12.750 0.664 0.298 N/A 0.962 C2K-54 12.750 0.673 0.309 N/A 0.982 02K F6 12.750 0.603 0.316 N/A 0.919 C2L-53 12.750 0.664 0.333 N/A 0.997 02L-54 12.750 0.678 0.323 N/A 1.001 C2m 53 12.750 0.662 0.404 N/A 1.066 C2N 54 12.750 0.684 0.291 N/A 0.975 02N-F7 12.750 0.570 0.512 N/A 1.082 028-59 22.000 1.184 0.514 0.113 1.698 C2AD-56 28.000 1.432 0.497 N/A 1.929 02AD-F12 28.000 1.377 0.575 N/A 1.952 02AS s4 28.000 1.425 0.499 N/A 1.924 C2AS-59 28.000 1.363 0.488 N/A 1.851 02As-s12 28.000 1.36/ 0.557 N/A 1.944 C2AS-F14 28.000 1.360 0.570 N/A 1.930 C280 56 28.000 1.420 0.530 N/A 1.950 C2BD-F8 28.000 1.455 0.540 N/A 1.995 C2BS F2 28.000 1.393 0.50s8 N/A 1.901 0285-53 28.000 1.418 0.492 N/A 1.910 C2BS-F7 28.0ba 1.250 0.484 N/A 1.734 02BS 512 28.000 1.417 0.525 N/A 1.942 10s-F1 20.000 1.016 0.491 N/A 1.507 1CS-F5 20.000 1.021 0.543 N/A 1.5 64 NOTESs (1) OD = outside diameter. (2) Low ferrite number (FN) first layer thickness. (3) Total thickness = t, + t,. (4) Unflawed welds. . (5) All thickness dimensions are as-built dimensions. ~ COE-301-200 5.4
@P/4ElFIE Revision 0 NUELE/4R.
Table 5.1-2 > j OUAD CITIES UNIT 2 , CIRCUMFERENTIALLY FLAWED OVERLAY-REPAIRED WELDS FLAW GEOMETRY DET_ AILS EVALUA110N FLAW LINGTN (L) EVALUATION FLAW DEP1h (a) WELD Inches or s"' a," t,* a* ID ,L, Degrees (radians) OI (inches) (inches) (inches) , 02C-53 360 DEG. 3.14 100 0.005 N/A 0.658 ! 02C-54* 360 DEG. 3.14 100 0.005 N/A 0.695 02C-F7 360 DEG. 3.14 100 0.005 N/A 0.689 ; C2D-53 360 DEG. 3.14 100 0.005 N/A 0.674 , 023-76 360 DEG. 3.14 100 0.005 N/A 0.600 t 02E-s3 360 DEG. 3.14 100 0.005 N/A 0.661 , CZE F6A 360 DEG. 3.14 100 0.005 N/A 0.658 l 02F-53 360 DEG. 3.14 100 0.005 0.61 0.666 l 02F-F6 360 DEG. 3.14 100 0.005 N/A 0.595 ; 02G-s3 360 DEG. 3.14 100 0.005 0.65 0.667 ; 02G s4 360 DEG. 3.14 100 0.005 N/A 0.716 02N-53 360 CEG. 3.14 100 0.005 N/A 0.689 ! 02N-54* 360 DEG. 3.14 100 0.005 N/A 0.685 ! 02J-s3 360 DEC. 3.14 100 0.005 N/A 0.831
- 02J-54 360 DEG. 3.14 100 0.005 N/A 0.656 I 02J-F6 360 DEG. 3.14 100 0.005 N/A 0.653 02K-s3 360 DEG. 3.14 100 0.005 k/A 0.669 02K-54 360 DEG. 3.14 100 0.005 N/A 0.678 !
02K-F6 360 DEG. 3.14 100 0.005 N/A 0.608 ' i 02L 53 360 DEG. 3.14 100 0.005 0.76 0.669 ; 02L-54 360 CEG. 3.14 100 0.005 N/A 0.683 l 02M-53 360 DEG. 3.14 100 0.005 N/A 0.667 , 02M-s4 360 DEC. 3.14 100 0.005 N/A 0.689 f 02M-F7 360 DEG. 3.14 100 0.005 N/A 0.575 i 028-s9 360 DEC. 3.14 100 0.005 N/A 1.302 [ 02AD-s6 360 DEG. 3.14 100 0.005 N/A 1.437 02AD-F12 360 CEG. 3.14 100 0.005 N/A 1.382 i 02AS-54 360 DEC. 3.14 100 0.005 N/A 1.430 l 02As s9 360 DEG. 3.14 100 0.005 k/A 1.368 ! 02As 512 360 DEC. 3.14 100 0.005 N/A 1.392 ( 02AS F14 360 DEG. 3.14 100 0.005 N/A 1.365 f 0280-56 360 DEG. 3.14 100 0.005 N/A 1.425 i 02BD-F8 360 DEC. 3.14 100 0.005 N/A 1.460 i 02ss F2 360 DEG. 3.14 100 0.005 k/A 1.398 0285 s3 360 DEG. 3.14 100 0.005 0.52 1.423 f 0285 F7 360 DEG. 3.i4 100 0.005 N/A 1.255 ! 0285-512 360 DEG. 3.14 100 0.005 N/A 1.422
- 10s-F1 360 DEG. 3.14 100 0.005 N/A 1.021 105 F5 360 DEG. 3.14 100 0.005 N/A 1.026 l NOTES:
(1) Half crack angle . ! (2) Crack depth from inside surface as % of wall thickness. l (3) Balance-of-plant life fatigue allowance. (4) Remaining ligament from outside surface. ' (5) Flaw Depth = maximum of ( % t, + tr +r a ) or (t - t, + at) . ! (6) Unflawed weld. : t l COE-301-200 5.5 OP/4EIFIC Revision 0 NUELFAR. t
m ._. 1 - m;2 a u ., _ ._ . ~ . , - .
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i Table 5.1-3 l l t OUAD CITIES UNIT 2 i CIRCUMFERENTIALLY FLAWED OVERLAY-REPAIRED WELDS ! PREDICTED VS. ALLOWABLE FLAW DEPTH RATIOS I WELD FLR"' S.* $ I ALLOWABLE PREDICTED FDR ID RATID . FDR FDR* CHECK'* f i 02C-S3 1.0 16950 0.27 0. 75 0.65 OK i 02C-54* 1.0 16950 0.29 0.75 0.67 OK l 1 02C-F7 1.0 16950 0.26 0.75 0.63 oc I C2D-53 1.0 16950 0.29 0.75 0.70 OK [ 02D-F6 1.0 16950 0.37 0.75 0.65 OK L 02E-53 1.0 16950 0.28 0.75 0.66 oc ; q C2E-F6A 1.0 16950 0.35 0.75 0.68 OK ; r 02F-s3 1.0 16950 0.29 0.75 0.69 OK i 027 F6 1.0 16950 0.40 0.73 0.63 OK ! 02G-53 1.0 16950 0.31 0.75 0.69 OK 1.0 f 02G 54 16950 0.30 0.75 0.74 OK , C2H 53 1.0 16950 0.28 0.75 0.68 OK j 02H-$4" 1.0 16950 0.30 0.75 0.69 OK J 02J-s3 1.0 16950 0.24 0.75 0.69 OK { 02J 54 1.0 16950 0.28 0.75 0.70 OK ! j C2J-F6 1.0 16950 0.33 0.75 0.64 OK C2K-s3 1.0 16950 0.30 0.75 0.70 OK t
< 02K-54 1.0 16950 0.27 0.75 0.69 OK [
02K-F6 1.0 0.40 ' 16950 0. 73 0.66 OK C2L-$3 1.0 16950 0.30 0.75 0.67 OK C2L-54 1.0 16950 0.29 0.75 0.68 OK C2M-53 1.0 16950 0.28 0.75 0.63 oc , C2M-04 1.0 16950 0.29 0.75 0.71 oc { C2M-F7 1.0 16950 0.35 0.75 0.53 OK i C28-59 1.0 16950 0.24 0.75 (8) (8) f C2AD-56 1.0 16950 0.31 0.75 0.74 OK f C2AD-F12 1.0 16950 0.37 0.75 0.71 oc C2AS-54 1.0 16950 0.29 0.75 0.74 OK f C2AS-39 1.0 16950 0.31 0.75 0.74 or 02AS 512 1.0 16950 0.31 0.75 0.72 OK '
- C2As-F14 1.0 16950 0.33 0.75 0.71 OK
, C2BD-so 1.0 16950 0.31 0.75 0.73 OK [
- 02BD-F8 1.0 16950 0.30 0.75 0.73 OK !
C285-F2 1.0 16950 0.29 0.75 0.74 OK [ C2BS-s3 1.0 16950 0.29 0.75 0.75 OK < J C2BS-F7 1.0 16950 0.33 0.75 0. 72 OK I C2B5-512 1.0 16950 0.29 0.75 0. 73 OK 105 F1 1.0 16950 0.40 0.73 0.68 OK 10$-F5 1.0 16950 0.26 0.75 0.66 OK ] t NOTES: ) (1) FLR = flaw length ratio = a/n; a from Table 5.1-2. [ (2) Allowable design stress intensity 9550*F per ASME j section III Appendices Table I-1.2 for Type 304 Material. > (3) Applied Stress Ratio = (total overlay stress /S.) x (tg/t). [ (4) Allowable flaw depth ratio from Table 3.1-1. . ' } (5) Predicted flaw depth ratio = a/t; "a" from Table 5.1-2. ~ , (6) If predicted FDR < allowable FDR, weld is "OK". ; (7) Unflawed weld.. (8) Detailed discussion of weld 02B-S9 may be found in f COE-301-200 5.6 OPACIFIE i Revision 0 NUELF.MR. i l t
Table 5.1-4 OUAD CITIES UNIT 2 AXIALLY FLAWED OVERLAY-REPAIRED WELDS PIPE AND WELD OVERLAY REPAIR GEOMETRY DETAILS MAXIWJM MlW. TOTAL LOW FN 1ST ' p g n FIPE WALL OvtRLAY LAYER ,THC. ID (imbes) T (inches') (inches) (inches) (inches) C20-53 12.750 0.653 0.355 N/A 1.008 C20- 54* 12.750 0.690 0.343 h/A 1.C33 02C-F7 12.750 0.6S4 0.406 h/A 1.090 02D-53 12.750 0.669 0.293 w/A 0.962 02D-F6 12.750 0.5 95 0.329 k/A 0.924 02E s3 12.750 0.656 0.351 N/A 1.007 C2E-F6A 12.750 0.653 0.314 N/A 0.967 02F-53 12.730 0.661 0.303 N/A 0.964 C2F-86 12.750 0.590 0.355 h/A 0.945 C2C-s3 12.750 0.662 0.307 h/A 0.969 C2G-$4 12.750 0.711 0.253 h/A 0.964 02H 53 12.750 0.6B4 0.326 h/A 1.010 , 02 H - $4 12.750 0.680 0.313 N/A 0.993 C2J-53 12.750 0.826 0.378 w/A 1.204 C2J-$4 12.750 0.651 0.280 k/A 0.931 C2J-76 12.750 0.648 0.3 72 h/A 1.C20 C2r-53 12.750 0.664 0.298 N/A 0.962 02r-$4 12.750 0.673 0.309 N/A 0.982 02K-F6 12.750 0.603 0.316 N/A 0.919 02L-s3 12.750 0.664 0.333 N/A 0.997 C2L-$4 12.750 0.678 0.323 N/A 1.001 C2M-53 12.750 0.662 0.404 m/A 1.066 C2M-54 12.750 0.684 0.291 h/A 0.975 C2M-F7 12.750 0.570 0.512 W/A 1.082 028-59 22.000 1.184 0.514 0.113 1.698 CZAD 56 28.000 1.432 0.497 N/A 1.929 C2AD F12 28.000 1.377 0.575 N/A 1.952 C2As-$4 28.000 1.425 0.499 W/A 1.924 02AS-59 28.000 1.363 0.488 N/A 1.851 C2AS-512 28.000 1.387 0.557 w/A 1.944 C2AS-F14 28.000 1.360 0.5 70 h/A 1.930 C2BD 56 23.000 1.420 0.530 N/A 1.950 C2BD-F8 28.000 1.455 0.540 N/A 1.995 i C2SS-F2 28.000 1.393 0.508 m/A 1.901 02E5-53 28.000 1.418 0.492 W/A 1.910 02Es-F7 28.000 1.250 0.484 W/A 1.734 02BS-512 28.000 1.417 0.525 W/A 1.942 105-F1 20.000 1.016 0.491 N/A 1.507 1CS-F5 20.000 1.021 0.543 W/A 1.5 64 NOTES: (1) OD = outside dia2neter. (2) Low ferrite number (TN) first layer thickness. (3) Total thickness - t, + t . Unflawed welds. (4) (5) All thickness dimensions are as-built dimensions. , COE-301-200 5.7
@PAEIFIE Revision 0 NUELEAR.
Table 5.1-5 OUAD CITIES UNIT 2 AXIALLY FLAWED OVERLAY-REPAIRED WELDS FLAW GEOMETRY DETAILS tu gg L L.G1 t,De 4* t.Me ID (inches) (inches) (irches) (inches) (inches) 02C-s3 0.39 0.98 0.41 0.005 0.350 C2C-54* N/A 1.04 N/A 0.005 0.338 C2c-F7 0.43 1.C3 0.52 0.005 0.401 02D-13 0.30 1.00 0.30 0.005 0.288 C2D-F6 0.39 0.89 0.50 0.005 0.324 02E-53 0.41 0.98 0.38 0.005 0.346 C2E-F6A N/A C.98 h/A 0.005 0.309 C27-53 N/A 0.99 W/A 0.005 0.298 02F-F6 N/A 0.89 N/A 0.005 0.350 C20-53 N/A 0.99 N/A 0.005 0.302 C2G-54 0.25 1.07 0.43 0.005 0.248 C2N-53 0.31 1.C3 0.65 0.005 0.321 02H S4' N/A * .C2 N/A 0.005 0.308 C2J-s3 0.50 1.24 0.47 0.005 0.3 73 C2J-s4 0.80 0.98 0.38 0.005 0.275 02J-F6 0.51 0.97 0.42 0.005 0.367 C2K-53 0.39 1.00 0.38 0.005 0.293 C2C-54 0.61 1.01 0.35 0.005 0.304 C2K-F6 0.65 0.90 0.38 0.005 0.311 C2L-53 0.70 1.00 0.44 0.005 0.328 02L-s4 N/A 1.C2 N/A 0.005 0.318 C2M s3 0.60 0.99 0.42 0.005 0.399 02M-54 N/A 1.03 N/A 0.005 0.286 02m F7 h/A 0.86 N/A 0.005 0.507 028-59 h/A 1.78 N/A 0.005 0.396 4 C2AD-56 N/A 2.15 N/A 0.005 0.492 02AD-F12 N/A 2.07 N/A 0.005 0.570 C2AS-54 N/A 2.14 N/A 0.005 0.494 02AS-59 N/A 2.04 N/A 0.005 0.483 CZAs-512 N/A 2.08 N/A 0.005 0.552 C2AS-F14 N/A 2.04 N/A 0.005 0.565 C2sD-56 N/A 2.13 N/A 0.005 0.525 02BD-F8 N/A 2.18 N/A 0.005 0.535 C2Bs-F2 N/A 2.09 N/A 0.005 0.503 C285-s3 h/A 2.13 k/A 0.005 0.487 02ES-F7 N/A 1.88 N/A 0.005 0.479 C2SS-512 N/A 2.13 N/A 0.005 0.520 10$-F1 N/A 1.52 k/A 0.005 0.486 105-F5 N/A 1.53 k/A 0.005 0.538 NOTES: (1) Maximum measured axial flaw length. (2) Flaw evaluation length, taken as the greater of:
- a. "L" o-
- b. 1.5=t per NUREG-0313, Rev. 2; t, from Table 5.1-4.
(3) Minimum measured remaining ligament. (4) Balance-of-plant life fatigue allowance. , (5) Minimum overlay thickness, taken as the lesser of :
- a. t, - a, o r ~
li
- b. t, - (tp a,) ; t, and tr f rom Table 5.1-4.
(6) Unflawed weld. l I i COE- 3 01-2 00 5.8 @PMEIFIE ! Revision 0 NUELFAR. I l l
Table 5.1-6 OUAD CITIES UNIT 2 j I AXIALLY FLAWED OVERLAY-REPAIRED WELDS PREDICTED VS. ALLOWABLE REMAINING LIGAMENT THICKNESS l IW1. press. s*n, APPLIED FLR REQUIRED t. ! WELD ACTUgL ALLO,W. I= sfREss M' I CHECKt t." CHECK 1D (P) (psi) R A11D* 5) (951) (inches) 48) 02C-53 1250 16950 0. 72 0.48 1.00 OK 0.350 0.125 oK C2C-$4" 1250 16950 0.68 0.49 1.00 OK 0.338 0.125 OK { C2C-F7 1250 16950 0.69 0.49 1.00 OK 0.401 0.125 OK C2D 53 1250 16950 0.70 0.49 1.00 OK 0.288 0.125 OK ! C2D F6 1250 16950 0.79 0.46 1.00 OK 0.324 0.125 OK 02E-53 1250 16950 0.72 0.48 1.00 OK 0.346 0.125 OK C2E F6A 1250 16950 0.72 0.48 1.00 ot 0.309 0.125 or i 02F-s3 1250 16950 0.71 0.48 1.00 OK 0.298 0.125 OK C2F F6 1250 16950 0.80 0.46 1.00 ot 0.350 0.125 OK C2C-s3 1250 16950 0.71 0.48 1.00 oK 0.302 0.125 OK 02C-54 1250 16950 0.66 0.50 1.00 OK 0.248 0.125 OK ! C2H-53 1250 16950 0.69 0.49 1.00 or 0.321 0.125 oc ! C2H-$4" 1250 16950 0.69 0.49 1.00 OK 0.308 0.125 oK , C2J 13 1250 16950 0.57 0.54 1.00 oK 0.373 0.125 or 1 02J-54 1250 16950 0. 72 0.48 1.00 or 0.275 0.125 OK I C2J-F6 1250 16950 0.73 0.48 1.00 oK 0.367 0.125 or C2K-53 1250 16950 0.71 0.48 1.00 OK 0.293 0.125 OK + C2K-$4 1250 16950 0.70 0.49 1.00 or 0.304 0.125 oK - I C2K-F6 1250 16950 0.78 0.46 1.00 OK 0.311 0.125 oK C2L-53 1250 16950 0.71 0.48 1.00 or 0.328 0.125 OK l C2L-s4 1250 16950 0.69 0.49 1.00 OK 0.318 0.125 ot ! 02M-s3 1250 16950 0.71 0.48 1.00 or 0.399 0.125 oK I C2M-s4 1250 16950 0.69 0.49 1.00 OK 0.286 0.125 OK ! 02M-F7 1250 16950 0.82 0.45 1.00 OK 0.507 0.125 ot ; 028-s9 1250 16950 0.69 0.49 1.00 or 0.396 0.125 OK l 02AD s6 1250 16950 0. 72 0.48 1.00 or 0.492 0.125 OK l 02AD-F12 1250 16950 0.75 0.47 1.00 OK 0.570 0.125 oc ; C2AS-54 1250 16950 0.72 0.48 1.00 ot 0.494 0.125 OK 02AS-59 1250 0.76 0.47 C2AS-s12 1250 16950 0.74 1.00 OK 0.483 0.125 OK- l 16950 0.47 1.00 cc 0.552 0.125 OK C2As-F14 1250 16950 0.76 0.47 1.00 or 0.565 0.125 OK 028D-56 1250 16950 0.73 0.48 1.00 OK 0.525 0.125 OK l 02BD-F8 1250 16950 0.71 0.48 1.00 OK 0.535 0.125 OK : C2BS-F2 1250 16950 0.74 0.47 1.00- OK 0.503 0.125 OK f 02Bs-$3 1250 16950 0.73 0.48 1.00 OK 0.487 0.125 OK l C2Bs-F7 1250 16950 0.83 0.45 1.00 OK 0.479 ot 0.125_ _) . 02Bs s12 1250 16950 0. 73 0.48 1.00 or 0.520 0.125 OK t 105-F1 1250 16950 0. 73 0.48 1.00 OK 0.486 0.125 OK L 10s-F5 1250- 16950 0.72 0.48 1.00 OK 0.538 0.125 OK l i NOTES: i (1) Allowable design stress intensity 9550*r per Aswa section III ! Appendices Table I-1.2 for Type 304 material. . (2) Applied Stress Ratio = (P*OD) / (2xt,xSm); OD and t, from Table 5.1-4. l (3) Flaw Length Ratio = L,//0. 5
- ode t,; L, from Table 5.1-5. l (4) Allowable FLR from Table-3.1-2.
(5) If actual FLR < allowable TLR, *0K". { (6) Minimum end-of-evaluation period (balance-of-plant life) overlay t thickness; from Table 5.1-5. , , 2' (7) Minimum required Leakage Barrier overlay thickness; from Table 3.1-2". j (8) I f t, > t., "OK". i (9) Unflawed weld. ' i COE-301-200 5.9 OPAE1 Fir. ! s Revision 0 NUELEAR. ' F
)
I 6.O
SUMMARY
AND CONCLUSIONS Ultrasonic (UT) examinations performed during the 1983 outage at Commonwealth Edison's Quad Cities Nuclear Power Station Unit 2 identified flaws judged to be IGSCC in the vicinity of twenty-three welds. Nineteen of these welds currently have
" standard" weld overlay repairs, two are currently thought to be unflawed, and two have been replaced.
During the Quad Cities Unit 2 1985 outage, two new welds were identified as possibly cor.taining IGSCC. These welds currently have " standard" weld overlay repairs. UT examinations performed during the 1986 outage at Quad Cities Unit 2 identified flaws judged to be IGSCC in the vicinity of five additional welds. All of these welds currently have " standard" weld overlay repairs. I UT examinations performed during the 1988 outage at Quad Cities Unit 2 identified flaws judged to be IGSCC in the vicinity of twelve additional welds. Ten of these welds currently have " standard" weld overlay repairs and two have been replaced. Two other unflawed welds received " load leveling" overlays to reduce weld overlay axial shrinkage stresses at other unflawed weld locations in the RR system. UT examinations performed during the 1990 outage at Quad Cities Unit 2 identified no new flaws judged to be IGSCC. One weld thought to have IGSCC flaw growth into the overlay repair . was shown through the use of a boat sa=ple to have IGSCC only up to the pipe wall-to-weld overlay repair interface. No volumetric ultrasonic examinations of the Reactor Recirculation and Shutdown Cooling system weldments were performed during the 1992 outage at Quad Cities Unit 2. ' COE-301-200 6.1 n Revision 0 wPAtlFIC NUELEAR.
Ultrasonic (UT) examinations performed during the 1993 outage
~
at Quad Cities Unit 2 identified one flaw judged to have IGSCC. This flaw was repaired using the weld overlay technique. Evaluations presented in this report for the thirty-seven Quad Cities Unit 2 welds believed to currently contain IGSCC demonstrate that the applied stress levels are acceptable for all design conditions. The analyses performed in the evaluation demonstrate that all the flawed welds having
" standard" weld overlay repairs are acceptable for the balance-of plant life per the requirements of NUREG-0313 (Reference 6) and can be placed in IGSCC Inspection Category "E".
Appendix C presents the sustained stress vs. allowable stress ratios for all unflawed and unrepaired IGSCC-susceptible welds outside of NUREG-0313 ISI Inspection Category "A". COE-301-200 6.2 M Revision 0 wP/4ElFIE NUELEAR.
7.0 REFERENCES
- 1. NUTECH Document No. COM-75-002, " Evaluation and Disposition of IGSCC Flaws at Quad Cities Nuclear Power Station Unit 2", Revision 1, March 1984.
- 2. NUTECH Document No. CEC-20-013, " Evaluation and Disposition of Flaws at Quad Cities Nuclear Power Plant Unit 2", Revision 1, July 1985.
- 3. NUTECH Document No. CEC-73-203, " Evaluation and Disposition of Flaws at Quad Cities Nuclear Power Plant Unit 2 (1986 Outage)", Revision 0, January 1987.
- 4. Structural Integrity Associates (SIA) Report No.
SIR-88-018, Vol. 1 (Rev. 1) & Vol. 2 (Rev. 0), " Design Report for Recirculation and Reactor Water Clean-Up System Evaluations and Repairs Performed During the 1988 Refueling Outage at the Quad Cities Nuclear Power Plant, Unit 2", May/ June 1988.
- 5. NUTECH Document No. XCE-42-252, " Evaluation and Disposition of IGSCC-Susceptible Weldments At Quad Cities Nuclear Power Station Unit 2 1990 Outage", Revision 2, September 1991.
- 6. NRC Document No. NUREG-0313, " Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping", Revision 2.
- 7. NUTECH Drawing No. M-3113, " Inservice Inspection Isometric - Recirculation System - Quad Cities Unit 2;"
Sheets 1-2, Revision B; Sheet 3, Revision C; Sheet 4, Revision A.
- 8. Kulat, S.D., Pitcairn, D.R., and Sobon, L.J.,
" Experimental Verification of Analytically Determined Weld Overlay Residual Stress Distributions", Transactions of the 8th International Conference on Structural Mechanics in Reactor Technology (SMiRT), Paper D2/1, Brussels, Belgium, August 19-23, 1985.
9. EPRI Document No. NP-2423-LD, " Stress Corrosion Cracking of Type-304 Stainless Steel in High-Purity Water: A Compilation of Crack Growth Rates", June 1982.
- 10. ASME Boiler and Pressure Vessel Code (BPVC) Section XI, 1986 Edition with Addenda through 1989.
- 11. NUTECH Document No. COM-76-001, " Weld Overlay Design Criteria for Axial Cracks", Revision 0, March 1984. ~-
COE-301-200 P 7.1 Revision O hpg{lpl{ NUELF11R.
- 12. NRC Generic Letter 88-01,
Subject:
NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, January 25, 1988, with Supplement 1, February 4, 1992.
- 13. ASME Boiler and Pressure Vessel Code (BPVC) Section III, 1986 Edition with Addenda through 1989.
- 14. ABB Impell Letter No. 0591-417-114, dated April 19, 1991 (for Reactor Recirculation and Shutdown Cooling systems inside drywell).
- 15. ABB Impell Letter No. 0591-417-124, dated May 15, 1991 (for Reactor Recirculation and Shutdown Cooling systems inside drywell).
- 16. Sargent & Lundy Letter dated June 25, 1991, Project No.
8827-97 (for RHR system).
- 17. Sargent & Lundy Letter dated July 22, 1991, Project No.
8827-96/97 (for RHR system). .'
- 18. NUTECH Analysis No. 28.0202.0500 (dated September 29, 1982) and NUTECH Document No. XCE-09-100 (QC2.05),
Revision 0 (for Shutdown Cooling System outside drywell) .
- 19. NUTECH Document No. COM-0710-06, dated August 21, 1980 (for Core Spray system).
- 20. Pacific Nuclear Computer Program PISTAR, Version 4.1.0 User's Manual, PSD-89-005, Revision 1, NUTECH Corporate File No. QASJO. SOFT. 2.036.4.0.0.2.
i COE-301-200 Revision 0 7.2 gp p l NUELFAR. . l
Appendix A OUAD CITIES UNIT 2 COMPARISON AND DESCRIPTION OF FLAWED WELDMENTS WITH AS-BUILT OVERLAY DIMENSIONS WTLD NO. PAGE NO. WTLD NO. PAGE NO. REACTOR RECIRCULATION: 12* NPS REACTOR RECIRCULATION: 22* NPS O2C-S3 A.2 02A 510 A.26 02C54 A.3 02B-59 A.27 02C-F7 A.4 REACTOR RECIRCULATION: 28' NPS O2D-S3 A.5 02 AD >S6 A.28 02D-F6 A.6 02 AD-F12 A.29 02E-S3 A.7 02AS 54 A.30 02E-F6A A.8 02 AS-S 6 A.31 02F-S3 A.9 02AS.S9 A.3 2 02F-F6 A.10 02 AS-S12 A.3 3 02G-S3 A.11 02AS F14 A.34 02G-54 A.12 02BD S6 A.3 5 02H-S3 A.13 02BD-F8 A.3 6 02H-S4 A.14 02BS-F2 A.37 02J-S3 A.15 02BS 53 A.38 02J-S4 A.16 02BS-F7 A.3 9 02J-F6 A.17 02BS-512 A.40 02K S3 A.18 02BS-F14 A.41 02KS4 A.19 SHUTDOWN COOLING: 20* NPS O2 K-F 6 A.20 105-F1 A.42 l 02L-53 A.21 10S-F 5 A.43 l I O2L 54 A.22 REACTOR WATER CLEAN-UP: 6' NPS ; O2MS3 A.23 125 S24 A.44 i 02MS4 A.24 125-F2 ER A.45 l 02M F7 A.2 5 125 S27 A.46 ' cOE-3oi-2co nevision A.o $ PACIFIC NUELEAR. ; I
b h
= 0 =
A i k
~ '
4s* Wet. 1 M- .
. /..::'::*::::::::::::::::::::::'::::':::::::::::::::::::*:*:
4NNNNNNNNNV///////A%J_
> i
'J i t-TYPE 1 ;
f [
=
D
.= A :-
r 4s uw. , f 6 . A m t m a m m i m ir = : = m m i:- .
- t. \ .
tP (g ' TYPE 2
= D r ;
4s un. i , . 6 . /. ..i.
.. . ::.. :. :. ::...:. .:. :. ::::. :. ::. :. , :. :. ::. ::i A ,
. .J ANNNNNNNN i /A l
',J t l :
TYPE 3 )
. 1 WELD OVERLAY TYPES 1 l
COE-301-200 Revision 0 A.I hpg{gpg{ N'A M R i l i
1 i i i l 1 1 IC-53 PIPE SIZES 12.75" wER NO. l In, .p. 4.4* wCR *YFE AXIA:. SHR.t 0.203* i
; UPSTREAM DN$TREAM l
CONFIOtJRATIOWs ELBOW PIPE i PIPE WALL THK. (tp): 0.653" 0.561* OVERLAY THK. (to): 0.391* 0.355' LOW CELTA FERRITE FIRST 1AYER THK.s N/A N/A ,
)
CIPtENSION *A*a N/A 2.2* l l
<l t
REMAINING ! OUTAOE LENOTH CEPTH LIGAMENT ORIENT. 14 CATION COMMENT { 1983 - NO REPORTABLE INDICATINS ------------- IMSI TREATED 1985 -- NO REPORTABLE INDICATINS I 1986 BEFORE OVERIAY REPAIR: 1-1/4* 29% N/A CI % ELBOW SICE
--- 36% N/A AXIAL E JbOW SIOE l
AFTER OVERIAY REPAIRS *STANOARD* OVERIAY REPAIRED ; i i 0.75* N/A 0.36" AXIAL ELBOW SIOE , 0.60* N/A O.34* AXIAL ELBOW SIDE 1
?
19B8 - NOT INSPECTED --- ! I 1990 === NO REPORTABIE INDICATI m$ ------------- .l; 1992 - - - - - - - - -
- NOT INSPECTED - - - - - -
l t 1993 0.39' N/A 0.47* AXIAL PIPE SIDE i 0.28' N/A 0.41* AXIAL ELBOW EIDE ! 0.34* N/A 0.42* AXIAL PIPE 51ct ! 0.22' N/A 0.43' AXIAL ELBOW SIDE j i
.(OC2rLAW.wA1/all) f l
i I i I l l
.i
)
. i 1
i
-)
COE-301-200 Revision 0 A.2 O N IFIE NUELFAR. 1 i 9 i I I
)
PIPE SIZE 12.75* hT O NO.: 01I-54 CIM. *D*: 4.5* wc2 Tvrte . AXIAL SHR.s 0.254* UPSTREAM ONSTREAM COhTIOURATIOWs PIPE ELBOW PIPE WAIL THK. (tp): 0.605" 0.690* OVERLAY THK. (to): 0.365* 0.343* LOW CELTA FERRITE FIRST LATER THK.I N/A N/A DIMENSION *A*- 2.25" N/A RDs.AINING 0"TAGE LENOTH CEPTH LICAMZ"NT ORIENT. IDCATION COMMDIT 1988 ------------- NO REPORTABI.E INDICATI345 ------- - -
*STAN;ARD* OVERLAY AFPLIED (FOR 14AD ID E ING) 1990 --------=-
----- NOT INSFECTED -------------
1992 - - - - - - - - - -
- ---- - NOT INS PECTED - =--------
1993 =
- - ----- NO REPORTABLE INDICATICNS -
(QC2rLAw.wt1/all) COE-301-200 A.3 gp74{gpg{ Revision 0 NUCLF/4R.
PIPE SIIE: 12.75* WEI.0 NO.: III-r' OIM. *D*: 3.874* wcp ;ypt. I AXIAL SHR.: 0.197* UPSTREAM ONSTREAM CONTIA' RATION: SWEEPCIIT PIPE PIPE WALL THK. (tp): C.644* 0.630* OVERIAY TKK. (to): 0.407* 0.406* LOW CELTA TERRITE FIRST LAYER THK.: N/A N/A CIMENSION *A*t N/A 2.3* REMAINING OtJIAGE ENCTH DEPTH LICAMENT CRIENT. IDCATION congENT 1993 BETCRE CVERIAY REPAIRS
$* 21% N/A CIRC. PIPE SIDE 0.3* 72% N/A AXIAL PIPE SI E AFTER CVERIAY REPAIRS 0.43* N/A 0.58* AXIAL PIPE SIDE *STANOARD* OVERIAY REPAIRED 0.24' N/A C.52* AXIAL PIPE SILE 0.41' N/A 0.54' AXIAL PIPE SIOE l (QC2rIAW.wki/all)
=
I COE-301-200 A,4 i Revision 0 l3Ab - NUELEAR. I I l
__ ._= i I i PIPE SIIEs 12.75* C NO*8 02D-53 f CIM. *D*a 4.8* "0" I M ' I f AXIAL SKR.s 0.230" ! t 7 UPSIREAM ONSTREAM i 1 , EIJCW PIPE . CONr1CURATIOWs PIPE WA1.L THK. (tp): 0.669* 0.600* l CVERLAY THK. (to): 0.316" 0.293* Iow CELTA TERRITE FIRSI LAtER TRK.s N/A N/A k I DIMENSION *A*: N/A 2.4* I i REMAININ OUTAGE I.ENGTH DEPTH LI~.TAKENT CRIENT. ICCATICW COMMENT 1 1983 1/2* 25% N/A CIRC. PIPE SIDE ~ INSI TREATED [ [ 1985 1/2" 26-28% N/A CIRC. PIPE SIDE f 1986 0.6* 17% N/A CIRC. PIPE SIDE o 1988 BEFCRE C%TRLAT REPAIRS , 1.5" 0.24* N/A CIRC. PIPE SICE l 2' O.15" N/A CIRC. elbow SIDE i l' O.15' N/A CIRC. ELBoer SIDE ! 1* 0.15* N/A CIRC. ELBOW EICE [
- 0. 9
- MAX . 0. 2 4
- MAX N/A AEI E (3) PIPE SIDE ;
0.8* MAX.0.22* MAX N/A AXIAL (3) Elaost SICE l ATTER OVERLAY REPAIRS
- STANDARD
- CVERIAY REPAIRED 0.5* N/A 0.38' AXIAL PIPE SIDE 0.5* N/A 0.52* AXIAL elbow SIDE I 0.8* N/A 0.39* AIIAL ELhow SIDE p 0.7" W/A 0.29" ARIAL elbow SIDE ;
6 1990 0.20* N/A 0.36* AXIAL PIPE SIDE 0.30' N/A 0.39' ARIAL elbow SIDE l O.2T* N/A 0.30* AIIAL ELBOW SIDE I I 1992 .-.-. ~~- NOT INSPECTED ------- I 1993 0.30* W/A 0.38* AXIAL ELaow SIct j 0.19' N/A 0.30* AXIAL EIaow SIDE > 0.21' N/A 0.36* AXIAL elbow SItt (OC2rIAw.wt1/all) l r
'I
.- t i
1 1 COE-301-200 Revision O A.5 g ! i NUELEAR. !
I PIPE SIIEs 12 75*
WOR TYPE: I gyg, .p., g,g. AXIAI,SHR.: 0.1C6*
- UPS TR.EAM DNSTREAM C0hTICURATION: S WEEPOI.ET FIFE PIPE WAI.I. THK. (tp): N/A 0 595*
CVERIAT TEK. (to): N/A 0.329* LOW OELTA FIPRITE FIRST LAYER THK.: N/A N/A DIMENSION *A*: N/A 2.0* REMAINING OEPTH ! M'T CRIENT. IDCATION COMMENT CUTACE LENOTH 1983 8* 909 N/A CIRO. FIFE SIDE *ENGIhT.ERED* OVERLAY REPAIRED 1985 - - - = - N2f INSFECTED - 1986 0.4* N/A 0.62* AXIAL PIFE SIOE BUILT-UP TO
- STANDARD
- DVERIAT 0.5* N/A 0.62* AKIAL PIFE SIOE 1968 0.4* N/A 0.61* AXIAL PIFE SILE 1990 - -
- - NO REPORTABLE INDICATICNS == =-- -
1992 NOT INSFECTED 1993 0.39* N/A 0.50* ARIAL SWEEPOLET (OC2Fu W.wk1/all) COE-301-200 A*6 Revision 0 $ PACIFIC NUCLEAR. l 1 i
PIFE SIZES 12.75* WEI.D NO.s IIE-53 OIM. *D* 4.7 WOR TYPES . AxIAI. SHR.: 0.215* 7 UPSTREAM LNSTREAM CDhTIGURATION: Elb3W PIPE PIPE WAI.I. TMK. (tp): 0.656* 0.584* OVERI.AY TKK. (tc): 0.351* 0.366* IDW OELTA TERRITE TIRJT IAT ER THK. : N/A N/A DIMENZION *A*e N/A 2.4* REMAINING OUTAGE LENOTH OEPTH LIGAMENT ORII2iT. IDCATION COMMENT 1983 INSI TREATED 1988 EETORE OVERIAF RT*. AIR s
--- C.14' N/A AXIE PIPE SIOE 0.11' N/A AXIE PIFE SIDE AFTER OVERIJ T REPAIR s
- STANDARD
- OVERIAT REPAIRED 0.50' N/A 0.42* AKIE PIPE SIOE 0.50' N/A 0.42* AKIAL PIPE SIOE 1990 0.30* N/A 0.42' AXIE ---
0.40' N/A 0.37' AXIAL --- 1992 ---------- NOT INSPECTED -----: -- 1993 0.49' N/A 0.43* AIIE elbow SIcE 0.37' N/A 0.38* AIIAL EISDW SIOE (OC2nAW.wki/ ell) 1 cor-3oi-2oo Revision o A.7 gpgggp,g NUELFAR.
PIPE SIZES 12.75* hT*J NO . IIE-FtA DIM. *D*: 4.5* WOR TYPEr . Ax AI. SHR.s 0.297*
-, UFSTREAM ONSTREAM CONFIGURATION: PIPE PIPE PIPE tiAI.I. TMK. (tp): 0.653* 3.601*
OVERI.AY THR. (to)s 0.314" 0.373* IDW CELTA FERRITE FIRST LAYER THK.s N/A N/A OIMENSION *A*a N/A 2.25' REMAININO OUTAGE *ENGTH LEPTH LICAMENT ORIENT. LOCATION COMMENT 1993 - NO REPORTABLE INOICATICNS - IHSI TREATED 1995 BETCRE OVERLAY REPAIRS
- ENGINEERED
- OVERLAY REPAIRED l' 18% N/A CIRC. UPSTREAM w/ 1/4* lit N/A AXIAI.
1/2* 14% F/A CIRT. UPSTREAM w/ 0.2* 13% N/A AXIAL r 1986 ------------- NO REPORTABI.E INDICATICES ------------- BUILT-UP TO *STANDARO* OVERLAY 1988 ---------- NOT INSPECTED -- =- - - = - 1990 ------------- NO REPCRTABI.E INDICATI248 - - - 1992 ------------------ NOT INSPECTED -- - -- 1993 ----------~~- NO REPORTABLE INDICATIONS (OC2rLAw.wk1/all) i l l l l i 1 1 1 l l l 1 COE-301-200 A.8 nevision 0 O. PAtlFIC NUCLEAR. l l
PIPE SIZES 12.75* WELD No.: ::Ir.s 3 , DIM. *D's 4.6* WCR TYPES 1 ; AKIAL SHR.s 0.184* UPSTREAM DNSTREAM f CONFIGURATION ELBOW PIPE , f PIPE WALL THK. (tp): 0.651* 0.661* l CVERLAY THK. (to): 0.364* 0.303* I LOW DELTA FERRTTE FIRST IAYER THK.: N/A N/A l t DIMENSION *A*s N/A 2.3" j
?
i REMAINING OUTAGE LENGTH DEPTH LIGAMENT CRIENT. ICCATION COMMENT I ( 1983 IMSI TREATED l 1980 BEFORE OVERIAY REPAIRS i 0.5* 0.28* N/A CIRC. PIPE SIDE j 1.0* 0.13' N/A CIRC. PIPE SIDE 0.9* 0.22' N/A AXIAL - JIPE SIDE 1.0* MAX.0.13* MAK N/A AXIAL (4) ELBc4 SIDE I AFTER CVERLAY REPAIDs ' STANDARD
- CVERLEY REPAIRED l
I 0.10' N/A 0.72* CIRC. PIPE SIDE , 0.10* N/A 0.61* CIRC. PIPE SIDE j i 1990 6.5* N/A 0.71* CIRC. PIPE SIDE 3 0.30' N/A 0.63* CIRC. PIPE SIDE i I 1992 - NOT INSPECTED --- - - --- i 1993 20.1* N/A 0.61* CIRC. --- l 7.1* N/A 0.57' CIRC. --- ' 5.4* N/A 0.66* CIRC. --- 2.9* N/A 0.67* CIRC. --- l 1 (QC2TIAN.vk1/all) . i l l 1 1 cot-3oi-2oo A.9 Revision gggpgt - NtJELE4R.
PIPE SIIE: 12.75* wE;p No. IIr-re OIM. *D* 4.3* WOR TYPE: . AXIAL SHR. : 0.254* UPSTRE.AM ONSTREAM CONTICURATION: PIPE PIPE PIPE WALT TEK. (tp): C.590* 0.561* OVERLAY THK. (to): 0.355' O.392* LOW CELTA TEPJtITE FIRST IATER THK. s N/A N/A DIMENSION *A*: N/A 2.1* AEMAINING OUTACE LENOTH OEPTH LIGAMTNT CRIENT. LOCATION COMMENT 1983 360 CEG. 80% N/A CIRC. PIPE SIOE
- ENGINEERED
- OVERLAY DIFAIRED 1985 ------------ -- Nor INSPEerga 1986 -----=-
NO REPCRTABLE INDICATICES ----------~~- BUILT-UP TO
- STANDARD
- CVERIAY 1988 ------------- NO REPORTABLE INOICATIG45 1990 -----
- ----- NOT INSPECTED - -- - - --
1992 --------- NOT INSPECTED --------- - 1995 ------------- NO REPORTABLE INDICATIOC -* - (DC2rLAW.wk1/all)
~.
cor-301-2oo A 10 nevision gpgtipic NUELEAR.
PIPE SIIE: 12.75* WELD NO. "I -32 OIM. *D*: 4.4* "UN IIIE8 AXIAL SHR.: 0.280*
, UPSTREAM CNSTREAM COh710URATION: E* BOW PIPE PIPE WALL THK. (tp): 0.662* 0.591*
CVERLAY THK. (to): 0.307' O.313' thw OELTA TERRITE TIRST IAYER THK. : N/A N/A DIKENSION *A*: N/A 2.25' REMAINING OUTA0E LENOTH LEFTH LICAMENT CRIENT. 14 CATION COMMENT 1983 2-1/4* 32% N/A CIRC. PIPE SIDE
- ENGINEERED
- OVERLAY REPAIRED 1985 ------------- ----- NOT I N S PECTED -------- - - - --
1986 26* N/A 0.58' CIRC. ELBOW SIDE BUILT-UP TO *STANOARD* CVERIAY (intamit . ) 19R8 --
- NOT INSPECTED 1990 9.5" W/A D.66* CIRC. ---
3.0* N/A 0.60* CIRC. --- 1992 --
---------- NOT INSPECTED -- - -------
1993 17.4* N/A 0.66" CIRC. --- 5.0* N/A 0.60* CIRC.- --- 6.4* N/A 0.65* CIRC. --- (Oc2rLAw.wk1/s11) COE-301-200 A.11 M' Revision 0 wP/4ElFIC NUELEAR.
l I 12.75* WEI.D NC.: IIO*54 PIPE SIIE: OIM. 'D*: 4.6* WOR TYTE: . AXI E SHR.: 0.221* I
;- UFSTREAM DNSTREAM CohTIGiJRATION: PIPE EI. BOW PIPE WALL THK. (tp): 0.603* 0.711*
OVERAY THK. (to): 0.319* 0.253* LOW CELTA TERRITE FIRST LAYER THK.: N/A N/A DIMENSION *A*: 2.3* N/A REMAINING OUTAGE LENOTH CEPTH LIOAMENT ORIENT. LOCATION COMMENT 1983 IMSI TREATED 1988 BETCKE OVERLAY REPAIRS 0.17' N/A ARIAL PIPE SIDE 0.32* N/A AXIAL PIPE SIOE ATTER OVERLAY REPAIR *STANOARO* OtT.RIJLY REPAIRED 0.10* N/A 0.44* AXIAL PIPE SIOE 0.10* N/A 0.45' AZIAL PIPE SIOE t 1990 0.10* N/A 0.44* AZIAL --- 1992 - - - - - = - NOT INSPECTED ---- -- 1993 0.25* N/A 0.43* AXIAL ELBOW SIOE ( QC2TLAW.wk1/all)
~.
coz-3oi-2co Revision 0 A.12 gpaggpic NUELEAR.
PIPE SIIEs 12.75* h*EIC NC.: 12H-53 OIM. *O*a 4.5* "C" IYPE' - AKIE SHR.: 0.318' UPSTREAM DNSTREAM CohTIOURATION: ELBOW PIPE PIPE WAI/I,THK. (tp) 0.684* 0.601" OVERIAY THK. (to)s 0.326' O.346' LOW CELTA TERRITE FIRST IAYER THK. s N/A N/A DIMENSION *A*: N/A 2.25" REMAINING OUTAGE LENOTH CEP"H I.IGAMENT CRIENT. LOCATION COMMENT 1983 IHSI TREATED 1988 BEFORE OVERIAY REPAIRS 0.5* 0.20' N/A AXIAL PIPE SIDE 0.5* 0.30' N/A AKIAL PIPE SI E AFTER OVERIAY REPAIRS *STACARD* CVERIAT REPAIRED
------------- NO REPORIABLE ICICATINS - --
1990 0.30' N/A 0.67* AIIAL --- 1992 -- - NOT INSPECTED --- 1993 0.31' N/A 0.65* AKIAL ELBOW SIDE (GC2r:Aw.wt1/s11)
- n'n;2o ^ 1'
#mtiric NUcLFAR.
PIFE SIZES 12.75* wEL: NO.: 0;M-s4 OIM. *D's 4.5* WOR TYPEt - AXIAL SHR.s 0.229" UPSTREAM DNSTREAM CohTICURATION: PIFE elbow PIPE WALL THK. (tp): 0.622' O.680* CVERLAY THK. (to): 0.338' O.313' LOW CELTA TERRITE FIRST LAYER THK. N/A N/A DIMENSION *A** 2.3* N/A REMAININO OUTAGE LENGTH OEPTH LIGAMENT CRIENT. LOCATION COMMENT 1983 IMSI TREATED 1988 -
- - -- NO REPORTABLE INDICATI3fS ------- ==
- STANDARD
- CVERIAY APPLIED (FOR ICAD LEVELING) 1992 ----=- -
NOT INSPECTED ------ - - 1993 - -
- NOT INSPECTED --------
(OC2rLAW.wt1/ ell) I COE-301-200 A,14 nevision 0 O PA EIFIC NUCLEf4R.
PIPE SIZES - 12.75" weir NO. OIJ-s3 OIM. *D*: 4.6* WCR TYPri . AXIAL SHR.: 0.201* UPSTREAM CNSTREAM CONFIOURATIONs ELBCW PIPE 4 FIPC WALL THK. (tp): 0.826* 0.595* OVERIAT THK. (to): 0.378* 0.482* LON DELTA TERR 2TE FIRST IAYER THK.: N/A N/A DIMENSION *A*: N/A 2.3" 1-
. REMAINING OUTACE LENGTH DEPTH LIGAMENT ORIENT. LOCATION COMMENT 1983 IHSI TREATED 1988 SEFORE OVERIAY REPAIRS 0.72* 0.10" ' N/A AEIAL ELBON SIOC ATTER CVERIAY REPAIRS 'STANOARD* CVERIAY REPAIRED 0.80* N/A 0.32" ARIAL ---
0.50' N/A 0.32' AIIAL --- 1990 AFTER BOAT SAMPIZ EXTRACTION: BCAT SAMPLE EXTRACTED, MANUALLY REPAIRED, AND ONE ADDITIONAL 0.50* N/A 0.47" AXIAL --- MACHINE CTAN IATER ADOED 1992 --- NOT INSPECTED 1993 0.50'. N/A 0.47' AXIAL ELBON SIOE IQC2rLAN.vA1/all) i
*+
COE-301-200 Revision 0 A.15 g NIELE/4R.
PIPE SIIE: 12.75* wELO NO.s IIJ+54 OIM. *O*s 4.9* WOR TYFE . AXIE SHR. : 0.197*
, UFSTREAM ONSTREAM CohTIGURATION: PIPE ELBCW PIPE WALL THK. (tp): 0.649' O.651*
OVERLAY THK. (to): 0.280* 0.414* LOW OELTA FERRITE FIRST IAYER THK. : N/A N/A DIMENSION *A*: 2.5* W/A REMAINING OUTACE I.ENOTH CEPTH LIGAMENT CRIENT. LOCATION COMMENT 1983 IHSI TREATED 1988 BEFORE OVERLAY REPAIR: 2.5* 0.15' N/A CIRC. PIPE SIDE w/ 0.25' O.15" N/A AXIAL AFTER OVERLAY REPAIRS *STAN0ARD* 0%T.RIAY REPAIRID 0.80* N/A 0.48* AXIE PIPE SIDE 0.30" N/A 0.47' AXIE TJOW SILE 1990 0.85* N/A 0.45" AXIAL --- 0.75* N/A 0.35* AXIE --- 0.30* W/A 0.39' AXIAL- --- 0.50' N/A 0.58* AXIE --- 1992 --- NOT INSPECTED ---- 1993 0.80* N/A 0.48' AXIAL PIPE SIDE 0.7D* N/A 0.40* AXIAL P!PE SIDE 0.30* N/A 0.38* AXIAL PIPE SIOE 0.50* N/A 0.47* AXIAL EI. BOW SIDE (QC2 FLAW.vt1/all) COE-301-200 Revision 0 A.16 hpg{gpg{ NUELFAR.
PIPE SIIE 12.75* hT'J NO. :10-rf OIM. *D's 3.B* WOR TYFE' 2 AXIAI. SHR. 0.263*
~
-- UPSTRE.AM ONSTREAM OONTICURATION: SVEEPOLET PIPE PIPE WALL THK. (tp): N/A 0.648' CVERIAY THK. (to): N/A 0.372*
LOW OELTA FERRITE FIRST LAYER THK.s N/A N/A DIMENSION *A's N/A 2.0* REMAINING OUTACE LENCTH CEPTH LIGAMENT CRIENT. LOCATION COMMENT 1983 15* 15% N/A CIRC. PIPE SIOE
- ENGINEERED
- OVERLAY REPAIRED 1985 -- ---
-- NOT INSPECTED -- ---
1986 ------- NO INDICATIONE IN WELD OVERIAY REPAIR ------- BUILT-UP TO
- STAR ARD* OVERIAY 1988 0.50' N/A 0.44* AZIAL PIPE SIDE 1990 0.35' N/A 0.45* Ax!AL PIPE SIDE 1992 ------------------ NOT INS PEOTZD --
1993 0.51' N/A 0.42* AIIAL SWEEP. 510E (Oc2rIAw.wki/all) l j i COE-301-200 A,17 w PA tlFIC i Revision 0 M ' NUCLFAR.
12.75* WELD NO. IIr.s3 PIPE SIIE: ggg, .p., 4,0* WOR TYPE: . AXIAL SHR.s 0.168* UPSTREAM DNS TRE.AM CONFIGURATION EI. BOW PIPE PIPE WAI.L THK. (tp): 0.664* 0.587* OVERLAY THK. (to): 0.298* 0.316* LOW CELTA TERRITE FIRST IAYER THK.: N/A N/A DIMTNEION *A*: N/A 2.0* REMAINING OUTAGE LENGTH CEPTH LIGAMDfT ORIENT. LOCATION COMMENT 1983 ------------- NO REPORTABLE INDITATI WS ------------- INSI TREATED 1985 ------ - ND REPCRTABLE INDICATI ms ------------- 1986 EETORE OVERLAY REPAIR PINHOLE LEAKING N/A AXIE EI. BOW SIDE ATTER OVERLAY REPAIRS
- STANDARD
- CVERIAY REPAIRED 1.0* MAX. N/A 0. 4 0' MIN. AXIE (3) EI. BOW SICE 1988 --
= NOT INSPECTED - ---
1990 0.40" MAX N/A 0.38* MIN. AXIE ( 4 ) --- 1992 - - NOT INSPECTED 1993 0.39' N/A 0.39' AXIAL PIPE SIDE 0.31' N/A 0.38* AXIAL PIPE SIDE 0.30" N/A 0.30* AXIAL EI. BOW SIDE 0.35' N/A 0.44' AXIAL EI. BOW SIDE IOC2TIAW.wk1/all) COE-301-200 A.18 nevision 0 @PAtlFIC NUCLEAR.
PIPE SIIE: 12.75* hTD NO. : 0;It-54 OIM. *D*: 4.1* WOR TYPE: . AXIAL SHR.: 0.290* UPSTREAM CNSTREAM COhTIGURATION: PIPE ELBOW PIPE WALI. THK. (tp): 0.600* 0.673* CVERIAY THE. (to): 0.309* 0.329' LOW CELTA TEARITE FIRST LAYER THR. N/A N/A DIMENSION *A* 2.05* N/A REMAINING OUTAGE LENOTH CEPTH LICAMENT ORIENT. ICCATION COMMENT 1983 ------------- NO REPORTABLE INOICATI NS -- IHSI TREATED 1985 --
---- NO REPORTABLE INDICATINS ---
1986 BEFORE OVERIAT REPAIRS NOT CIVEN 0.15' N/A AXIE PIPE SIOE ATTER OVERIAT REPAIRS
- STANDARD
- 0%TRLAY REPAIRED 3/8' N/A 0.50* AXIAL PIPE SIDE 3/0* N/A 0.51* AIIE PIPE SIOE 1969 - - - - - - - - - - -
= NOT INSPECTED - - - - - -
1990 0.70* N/A 0.34* AXIE PIPE SIOE 0.40' N/A 0.36' AIIAL PIPE SIOE 1992 -- NOT INSPECTID - 1993 0.61= N/A 0.35* AXIAL PIPE SIOE D.31' N/A 0.37' AIIE PIPE SIDE (CC2TLAW.vt1/all) cor -a oi-2 co A.19 Revision 0 @PMORE gg
PIPE SIIts 12.75* WEIO WC.: I;F-Ff OIM. *D*: 4.1* WIR TYTE: I AXIAL SHR.: 0.169" , UPSTREAM DNSTREAM CONFIG'JRATION: ShTEPOI.ET PIPE PIPE WALL THK. (tp): N/A 0.603* OVERIAY TEK. (to): N/A 0.316* LOW CELTA FERRITE FIRST IAYER THK. a N/A N/A CIMZ"NSION *A* e N/A 2.5" REMAINING OUTAOE LENOTH CEPTH LI"m'T ORIENT. LOCATION CCF. MENT 1983 IHSI TREATED 1966 BEFORE OVERIAY REPAIR: 0.4* 0.33' N/A CIRC. PIPE SIDE 0.5* 0.30* N/A AIIAL PIPE SI:E ATTER OVER:AY REPAIRS *ETANDAAD* OVERIAY REPAIRED 0.60* N/A 0.39* ARIAL PIPE SIDE 1990 0.56' N/A 0.35" AIIAL PIPE SIOE 1992 - NOT INSPECTED --- ------- 1993 0.65* N/A 0.38' AXIAL SWEEP. SIOE (OC2rIAW.wki/all) cor-aoi-2co A.20 nev1sion gpgggggt NUELEAR.
PIPE SIzt: 12.75* wE*J NO.: :IL-s] DIM. D*: 4.5* WOR TYPE: . AXIAL SHR.: 0.259* UPSTRT.AM ONSTREAM COhTIOL* RATIONS ELBOW PIPE PIPE WALL THit. (tp): 0.664* 0.601* OVER1AY THK. (to): 0.333* 0.338* LOW OELTA TERRITE TIRST LAYER THK.: N/A N/A DIMENSION *A*8 N/A 2.25* REMAINING OUTAGE LENGTH OEPTH LIGAMENT ORIENT. IhCATION COMMDfT 1983 IHSI TREATED I 1988 BEFCRE OVERIAf REPAID s 0.10' N/A AXIAL ELBOW SIDE SPOT 0.CB* N/A AXIAL ELBOW SIOE ATTER OVERIAY REPAIRS
- STANDARD
- MT.RLAY REPAIRED 1990 0.50" N/A 0.42' AXIAL ---
0.50* N/A 0.54' AXIE --- 0.60* N/A 0.47' AXIAL --- 0.65* N/A 0.60- AXIAL. --- 1992 ----------
- - NOT INSPECTED ----= -
1993 0.40' N/A 0.51* AXIAL PIPE SIDE 0.45' N/A 0.44' AXIE PIPE SIOE 0.50* N/A 0.54' AXIAL PIPE SIOE 0.50' N/A 0.46* AXIAL PIPE SIOE 0.70* N/A 0.59' AXIAL PIPE SIDE I.40* N/A 0.76* CIRC. ELBOW SIDE (OC2rLAw.wka/ ell)
~.
COE-301-200 A.21 PAEIFIC Revision 0 NUCLEAR.
l PIPE SIZE .2.75* wEI.D NO. I I:.- 5 4 OIM. *ca: 4.5" WCR TYPE: - AXIAL SHR.: 0.235' UFSTREAM DNSTREAM CONTI0wtATION: PIPE EI. BOW PIPE WALL THK. (tp): 0.599* C.678* OVERIAY THK. (to): 0.346' O.323' Iow CELTA FERRITE FIRST IAYER THK. : N/A N/A DIMENSION *A*: N/A 2.25" REKAINING LENGTH OEPTH LICAMENT ORIENT. LOCATION COKKENT i OUTACE 1983 IHSI TREATED 1988 BEFORE CVERIAY REP AIR 0.3* 0.25' N/A AXIAL ELBOW SI E AFTER OVERIAY REPAIRS " STANDARD
- OVERIAY REPAIRED
------------- NO REPORTABLE INDICATICES 1990 -------
NO REPORTABLE INDICATICNS -- 1992 ---- - NOT INSPECTED 1993 ------ - NO REPORTABLE INDICATI ES ------ -- (DC TIAW.wki/all)
~.
COE-301-200 A.22 M Revision 0 w PA CIFIE NUELEAR.
~ . - . . _ _ -
9 i
.I l
wrLD NO. :In-s3 t PIPE SIIE: 12.75* ! DIM. *D*: 4.5* wor TYPE: , )! l Ax1AL SHR.: 0.253* ,
; UPSTREAM DNSTREAM !
CONFIGURATION: ELBOW PIPE y I PIPE WALL THK. (tp): 0.662* 0.591* OVERIAY THK. (to): 0.408* 0.404* Iow DELTA FERRITE FIRST LAYER THK.a N/A N/A . i DIMENSION *A** N/A 2.25' ; i REMAINING OUTAGE LENGTH DEPTH LICAMENT ORIENT. IDCATION COMMENT f 1 1983 1-1/2* 30% N/A CIRC. ElaOW SIDE IHEI TREATED f 1* 13% N/A CIRC. PIPE SIDE 1985 3-1/2* $0% N/A CIRC. EIDOW SIDE
- ENGINEERED
- CVERIAY REPAIRED e 2* 65% N/A CIRC. PIPE SIDE 7/8' 70% N/A AXIAL PIPE SIDE 1996 0.6* N/A 0.7* CIRC. EISOW SIDE BUILT-UP TO 'SIANDARD* CVERIAY 0.20* N/A 0.70* MIE PIPE SIDE r
, 0.60* N/A 0.60* AXIAL PIPE SIDE 0.4$* N/A 0.45* AXIAL PIPE SIDE t 0.40- N/A 0.45* AIIAL PIPE SIDE , 1988 0.6* N/A 0.7* CIRC. E130W SIDE , 0.20* N/A 0.70* AXIAL PIPE SIDE 0.60* N/A 0.60* AEIE PIPE SIDE , 0.45' N/A 0.45* AKIAL PIPE SIDE ; 0.40* N/A 0.45* AXIAL PIPE SIDE 1990 0.50' N/A 0.51' AXIAL PIPE SIDE 0.50* W/A 0.45' AXIAL PIPE SIDE ! I 0.45' N/A 0.52" AXIAL PIPE SIDE. , 0.10* N/A 0.40* AXIAL PIPE SIDE r 1992 --- NDT INSPECTED - ---- i 1993 0.40* N/A 0.56" AXIE PIPE SIDE 0.50*- N/A 0.42" AXIAL PIPE SIDE j 0.60* N/A 0.49* AXIAL PIPE SIDE I 0.40' N/A 0.70* ARIAL PIPE SIDE 0.50' N/A 0.56' ARIAL PIPE SIDE 0.58' N/A 0.55* AXIAL PIPE SIDE ', 0.50* N/A 0.46* AEIAL PIPE SIDE i (QC2 FLAW. wit 1/all) l cor-soi-2co Revision 0 A.23 Spnggppt , NtJELFAR. ! b
PIPE SIIEs 12.75* WELO NO.s IIM-54 OIM. *D* 4.6* WOR TYFEs . AXIAL SHR.: 0.241"
*_ UFSTREAM ONSTREAM CONTIOURATION: PIFE ELBOW PIFE NAI.L THK. (tp): 0.6D9* 0.684*
i OVERIAY TRK. (to): 0.291* 0.348* LOW CELTA TERRITE FIRST LAYER THK.: N/A N/A O!MENSION *A*: 2.3* N/A RD AINING OUTAGE I.ENOTH CEPTH LICAKENT ORIENT. LOCATION COMMENT 1983 1/2* 9% N/A CIRC. ELBOW SIOE IHSI TREATED 1985 1/2* 15% N/A CIRC. ELBOW SIDE 1986 1/2" 12% N/A CIRC. ELBOW SILE 1988 BEFORE OVERLAY REPAIRS 1.3* 0.1" N/A CIRC. ELBOW SIOE w/ 0.4* 0.1* N/A AXIAL EI. BOW SIDE 0.7* 0.1* N/A CIRC. ELBOW SI:E ATTER CVERLAY REFAIR: *STANOARD* OVERM Y REFAIRED
------------- NO REPORTABLE INOICATIWS. - --
1990 ---
-- - -- NO REPORTABLE INOICATIWS -------------
1992 ------------------ NOT INSFECTED -- -- ------ 1993 ------------- NO REPORTABLE INDICATIONS ------ -- ( QC2TI.AW. w ki/all) cor-aoi-2co nevision A.24 gpjaggggg NUELFAR.
PIPE SIIE: 12.75* hT*J NO. !!M.r* i CIM. *O*: 3.B* WOR YYPE8 2 AXIAL SHp.: 0.194*
^
UPSTREAM CNSTREAM CONTIGURATIOh Sk'EEPCLET PIPE PIPE MAIJ., THK. (tp): N/A 0.570* OVERLAY THK. ( t.o) e N/A 0.512* LOW OELTA FERRITE l FIRST LAYER THK.I N/A N/A ' OIMENSION *A*: N/A 2.0* REMAINING OUTAGE I.ENGTH DEPTH LICAMENT ORIENT. LOCATION COMMENT 1983 ------------ 1/ 2
- IONG IACK-CF- FUSION ------------ IMSI TREATED 1985 7-1/2* 100% N/A CIRC. ShTEP. SIDE *ENOINEZ1ED* CVERIAY REPAIRED 1986 0.5* N/A 0.68* CIRC. PIPE SIOE BUILT-UP TO
- STANDARD
- CVCdAY 1968 0.5* N/A 0.68* CIRC. PIPE SIOE 1990 ------------- NO REPORTABI.E INDICATICNS --- ----
1992 --- NOT INSPECTED ------- -- -- 1993 --------- --- NO FIPORTABLE INDICATICNS ------ : -- (QC2FIAw.wk1/all) l COE-301-200 A.25 Revision 0 w PM EIFIC
- n. l NUCLEAR. 1 l
l l
PIPE SIZE: 22* WEI.D NC . : 2 I A - 5 *. :
- CIM. -D*: N/A WCR TYPE: N/A ARIAL SHR.: N/A
- RDIUMBERED
; UPSTREAM DNSTREAM 02A-FIIR CONTIOURATION: PIPE END CAP PIPE WALL THK. (tp): 1.07* 1.24' OVERLAY THK. (to): N/A N/A IDW CELTA FERRITE FIRST LAYER THK.: N/A N/A DIMENSION *A*: N/A N/A REMAINING OUTAGE LENGTH CEPT.4 LICAMENT ORIENT. 14 CATION COMMENT 1983 4* 26% N/A CIRC. END CAP SIOE IHSI TREATED 1985 4* 16% N/A CIRC. END CAP SIDE 1986 EEFORE OVERIAY REFAIR:
8.6* TOTA 26% MAX. N/A CIRC. (9) END CAP SIDE 30% MAE. N/A AXIE (29) END CAP SICE ATTER OVERLAY REPAIR: *STANOARD* 0%*ERLAY REPAIRED 0.8* N/A D.38* CIRC. DiD CAP SICE 1.0* KAX. N/A 0.35* MIN. AII E (8) END CAP SIDE 1988 ATTER FABRICATION CETECT REPAIRS: 1986 FAB. DETECTS EXCAVATED 0.6* W/A 0.71* AXIAL. END CAP SIDE 0.4* N/A 0.76* AZIAL END CAP SIDE 1990 ATTER FIPLACDLENT: END CAP REPLACED
------=--
NO REPORTABLE INOICATI345 - - - - ( OC2 FIAW.wt1/all) cor-3oi-2co A.2s acvision OPAEIFIC NUCLEAR.
h*E*J No. : I;B-57 PIPE SIIE: 22* 5.C* WOR TYPES . DIM. *D*: _ AXIE SHR.: N/A
~_ 1PSTREAM CNSTREAM CONFIGURATION: PIPE END CAP PIPE WAL1,THK. (tp)s 1.044* 1.194*
OVERLAY THK. (to): 0.601- 0.514* Iow DEI.TA TERRITE TIRST IAYER THK. : 0.105* 0.113* DIMENSION *A*: 3.0* N/A REMAINING CUTAGE IINOTH CEPTH LICAMENT CRIENT. ICCATION COMMENT 1983 17' TOT E15% MAX. N/A CIRC. END CAP SIOE IMSI TREATED 1965 17
- TOTAL 14 4 MAX. W/A CIRC. END CAP SI E 1996 BETCRE CVERIAY REPAIR:
11.6* TOT 17% MAX. N/A CIRC. (10) END CAP SIDE NOT CIVEN256 MAX. N/A AXIAL (15) END CAP SICE ATTER OVERIAY REPAIR:
- STANDARD
- OVERLAY REPAIRED 2.5* W/A 0.60* CIRC. END CAP SIOE 2.5* N/A 0.56' CIRC. END CAP SICE 1.0* MAX. N/A 0.55" MIN. AXIAL ( 6 ) END CAP SIOE 1989 2.5" N/A 0.60* CIRC. END CAP SIOE 2.5* N/A 0.56" CIRC. END CAP SIOE 1.0* MAX. N/A 0.46' MIN. AXIAL (8) END CAP SIDE 1990 ------------- NO REPORTABLE INDICATICRIS 1992 -------= ---
NOT INS PECTED --------- = -- - - - 1993 --
---===== NO REPORTABIZ INDICATI345 - =
( DC2TIAN.w ki/ ell) COE-301-200 A.27 Revision 0 P/*1EIFIC NUCLEAR.
WE*- No.: ;2AO-54 PIPE SIIEs 18* WOR TYPE: OIM. *O*s 6.7* AXIA1. SHR.: 0.07E' UPSTRr>Ji ONSTRI.AM CONFIO'TRATION: ELBOW PIFE PIPE WAIL THK. (tp): 1.432' 1.412' OVERIAY THK. (to) 0.497- 0.510* LOW OELTA TERRITE FIRST LAYER THK.s N/A N/A CIMENSION 'A*: 4.4* N/A REMAININO OUTAOE LENOTH CEPTH LIOAMDIT ORIENT. LOCATION COMMDIT 1983 ----------- ---- ID CEOMETRY =-= ----- IHSI TREATED 1985 -- HOT INSFECTED -- - - - - - - - - - - -
=-=
ROOT GEOMETRY 1986 ------- 1988 3* 7% N/A CIRC. EI. BOW SIOE TIAWED PIPE EVALUATION TERFORMED 1990 --- NO REPORTABLE INDICATI WS ------------- *STANDAAD* OVERLAY REPAIRED 1992 = NOT Is % F ECTED ------------ - - -- 1993 --- - --- NO REPORTABI.E INDICATI NS --- (QC:rLAW.vki/all) COE-301-200 A.28 Revision 0 m'd'PAEIFIC
'O NUELEAR.
-. _ _ __ . - , ,-, . m . . - s PIPE $1IEs 28' WE!D NO.s' I'AD-T*I 5
i DIM. *D** 7.3* WOR TYPE: I i AXIAI,SHR.: 0.005* l UPSTREAM DNSTREAM COhTIGURATIONs PUMP PIPE I LPIPE WAI.L TMK. (tp): 1.377* 1.357* 1 OVERIAY THK. (to}s 0.762* 0.575* ~! i LOW DELTA TERRITE ; TIRST LAYER THK.s N/A N/A l
-f DIMEWSION *A* N/A 4.5* r
-i 1
REMAINING ; OUTAGE LENCTH DEPTH I.IGAMENT ORIENT. LOCATION COMMENT l 1983 24* 10% N/A CIRC. PIPE SIDE IHSI TREATED; FLAWED PIPE ! total EVALUATION PERFORMED l I 1985 1* 16% N/A CIRC. PIPE SIDE FLAWED PIPE EVALCATIN PEAFORMED ! I 1986 1* 17% N/A CIRC. PIPE SIDE FIAWED PIPE EVALUATIN PERFORMED 1988 1* 174 N/A CIRC. PIPE SIDE TLAWED PIPE EVALUATIN PERFORMED ! 1990 ------- NO REPORTABLE INDICATI NS --------
- STANDARD
- OVERLAY REPAIRED 1992 ---
NOT INSPECTED --- ; I 1993 --- - - NO REPORTABLE INDICATINS ----- f t (OC2rIAW.Wk1/a11) [ I e t
,5 b
j' ! b t l i COE-301-200 A.29 ' Revision 0 OPAEIFIC - NtJELEAR. : 4 b
i s t PIPE SIZES 20* C NO.t l W -54 CIM. *D's 8.5" "OR TYPE 8 - AXIAL SHR.: NOT GIVEN
.- tPSTREAM ONSTREAM i COh710URATICH: EI.DOW PIPE PIPE WAIL THK. (tp): 1.425' I.210*
CVERIAY THK. (to): 0.499* 0.504* , Iow CELTA TERRITE TIRST IAYER TEK. s N/A N/A OIMENSION *A's N/A 4.2$* REMAIN!NG OUTAGE I.ENCTH CEPTH LICAMENT ORIENT. LOCATION COMMENT 1983 27' TOTAL 13% N/A CIRC. ELBOW SIOE IHSI TREATED 4* Ill N/A CIRC. PIPE SIDE 1985 58" *0% MAX.
, N/A CIRC. EI. BOW SIDE *ENCINEERED* OVERIAY REFAIRED 1986 ------------- NO REPORTABLE INOICATINS -- -
BUILT-UP TO 'STANLARD* CVERIAY 1988 - == NO REPORTABLE INDICATINS ==- 1990 -- NO REPORTABLE INDICATINS ------------- 1992 -- --
----- NOT INSPECTED =- = - - - - - - - - - -
1993 ------------- NO REPORTABI.E INDICATINS - ---- (OC2rIAw.ws1/all) O COE-301-200 A.30 Revision O PACIFIC NUELEAR.
PIPE SIIE IS* WER NC.: I2AS-Se g;g, .g., y/A WOR TYPE: N/A AXIAI. SHR.s N/A
~
- UPSTFIAM ONSTREAM CONFIOURATION: PIFE PIPE PIPE WAI.L THK. (tp)2 1.25" 1.25*
CVERLAY THK. (to): N/A N/A W OELTA TERRITE FIRST LAYER THK.a N/A N/A CIMENSION *A*: N/A N/A REKAININO OUTAGE LENOTH CEPTH LIOJpINT CRIENT. 14CATICN COMMENT 1983 7-1/2* 21% N/A CIRO. UPSTREAM IMSI TRIATED 1985 B* 18% N/A CIRC. UPSTREAM 1986 8' 18% N/A CIRC. UPSTREAM 1988 - ---- NO REPORTABLE INDICATI NS -= 1993 ------- ----- NO REPCRTABLE INDICATISS -- --- (QC2rLAw.wk1/all) COE-301-200 A.31 nevision 0 @PAtlFIC NUELFAR.
t PIPE $2Its 28* E'J NO.+ 02A$-59 OIM. *0*: 4.5* w:S TYPE: 3 AKIA1,SHD.* O.081*
.. UFS TRTAM ONSTREAM COAT 10URATIONs VAI,VE E1JCW PIPE WA1.1, THK. (tp)s N/A 1.363*
OVERLAY THK. (to): N/A C.488* LOW OE,TA TERRITE FIRST '.AYER THK. : N/A N/A DIMENSION *A*: N/A N/A REMAINING OUTAGE LENGTH OEPTH LIGAMENT ORIENT. IDCATION COMMENT 1963 1/2* 10% N/A AKIAL ELBDW SIOE *ENGIhTERED* CSTRIAT REFAIREO 1* 96 N/A CIRC. EI. BOW SIOE II* 23% N/A CIRC. E'MW SIOE 12* 13% N/A CIRC. ELBOW SILE 1965 - - - ---- - NOT INSPECTED - - ---- 1986 ----- - NO REPORTAELE IN0! CATI 25 =-= =--- - BU!I.T-UP TO *STANOARD* CVERLAY 1988 ------
--- NO REPORTABLE INDICATICNS - - - -
1990 -
=---- NO REPORTABI.E INDICATI25 --- - - - - -
1992 --
------- NOT INSPECTED - - -
1993 - - - NO REPORTABLE INDICATIONS --- - -== (QC2TIAN.wt1/all) i I cor-3oi-2co Revision 0 A.32 @PAtlFIC ! NUELFAR. : l 1 i I
- _ . _ . .- m m h
1 o i t WELD NO. IIAS-51I j PIPE SIIE 28' ~: W R TYPE: I CIM. "D*: 7.3* 8JIAI,SHR.: C.081* C UPSTREAM DNSTREAM l CONTI0tTRATION: EI. BOW PIPE l t PIPE WAIL THK. (tp): 1.387* 1.232* 1 i CVERIAY THK. (to): 0.582* 0.557* i IDW DELTA FERRITE ! TIRST IAYER TKK.4 N/A N/A t i s DIMENSION *A*: N/A 3.2* l REMAINING , I.ICAMDfT CRIENT. LOCATION CosmENT [ OUTAGE LENGTH DEPTH 1983 8" 14% N/A CIRC. PIPE SIDE INSI TREATED
- FIAWED PIPE 4* 11% N/A CIRC. PIPE SIDE EVALUATION PERFORMED 1* 8% N/A CIRC. EIJCW SIDE 2* 9% N/A CIRC. ELICW SIDE i
L 2985 8* 44 N/A CIAC. PIPE SIDE TIAWED PIPE EVALUATIN PERFORMED e 6.$* 54 N/A CIRC. PIPE SIDE + i 2.5* 15% N/A CIRC. ELBOW EIDE I 1986 6* 4% N/A CIRC. PIPE SIDE TIAWED PIPE EVAI/UATIces PERFORMED > 5* 13% N/A CIRC. PIPE BIDE f 2* 22% N/A CIRC. ELBOW SIDE i FIAWED PIPE EVALUATItaf PERTORMED ',
'1988 8" 8% N/A CIPC. PIPE SIDE i i
- STANDARD
- DVERIAT REPAIRED ;
1990 --- - --- NO REPORTABI.E INDICATIONS ----*-*------ f 1 1992 ---- NOT INSPECTED -- ------ l r 1993 ---
-- - NO REPORIABLE INDICATINS ------------
(QC2rIAW.wt1/s11) i i i t i i h t t r I cor-aoi-2co Revision o A 33 Spqtgpst j NLELEAR. !, f
.. -. . , . . . - . . .. -.,...a t . a w. - a
't I
PIPE SIZES 28" wE*D. NO.s II AS -r H - DIM. *O*a. 6.6* wCR TYPES -1 l k AXIAL SHR.: 0.05:* i
- UPSTREAM DNSTREAM COhTICURATION: PIPE EIJbOW PIPE WALL THR. -( t p ) : 1.235* 1.360*. ,;
OVERIAY THR. (to): 0.570* 0.570* 3 f LOW CELTA FER3,ITE - I FIRST IAYEit THK.s N/A N/A f t DIMENSION *A's N/A 2.8* REMAINING f OUTAGE LENCTH CEPTH LICAMENT ORIENT. LOCATION COMMENT [ 1983 43* 20% N/A CIRC. PIPE SIDE INSI TREATED; FLAWED PIPE " ,
- 30% N/A SPOT ELBOW SIDE EVALUATION PERTORMED l I
1985 43* 13% N/A CIRC. PIPE SIDE PU WED PIPE EVALUATION PERFORMED ; (intermit l 1926 43* 14% N/A CIRC. PIPE $!DE TIAwCD PIPE EVALUATION PERFORMED i (intermit { 1968 42.5* 12% N/A CIRC. PIPE SIDE FLAWED PIPE ETALUATION PERFORMED (intarait.)** i 1990 NO REPCRTAR2 INDICATIONS -------~~-- -
- STANDARD
- OVERIAY REPAIRED t f
1992 -- . NOT INSPECTED ----- -- -
'f I
l 1993 --- NO REPORTABLE INDICATI NS --- i i l THIS INDICATION HAS NO MEASURABLE LENCTH. ( 42-1/2* IS THE TOTAL EXTENT OF THE FLAWS WITH A COMBINED LENCTH Cr 34-1/2*. (QC2rIAv.wk1/all) r i
~
P i J
- i. !
i i 1
)
. s i
i ! i i COE-301-200 A.34 'M i Revision 0 wPREIFIC ! NUELFAR. I 1 l
FIFE SIIEs IB* WEID NO.r M BC - s e OIM. *D's B.C* WOR TYFEs . AXIAL SMR.s 0.065* UFSTREAM DNSTREAM COFIOL' RATION: ELBOW FIFE PIIE WALL TKK. (tp): 1.420* 1.349' OVEELAY THK. (to): 0.530' C.670* ICW CELTA EERRITE FIRST LAYER THK.3 N/A N/A CIKENSION *A*s N/A 4.D* RDtAINING OUTAOE I.ENGTH OEPTH LIGAKENT CRIENT, LOCATION COMMENT 1983 17* 39% N/A CIRC. elbow EIOE
- ENGINEERED
- CVERIAY REFAIRED I-1/4* 64% N/A AKIAL ELBOW SICE 1985 ------------- NOT INSFECTED ----=- - ----
1986 -------- NO REPORTABLE ICICATINS - = BUILT-UP TO *STACARD* OVERIAY 1998 2.75* N/A 0.58" CIRC. FIFE SIDE 1990 ------------- NO REPCRTABI.E INDICATIWS ---- - 1992 --------- - - NOT INS FECTED ------------------ 1993 ------------- NO REPORTAELE INDICATI ONS ------------- (OC2rIAW. wit 1/s11) COE-301-200 A.35 nevision 0 @P/1CIFit NUELFAR.
FIFE SIEEs 28* WE*J NO.s I;BO-F* 7.5* WOR TYPE 2 D!M. "D* AxIAI 5NR.3 C.056*
-- UFSTREAM ONSTREAM CONTIOURATIONs VAI.VE EI. BOW FIFE WALL THK. (tp): 1.455* 1.397*
CVERIAY THK. (to): 0.690* 0.540 LOW DELTA TERRITE TIR$'t LATER THK. s N/A N/A DIMENSION *A*s N/A 4.7* , REMAINING OUIACE LENOTH CEPTH LICAP3T CRIENT. LOCATION CNT 1963 ---- - ---- ROCT OEOMETRY ---------- -- --- IMSI TREATED 1985 ----------- NOT INSFECTED - - - - - 1986 4.5* 15% N/A CIRC. EI. BOW SIDE FLAWED FIFE EVALUATIN PERFORMED total 1988 3.0* 0.34' N/A CIRC. ELBOW SIOE FLAWED FIFE EVALUATIN FERFORMED w/ AIIAL COMPohTNT 3.0* 0.35' N/A CIRC. ELBOW SIDE 3.0* 0.35* N/A CIRC. ELSOW SIDE 1990 ------ - ----- NO REPORTABI.E INOICATI WS ------------- *STANOARD* CVERLAY REPAIRED 1.92 - - - - - - - - - - - - - NOT INSFECTED -- - + 1993 ------------- NO REPORTABLE INOICATI NS ------------- (QCITIAW.wal/all) COE-301-200 A*36 nevision 0 O. PAElFIC NUELEAR.
WELD NO.s II55-r; PIFE SIIE: 28' WDR TYFE: 2 OIM. 'C* 9.C* AXIAL SElt.: C.044* UPSTREAM ONSTRII.M COhTICUFJLTION: SATE END ELBOW PIFE WAI? THK. (tp): 1.260* 1.393* OVERLAY THK. (to): 0.57" D.518* LOW OELTA TERRITE FIRST IAYER THK.s N/A N/A DIMENSION *A* N/A 4.5* REFAINING OUTAGE LENGTH OEPTH LIGAMENT CRIENT. I.CCATION COMMENT 1983 ------ - NO REPORTABLE I C ICATI NS ------------- IHSI TREATED 1985 ------------- NO REPORTABIE I C ICATI NS ------------- 1986 BETCRE OVERIAY REPAIRS 15' 73% N/A CIRC. EI. BOW SIOE ATTER OVERLAY REFAIR: *STACARD* OVERIAY REPAIRED
-- NO REPORTAB'E ICICATI NS - - - - - - - - -
1988 NO REPORTABLE ICICATIms - - - - - - - 1990 NO REPORTABLE ICICAT!WS 1992 ----------
---- NOT INSFECTED --------- - ---
1993 ---- -
--- NO REPCRTABLE ICICAT!WS (OC TIAW.wki/all) l cor-3oi-2co Revision o A.37 gpg{gpg{
NtJCLEAR. i i i l
PIPE SIZES 28* C NO. s iib 5-52 DIM. *D's 8.3 WOR TYFE . AX I AI. S HR . : 0.067*
~~
UPSTREAM CNSTREAM CONTIOURATIONs EI. BOW PIPE PIPE WAI.I. THK. (tp): 1.418* 1.232* OVERI.AY THK. (to): 0.492* 0.495* LOW CELTA TERRITE FIRST LAYER THK.s N/A N/A OIMENSION *A*8 N/A 4.2* REMAINING OUTAOE LENGTH OEPTH I.ICAMENT ORIENT. *M *. TION COP 9'.ENT 1983 12" 404 N/A CIRC. EI. BOW SIDE *ENOINEERED* OVERLAY REPAIRED 1985 ----------- NOT INSFECTED = ----- 1986 --
----- NO REPCRTABLE INDICATICNS BUILT-UP TO 'STANOARD* OVERLAY 1988 1.0* N/A 0.48' CIRC. ELBOW SI E 2.0* N/A 0.44* CIRC. EI. BOW SIOE 1990 0.35' N/A 0.51* CIRC. ---
0.25* N/A 0.60* CIRC. --- 1992 -- - NOT INSPECTED - ---- 1993 0.30' N/A 0.52* CIRC. --- 0.30* N/A 0.58* CIRC. --- ( QCImW.w ki/all) COE-301-200 A.38 M Revision 0 wPACIFIE NUELEMR.
l
,I,E ,11E, I,. c N=.. II m ,-
WCR TYFE I OIM. 'D* 7.3 ARIAL $HR.: 0.C91*
~
- UFSTREAM ONSTREAM COhTIGURATIOWs VALVE PIFE PIPE WALL THK. (tp): N/A I.I50*
CVERI.AY THK. (to)e N/A C.484* LOW CELTA FERRITE FIRST I.AYER THK.: N/A N/A DIMENSION *A* N/A 4.1* REMAINING CUTACE LENOTH CEPTH LIGAMENT ORIENT. IDCATION COMMENT l 1983 360 DEO. 26% N/A CIRC. FIFE SIOE *ENOINEERED* CVERIAY REFAIRED 198$ - - - - - - - - - - - - --- HCT INSFECTED --- 1986 ------------- NO ELEPCRTABI.E INDICATINS - - - - - - - - = BUILT-UP TO *STWAAD* UVERIAY 1988 ------------- NO REPORTABLE INOICATINS = ------- 1990 --------- ---- NO RE PORTABLE INO I C ATI NS ------------- ( 1992 -
------ NOT INS FECTED -~ ~---- - - -----
i l 1993 ------------- NO REPORTABI.E INDICATI:E5 ------------- (DC2r:AW.wt1/all) ( l 1 COE-301-200 A,39 nevision o @ PACIFIC NUCLEAR. l j
20* hT*J No.: I;BS-S;. PIFE SIIIs LIM. *D*: 6.Ba w R TYPE: . l AXIAL SHR.: C.060* UPSTREAM ONSTREAM CONTIO'JRATIOWs EIJcw PIPE PIPE WALL THK. (tp): 1.417* 1.247' OVERLAY THK. (tc)3 C.525* 0.557* LOW CELTA TERRITE I l FIRST LAYER TEK.: N/A N/A 1 l l LIMENSION *A*: 4.1* N/A 1 l RIMAINING OUTAGE LENOTH CEPTH LI*M ORIENT. IDCATION COMMENT 1983 32* 16% N/A CIRC. PIPE SIDE IHEI TREATED; TLAWED PIPE j ROOT CEOM. EVALUATION FERTORMED j i 1985 36* 21% N/A CIRC. PIPE SICE CALLED
- ROOT GEOMETRY
- ONLY I ROOT CEOM.
1986 36* 13% N/A CIRC. PIPE SIOE CALLED
- ROOT GEOMETRY
- ONLY l l ROOT CEOM.
1968 36* 13% N/A CIRC. PIFE SI E FI. AWED PIFE EVAI.UATI:24 PERTCRMED ROOT CEOM. 1990 -------- ---- NO REPORTASLE IND IC ATI ONS ------------- *STAN0ARD* OVERIAY REFAIRED l l 1992 ------------ NOT INSPECTED - - - - - - - - - - 1993 ------------ NO REPORT ABI.E INDIC ATICNE ------------- (OC2rIAW.wt1/all) COE-301-200 A.40 K Revision 0 'eirPACIFIC NUELEAR.
WE1.0 No.: ::BS-r:4 p;pg SIggs 28* WOR TYPE: N/A
- p, *;*: N/A AX A1 SHR,3 N/A UPS*R.EAM CNETREAM COhTICURATION: PIFE ELBOW PIPE WA1.L THK. (tp)a 1.22* 1.34' ONTRIAY THK. (tols N/A N/A 14W OELTA TERRITE FIRST 1AYER THK. : N/A N/A DIMENSION *A*: N/A N/A REMAINING OEPTH LIGAMENT ORIENT. IDCATION COMMENT OUTAGE LENOTH 19% N/A CIRC. FIPE SIOE IMSI TREATED 1983 5-1/4*
1985 la 16% N/A CIRC. UPSTREAM WITH I.D. ROOT GEOMETRY 1996 ---------------- I . O . ROOT CEOMETRY - - - - - - = - - = 1988 - - - - - - - - - I.D. ROOT CEOMETRY ----- --- --- 1993 -------- NO REPORTAELE INDICATIOiS - - - (OCII' LAW vk1/all) COE-301-200 A*41 Revision 0 @ PACIFIC NUELFAR.
WELO NO.s .05-r; PIPE SIZES 2C' WOR TYFE: I DIM. *O*: 4.3* AXIAI. SHR. 0.C86* UPSTREAM ONSTPEAM CONTICURATION: TEE PIPE PIPE WALL THK. (tp): N/A 1.016* i C%TRLAY THK. (to): N/A C.491* LOW LELTA TERRITE FIRST IAYER THK. a N/A N/A OIMINSION *A*: N/A 3.25* REMAINING CRIENT. IDCATION cop.ENT OUTAOt 1.ENOTH CEPTH LI"M 'T 6* N/A CIRC. PIPE SIOE *ENOINEERIO* OVERI,AY REPAIRID 1983 11%
.... NOT INSPECTED - -
1935 .......____ 1986 ----- NO REPORTABLE INOICATICNS -- - ===- BUILT-UP TO *STANOARD* OVERIAY 1992 ------------------- NOT INSPECTED ------------------- 1993 ------------- NO REPORTABLE INOICATICNS =--- -- ( QCITIAW.wki/ ell) COE-301-200 A.42 Revision 0 @P/4ElFit NUCLEAR. . i a 4
WELO NO.3 '05-r? P!PE S!IE 20' W:R TYFEr 3 OIM. -D*: 3.9* NIM SHR.s C.Ct9e UPS M Ag gg3?R An COhTIOURATION: VAIAT PIPE PIFE EALI, TEK. (tp)s N/A 1.021' CVERIAY TMK. (to): N/A 0.543* LOW CELTA FERRITE FIRST IAYER THK. N/A N/A OIKENSION *A* N/A N/A REMAINING CRIENT. IDCATION COMMENT OUTAGE LENGTH OEPTH I.IGAMENT 3-1/I* 18% N/A CIRC. PIPE SI:E IHSI TREATED 1983 8* 12% N/A CIRC. PIPE SICE 11% N/A CIRC. PIPE SIOE
- ENGINEERED
- OVERLAY REPAIRED 1985 9*
10" 17% N/A CIRC. PIPE SIDE 3* 13% N/A CIRC. PIPE SIDE
---- NO REPCRTABLE INDICATI@5 ----
=- BUILT-UP TO
- STANDARD
- OVERIAT 1966 ---=
- - - - - - - =
1988 --------- NO REPORTABLE I!CICATIWS
------------- NO REPORTABLE INDICATI@S ---- ---
1990 ( DCIT JW.vk1/all) cot-201-2co nevision A.43
@patipic NUELFAR.
PIPE SIIEs 6.625* WEO NO.s .25-534 OIM. *D*s N/A WCR TYPE: N/A AXIAI. SHR.s N/A T. UPSTRE.AM CNSTREAM CONTICURATION: TLUED NEAD PIPE FIPE Wall. THK. (tp): 0.432' O.432' OVERI.AT THK. (to): N/A N/A LOW OELTA TERRITE FIRST I.AYER THK.s N/A N/A DIMENSION *A* N/A N/A REMAINING OUTAGE LEN::TH OEPTH LIGAMENT ORIENT. 14 CATION COMMENT 1988 3.75* 0.22' N/A CIRC. PIPE SILE *STAN;ARD* OVERLAY REFAIRED 6.2* 0.21' N/A CIRC. PIPE SIDE
--- 100% N/A AXIAL PIPE SIOE 0.10" N/A AXIAL PIPE SIOE 1990 REPLACED (QC2Tuw.wk1/all) l COE-301-200 A.44 Revision 0 b NUELE/-1R.
f l PIPE SIIE: 6.625 C NC.: ;IS-rIts
;;n, .g., y/g WCR TYPE: NIA l
AXIAI. SHR.: N/A J 1
~
UPSTREAM ONSTREAM i CONFIOURATION: PIPE PIPE PIPE W C THK. (tp): 0.432* 0.432' OVERLAY THK. (to): N/A N/A IDW CELTA FERRITE FIRST IAYER THK. : N/A N/A DIMENSION *A*: N/A N/A REMAINING OUTACE LENOTH OEPTM I,ICAMENT ORIENT. LOCATION COMMENT 1988 0.75* 0.ID* N/A CIRC. PIPE STOE
- STAh".,ARD
- DVERIJ.Y REP AIRED 1990 REFIACED (QC2FIAW.wki/all)
COE-301-200 A*45 Revision 0 O. P/4EIFIC NUELE/4R.
WEJ* NO. ;IS-51'* PIPE SIIE: 6.625* N/A WOR TYFEB N/A OIM. *O*: AKIAL SHR.s N/A
- F.r.NUMBERIO IIS-FI J UPSTRIAM ONSTRE.AM OONTIOURATIONs ELBOW PIFE PIFE WAI.L THK. (tp): C.432' O.432*
OVERIAY THE. (tels N/A N/A I4*f CELTA TERRITE TIRST IAYER THK.
- N/A N/A OIMENSION *A*: N/A N/A R.EMAINING !
i OUTAGE LENGTH OEPTH LI"m l? CRIENT. W ATION COMMDl? 1983 1-1/4" 20% N/A CIRC. ELDOW SILE REPLACED ( OC2TIAW.wki /all) cor-.3 o1-2 o o x.4s gpgg;pgg Revision 0 NUELEAR.
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02AS-S9 4.0" 042" FULL-STRUCTURAL WOR DESIGN i
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(1) Toe of overlay to blend smoothly into valve transition REF: Ceco ECN No. 04-00026M
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R EY. DESCRIPTION DATE DATE DATE DATE DATE JOB NO: PLANT: REV.
XCE-42 Quad Cities Unit 2 SHT.
1 FILE NO: DWG. NO:
OP XCE042.0201 XCE-42-201 ,
FadETB60141 cor-soi-2co a.32 $ PACIFIC Revision 0 NUELF.AR.
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0 FILE NO: DWG. NO: I OF CEC 047.0224 CEC 47-224 ,
A COE-301-200 B.33 OPAEIFIC Revision 0 NUELEAR.
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, A t 02ES-F2 100% x 360 4.0" 0.44" Full-Structural WOR Design
, 0 @ 44}p @ct/
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DESIGN OtMENSIONS WELD NUMBER FLAW CHARACTERIZATION COMMENTS 02BS F7 100% a 300* 40" 0.42" FULL STRUCTUR A L
, WOR DESIGN "8C WC M M Corrected sketch:
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REPAIR DETAILS NOTES:
- 1. Cwrity to ortand toward branch line as far as possible. *A* drn. need not i exceed 4 C' or shall not be issa than 2.S'. _y - -
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DESIGN DIMENSIONS WELD NUMBER FLAW CHARACTERIZATION COMME NTS t A B r
02BS-512 100% x 360'
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FILE NO: DWG. NO: e I l
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Revision 0 NUELF.AR.
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- t A B 105 F1 100% x3 d 0.45" (1) 3.25" FULL STRUCTUR AL !
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0 FILE NO: DWG. NO: '
OF CECD47.0215 CEC-47 215 COE-301-200 B.38 OPACIFIC Revision 0 NUELEAR. i
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I CEC 47 QUAD CITIES UNIT 2 SHT.
1 FILE NO: DWG. NO: '
OF CEC 047.0216 CEC 47 216 1
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i
Appendix C OUAD CITIES UNIT 2 SUSTAINED STRESSES AT UNFLAWED WELD LOCATIONS Table System Pace C-1 Reactor Recirculation System - 12" Risers C.1 C-2 Reactor Recirculation System - 22" Header C.2 C-3 Reactor Recirculation System - C.3 28" Suction & Discharge C-4 Shutdown Cooling System C.4 C-5 RHR (LPCI) System C.5 C-6 Core Spray System C.6 NOTES:
(1) Internal pressure (IP) stress (psi)= 'j *, { '
where:
P = Internal pressure (psi).
OD = Outside diameter (in.)
t, = Pipe wall thickness (in.)
(2) DW, TH, and WOS stress = h . A\*"'
where:
DW = Dead weight load / moments.
TH = Thernal expansion load / moments.
WOS = Weld overlay shrinkage load / moments, Fx = Axial load (1bs.)
My or Mz = Bending moments (in.-lbs.)
A S
= Metal cross-sectional area (in.2)
= Metal section modulus (in.3)
(3) Unless noted otherwise:
Total stress = lIPl + lDWl + lTHl + lWOSl.
(4) S = Allowable design stress intensity for Type 304 stainless i steel at design temperature of 550*F per ASME Section III Appendices Table I-1.2.
(5) Stress ratio = (total stress) / S,. .
(6) Total stress = algebraic sum of IP + DW + TH + WOS.
COE-301-200 C.0 @P/4EIFIC Revision 0 NUELEAR. I l
Table C-1 OUAD CITIES UNIT 2 SUSTAINED STRESSES REACTOR RECIRCULATION SYSTEM 12" RISERS IP DW TH WOS TOTAL STRESS STRESS STRESS STRESS STRESS S*
WELD NO. (1) (2) (2) (2) (3)
R O (4)
(psil (psi) (psi) (psi) (psil (ps0 02C-F2 5800 1676 2128 11430 21033 16950 1.24 02C 56 5800 562 4032 5640 16034 16950 0.95 02D-F2 5800 598 2096 19450 22856* 16950 1.35 02D-F6 5800 415 3239 438 9892 16950 0.58 02D-54 5800 222 878 2871 9771 16950 0.58 02E-F2 5800 59 1979 7919 15756 16950 0.93 02E-F6 5800 331 1988 4841 12960 16950 0.76 02E-54 5800 97 643 4281 10821 16950 0.64 02B F6 5800 642 1134 1226 8802 16950 0.52 02F-F2 5800 76 704 526 7106 16950 0.42 02F-54 5800 99 384 762 7045 16950 0.42 02G-F2 5800 724 2009 2214 10746 16950 0.63 02G-F6 5800 531 1265 3810 11406 16950 0.67 02H F2 5800 554 1291 7413 15058 16950 0.89 02H-F6 5800 120 1918 5619 13457 16950 0.79 02)-F2 5800 388 715 6291 13194 16950 0.78 02K-F2 5800 240 841 7311 14193 16950 0.84 02L-F2 5800 140 757 17437 24133 16950 1.42 02L-F6 5800 709 1694 354 8556 16950 0.50 02M-F2 5800 810 1293 5042 12945 16950 0.76 02 M-F6 5800 444 2135 3875 12253 16950 0.72 COE-3oi-2co Revision 0 C.1 @PMEIFit NUCLEAR.
Table C-2 OUAD CITIES UNIT 2 SUSTAINED STRESSES REACTOR RECIRCULATION SYSTEM 22" HEADER PIPING IP DW TH WOS TOTAL STRESS STRESS STRESS STRESS STRESS S. k WELD No. (1) (2) (2) (2) (3) (4)
(psil (psil (psil (psi) (psil 5)
(psi) 02 F1 6290 109 864 182 7444 16950 0.44 02-F1 D 6290 330 802 505 7926 16950 0.47 02-F1 E 6290 547 737 773 8348 16950 0.49 02-F2 6290 687 671 1009 8657 16950 0.51 02 A-F1 6290 149 844 665 7948 16950 0.47 02 A-F5 6230 316 275 5904 12785 16950 0.75 02A 53 6290 203 734 6009 13236 16950 0.78 02B-F1 6290 539 461 1475 8765 16950 0.52 028 F5 6290 600 2273 703 9866 16950 0.58 02BS7 6290 252 1727 542 8812 16950 0.52 l
1 l
l CoE-3oI-2co nevision o C.2 @ PACIFIC !
NUELEAR.
I
Table C-3 OUAD CITIES UNIT 2 SUSTAINED STRESSES REACTOR RECIRCULATION SYSTEM 28" PUMP SUCTION & DISCHARGE PIPING IP DW TH WOS TOTAL STRESS STRESS STRESS SS STRESS STRESS S-WELD NO. (1) (2) (2) (2) RATao (3) (4)
(psd (psd (psd g
(psd (ps4 (p sd 02 A-54 6439 85 167 -146 6544 16950 0.39 02 AD.F1 6439 384 368 226 7416 16950 0 44 02AD-F8 6439 123 73 557 7191 16950 0.42 02AD-F9 6439 339 148 145 7070 16950 0.42 02 ADS 2 6439 390 320 854 8003 16950 0.47 02 BD-F1 6439 342 1803 199 8783 16950 0.52 02BD F12 6439 420 747 171 7777 16950 0.46 02BD-F9 6439 321 771 147 7677 16950 0.45 02BD.51 A 6439 76 105 135 6754 16950 0.40 02BD-S2 6439 384 1471 228 8521 16950 0.50 02 AS-F2 7273 317 359 275 8224 16950 0.49 02AS-F5 7273 196 142 855 8467 16950 0.50 02AS-F8 7273 57 257 609 8196 16950 0.48 02 AS-S3 7273 243 318 138 7972 16950 0.47 02 AS-S6 7273 278 93 736 8381 16950 0.49 02BS-F14 7273 234 310 175 7993 16950 0.47 02BS-F2 7273 124 1872 318 9587 16950 0.57 02BS-F4 7273 384 219 355 8232 16950 0.49 02BS-F8 7273 131 1123 518 9046 16950 0.53 02BS-55 7273 488 2978 602 11341 16950 0.67 02BS 59 7273 231 228 371 8104 16950 0.48 COE-aoI-2co Revision o C.3 @PAEIFIC NUCLFAR.
Table C-4 OUAD CITIES UNIT 2 SUSTAINED STRESSES SHUTDOWN COOLING SYSTEM i
IP DW TH WOS TOTAL STRESS STRESS STRESS STRESS STRESS 5 WELD No. (1) (2) (2) (2) ratio (3) (4)
(psi) (psi) (psil g (psil (psi) (psi) 105-F 11 6062 476 2434 357 9329 16950 0.55 105 F14 A 6062 142 3349 650 10203 16950 0.60 105-F 15 A 6062 508 1184 840 8595 16950 0.51 105-F18 6062 716 250 0 7028 16950 0.41 105-F4 6062 357 5971 706 13097 16950 0.77 105 512 6062 282 2084 249 8678 16950 0.51 105S13 6062 158 4860 632 11712 16950 0.69 10S517 6062 265 1064 0 7392 16950 0.44 105-519 6062 734 389 0 7186 16950 0.42 105-53 6062 461 2790 497 9809 16950 0.58 105-56 6062 332 5536 622 12552 16950 0.74 105-57 6062 198 1874 157 8241 16950 0.49 105-S8 6062 105 2524 292 8983 16950 0.53 )
105-59 6062 304 2558 301 9225 16950 0.54 ;
105-F20 6062 294 887 0 7244 16950 0.43 1
cor-3oI-2co c.4 @P/4CIFIC nevision o NUELEAR.
Table C-5 OUAD CITIES UNIT 2 SUSTAINED STRESSES RHR (LPCI) SYSTEM IP DW TH WOS TOTAL STRESS STRESS STRESS STRESS STRESS STRESS $* RATIO WELD No. (1) (2) (2) (2) (3) (4) g (pad (psd (psi) (psi) (ps0 (pos)
LOOP A 10ADJ1 6061 2814 11842 3008 23725 16950 1.40 10 AD-F11 6061 695 755 2388 9899 16950 0.58 10 AD-F12 6061 1321 5918 3767 17067 16950 1.01 10 AD-F3 6061 917 7754 1223 15954 16950 0.94 10 AD-F4 6061 372 3674 1754 11861 16950 0.70 10 ADJ8 6061 651 9034 1259 17004 16950 1.00 10 AD-S 2 6061 271 3448 269 10049 16950 0.59 10 AD 55 6061 1248 8347 2149 17805 16950 1.05 10 AD-S6 6061 864 7121 1349 15395 16950 0.91 10 AD-57 6061 109 1972 256 8398 16950 0.50 10 AD-59 6061 302 9325 161 15848 16950 0.93 LOOP B 10BD-F1 6061 1057 12074 1071 20262 16950 1.20 10BD-F14 6061 290 2368 941 9660 16950 0.57 10BD-F15 6061 1328 4485 1524 13397 16950 0.79 10BD-F5 6061 605 6812 744 14222 16950 0.84 10BDJ6 6061 1272 5920 1004 14256 16950 0.84 10BD-S10 6061 105 2291 108 8564 16950 0.51 10BD-511 6061 323 3944 288 10616 16950 0.63 10BD-512 6061 744 6698 603 14105 16950 0.83 10BD-513 6061 333 8290 59 14743 16950 0.87 10BD S2 6061 310 2048 238 8657 18950 0.51 10BD-S3 6061 312 10203 232 16808 16950 0.99 10BD S4 6061 279 8778 257 15374 16950 0.91 10BD-57 6061 967 9479 1217 17724 16950 1.05 10BD-58 6061 748 7503 739 15050 16950 0.89 .
10BD-S 9 6061 57 7634 613 14364 16950 0.85 CoE-3oI-200 c.s @ PACIFIC Revision NUELEAR.
Table C-6 OUAD CITIES UNIT 2 SUSTAINED STRESSES CORE SPRAY SYSTEM iP DW TH WOS TOTAL STRESS STRESS STRESS STRESS STRESS STRBS S* RATIO WELD No. (1) (2) (2) (2) (3) (4)
(ps.) (p si) (poil (psi) (psi) (psi)
LOOP A 14 A-F10R 5665 274 2398 0 8336 16950 0.49 14 A-F12 5665 279 5124 0 11068 16950 0.65 14 A F13 5665 467 3391 0 9523 16950 0.56 14 A-F17 5665 101 6911 0 12678 16950 0 75 14 A-F2 5665 601 6296 0 12562 16950 0.74 14 A-F 4R 5665 552 5587 0 11804 16950 0.70 14 A-S 1 5665 795 8255 0 14715 16950 0.87 14A 511 5665 217 1232 0 7114 16950 0.42 14 A-S14 5665 120 2958 0 8743 16950 0.52 14 A S15 5665 281 2423 0 8369 16950 0.49 14 A-516 5665 340 6249 0 12254 16950
[ 0.72 LOOPB 14B F11R 5665 264 1748 0 7678 16950 0.45 148-F13 5665 240 3022 0 8927 16950 0.53 14B F14 5665 598 3280 0 9544 16950 0.56 F14B.F14 AR 5665 756 3784 0 10204 16950 0.60 14B F16 5665 184 7113 0 12962 16950 0.76 148-F2 5665 472 3377 0 9513 16950 0.56 14B-F4R 5665 783 2287 0 8736 16950 0.E2 148-51 5665 69 6068 0 11801 16950 0.70 14B512 SE65 275 708 0 6648 16950 0.39 14B 515 5665 286 6905 0 12856 16950 0.76 14 B-S8 R 5665 328 6993 0 12986 16950 0.77 COE-301-200 C.6 @ PACIFIC nevisia o NUELEAR.
Appendix D EVALUATION OF WELD 02J-S3 OVERLAY BOAT SAMPLE i
COE-301-200 D.0 @P/4ElFIE nevision NUELFMR.
i e....
- t SYSTEM MATERIALS ANALY3:5 OEPARTMENT REPCRT ON )
02J-53 R:5ER WELD OVERLAY ECAT 3 AMPLE FRCM l OUAD CITIES 5TATION 'JNIT 2 ~
i l
During the Rio outage of Quad Cities station 'Jnit 2. an i ultras-- inspection of the overlay on 02J-53 etset weld, e't:s .
side. revealed axial cracts extending into the overlay. As a r e s . '.
of the apparent cract extension into the overlay. a boat sample .as d
removed which captured the deepest cract penetration into the overlay. This boat sample was metallurgically examined to verify !
the depth of cract penetration into the overlay and to identify the ;
l mechanism of crac, ting. Based on this analysis. no cract penetrati:n into the weld overlay occurred. Evidently, the UT sizing of the ;
eract (remaining ligament) was overly conservative. One axially oriented IGSCC type cract was observed which terminated at the case metal-weld metal overlay interface.
i NDE Inspection Bactoround l During the R9 outage in 1988 CAPCo applied an overlay to the i i
02J-S3 risst veld due to an axial cract indication. The overlay thickness was approximately 0.3". Upon completion of the overlay a baseline UT inspection, performed by General Electric, tevealed two f i
axial indications terminating at or near the fusion line of the i overlay. Reinspection of the overlay during the R10 outage by ;
Lambert. McGill and Thomas (LMT) revealed two axial indications.
, One of the axial indications was reported to have a remaininq !
i ligament of 0.12". The other indication had a remaining ligament of 0.45". SKAD NDE personnel also inspected the overlay and ,
I l :
i COE-301-200 Revision o D.1 OPACIFIC !
NUCLEAR. 3 l
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I 6
w - ! ; *. ; . ,
- 4;e 2 E reported Vo axial flaws approximately 1/2" apart vita ge gee;e - I penetration resulting in a remaining 11; ament te: ween 3... s
[
3 25* Tne otner axial indication was not in :ne overlay. Bo . . e- I ang $ MAD personnel located and marted the area wnere One ti.nnegt II; ament (deepest cract penetration into One overlay) sas coserved !
t This area was then captured in a boat sample for further ana;fsts.
- Metallucrical Analysis e
The as-receiaed boat sample was visually examined. Two ;unen {
marks approximately 1/2" apart were on the boat sample. The N;g I
personnel reported the thinnest remaining ligament was located between the two punch marts. The boat was approximately 3- long.
3/4" wide and 0.383" deep. j Based on the location of the punch marks, five different cross sections through the boat sample were metallographically prepared ,
and examinsd. The deepest crack observed was in the first cross f
section examined. An intergranular crack was observed in the base ,
i metal directly beneath the fusion line of the overlay. The cract ;
was in the center of the material captured by the sample. Figure 1 is a photctierograph of the cract. Note that the cract stops at ne fusion line and does not penetrate into the weld metal overlay. I Figure 2 is a closer view of the cract which terminates at the I
- i fusion line. Examination of ;% other cross sections showed the cract to be either further from the fusion line or not present. l This indicates that the deepest cract penetration (which is i
synonymous with the thinnest remaining ligament) did not penetrate
)
into the weld overlay. The measured remaining ligament was 0.27". )
the thickness of the overlay at that location. In other cross .
1 sections,'the overlay was measucc4 to be as thlet am 0.35" ,
j 1
i I
l COE- 3 01-2 00 Revision 0 D.2 OP/4EIFit NUELE/1R.
i d . ; i t. ,
.:4;e Metallographic examination of the weld metal ses ;erf:r e: -
*te unet:ned and etened conditi0ns. This was done to ident;!/ .. ,
possible sources of a UT reflector. No evidence of any sel:;.; :
related defect was observed. F quee 3 ts a pnotomterogra;n Of ~~e weld metal microstructure. The delta ferette content of ne se.!
was determined with the aid of a computer enhanced ; mage andi/2er The average delta ferrite content was 12.7%.
Conclusion Based on this analysis and conversations with the inspection ersonnel, the flaw which was reported to be in the weld overlay was t found and implies the indication was over-sized. The 2 termination of the remaining ligament was overly conservative. No vidence of defec'ts such as, cracks. lack of fusion, porosity, or lag were found. The thinnest remaining ligament which should have een measured was 0.27a. the minimum thickness of the overlay at 3at location.
3 *s f Approved by* ! - / /d Reported by: ~ /4- l i
t A 'A % f >
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' / ' Copies to: R. ' L. ia r , Qu a d Ci t ie s .
fg R. P. fuetken. Opus
. G. C. Tietz, Opus ;
R. J. Tanainga. Opus H. Do, Opus L. Petrie, Quad Cities ;
T. A. Kutsut. Quad Cities ;
i i
12.1.2 ' -
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COE-301-200 Revision 0 0.3 hpg{lpg{
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11.25I Magnification 10% oralie Acid Electrolytie figure 1. Boat sample cross section showing the craet terminating at the fusion line of the overlay.
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'l 150% Magnification 10% Oxalic Acid-Electrolytic figure 2. Magnified view of the crack in Figure 1. Note that the crack extends to the fusion line but does not progress any further.
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2837M-5 COE-301-200 Revision 0 D.5 OPACIFIC NUCLEAR.
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l 3OOK Magnification 10% Oxalic Acid Electrolytic Figure 3. The typical weld metal microstructure. The delta ferrite content of the veld was determined to be 12.71L using a computer enhanced image analyzer.
i 2837N-6 COE-301-200 D.6 OPACIFIC Revision 0 NUCLEAR. i
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