Text

Forwards Final Rept of Fall 1989 IGSCC Insp Plan,Discussing Items Such as Overlay Repair on Weld 02G-S4,mechanical Stress Improvement & Piping Mods
	ML20005E121
Person / Time
Site:	Quad Cities
Issue date:	12/18/1989
From:	Stols R; COMMONWEALTH EDISON CO.
To:	Murley T; Office of Nuclear Reactor Regulation
References
	0037K, 37K, NUDOCS 9001030315
	Download: ML20005E121 (131)
	v • d • e

{{#Wiki_filter:. ~.. i . ;$.a;, k. a N_ Commonwealth Edloon f l _ ( One Fir:1 N r.ional Plaza, Chicago, Illinois ~ ( Address Reply to: Post Ofhoe Box 767

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M 4 Y,. A f Chicago,ilhnois 60690 0767 4 L December 18, 1989 E Dr. Thomas'E. Murley, Director . Office of Nuclear Reactor Regulation 'U.S. Nuclear Regulatory Comission Washington, DC 20555-

Subject:

- Quad Cities Nuclear Power Station Unit 1. .Intergranular Stress Corrosion Cracking (IGSCO) Final Inspection Results~ NRC Docket No. 50-254

Reference:

(a) R. Stols to T.E. Murley letter dated June 9, 1989 (b) R. Stols to T.E. Murley. letter dated November 17, 1989 ~ Dr. Hurleys. 2 Reference (a) transmitted the inspection plan for piping susceptible to intergranular stress corrosion cracking (IGSCC). Following the completion of the inspection, Comonwealth Edison transmitted the preliminary results of the inspection plan implementation.(reference (b)). In reference (b)-Comonwealth Edison comitted to transmit the final report of the Fall, 1989 ICSCC Inspection Plan.-' Enclosure 1 provides a summary of the ultrasonic examination and other IGSCC related activities performed during the refueling-outage. In addition, enclosure-1 contains the response to the issues discussed during the conference call conducted on i November 21, 1989. Enclosure 2 provides the analysis and evaluation of indications-in the Reactor Recirculation, Residual Heat Removal, and Core . Spray piping systems. Please direct any questions on this topic to this office. Very truly yours, ~ Rita Stols Nuclear Licensing Administrator RS/ gad /0037k L

Attachment:

Ultrasonic Examination of IGSCC Susceptible Stainless Steel Weldments 7 l-Evaluation and Disposition of Flaws at Quad Cities Nuclear Power Plant - Unit 1 cc: Regional Administrator, Region III av Senior Resident Inspector, Quad Cities Quad Cities Project Manager / W. Koo, NRR 9001030315 891218 i L PDR ADOCK 05000254 sq PDC g

e. w .y, I$ I ENCLOSUEE_1 ULTRASONIC EXAMINATION OF IGSCC SUSCEPTIBLE STAINLESS STEEL HELDMQQS 00AD CITIES UNIT 1 - FALL 1989 REFUELING OUTAGE INTRODUCTION This enclosure provides a report of the ultrasonic examinations (UT) performed on-Intergranular Stress Corrosion Cracking-(IGSCC) susceptible stainless steel weldments during the Quad Cities Unit 1 Fall 1989 refueling - outage. In addition _to the UT examinations results, this report also provides: a comparison of the current overlay UT results with those of the e 1987. refueling outage. a description of the repair activities to the overlaid weld e 02G-S4. a description of the repair activities to the overlaid weld 02H-S3 which had a pipe lock. a discussion of the stress improvement activities during the 1989 refueling outage. a brief discussion of the RWCU,-Head Spray, and CRD piping e removal modifications. responses to the NRR concerns discussed on November 21, 1989. EXAMINATION SCOPE As shown in Table 1, a total of 182 weldments were ultrasonically examined during the current Quad Cities Unit 1 refueling outage. This examination scope meets or exceeds the requirements of Generic Letter 88-01. It also addresses the requirements of the Safety Evaluation dated June 6, 1989 for Quad Cities Nuclear Power Station, Unit 1. The examination scope includes: Six (6) category "A" weldments. All 105 category "C" weldments, including 1007. of the unrepaired IHSI welds. All 25 remaining category "D" weldments after the removal of the Head Spray and Control Rod Drive piping. l

sq q M 3 p 64 I t All'15 category "E" weldments.

All 16 category "F" weldments after build'up or application of standard overlay repair, inc1'Jding welds 02G-S3, 028S-SS, 02BS-S9,.02M-S3, and 10BD-S13.

g All 15 remaining and accessible category "G" weldments after the Pa=ctor Hater Clean Up piping modification. Lambert, MacGill, and Thomas, Inc. (LMT) performed the ultrasonic examinations using level II and III examiners qualified by EPRI after September 10.-1985. Both manual and automated UT techniques were utilized. No new IGSCC-like flaw indications were identified this outage. However, indications were detected in the overlay material of three weld overlay repairs; 02G S4, 02D-S3, and 02C-S3, For wold overlay 02G-S4, flaw indications were removed and the weld overlay was repaired. The flaw indications in the weld overlay repairs on welds 020-S3 and 02C-S3 were judged .to be welding defects and found acceptable for continued operation without additional repairs. Because the scope of the examinations performed satisfies the Generic Letter 88-01 inspection requirements of categories A, C, D, and E welds for two (2) refueling cycles and because no new flaws are found this outage, no ultrasonic e'xamination of the aforementioned welds will be performed during the next Unit 1 refueling outage currently scheduled in the Fall of 1990.- DISCUSSION. 1. HELD OVERLAY REPAIR ON HELD 02G-S4 A standard weld overlay repair was applied to this weld in 1987. Two layers of weld overlay material were applied without any steam blowouts. The surface of the overlay repair was machined to obtain an acceptable surface condition for UT. This surface conditioning process resulted in the overlay repair thickness to be below the minimum thickness required for a standard overlay repair. A third layer was added to the overlay repair. A steam blowout was E experienced during the addition of the third layer. The steam blowout was repaired and a fourth layer was added to the overlay repair. Again, a steam g blowout was experienced during the addition of the fourth layer. The steam blowout was repaired without water inside the pipe. No additional layer was added to the overlay repair after the fourth layer steam blowout repair. 1 ] I I {'

g l 5.! 1 The overlay repair was ultrasonic examined in 1987 after the application of four (4) layers of weld overlay' material. Several axial-indications were detected.with the deepest flaw at 0.38" remaining ligament. In-1989, this weld overlay repair was re-examined ultrasonically. Two (2) linear indications were detected at low amplitude in the weld overlay material at 0.14" and at 0.17"/0,19" remaining ligament; however, the indications could not be followed into the base material. These indications were located in the general location of the deepest flaw found in 1987 at 0.38" remaining ligament. This was also the location of a steam blowout i repair. A boat sample was taken in order to determine if IGSCC had grown into the overlay material. The results'of the destructive examination of the boat sample indicated that the linear indications were stringer slag inclusions, possibly introduced into the weld overlay during the repair of the steam blowouts. No water leakage was observed during the removal of the boat sampie. The boat sample cavity was filled with welding material and an additional layer of welding material was applied. A new baseline UT was performed on the repaired weld overlay with no indications reported in the overlay material. 2. HELD OVERLAY REPAIR ON HELD 02M-S3 A leak barrier. overlay repair was applied to weld 02M-S3 in 1984. Only a bonding examination was performed after the overlay application. In addition, a pipe lock was installed on this leak barrier weld overlay repair. In 1989, the pipe lock was removed from this weld. As previously committed, a best effort ultrasonic examination was performed on the leak barrier overlay repair. It was determined that the pre-existing flaws had not propagated. The leak barrief overlay repair was built up to a standard overlay design. An ultrasonic examination was performed after the standard overlay build-up and no indications were reported. Since a standard overlay has been applied to this weld, the pipe lock was not reinstalled. 3. MECHANICAL STRESS IMPROVEMENT A total of twenty-nine (29) stainless steel welds were stress improved during this outage using the Mechanical Stress Improvement Process (MSIP). The original plan called for stress improvement of a total of thirty-six (36) stainless steel welds. Seven (7) welds could not be stress improved because of weld geometry or interferences.

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A post treatment ultrasonic examination was performed on these twenty-nine (29) welds with.no IGSCC-like indications reported.

4.- iPIPING MODIFICATIONS-a. Reactor Hater Clean UD (RHCU) 1 The Reactor Water Clean Up (RHCU) piping modification replaced a section of the non-conforming Class 1 RHCU piping with conforming material-(316L stainless steel). This section begins at the last elbow inside the j containment and ends at the outboard' containment isolation valve.- a i This modification replaced one (1) category A, three (3) category D, and one (1) inaccessible category G welds with six (6) category A -welds. These six (6) category A welds were also stress improved by the q -Mechanical Stress Improvement Process (MSIP). Two (2) of these six (6) 1 category A welds are inaccessible, and they received a baseline UT prior to. installation inside.the flued head penetration, b. Head Sorav The Head Spray piping modification removed all Class 1 IGSCC susceptible welds that are at least 4".in diameter in the Head Spray system j except for the Nozzle-to-Safe End and the Safe End-to-Flange welds. l This modification eliminated one (1) category A, twelve (12) category D, and one (1) category G welds in the Head Spray system. A blind flange has.been installed on the Head Spray nozzle. The Nozzle-to-Safe End and the Safe End-to-Flange welds were stress improved by MSIP. c. CRD Return The CRD piping modification eliminated all Class 1 IGSCC susceptible welds that were at least 4" in diameter from the CRD Return line. This modification also eliminated some 3" IGSCC susceptible welds from the CRD i Return line. This' modification eliminated one (1) category A, two (2) category D, and one (1) category G welds on the CRD Return line. These four (4) welds were 4" in diameter. An end cap was welded to the Safe End of the CRD return nozzle. The Nozzle-to-Safe End and the Safe End-to-Cap welds were stress improved by MSIP. These two (2) welds are 3" in diameter.

v: > m i:r 't .. - -i, ; !( ~ it 5.. RESPONSES TO NRR CONCERNS a. Characteristic of two (2) indications in 02G-S4 overlav. Indication: Type Remaining Indicati_on A Liaament Lenath Distance 1: Circ. 0.14" 0.30"- 0.10" r.~ 2-downstream: Circ. 0.17" 0.60" 1.10" 2-upstream. Circ. 0.19" 1.20" 0.30" / ___m_/_. i I b elbow 1 C Slow ) )

y D b I. yy b. Thickness of overiny renair on weld 02G-S4. - The thicknesses of the overlay repair on weld 02G-S4 before the removal of the boat sample were:

Pipe side - 0.347 inch.
Elbow side - 0.331 inch.

The thicknesses of the overlay repair on weld 02G-S4 after the 4 reliair of the boat sample removal and surface conditioning are:

Pipe side w 0.495 inch.

Elbow side - 0.480 inch. c. Re-examjnation of the weld overlay 02G-S4 during the next Unit _1 -Ifiqelipa outage.- g _ Quad Cities station will' not UT veld overlay 02G-S4 during the next refueling outage, currently scheduled for the Fall of 1990, because: The linear _ indications detected in the weld overlay 02G-S4 were not due to the IGSCC growth into the overlay material. The destructive examination of the boat sample which was removed from the location of the indications confirmed that the indications were stringer slag inclusions. The new UT baseline of the weld overlay 02G-S4 recorded no indications in the overlay material. This UT result indicated that the linear indications in the overlay material were completely removed by the boat sample.

g 4 s i i i TABLE 1 Ultrasonic Examination Scope Quad Cities Unit 1 - Fall 1989 Refueling Outage TOTAL NUREG-0313 HELD CATEGORY NEW SYSTEM SIZE EXAM. A-C D E F G FLAH RECIRCULATION Outlets 28" 30 0 28 -0 0 2 0 0 Noz-SE 28" 1 1-0 0 0 0 0-0 Header 22" -12 0 7 2 2 1 0 0 Risers 12" 41 0 22 0 13 6 0 0 Noz-SE 12" 4 4 0 0 0 0 0 0 Bypass 4" 8 0 0 5 0 0 0 0 RHR SDC 20" 16 0 3 10 0 0 3 0 LPCI 16" 26 0 25 0 0 1 0 0 CORE SPRAY 10" 26 0-20 0 0 6 0 0 JPI. 12",8",4" 10 0 0 3 0 0 7 0 RHCU & SPARE. N0Z & ~ 6" 5 1 0 4 0 0 0 0 HD SPRAY - HD VENT & 4" 3 0 0 1 0 0 2 0 CRD' - TOTAL EXAMINATIONS -182 6 105 25 15 16 15 TOTAL NEW FLAWS 0 1.

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En ', TABLE 2 Flaw Characterization Comparisons Standard Held Overlay (OL) Repairs U

o Quad Cities Unit 1 - Fall 1989 Refueling Outage-Minimum Year-Stand. OL Held ID Examined UT Results-Thishnail

. RECIRC - :12" 02C-S3 (1) 1987-OL not examined due to Leak 0.23" Barrier Overlay (LBOL). r 1989 Axial; 0.19" Remaining Ligament (RL). Axial; 0.73" RL. 02C-S4 1987 Axials; 0.40" Min-RL. 0.265" 1989 Axials; 0.36" Min RL. 02D-S3 (1) 1987 OL not examined due to LBOL. 0.23"- 1989 Circ; 0.16" RL (No measurable depth). 02D-S4 1987 Axials; 0.38" Min RL. 0.25" 1989 Axials; 0.38" Min RL. 02E-S3 (1) 1987 OL not examined due to LBOL. 0.24" 1989 1k) reportable indications after-standard OL application. 02E-S4 1987 Axials; 0.36" Min RL. 0.24"- 1989 Axiels; 0.30" Min RL. 02F-S3 1987 No indications in OL. 0.21" 1989 Axial; 0.41" RL. 02F-S4 1987 Axial; 0.41" RL. 0.24" 1989 Axial; 0.38" RL. 02G-S3 1987 Axials; 0.38" Min RL. 0.26" 1989 Axials; 0.35" Min RL. 02G-S4 1987 Axials; 0.35" Min RL. 0.24" Laminar at 0.32" RL. 1989 No reportable indications after repair of boat sample I excavation. 02H-S3 1987 Axials; 0.43" Min RL. 0.25* 1989 Axials; 0.44" Min RL. 02H-S4 1987 Axials; 0.35" Min RL. 0.24" 1989 Axials; 0.35" Min RL. 02J-F6 1987 Axials; 0.26" Nin RL. 0.21" 1989 Axials; 0.25" Min RL. l l. 1 l

cr n, ? + b-C y s TABLE 2 -Flaw Characterization Comparisons Standard Held Overlay (OL) Repairs Quad Cities Unit 1 - Fall 1989 Refueling Outage Minimum . Year Stand. OL i Held ID Examined UT Results Thicknen RECIRC - 12" 02J-S3l 1987 Axials; 0.37" Min RL. 0.24" 1989 Axials; 0.37: Min RL. 02J-S4-1987 Axials; 0.33" Min RL. 0.235" 1989 Axials; 0.33" Min RL. 2 02K-F6 1989 No reportable indications after 0.24"' standard OL application to balance 1 system. shrinkage stresses. 02K-S3 1987 Axials; 0.35" Min RL. 0.235" Ci rc. ; 0.50" RL. 1989 Axials; 0.35" Min RL. 02K-S4' 1987 Axials; 0.37" Min RL.

0. 24" ~

1989 Axials; 0.37 Min RL. 02L-S4 1989' No reportable indications after 0.24" standard OL application to balance system shrinkage stresses. '02M-S3 (1) 1987 OL not examined due to LBOL. 0.24" 1989 No reportable indications after standard OL application. -02M-S4 (1) 1987 OL not examined due to LBOL. 0.25" 1989 No reportable indications after standard OL application. RECIRC - 22" 02B-F1 (1) 1987 OL not examined due to LBOL. 0.37" 1989 No reportable indications after standard OL application. 028-S7 1987 Axial; 0.56" RL. 0.37" 1989 Circs.; 0.6" Min RL. 028-S10 1987 Axials; 0.45" Min RL. 0.37" 1989 Axials; 0.32" Min RL. (Evaluated in 1989 by NUTECH and found acceptable for coritinued operation). -- l

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u y JABLL2 (Continue'd)- x Flaw' Characterization' Comparisons ~ r Standard Held Overlay (OL). Repairs

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Quad Cities Unit Fall 1989 Refueling Outage Minimum. . Year -Stand. OL-Held-ID' " Examined UT Results Thickness RECIRC - 28"- J 02BS-SS-(1) '1987 OL not examined due to LBOL. 0.46" 1989 No reportable indications after standard OL application. 02BS-S9 (1); 1987 OL not examined due to LBOL.- 0.49" 1989 No reportable indications after standard OL application. CORE SPRAY 30" 14A-F2 (1) 1987 OL not examined due to LBOL. 0.22" 1989 No reportable indications after standard OL-application. -14A-F11~(1) 1987 OL not examined due to LBOL. 0.22" 1989 No reportable-indications after standard OL' application. 14A-S8 1987 Not Examined. 0.21" 1989 No Reportable Indications. - 14A-S9 (1) 1987 OL not examined due to LBOL. 0.21" 1989 No reportable indications after standard OL application. 148-F2'(1) 1987 OL not examined due to LBOL. 0.27" 1989 No reportable indications after standard OL application. 14B-S8 (1) 1987 OL not examined due to LBOL. 0.21" 1989 No reportable indications after standard OL application. RHR LPCI - 16" 10BD-S13 1987 MSIP Treated. 0.27" 1989 No reportable indications after l standard OL application. NOTE (1) Leak Barrier OL built up to Standard OL in 1989. 6645B/15-24 HD/ LUC

1 + NUTECH l CONTROLLED i XCE-42-250 i COPY NO. 6 Revision 0 December 1989 XCE042.0250 ) l! i EVALUATION AND DISPOSITION OF FIAMS AT . QUAD CITIES NUCLEAR POWER PLANT' UNIT 1 (1989 CUTAGE) 1 -s Prepared for: Commonwealth Edison Company F Prepared by: NUTECH Engineers Reviewed by: Issued by: N; N. G.'Cofie, Ph.D. C. H. Frochlich, P.E. . Project Engineer Project Manager Approved by: Date: C. H. Froehlich, P.E. Engineering Manager nutech

t j, - REVISION CONTROL SHEET i - TITLE: Evaluation and Disposition of DOCUMENT FILE NUMBER: XCE042.0250 L. Flaws at Quad Cities Nuclear Powel Plant Unit l' (1989 Outage) C. H. Froehlich. P.E./ Staff Engineer Nh l N AME / YlTLE INITI A L$ N. G_._.Cofie, Ph.D./ Staff Consultant MD N AME / TITLE

NITI A LS NAME / itTLE INITIALS y

i N AME < TITLE INir: A gg N AME / TITLE INat! A L5 AFFECTED DOC rREPARED ACCURACY CRITERI A REMRK$ PAGE!S) REV BY10 ATE CHECK SY / DATE CHECK SY / DATE i-vi 0 MMM NSc *L/7/ fry

rg sQ7/Q Initial Issue 1.1 -

0 1.9 2 1. - 0 3.2 3.1 - 0 3.7 4.1 - 0 4.4 5.1 - 0 5.9 6.1 - O 6.2 1 7.1 - 0 L 7.3 l-I A.0 - 0 A.34 B.O - 0 i B.33 9 y y l-use 4h/sy ~* c <*/5/es O oug <gj 1 PACE OF 11 CEp J31' nEV 1

l CERTIFICATION BY REGISTERED PROFESSIONAL ENGINEER I l I hereby certify that this document and the calculations contained herein were prepared by 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 herein. I am a duly Registered Professional Engineer under the laws of the State of California and am competent to review this document. .- ~i5SST~;, Certified by: U !c ($l h C2M62 C. H. Froehlich, P.E. F Registered Professional Engineer $6 Vj/ i l \\4 State of California \\ Registration No. C 027862 j [ \\ @g (ClVilCh / 's Date: l l l l XCE-42-250 111 Revision 0 nutech

i t V l' IABLE OF CONTENTS Etaa LIST-OF TABLES v LIST OF FIGURES vi

1.0 INTRODUCTION

1.1 - 2.0 REPAIR DESCRIPTION 2.1 3.0 EVALUATION CRITERIA 3.1 3.1 Conventional Weld Overlay Repair' 3.1 Evaluation 3.2 Short Weld overlay Repair Evaluation 3.2 3.3 Evaluation of Flaws-in Overlay Repairs 3.3 s 3.4 Evaluation of Sustained Stresses at 3.3 Unflawed Locations 4.0 STRESSES 4.1 4.1 Weld Overlay Repair Design 4.2 4.2 Sustained Stress Evaluation at 4.2 Unflawed Weld Locations 5.0 EVALUATION HETHODS AND RESULTS 5.1 5.1 Conventional Weld Overlay Repairs 5.1 5.2 Short-Weld Overlay Repairs 5.2 5.3 Evaluation of Flaws in Overlay Repairs 5.2 6.0

SUMMARY

AND CONCLUSIONS 6.1

7.0 REFERENCES

7.1 APPENDIX A - Comparison and Description of Flawed A.0 Weldments with As-built Overlay Dimensions APPENDIX B - Weld Overlay Design Drawings D.0 APPENDIX C - Sustained Stresses at Unflawed Weld C.0 Locations XCE-42-250 iv Revision 0 nutech

l i R-- i I LIST OF TABLES i Number Title, EAgg ) j 3.2. Expanded Allowable End-of-Evaluation 3.5 Period Flaw Depth-to-Thickness Ratio for j Circumferential Flaws - Normal Operating 1 Conditions j 3.2-2 Leak Barrier Repair Criteria for 3.6 Axial Flaws 4.1-1 Quad Cities Unit 1 - Applied Stresses 4.4 ] for Weld Overlay Repair Design 5.'l-1 " Standard" Overlay-Repaired Welds - 5.3 Pipe and' Flaw Geometric Details 5.1-2 " Standard" Overlay-Repair Welds - 5.4 Predicted vs. Allowable Flaw Depth Ratios t 5,1-3 Axially Flawed Overlay-Repaired Welds - 5.5 Pipe and Flaw Geometric Details ( 5.1-4 Axially Flawed Overlay-Repaired Welds - 5.6 l Predicted vs. Allowable Remaining l Ligament Thickness 5.2-1 Welds 14A-F11 and 02BS-S5 ASME Section 5.7 III Code Results 1_ 5.3-1 Quad Cities Unit 1 Planar Flaws in 5.9 Overlays - Actual Versus Allowable Flaw Geometries I i XCE-42-250 v Revision 0 nutech L

I F 1 m LIST OF FIGURES 1 i Number Title Pace I 1,. 0 -1 Quad. Cities Unit 1 - Flawed Weld '1. 5 l Locations - Reactor Recirculation System Loop "A" 1 0-2 Quad Cities Unit 11 - Flawed Weld - 1. 6 Locations - Reactor Recirculation System Loop "B" a 1.0-3' Quad Cities Unit 1 - Flawed Weld 1.7 Locations - Residual. Heat Removal (RHR) System Loop "B" 1.0-4 Quad. Cities Unit 1 - Flawed Weld 1.8 3 Locations - Core Spray System Loop "A" j 1.0 Qitad Cities Unit 1 - Flawed Weld 1.9 Locations - Core Spray System Loop "B" l 3.2 Source Equations for Allowable End-of-3.7 Evaluation Period Flaw Depth-to-Thickness l-Ratios for Circumferential Flaws i 5.2-1 Finite Element Model for Welds 14A-F11-5.8 and 02BS-SS-i l l-l' XCE-42-250 vi l Revision 0 nutech m

1 ~ f L

1.0 INTRODUCTION

This report summarizes analyses performed by NUTEC11 to evaluate indications in the Reactor. Recirculation,. Residual Heat Removal (RRR), and Core Spray systems at Commonwealth Edison's Quad Cities Nuclear Power Plant f Unit 1. Ultrasonic (UT) examinations of-welds in these systems since 1984 have identified flaws judged to be intergranular stress corrosion cracking (IGSCC) in the-q vicinity of a total of thirty-one welds. Seventeen flawed welds in the Reactor Recirculation system were identified prior to and/or after Induction Heating Stress Improvement (IHSI) mitigation of this system during the 1984 outage. Fourteen additional flawed I welds were identified during the 1987 outage. Of these fourteen welds, six flawed welds were discovered in the [ Core Spray and one flawed weld was discovered in the'RHR systems not previously mitigated by a stress improvement process. Of the remaining seven welds, five welds in the previously IMSI-mitigated Reactor Recirculation system were discovered to have only axial flaws. The ~ locations of all these welds are shown in Figures 1.0-1 through 1.0-5. No new IGSCC flaws were identified during the 1989 outage. There was also no evidence of cracks propagating into existing overlays. Three indications found in the weld overlay repair on Weld 02G-S4 were initially thought to be IGSCC. They were later found to be slag inclusions associated with manual arc weld repairs performed on this overlay during the previous outage. There was no evidence of any cracks linking the three indications or propagating into the overlay from the pipe base metal. These conclusions were based on metallurgical examina-tions on a boat sample taken from this overlay as presented XCE-42-250 1.1 Revision 0 nutech

i + in Reference 1. The boat sample excavation was filled with ER308L weld metal and this overlay received an additional layer of weld metal. This weld overlay repair currently 1 contains no indications as reported in Appendix A. j Appendix A presents descriptions of the IGSCC flaw indications at Quad Cities Unit 1. Three Reactor Recirculation system welds were overlay-repaired during the 1984 outage and built-up to " standard" overlays during the 1986 outage. Twelve Reactor Recirculation system welds were overlay-repaired during the 1984 outage and built-up to " standard" overlays during the 1987 outage. One Reactor Recirculation system weld was " leak barrier" overlay-repaired in 1984 and had a pipe clamping device on it until the 1989 outage when the pipe clamp was removed and the overlay was built-up to a " standard" overlay. Two Reactor Recirculation system welds were IHSI-mitigated during the 1984 outage and repaired with " standard" overlays during the 1987 outage. Six Reactor Recirculation systems welds were IHSI-mitigated in 1984, overlay-repaired with " leak barriers" in 1987 and built-up to " standard" overlays during the 1989 outege. Six unmitigated Core Spray system welds were overlay-repaired during the 1987 outage with " leak barrier" overlays and built-up to " standard" overlays during the 1989 outage. One RHR system weld was mitigated by the Mechanical Stress Improvement Process (MSIP) during the 1987 outage and repaired with a " standard" overlay during the 1989 outage. By the end of the 1989 outage, all thirty-one flawed welds at Quad Cities Unit 1 have been repaired with " standard" overlays. The overlay repairs have been surface finished to permit volumetric inspection of the overlay and part of the original pipe wall thickness. XCE-42-250 1.2 Revision 0 nutech

~1c i.

41 'Two additional " standard" overlays were' implemented on two unflawedLwelds in the Reactor Recirculation system (Melds 02K-F6 and 02L-S4) to help reduce weld' overlay-induced shrinkage stresses in'this system. The design of previous weld overlay repairs and the analysis of IHSI-mitigated weld flaws discovered during the 1984 outage at-Quad Cities Unit 1 are described in NUTECH Report COM-96-202 (Reference 2). The evaJuation 1 of-thren weld overlay repairs built-up during the 1986 outage and the effectiveness of one previously IHSI-mitigated flawed' weld re-examined during the 1986 outage at Quad Cities Unit 1 is described in NUTECH Report CEC-47-100 (Reference 3). NUTECH Report CWE-15-203 (Reference 4) describes weld overlay repairs and disposition of flaws during the 1987 outage. The purpose of this report is to demonstrate that all the overlay repairs at Quad Cities Unit 1 at the end of the 1989 outage meet the requirements of a " standard" overlay design as defined in NUREG-0313, Revision 2 (Reference 5). Section 2.0 presents a general descrip-tion of the overlay repairs and build-ups performed at Quad Cities Unit 1. Sections 3.0 and 4.0 present the evaluation criteria and stresses used in the analysis of overlay repairs. Section 5.0 presents the evaluation methods and results. Sections 6.0 and 7.0 present a summary of conclusions and the references used in the evaluation. Appendix A presents a comparison and description of the flawed weldments for the 1984 through 1989 outages. This appendix also presents the current as-built dimensions for all the Quad Cities Unit 1 weld overlay repairs. Appendix B presents the weld overlay XCE-42-250 1.3 Revision 0 nutech

y a"r i ,o t k' design drawings for all the overlayed welds. Appendix C . presents the magnitudes of sustained stresses for.all l unflawed, but IGSCC-susceptible, weldments in the Reactor Recirculation, Shutdown _ Cooling, RER, Core Spray, RWCU, and CRD Return Line' systems at Quad Cities ) Unit 1. o l XCE-42-250 1.4 Revision 0 nutech

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UNFLAWED WELDS WriH LOAD BALANCING OVERLAYS.

Figure 1.0-1 QUAD CITIES UMIT 1 FLAWED WELD LOCATIOt!S PIACTOR PECIRCULATION SYSTEti LOOP "A" (Reference 6) XCE-42-250 J.5 Revision 0 nutech

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I r

r 14A $$ = l' 4 1' l f 14A.F) a I NbA l. NQZZLt i 'l )

l 1

14 A 50 REACTOR SVILDING 14 A.F i t 081YWE L4 g i l' l-l i l Figure 1.0-4 l 0U73 CITIES UNIT 1 FLAWED WELD LOCATIONS CORE SPRAY. SYSTEM LOOP "A" (Reference 8) l' l:. XCE-42-250 1.8 i Revision 0 nutech +

i '] I r N 1 1 l u Nse Noz2Lt l ':, R i 146 se ,/ 14912 ,l l l i i + DRYWELL REACTOR. sutLDING w Figure 1.0-5 OUAD CITIES U11IT 1 9 FLAWED WELD LOCATIO11S CORE SPRAY SYSTEM LOOP "B" (Reference 8) XCE-42-250 1,9 Revision 0 nutech

2.0 REPAIR QESCRIPTION L By the end of the 1989 outage, all weld overlays at Quad Cities Unit 1 are " standard" overlays. There are two categories of these overlays. The first category con-sists of those overlays that were first implemented as limited service overlays or leak barriers and then built-up to " standard" overlays at a subsequent outage. The second category consists of those overlays that were designed and built as " standard" overlays during a single outage. For both of these categories, repairs have been made by increasing the pipe wall thickness through the deposi-tion of weld metal 360 degrees around and to either side of the existing weld. The weld-deposited band provides additional wall thickness to restore the original Code safety margin. In addition, the welding process pro-duces a strong compressive residual stress pattern on the inside portion of the pipe wall (as discussed in the Reference 9 paper), which prevents further crack growth. The deposited weld metal is either Type 308L or Type 309L with controlled delta ferrite content so as to be i resistant to the propagation of IGSCC. Design drawings for all the overlays are presented in Appendix B while the current as-built information for all overlays are presented in Appendix A. I The application of a weld overlay causes a small amount of axial shrinkage underneath the overlay. These shrinkages cause additional stresses on the piping system and must be evaluated. The recorded shrinkages at the overlay locations are shown in Appendix A. XCE-42-250 2.1 Revision 0 nutech

i The nondestructive examination (NDE) of each weld overlay repair applied at Quad Cities Unit 1 consisted of the following: 1. Surface examination of the existing pipe surface at new weld overlay repair locations by the liquid-penetrant testing (PT) technique in accordance with ASME Section XI. 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 weld overlay layer for evidence of IGSCC flaws for new and built-up overlays (discoloration, porosity, etc.). 4. Surface examination of the completed weld overlay by the PT technique in accc:rdance with ASME Section XI. 5. Volumetric examination of the completed weld over-lay repair and part of the original pipe wall by i the ultrasonic testing (UT) technique developed by EPRI. All UT examinations were performed by EPRI-qualified examiners. XCE-42-250 2.2 Revision 0 nutech

3.0 EVALUATION CRITERIA 3.1 Conventional Wald Overlay Reemir Evaluation All weld overlays at Quad Cities Unit 1 were designed to meet the requirements of " standard" overlay repairs as defined in NUREG-0313, Revision 2 (Reference 5). The following criteria were used by NUTECH to design / - evaluate all of the weld overlay repairs presented in Appendix At 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 degree 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 pipe wall thickness or its measured length. If an axial flaw was drawn up into the overlay due to a steam blow-out, the actual flaw depth 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 circum-forential 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 analysis performed by XCE-42-250 3.1 Revision 0 nutech

Li 1 1 NUTECM in References 2, 3, and 4 using a conserva-tive crack growth correlation derived from data presented in Reference 10. l 5. For circumferential flaws, the weld overlay repair j strength for a combination of dead weight, internal pressure, and seismic stresses was compared to the not section plastic collapse criteria of ASME Section XI, Table IWB-3541-1 (Reference 11). ] Because this table has an arbitrary cut-off point at a stress ratio of 0.6, NUTECH has developed an expanded version (Table 3.2-1) based upon the Table IWB-3641-1 source equations shown in Figure 3.2-1. 6. For axial flaws, the weld overlay repair was compared to " leak barrier" weld overlay repair criteria presented in Table 3.2-2 from HUTECH Document COM-76-001 (Reference 12). 3.2 Short Wald Overlav Roomir Evaluation All of the weld overlay repairs presented in Appendices A and B have a conter of original butt weld-to-overlay shoulder length approximately equal to the square root of the original pipe wall thickness times mean radius except for Welds 02B-S7, 02BS-SS ad 14A-F11 (this simple rule-of-thumb for acceptable weld overlay repair length has been demonstrated both analytically and exper-imentally by NUTECH and others). Various interferences would not permit the automated welding machine applica-tion of a full length overlay to these welds. End effects created by this shortened overlay affect an assumed through-wall-by-360' flaw on the flawed side of these welds. Therefore, in addition to the weld overlay repair thickness evaluation criteria discussed in XCE-42-250 3.2 Revision 0 nutech

Section 3.1, the stress intensity results of axisym-metric linear elastic finite element analyses for assumed through-wall-by-360* flaw on the flawed side of these welds were compared to ASME Section III (Reference 13), Subsection NB allowable stress intensity criteria. The evaluation for Weld 025-S7 has been previously presented in Reference 4 and so only the evaluations for Weld 14A-Fil and 02BS-S5 are presented in this report. 3.3 Evaluation of Flaws in Overlav Recaira As shown in Appendix A, spot indications were identified in some of the overlays during UT examinations during the 1989 outage. These spot indications are evaluated against the requirements of ASME Code, Section XI, IWB-3514.3 to show that thSy are acceptable. Since all overlays have been designed and repaired as " standard" overlays, the original pipe wall thickness was not taken into consideration in this evaluation. 3.4 Evaluation of Sustained Stresses at Unflawed Locations As part of the IGSCC mitigation program by CECO, various susceptible piping welds at Quad Cities Unit I have received Induction Heating Stress Improvement (IMSI) or Mechanical Stress Improvement Process (MSIP). Other susceptible welds are also being considered for future stress improvement (SI) mitigation. Because the effectiveness of SI treatment is related to the applied stress acting on a weldment, it is recommended in NUREG-0313, Revision 2, Section 4.5 that the service or sustained stress (unintensified internal pressure plus dead weight plus thermal expansion plus weld overlay XCE-42-250 3.3 Revision 0 nutech

shrinkage stresses) for weldments receiving SI treatment should not be greater than 1.0 S SI treatment is also m. not recommended for circumferential cracks deeper than 30% of pipe wall.:or longer than 10% of the circum-forence, or axial cracks of any extent. The sustained stresses for welds in various susceptible systems are evaluated against this NUREG-0313 requirement. 1 l XCE-42-250 3.4 Revision 0 nutech 1

'o X $Q Table 3.2-1 P-t U. $ EXPAt3DED ALLOWABLE END-OF-EVALUATIOff PERIOD o e Dy FLAW DEPTH-TO-THICKNESS RATIO FOR CIRCUMFERENTIAL FLAWS NORMAL OPERATING CONDITIONS P,, Pb Ratio of Flaw Length, ig, to Pipe Circumference l Note (3)) Sm 0.5 (Note (2)] 0.0 0.1 0.2 0.3 0.4 or More 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 I.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 vi 1.0 0.75 0.75 0.75 0.63 0.51 0.41 0.9 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 0.5 (5) 0.75 0.75 0.75 0.75 0.75 0.68 0.4 (5) 0.75 0.75 0.75 0.75 0.75 0.73 0.36 (5) 0.75 0.75 0.75 0.75 0.75 0.75 NOTES: (1) Flaw depth = a for a surface flaw n 2a for a subsurface flaw t = nominal thiEkness Linear interpolation is permissable. (2) P,= primary membrane stress Pb

Primary bending stress S

= allowable design stress intensity (in accordance with Sect ion III) E (3) Circumference based on nominal pipe diameter. C (4) Iwn-3514.3 shall be used. (5) Derived using source equations. (93 O7

Table 3.2-2 M AK BARRIER REPAIR CRITERIA FOR AXIAL FLAWJ (Reference 12) NONDIMENSIONA P W LENGTH STRESS %/ RAT 10 0.00 0.36 0.90 1.00 2.00 s a 0.40 0.00 r 0.00 = 0.70 o. 0.80 r 0.90 = 0.98 r 1.00 s

LEAK BARRIER ONLY REQUIRED STRESS RATIO = PO /2 T Sm P = MAXIMUM PRESBURE FOR NORMAL OPERATING CONDITIONS O = NOMINAL OUTSIDE DIAMETER OF THE PtPE T = NOMINAL THICKNESS g = ENO4F. EVALUATION PERICO FLAW LENGTH R = NOMINAL RAOluS OF THE PIPE XCE 42-250 3.6 Revision 0 nutech

g +. s a s-- +,-.. 2

Y l

I i For

8( 180' I

a e-a 8 e (radians) 2 1 0.5-h(2 sin 8-{ sins) 2.773'(sR) = 0 8 for a + 8 2 180 f 8) e ( 6e (radians) 2-{ l i 2.713 (SR) -0.S-{(2-{lsin6o 0 i Whore I ee half-crack length (radiano) 6e neutral amis location ang16 (radians) ae flaw depth (inches) pipe thickness (inches) t a SR

strose ratto e Pm + Pb Pm o primary membran. Mree.

Pb o primary bending stress Se e allowable stress intensity (per Asnt section !!! Appendices) b s s l e A a e NA Neutral Ante a - mean a.ato. l Figure 3.2-1 1 SOURCE EOUATIONS FOR ALLOWABLE END-OF-EVALUATION PERIOD FLAW DEPTH-TO-THICKNESS RATIOS FOR CIRCUfEERENTI AL FLAWS XCE-42-250 3.7 Revision 0 nutech c r--, w-v ow w

l l 4.0 STRESSES various stress combinations are used in evaluating weld overlay repairs at flawed weld locations and sustained stresses at unflawed weld locations as explained in Section 3.0. The purpose of this section is to present the stresses acting on the weld locations discussed in this report. Primary stresses include the effects of dead weight, internal pressure, and seismic loads. The design pressure of 1,250 psi was obtained from the original piping design specification (Reference 14). The dead weight and asismic stresses applied to each weld were obtained from References 15 through 18. The primary stresses associated with these various loads are shown in Table 4.1-1. Secondary stresses include the following: 1. Thermal Stresses The piping system differential thermal expansion stresses for each weld were obtained from References 15 through 18 and vied in the sustained stress evaluation of unflawed welds in various IGSCC-susceptible systems. 2. Weld Overlay Shrinkage-Induced Stresses Each weld overlay causes a small amount of axial shrinkage underneath the overlay. This shrinkage induces bending stresses in the remainder of the p piping system. These shrinkage-induced stresses are calculated using NUTECH computer program PISTAR XCE-42-250 4.1 Revision 0 nutech

l l i (Reference 19). The actual as-built shrinkages as i presented in Appendix A are used in the analysis. The resulting shrinkage stresses are included in l the evaluation of sustained stresses at unflawed l weld locations. 4.1 Wald Overlav Recair Desien f For the design of weld overlays, a combination of dead weight, internal pressure and seismic stresses for each weld location is used. These stresses are shown in Table 4.1-1 for the overlays at Quad Cities Unit 1. 4.2 Sustained Stress Evaluation at Unflawed Weld Locationg l As discussed in Section 3.4, sustained stresses at unflawed weld locations musc be evaluated to conform to NUREG-0313 requirements in order to take credit for stress improvement. This evaluation is limited to the following susceptible systems listed in CECO's response to Generic Letter i 88-01 for Quad Cities Unit 1: A) Reactor Recirculation System B) Shutdown Cooling C) RER Lines D) Core Spray E) Reactor Water Clean-up F) CRD Return System G) Jet Pump Instrumentation H) Head Vent I) Spare Nozzles XCE-42-250 4.2 Revision 0 nutech

l t l t The sustained stress level at a weld location consists of unintensified internal pressure, dead weight, thermal expansion and weld overlay-induced shrinkage stresses. In performing this evaluation, the possibility was explored whether for systems without weld overlay repairs, the sustained stress limits specified in NUREG-0313 are bounded by the code allowables used'in the design of these systems. It was realized that for l plants designed under USAS B31.3, a general statement to l this effect cannot be made because the design allowables are not related to S Furthermore, stress intensifica-m. tion 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 f spare nozzles are affected only by internal pressure stress which is less than 1.0 S The sustained m. stresses for the welds in the remaining systems are presented in Appendix C. There are no welds with sustained stresses greater than 1.0 S m. XCE-42-250 4.3 Revision 0 nutech

r

c Table 4.1-1

+ OUAD CITIES UNIT 1 APPLIED STRESSES FOR WELD OVERLAY REPAIR DESIGN (12 i I TOTAL PRESSL*RI DEADWi!Grf Obt APPLIED WELD FIPt $fRESS STRESS STRESS STRESS 90. Slit (PSI) (PSI) (PSI) (PSI) 02C-S3 12.750 4129 365 343 4838 02C 54 12.750 3596 206 221 4024 02D-53 12.750 3876 203 75 4155 02D S4 12.750 3717 89 46 3452 02t S3 12.750 3899 162 122 4183 021 S4 12.750 3865 96 94 4055 02T S3 12.750 4074 359 227 4660 02T $4 12.750 4D49 192 176 4417 020-53 12.750 3334 141 190 3665 02G 54 12.750 3438 58 115 3611 02FS3 12.750 3748 51 214 4012 02FS4 12.750 3918 50 161 4129 02J 53 12.750 3853 93 224 4170 02J S4 12.750 3891 66 122 4079 02J T6 12.750 4721 282 374 5377 02K 53 12.750 3791 123 185 4099 02K 54 12.750 3945 41 147 4132 02K f6 12.750 4012 234 315 4561 021 S4 12.750 3523 137 168 3828 02M-S3 12.750 4137 705 300 $142 02M 54 12.750 4321 362 230 4914 02B-T1 22.000 4157 213 242 4612 02B S7 22.000 4213 256 311 4779 02B-$10 22.000 4461 0 1 4463 02BS-S$ 28.000 4766 437 731 5934 02BS S9 28.000 4480 37 87 460) 14A T2 10.750 3875 336 1572 5782 14A 58 10.750 3460 89 461 4009 14A 59 10.750 3353 76 113 3542 14A F11 10.750 3417 184 152 3753 14B-T2 10.750 3446 2185 853 6484 14B-58 10.750 3559 893 463 4914 10B>$13 16.000 3623 57 2000(2) 5680 NOTES:

1. Based on as built veld overlay repair thiebess plus original pipe vall thlebess.

2.Assumedvalue, XCE-42-250 4.4 Revision 0 nutech

) I l i 5.0 EVALU4T.LQ}L}gIRODS AND RESULTS ) This section presents the evaluation methods and results used to assess the acceptability of the overlay-repaired flaw indications at Quad Cities Unit 1. 5.1 conventienal Weld Overlav Reemirs Table 5.1-1 presents the pipe and flaw geometry details needed to calculate the applied and allowable stress ratios for all the circumferential1y flawed overlay-repaired welds at Quad Cities Unit 1. Applied stresses are found in Table 4.1-1. Table 5.1-2 presents a com-parison of predicted flaw depth ratios due to applied loads versus the allowable flaw depth ratios for the circumferential flaws detailed in Table 5.1-1. As discussed in Section 3.1, the allowable flaw depth ratios shown were calculated using the source equations of ASME Section XI Table IWB-3641-1 with an arbitrary maximum allowable flaw depth ratio of 0.75. As a result, all of the weld overlay repairs shown in Table 5.1-2 meet NUREG-0313, Revision 2 " standard" overlay requirements. Table 5.1-3 presents the pipe and flaw geometric details needed to determine predicted and allowable remaining ligament thicknesses for all the overlay-repaired welds at i Quad Cities Unit 1. Table 5.1-4 presents a comparison of predicted remaining ligament thicknesses for the weld-ments given in Table 5.1-3 with allowable remaining l ligament thicknesses determined using the leakage I barrier criteria presented in Table 3.2-2. l XCE-42-250 5.1 l Revision 0 nutech

5.2 Short Wald Overlav Reemirs rigure 5.2-1 presents a typical axisymmetric linear elastic finite element model used to evaluate the acceptability of the overlay repair length for Welds 14A-F11 and 02BS-SS at Quad Cities Unit 1. This model contains a 100% through original pipe wall crack depth with a 360 degree length. The ANSYS computer program (Reference 20) was used to perform this analysis for both primary and secondary loads. A comparison of the maximum applied stress intensities acting through the weld overlay repair over the assumed crack with ASME Section III (Reference 13), Subsection NB allowable stress intensities is presented in Table 5.2-1. 5.3 Evaluation of Flaws in Overlav Reemirs Table 5.3-1 presents the evaluation of the spot indica-tions found in some of the we:d overlay at Quad Cities Unit 1. These indications were compared to the allow-able flaw eizes contained in Table IWB-3514-2 of ASME Code, Section XI and all were found to be acceptable. This evaluation did not consider the existence of the original pipe wall since a 360* by through-the-original pipe wall flaw was assumed in the design of these " standard" overlays. Hence, only the overlay thickness was used in this evaluation. XCE-42-250 5.2 Revirion 0 nutech

k Table 5.1-1 b " STANDARD" OVERLAY-REPAIRED WELDS PIPE AND FLAW GEOMETRIC DETAILS WORIbA!. WELD 0.D. (1) tp(2) to(3) tf(4) t(5) a(6) L (7) NO. (IN.) (IN.) (IN.) (IN.) (IN.) (IN.) (DECRIES) 02C-53 12.750 0.648 0.317 0.000 0.965 0.653 360 02C S4 12.750 0.684 0.424 0.072 1.108 0.761 360 02D 53 12.750 0.670 0.358 0.000 1.028 0.675 360 02D S4 12.750 0.710 0.362 0.000 1.072 0.715 360 02t53 12.750 0.679 0.343 0.000 1.022 0.684 360 02E $4 12.750 0.673 0.358 0.000 1.031 0.678 360 02T 53 12.750 0.672 0.306 0.000 0.978 0.677 360 021 54 12.750 0.690 0.294 0.000 0.984 0.695 360 020 $3 12.750 0.687 0.508 0.135 1.195 0.827 360 OSG-S4 12.750 0.679 0.480 0.000 1.159 0.684 360 028 53 12.750 0.703 0.360 0.000 1.063 0.708 360 028 $4 12.750 0.687 0.330 0.000 1.017 0.692 360 02J S3 12.750 0.698 0.336 0.000 1.034 0.703 360 02J 54 12.750 0.675 0.349 0.000 1.024 0.680 360 02J T6 12.750 0.584 0.260 0.000 0.844 0.589 360 02K 53 12.750 0.666 0.385 0.000 1.051 0.671 360 02K-S4 12.750 0.665 0.345 0.000 1.010 0.670 360 02K?6 12.750 0.610 0.383 0.000 0.993 0.615 360 02L-S4 12.750 0.684 0.447 0.000 1.131 0.689 360 02M 53 12.750 0.678 0.285 0.000 0.963 0.683 360 02M S4 12.750 0.601 0.321 0.000 0.922 0.606 360 02B-F1 22.000 1.095 0.559 0.000 1.654 1.100 360 02B-S7 22.000 1.073 0.559 0.102 1.632 1.180 360 02B-S10 22.000 1.070 0.471 0.000 1.541 1.075 360 02BS-S$ 28.000 1.244 0.592 0.000 1.836 1.249 360 02BS S9 28.000 1.422 0.531 0.000 1.953 1.427 360 14A f2 10.750 0.590 0.277 0.000 0.867 0.595 360 14A-58 10.750 0.632 0.339 0.000 0.971 0.637 360 14A 59 10.750 0.600 0.402 0.000 1.002 0.605 360 14A-F11 10.750 0.631 0.352 0.000 0.983 0.636 360 14B F2 10.750 0.570 0.405 0.000 0.975 0.575 360 14B 58 10.750 0.603 0.341 0.000 0.944 0.608 360 10BD-S13 16.000 0.999 0.381 0.000 1.380 1.004 360 NOTES:

1. 0.D.

outside disseter. 2.tp =pipewallthickness.

3. to = veld overlay repair thickness.

4. tf

=lowdeltaferritefirstlayerthickness(ifapplicable).

5. t

tp + to.

6. a

= evaluation flav depth

tp
tf + 0.005' bounding fatigue crack growth.

7. L

= evaluation flaw length. XCE-42-250 5.3 Revision 0 nutech

r Tablo 5.1-2 ) " STANDARD" OVERLAY-REPAIRED WELBS PREDICTED VS. ALLOWABLE FIAW DEPTH RATIOS WELD IIS-3641 1 PREDICTED NO. FLR(1) S.R.(2) TDR(3) FDR(4) l 02C 53 1.0 0.285 0.75 0.677 02C 54 1.0 0.237 0.*5 0.687 02D 33 1.0 0.245 0.75 0.657 i.. 02D 54 1.0 0.227 0.75 'O.667 02t $3 1.0 0.247 0.75 0.669 02t$4 1.0 0.239 0.75 0.658 02T 53 1.0 0.275 0.75 0.692 021 54 1.0 0.261 0.75 0.706 I 02G 53 1.0 0.216 0.75 0.692 OS0-$4 1.0 0.213 0.75 0.590 028 $3 1.0 0.237 0.75 0.666 028 54 1.0 0.244 ' 75 0.680 02J $3 1.0 0.246 0.75 0.660 02J S4 1.0 0.241 0.75 0.664 02J-T6 1.0 0.317 0.75 0.698 02K S3 1.0 0.242 0.75 0.638 02K S4 1.0 0.244 0.75 0.663 02KT6 1.0 0.269 0.75 0.619 02L-S4 1.0 0.226 0.75 0.609 02N-53 1.0 0.303 0.75 0.709 02N S4 1.0 0.290 0.75 0.657 02BF1 1.0 0.272 0.75 0.665 02B S7 1.0 0.282 0.75 0.723 02B-510 1.0 0.263 0.75 0.698 02BS 55 1.0 0.350 0.75 0.680 02BS-59 1.0 0.272 0.75 0.731 14A T2 1.0 0.341 0.75 0.686 14A S8 1.0 0.237 0.75 0.656 14A S9 1.0 0.209 0.75 0.604 141 T11 1.0 0.221 0.75 0.647 148-F2 1.0 0.383 0.74 0.590 14B-S8 1.0 0.290 0.75 0.644 10BD S13 1.0 0.335 0.75 0.728 NOTES:

1. FLR = flay length ratio = 1,0 for 360 degree assumed flawlength, l

2. S.R. = dead velgbt + internal pressure + seismic i

stressesfromfable4.1-1dividedby allowablestressintensity,Ss.

3. FDR = allovable flav depth ratio (a/t) from fable 3.2 1.

4.PredictedTDR=boundingevaluationflavdepth,a, from fable 5.1 1 divided by pipe + overlaythickness,t,fromfable 5.1 1. Thesatisusofupstreasand dovnstressisused. l l XCE-42-250 Revision 0 nutech

e ?- t i r i Table 5.1-3 t AXTAflY FT1WED OVERLAY-REPAIRED WELDS 1 PIPE AND FLAW GEOMitTRIC DETAILS H0KINAL liELD 0.D.(1) tp (2) to (3) L (4) tr'(5) NO. (IN.) (IN.) (IN.) (IN.) (IN.) 020-$3 12.750 0.648 0.317 0.972 0.317 02C 54 12.750 0.684 0.424 1.026 0.360 02D53 12.750 0.670 0.358 1.005 0.358 02D-S4 12.750 0.710 0.362 1.065 0.362 02!-S3 12.750 0.679 0.343 1.019 0.343 02I S4 12.750 0.673 0.358 1.010 0.300 02T S3 12.750 0.672 0.306 1.008 0.306 02T 54 12.750 0.690 0.294 1.035 0.294 02G $3 12.750 0.687 0.504 1.031 0.350 OSG 54 12.750 0.679 0.480 1.019 0.480 028 53 12.750 0.703 0.360 1.055 0.360 028 S4 12.750 0.687 0.330 1.031 0.330 02J $3 12.750 0.696 0.336 1.047 0.336 02J S4 12.750 0.675 0.349 1.013 0.330 s 02J P6 12.750 0.584 0.260 0.876 0.250 02K S3 12.750 0.666 0.385 0.999 0.385 02K $4 12.750 0.665 0.345 0.998 0.345 02K f6 12.750 0.610 0.383 0.915 0.383 02L-54 12.750 0.684 0.447 1.026 0.447 02N S3 12.750 0.678 0.285 1.017 0.285 02N S4 12.750 0.601 0.321 0.902 0.321 02B-F1 22.000 1.095 0.559 1.643 0.559 02B 57 22.000 1.073 0.559 1.610 0.559 02B-S10 22.000 1.070 0.471 1.605 0.320 02BS-55 28.000 1.231 0.592 1.847 0.592 02BS-S9 28.000 1.422 0.531 2.133 0.531 14A-F2 10.750 0.599 0.277 0.499 0.277 14A-$8 10.750 0.632 0.339 0.948 0.339 14A S9 10.750 0.600 0.402 0.900 0.444 14A fl1 10.750 0.631 0.352 0.947 0.352 14B-f2 10.750 0.570 0.405 0.855 0.405 14B-$8 10.750 0.603 0.341 0.905 0.341 10BDS13 16.000 0.999 0.381 1.499 0.381 NOTES: 1.0.D.=outsidediameter. 2.tp = pipe vall thlebess.

3. to = veld overlay repair thichess.

4. L

= flaw evaluation length a greater of seasured axial flav length or 1.5'tp.

5. tr' = lesser of remaining ligasent or U thichess (to).

XCE-42-250 5.5 Revision 0 nutech

i. l Table 5.1-4 AXIALLY FLAWED OVERLAY-REPAIRED WELDS PREDICTED VS. M10tahmLE REMAINING LIchMENT THICKNESSES APPLID AllhliABLE STANDARD PREDICT 2 WEIb STRESS STRESS to(3) tt (4) [ NO. 91f10(1) PATIO (2) (IN.) (IN.) 02C S3 0.726 0.900 0.125' O.312 02C S4 0.687 0.900 0.125 0.355 02D-33 0.702 0.900 0.125 0.353 02>S4 0.662 0.900 0.125 0.357 02I 53 0.692 0.900 0.125 0.338 02t54 0.699 0.900 0.125 0.295 02T33 0.700 0.900 0.125 0.301 02T 54 0.681 0.900 0.125 0.289 02C 5) 0.684 0.900 0.125 0.345 OSG S4 0.692 0.900 0.125 0.475 028 53 0.669 0.900 0.125 0.355 028 S4 0.684 0.900 0.125 0.325 02J 53 0.674 0.900 0.125 0.331 02J S4 0.696 0.900 0.125 0.325 02J T6 0.805 0.900 0.125 0.245 02K33 0.706 0.900 0.125 0.380 I 02K S4 0.707 0.900 0.125 0.340 02K T6 0.771 0.900 0.125 0.378 02L 54 0.68? 0.900 0.125 0.442 02N $3 0.693 0.900 0.125 0.280 02N 54 0.782 0.900 0.125 0.316 02B-F1 0.741 0.900 0.125 0.554 02B-S7 0.756 0.900 0.125 0.554 02B-$10 0.758 0.900 0.125 0.315 02BS 55 0.830 0.900 0.125 0.587 OBS-59 0.726 0.900 0.125 0.526 141T2 0.652 0.900 0.125 0.272 14AS8 0.627 0.900 0.125 0.334 14A $9 0.654 0.900 0.125 0.09 14A T11 0.628 0.900 0.125 0.347 14B-T2 0.6% 0.900 0.125 0.400 14B58 0.657 0.900 0.125 0.336 10BD S13 0.591 0.800 0.125 0.376 M IS: 1.Appliedstressratioiscalculatedforinternalpressure of1250psiusinggeometricpropertiesfrostable5.13 andformulapresentedinTable3.2-2 footnotes. 2.AllovablestressratioperTable3.2-2. 3.Standardleakbarrieroverlayrepaireinisusthickness.

4. Predicted tr tr' fros fable 5.1-3 sinus 0.005" bounding fatigue crack growth.

XCE-42-250 5.6 ' Revision 0 nutech

I i l Table 5.2-1 i WELDS 1&A-F11 AND 02BS-S5 ASME SECTION III CODE RESULTS i i STRESS INTENSITY (ksi) ALLOWABLE STRESS STRESS CATEGORY WELD WELD INTENSITY (See Notes) 14A-F11 02BS-S? (kei) Pm 7.93 13.23 19.95 Pm+Pb 13.83 23.94 25.43 PL+Pb+Pe+Q 28,13 34.63 50.85 NOTES:

1. Pm = general membrane stress intensity.

2. PL = local membrane stress intensity.

3. Pb = primary bending stress intensity.

4. Pe = thermal expansion. stress intensity.

5. Q = discontinuity stress. i XCE-42-250 5.7 I Revision 0 nutech

i i i I 1 I 1 i I j i / // 7 / / = = ~ =- ...c/ _= rN t l 1. I Figure 5.2-1 FINITE ET.'14ENT MODEL FOR WELDS 14A-F11 and 02BS-S5 l XCE-42-250 5.8 Revision 0 nutech

I i J Table 5.3-1 l OUAD CITIES UNIT i PtkNAR FLAWS IN OVERLAYS ACTUAL VERSUS 17.t0WABLE FtAW GEOMETRIES I 1 ASSUMED ALLOWABLE WELD to (1) L (2) a (3) a (4) NO. (IN.) (IN.) (IN.) (IN.) 02C-S3 0.317 0.10 0.03 0.064 02D-S3 0.358 0.20 0.03 0.072 ~ NOTES:

1. to = weld overlay thickness.

2. L = flaw length.

3. Actual flaw depth is defined as a " spot".

4. From ASME Section XI (Ref. 11), Table IWB-3534-2. i i l' i l l I XCE-42-250 5.9 Revision 0 nutech

~- 6.0 sine 4ARY AND CONCLUSIONS Ultrasonic (UT) examinations performed during the 1984 outage at Commonwealth Edison's Quad Cities Nuclear Power Plant Unit 1 identified flaws judged to be IGSCC in the vicinity of seventeen welds. Fifteen welds were overlay repaired, one weld was shown to be acceptable with only INSI mitigation, and one weld was both overlay repaired and covered by a pipe clamping device. During the Quad Cities Unit 1 1986 outage, three of the original fifteen overlay-repaired welds were built-up to " standard" design thicknesses and volumetrically inspected by the UT technique developed by EPRI. The previously INSI-mitigated weld was also inspected and found to be acceptable for continued operation. None of the other overlay-repaired welds were inspected. During UT examinations performed during the Quad Cities Unit 1 1987 outage, fourteen new welds were identified as possibly containing IGSCC. Seven of these welds were in systems not stress-improved prior to the 1987 outage. Of the remaining seven welds which were IHSI-mitigated during the 1984 outage, five welds contained only axigl flaws which have proven difficult to detect in the past. The last two welds contain relatively minor circumferential indications, which were first detected during the 1984 outage, but were evaluated as a i geometric discontinuities at the interface of the i original shop butt weld and an inside diameter root y repair. During the 1989 outage, no new IGSCC flaws were identi-fled. All existing overlays not meeting " standard" XCE-42-250 6.1 Revision 0 i1titen(:l1

t overlay requirements were built-up and one unrepaired flaw was repaired to meet " standard" overlay require-monts. Evaluations presented in this report for the thirty-one Quad Cities Unit I welds believed to contain IGSCC l demonstrate that the applied stress levels are accept-able for all design conditions. The analyses performed in the evaluation demonstrate that all the welds having " standard" weld overlay repairs are acceptable for the omlance-of plant life per the requirements of HUREG-0313 (Reference 5). s ( ? \\ I l l l i XCE-42-250 6.2 I Revision 0 nutech

? 4

7.0 REFERENCES

1. CECO Document M-5328-89, " System Materials Analysis Department Report on Metallurgical Evaluation of the 02G-S4 Riser Weld Sample from Quad Cities Station", dated November 28, 1989. 2. NUTECH Document COM-96-202, " Evaluation and Disposition of IGSCC Flaws at Quad Cities Nuclear-Power Station Unit 1", Revision O. 3. NUTECH Document CEC-47-100, "3 valuation and I Disposition of Indications at Quad Cities Nuclear Power Plant Unit 1", Revision O. [ 4. NUTECH Document CNE-15-203, " Evaluation and Disposition of Flaws at Quad Cities Nucletr Power Plant Unit 1 (1987 Outage) ", Revision 1. T 5. NRC Document NUREG-0313, " Technical Report on Material Selection and Processing Guidelinae for BWR Coolant Pressure Boundary Piping", Revision 2. L 6. Sargent & Lundy Drawing No. ISI-103, " Inservice l l Inspection Class 1 - Nuclear Boiler & Reactor l Recirculation Piping - Quad Cities Station Unit 1", Revision A. 7s Sargent & Lundy Drawing No. ISI-105, " Inservice Inspection Class 1 - RERS Piping - Quad Cities Station Unit 1", Revision A. 8. Sargent & Lundy Drawing No. ISI-104, " Inservice Inspection Class 1 - Core Spray Piping - Quad Cities Station Unit 1", Revision D. XCE-42-250 7.1 Revision 0 nutech

r 4 9.

Kulat, S.D.,

Pitcairn, D.R.,

and Sobon, L.J., " Experimental Verification of Analytically Deter-mined 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. 10. EPRI Document NP-2423-LD, "Strssa Corrosion Cracking of Type-304 Stainless Steel in High-Purity Water: A Compilation of Crack Growth Rates", June 1982. 11. ASME Boiler and Pressure Vessel Code (BPVC) Section XI, 1986 Edition with Addenda through 1989, 12. NUTECH Document COM-76-001, " Weld overlay Design Criteria for Axial Cracks", F.ovision 0, March 1984. 13. ASME Boiler and Pressure Vessel Code, Section III, 1986 Edition with Addends through 1989. 14. Sargent & Lundy Document R-2330, " Specification for Piping System - Quad Cities Units 1 and 2", with all supplements through Supplement 25. 15. EDS Nuclear Report No. 04-0591-0047, "IGSCC Evaluation for the Piping System of Quad Cities Nuclear Station Unit 1", Revision 0, August 1902. 16. IMPELL Letter No. 0590-003-2822 with Attachments, W.F. Tschudi to A.K. Rao (NUTECH), " Data for IGSCC Evaluation, Quad Cities Unit 1", April 19, 1984. XCE-42-250 7.2 Revision 0 nutech

l 1 i i 17 IMPELL Letter No. 0591-211-001 with Attachments, L.J. Barrett to C.H. Froehlich (NUTECH), " Quad j Cities Station Unit 1, Piping System Stresses," June 15, 1989, i 18. IMPELL Letter No. 0591-211-003 with Attachments, L.J. Barrett to C.H. Frochlich (NUTECH), " Quad Cities Station Unit 1, Piping System Stresses," { June 22, 1989, 19. HUTECH Computer Program PISTAR, Version 3.5.2 User's Manual, Volume 1, TR-76-002, Revision 12, NUTECH Corporate File No. QASJO. SOFT.2.036.3.5.0.2. 20. Computer Program ANSYS, Swanson Analysis Systems, Version 4.3, NUTECH Corporate File QASJO. SOFT.1.105. XCE-42-250 7.3 Revision 0 r1Litet(:t1

i i 1 2 i i ) i i i f i 1 Appendix A j COMPARISON AND DESCRIPTION OF FT WEB WELBMENTS WITH AS-BUILT OVEPT1Y DIMENSIONS } I F r k I .t XCE-42-250 A,o Revision 0 nutech

.. _, ~ ji, ' \\.. l. H D Z A t i, ' 45' MIN. % TYP. /-. p / N u$/////////////N/////////////////// "~'* m o ip-Q WELD Type 1 k D Z A 45' MIN. i._ r / to - w tp-l l l-qwao Type 2 l l WELD OVERLAY REPAIR (WOR) TYPES i I l t' 'XCE-42-250 A.1 Revision 0 gg

PIPE SIZE: 12' WEID NO.: 02C S3 DIN. "D": 5.05" WORTYPE: 1 AIIAL SR.: 0.305" -j CPSTREAR DNSTREAR (X* FIGURATION: ELBOW PIPE i PIPEWALLTRK.(tp):- 0.648' O.601' .? OVERLAYTHK.(to): 0.317' O.298" IDW DELTA FERRITE EIRST LATER TE.: N/A N/A DIN. 'A": N/A 2.25" 1 i RENAINING OCTAGE. LDGTE DEPTB LICAMENT ORIST. LOCATION CORUT 1984

~ ~ ----- NO REPORTABLE INDICATIONS -- - --- ---- - - IRSI TREATED

'I 1986 ~ ~ --- - ---- - --- NOT INSPECTED - ~ ~ ~ --- - --- - - .) 1987 0.75" N/A AXIAL PIPE SIDE " LEAKAGE BARRID" OVERLAY APPLIED =i 0.85' N/A AXIAL PIPE SIDE 1989 0.'1' SP0f** 0.19" AXIAL' PIPESIDE BUILT-CP TO " STANDARD" OVERLAY 0.15" N/A 0.73' AIIAL PIPE SIDE

AXIAL FLAWS ASSCRED TO HAVE 1001 PIPE WALL DEPfB.
- THIS INDICATION HAS NO NEASL'RABLE DEPTH.

1 + l XCE-42-250 A2 nutech Revision 0

PIPE S!!E: 12" WELD N0.: 02C.54 DIM. "D": 4.20" WDR TYPE: I AIIAL S E.: 0.316" CPSTREAM DNSTREAR CONFIGURATION: PIPE Ela0W PIPE WALL T E (tp):- 0.586" 0.684" 4 OVDLAY TE. (to): 0.423" 0.424" 11W DELTA TDRITE FIRST LAYD TE.: 0.089" 0.072" DIM. "A": 1.82" N/A l i RERAINING OCTAGE LDGTH DEPfB LICAMENT ORIDT. IDCATION CORENT 1984 4" 441 N/A CIRC. PIPE SIDE " LIMITED SERVICE" OV n LAY APPLIED 1" RAI.- N/A 3 AIIALS PIPE SIDE 1986-0.5" MAI. N/A 0.48" RIN.- 5 AIIALS PIPE SIDE' BUILT-UP TO " STANDARD" OVERLAY .i 1987 0.57" RAI. N/A 0.40" RIN. 5 AIIALS PIPE SIDE 1989 0.30" MAI. N/A 0.36" RIN. 4 AIIALS PIPE SIDE 0.35" N/A-0.43" AIIAL ELBOW SIDE

AIIAL TLAWS ASSCNED TO HAVE 1001 PIPE WALL DEPT 3.

XCE-42-250 A.3 Revision 0 nutech

i PIPE SIZE: 12" WELD NO.: 02D.......... DIN.."D": 4.69" WDR TYPE:. 1 AIIALSHR.: 0.259" UPSTREAN DNSTREAN CONTICt' RATION: EIA0W, PIPE PIPEWALLTE.(tp): 0.67" 0.596" OVERLAYTR.(to): 0.358" 0.329" IDW DELTA EERRITE EIRST LATER TE.: -N/A N/A DIN. "A": N/A 2.19" RENAINING 00TAGE LDCTH DEPTH LICANUT ORIUT. IDCATION 008 57 1984 -- ------------ NO REPORT ABLE INDICATIONS -------------- IRSI-TREATED 1986 --~~-------------- NOT I NSPECTED ------------------ 1987 0.2" N/A AXIAL PIPESIDE " LEAKAGE BARRIER" OVERIAT APPLIED 0.25" U/A AIIAL PIPE SIDE 1989-0.2" SPOT ** 0.7" CIRC. ELBOW SIDE BUILT-UP TO " STANDARD" OVERLAY 0.2" SPOT ** 0.16" CIRC. ELBOW SIDE 0.2" SPOT ** 0.7" CIRC. PIPE SIDE 0.6" N/A 0.75" CIRC. ELB0W SIDE

AXIAL ELAWS ASSUMED TO HAVE 100% PIPE WALL DEPTH.
- THIS INDICATION HAS NO E ASURABLE DEPTH.

XCE-42-250 A.4 Revision 0 nutech

4 Q PIPESIIE: 12"- WELD NO.: 02>S4. DIN. "D": 4.36" WDR TYPE:. 1 A!!AL SR.: 0.201" UPSTREAR DNSTREAR 'l CONFIGURATION: PIPE Ela0W PIPE WALL 75 (tp): 0.600" 0.71" i i 1 OVERLAY T U (to): 0.374" 0.362" i IDW DELTA FERRITE I FIRST LAfD TE.: N/A N/A DIN. "A": 1.93" N/A RERAINING OCTAGE LDCTH DEPTE LICAMBT ORIENT. IDCATION COMENT ...............................-.....~............ 1984 0.5" N/A AIIAL PIPE SIDE " LIMITED S DVICE" OVERLAY APPLIED 0.875"- N/A. AIIAL PIPE SIDE 3 c j 1986

...-..--..------- No! INSPECTED.--------.------.---

j 1987 1.12" MAI. N/A 0.38" RIN. 3 AIIALS ' PIPE SIDE BUILT-UP T0 " STANDARD" OGRLAY j 1989 0.40" MAI. N/A 0.38" KIN. 3 AIIALS PIPE SIDE

AIIAL FLAWS ASSUED TO HAVE 1001 PIPE WALL DEME.

.XCE-42-250 A.5 Revision 0 gg

(g PIPE SI!E:- - 12' WELD N0.: 02t S3 i-DIN. "D': 4.62'~ WDR ffPE: ~1 AIIAL SB.: 0.280' UPSTRFAX DNSTREAR .ORFIGURATION: -ELB0W PIPE PIPENALLTE.(tp): 0.679' O.603' OVERLAYTE.(to): 0.343' 0.341' IDW DELTA TERRITE s FIRST LAT D THK.: N/A N/A DIN. 'A': N/A 2.21' RENAINING OUTAGE' LENGTB DEPfB LICAMBT ORIENf. IDCATION 0* RENT 1984. ---~~~------ NO REPORTABLE INDICATIONS -------------- IRSI-TREATED 1986

NOT INSPECTED -------------------

1987 1.0" N/A AIIAL PIPE SIDE " LEAKAGE BARRID' OVERLAT APPLIED 1989

30 RDORTABLE INDICAf!0NS AffD OVERLAY APPLICATION --- BUILT-CP 70 ' STANDARD' OVDLAY

AIIAL FLAWS ASSURED TO BAVE 1001 PIPE WALL DEPfB.

XCE-42-250 A6 nutech Revision 0

s PIPESI!E:- 12" WELD No.: 02E 54-DIN. "D": 4.59" WDR TYPE: 1 AIIALSER.: 0.242" UPSTREAM DNSTREAR ~ CONFIGURATION: PIPE E!B0W PIPEWALL75.(tp): 0.611" D.673" OVDLAY 75. (to): 0.346" 0.358"~ IDW DELTA FERRITE FIRST LAYER TE.: N/A N/A DIM. "A": 2.03" N/A REMAINING OUTAGE LNGTB DEPTB LIGARENT ORIENT. IDCATION

0) RENT-1984 0.8"

65) -

N/A CIRC. PIPE SIDE " LIMIT E SERVICE" OVERLAI APPLI D - 1.125" N/A 8 AIIAIS PIPE SIDE 1986

NOT INSPECTE -------------------

1987 0.91" MAI. N/A 0.36" RIN. 14 AIIALS PIPE SIDE BUILT-UP 70 " STANDARD" OV D LAY 1989 0.40" RAI. N/A 0.30" MIN. 28 AIIALS PIPE SIDE

AIIAL FLAWS ASSUMED TO HAVE 1001 PIPE WALL DEPTH.

XCE-42-250 A.7 ilutech Revision 0

PIPE S11E:- 12' WELD No.: 02f-S3 DIR. "D': 4.12' WDR7YPE: 1 - AIIAL SER.: 0.231' CPSTREAR DNSTREAR CONTIGURATION: !!J0W PIPE PIPEWALLTE.(tp): 0.672" 0.593* OVERLATTE.(to): 0.306" 0.309' IDW DELTA TERRITE FIRST LAYER T E.: N/A N/A DIM. 'A': N/A 1.93* RDIAINING OCTAGE LBCTH DEPfH LIGAIENT ORIENT. IDCATION C0EDT 1984

~~~- NO REPORTABLE INDICATIONS --------------- IISI-TRIAfD 1986

NOT INSPECT 2 -----~~~~--------

1987 0.80" N/A AIIAL PIPESIDE ' STANDARD" OVERLA1 APPLI E 0.56' N/A AIIAL PIPE SIDE 0.88" N/A AIIAL PIPE SIDE - 0.76' N/A AIIAL PIPESIDE 0.72' -N/A AIIAL PIPESIDE 0.40" N/A AIIAL PIPE SIDE 1989 0.20" 0.41' AIIAL PIPE SIDE

AIIAL TLAWS ASSURED TO HAVE 1001 PIPE WALL DEPfB.

XCE-42-250 A.8 ilutech Revision 0

.I l PIPE SIZE: 12' WELD NO.: 02F S4 DIN. "D*: 4.06' WDR TYPE:- 1 AIIAL SR.: 0.319' UPSTREAR DNSTREAR CONFIGURATION: PIPE ELBOW PIPEWALLTE.(tp): 0.586* 0.69' OEELATTE.(to): 0.337' O.294" 14W DELTA FDRITE FIRST IAfD 75.: N/A N/A DIR. 'A*: 2.12' N/A RERAINING OCTAGE LDCTH DEPTB LIGAMENT ORIENT. IDCATION CORENI 1984 0.8" RAI. N/A 3 AIIALS EL*3W SIDE ' LIMITED SERVICE' OVDLAY APPLIED 1986

NOT INSPECTED ----------------

1987 0.%" N/A 0.41" AIIAL ELBOW SIDE BUILT-UP TO ' STANDARD' OVD LAY 1989 -0.35' N/A 0.38' AIIAL ELB0W SIDE

AIIALFLAWSASSUMEDTOBAVE1001PIPEWALLDEPH.

XCE-42-250 A9 Revision 0 nutech

-- r - d'. 5 PIPE SI!E: 12" WELD NO.: 02G S3 DIN. "D": -5.22" WOR TYPE:- 1 i 1 AIIAL SR.: 0.328" UPSTREAR DNSTREAR CONFIGURATION: ELBOW PIPE -1 PIPEWALLTR.(tp): 0.687" 0.606" q OVDLAITR.(to): 0.508" 0.504" IDW DELTA FDRITE PIR$f LAY D T R.: 0.135" 0.150"' DIM. "A": N/A 2.29" REEINING OUTAGE LDCTE DEPTE LIGANUT ORIENT. IDCATION (XMUENT 1984 0.75" 50% N/A CIRC. PIPE SIDE " LIMIT S S D VICE" OVERLAY APPLI E 1.125" MAI. N/A 7 AIIALS PIPE SIDE 0.875" N/A AIIAL ELBOW SIDE j 1986

NOT INSPECTED ---------------------

t 1987 0.96" MAI. N/A 0.38" RIN. 9 AIIALS PIPE SIDE BUILf-UP TO " FULL STRUCTURAL" 0.64" RAI. N/A 0.44" XIN. 2 AIIALS E1J10W SIDE OVERLAY l 1989-5.2" N/A 0.40" CIRC. PIPE SIDE BUILT-UP M " STANDARD" OVDLAY 0.5" RAI. N/A 0.35" RIN. 4 AIIALS ELB0W SIDE j 0.15" N/A 0.59" AIIAL PIPE SIDE

AIIAL FLAWS ASSURED TO BAVE 1004 PIPE WALL DEPfH.

XCE-42-250 A'10 Revision 0 b

u w PIPESI!E: 12' WELD NO.: 02G S4

. DIN. "D*:

4.30' WORTYPE: 1 'A!!AL SNR.: 0.327' UPSTREAR DNSTREAN CONFIGURAf!0N: PIPE EI30W PIPEWALLTE.(tp): 0.587' O.679* OVDuY TE. (to): 0.495* 0.480" IDW DELTA FDRITE FIRST LAfD TR.: N/A N/A DIN. 'A': 1.83" N/A RDAINING 00TAGE .LDCTH DEPTB LIGANDT ORIENT. IDCATION m RENT 1984 .l' 18% N/A CIRC. EIa0W SIDE ' LIMIT E S D VICE" OVER MY APPLI E 0.125' N/A AIIAL ELB0WSIDE 1986 .---------.----------- NOT INSPECT G ---------.--.---------- 1987 0.70' N/A 0.39' CIRC. ELB0W SIDE ' BUILT-UP TO " STANDARD' OtTRLAY 0.98' NAI. N/A 0.35' NIN. 3 AIIALS ELBOW SIDE 0.42' N/A 0.38' AIIAL PIPESIDE 1.0" NAI. M/A 0.32' NIN. LAMINAR ELB0W SIDE 1989

NO RDORTABLE INDICATIONS AFTD OVERLAY APPLICATION -.- BOAT SAMPLE RDOVE 11t0N OVERLAY.

ADDITIONAL LAYD APPLIG.

AIIAL FLAWS ASSCMG H) EAVE 100% PIPE WALL DEPTH.

XCE-42-250 A.11 Revision 0 nutech

PIPE SI!E: 12" WElb NO.: 028 S3 DIN. "D": 4.46" WDR!!PE: 1 AIIAL SR.: 0.239" UPSTREAN DNSTREAR (INTIGURAf!ON: EIa0W PIPE-PIPEWALLTE.(tp): 0.703" 0.598" OWRLAYTE.(to): 0.36" 0.434" IDW DELTA FEttITE FIRST LAI R T E.: N/A N/A DIN. "A": N/A 2.0" RENAINING OCTAGE LUGTB DEPTB LIGANDT 01157. IDCATION CO M NT 1984 3" 211 N/A' CIRC. PIPE SIDE "LIMITD SUVICE" OVERIAY APPLID 0.75" MAI. 6 N/A 3 AIIAI.S PIPE SIDE 1986-

NOT INSPECf D ---------------- -----

1987 0.64" NAI. N/A _0.43" NIN. 4 AIIALS PIPE SIDE BUILT-UP TO " STANDARD" OV ELAY 1989 0.65" MAI. N/A 0.44" NIN. 4 AIIALS PIPE SDE

AIIAL TLAWS ASSUND TO BAVE 1001 PIPE WALL DEPfB.

XCE-42-250 A.12 Revision 0 g

a s l PIPE $11E: 12' WELD NO.: 025 54 DIR. "D': 4.648 WDRTYPE: 1 AIIAL SR.: 0.289' UPSTREAR DNSTREAR ..~................ 03FIGURAf!05: PIPE ELBOW PIPEWALLTEK.(tp): 0.596* 0.687* OVERuf TEK. (to): 0.356' O.,33' IDW DELTA FERRITE FIRST MY D TEK.: N/A-R/A DIR.'A': 2.01' N/A RENAINING OUTAGE LDCTH DEPTB LIGARElff ORIElft. IDCATION ColOENT 1984 0.75' RAI. I/A 4 AIIALS PIPE & " LIMIT E SERVICE" OVERLAT APPLIED-ELB0W SIDE 1986

.----- Il0! INSPECTED ---------------------.

1987 0.48' E I. N/A 0.38' RIN. 2 AIIALS ELBOW SIDE ll01LT-UP 10 " STANDARD" OVERMY 0.64* RAI. N/A 0.35' RIN. 11 AIIAIS PIPESIDE 1989 0.45' MAI. N/A 0.35' NIN. 14 AIIALS PIPE SIDE 0.40' RAI. N/A 0.36' RIN. 3 AIIALS ELBOW SIDE

AIIAL fuWS ASSUED TO IAVE 1001 PIPE WALL DEPTH.

XCE-42-250 A.13 Revision 0 nutech I

y o PIPtSI!!: 12' WELD No.: .02J.f6 DIN. "D": '3.618 WDRTYPE: 2 AIIAL SR.: 0.198" UPSTREAR DNSTREAR (XETIGURATION: SWEEP. PIPt PIPEWALLTE.(tp): N/A 0.584* OVDLktTEK.(to): N/A 0.260' 14W DELTA FERRITE FIRST LAI R T R.: N/A N/A- ) DIN. 'A': N/A 1.97" i ~l RENAINING OUTAGE LDCTH DEPTB LIGARUT ORIDT. IDCATION COMEM .............~..~...... ~...........................~........ 1984 1.25' NAI. N/A 7 AIIAIS PIPE SIDE "LINITED S SVICE" OV D LAT APPLI E j 1986

.--------~.---. NOT INSPBCfD ------------------

1987 1.02" RAI. N/A 0.26" MIN. 13 AIIA!3 PIPESIDE BUILT-UP TO ' STANDARD" OVERLAY j 1989 0.40' MAI. N/A 0.25" RIN. 16 AIIALS PIPt SIDE l -

AIIAL FLAWS ASSOED TO HAVE 100% PIPE WALL DEPTH.

llCi;21 nutech ^"

PIPE S!!E: 12" WELD NO.: 02J 53 DIN. "D": 4.41" WOR TYPE: 1 AIIALSER.: 0.367" UPSTREAM DRSTREAN CONFIGURATION: E120W PIPE PIPEWALL15.(tp): 0.698" 0.601" OVERLAYTB.(to): 0.336" 0.397" IDW DELTA FERRITE FIRST LATER 7 5.: N/A - N/A DIN. "A": N/A 1.98" REMAINING OUTAGE LENGTH DEPfB LIGARENT ORIENT. IDCATION 00BDff 1984 0.6" ' 12% N/A CIRC. PIPE SIDE " LIMIT E SERVICE" OVERLAY APPLIED 0.5" N/A. AIIAL PIPESIDE 1986-

---- N0f I NSPECTE ----------------------

1987. 0.52" N/A 0.43" AIIAL E!A0W SIDE BUILT-UP 10 " STANDARD" OVERLAY 0.64" NAI. N/A 0.37" NIN. 4 AIIALS PIPE SIDE 1989 0.30" MAI. N/A 0.43" NIN. 2 AIIALS ELBOWSIDE 0.40" MAI. N/A 0.37" MIN. 4 AIIALS PIPESIDE

AIIAL FLAWS ASSUMED TO RAVE 100% PIPE WALL DEPTR.

XCE-42-250 A.15 l Revision 0 nutech

j ..... S4 ' lj IPIPESIZE: 12" WELD NO.: 02J DIN. "D": 4.64" WOR TYPE: 1 I AIIAL SR.: 0.326" UPSTREAN DNSTREAN (IMFIGCRATION: PIPE ELBOW PIPEWALLTR.(tp): 0.599" 0.675" OVERLAY 75.(to): 0.390" 0.349" i i I N DELTA FD RITE FIRST LAfD TR.: - N/A N/A 1 DIN. 'A":. 1.96" N/A RDAINING OUTAGE LDGTB DEPTH LIGAMENT ORIENT. IDCATION CORENT 1984 4.25"' 551 N/A CIRC. PIPESIDE " LIMIT S S D VICE" OVERLAY APPLI G 0.6" <301 N/A CIRC. PIPE SIDE 2.0" <30% N/A CIRC. PIPESIDE 1.8" <30% N/A CIRC. - PIPE SIDE 1.6" <30% N/A CIRC. PIPE SIDE 3.0" <30% N/A CIRC. PIPE SIDE 1.1" MAI. N/A 9 AIIA13 PIPE SIDE 1986 0.5" NAI. N/A 0.34" NIN. 16 AIIAIS PIPE SIDE BUILT-UP TO " STANDARD" OVERLAY 1987 0.70" Na!. N/A 0.33" NIN. 11 AIIA!S PIPE SIDE 1989 0.40" NAI. N/A 0.33" NIN. 18 AIIAIS PIPE SIDE 0.30" NAI. N/A 0.36" NIN. 4 AIIALS ELBOW SIDE

AIIAL FLAWS ASSCNED TO HAVE 100% PIPE WALL DEPTH.

l XCE-42-250 A.16 Revision 0 nutech

PIPESIZE: 12' WElb 90.: 02KF6-

DIN. 'D": .

3.56" WDR TYPE: 2 AIIAL SR.: 0.132' UPSTREAR DNSTREAR CONFIGCRATION: SWEEP. PIPE PIPEWALLTEK.(tp): B/A 0.610". OVERLA1TEK.(to): B/A 0.343" - IDW DELTA TDRITE FIRST LAYER T R.: N/A N/A DIN. "A": N/A 2.37' I RERAINING 00TAGE LUCTH DEPTB LIGARET ORINT. - IDCATION (DIOGNT 1989

NO REPORTABLE INDICATIONS AFT D OVERLAY APPLICATION --- 'STANDARDa OVERLAT APPLIED TO BALANCE SYST D OVERLAY AIIAL SERIBAGESTRESS!$

i

AIIAL FLAWS ASSURD TO RAVE 1004 PIPE WALL DEPTE.

f XCE-42-250 A.17 Revision 0 nutech

b i L -a 4 PIFF S!!E: 12" WELD No.: .....-S3, 02K i 1' DIN. "If: ,4.65" WDR TYPE: 1 .AIIAL SNR.: 0.440" UPSTREAN DNSTREAN CONFIGURATION: EIJ10W PIPE PIPEWALLTE.(tp): 0.666" 0.584" OVDLAY TE (to): 0.385" 0.365" LOW DELTA FERRITE TIRST Lain T E.: N/A N/A DIN. "A": N/A 2.18" RENAINING OUTAGE LNGTH DEPfB LIGANENT ORI57. IDCAf!0N CDIOENT 1954 1.6" 251 1/A CIRC. PIPE SIDE- "LINITED S D VICE" OVERLAY APPLIED i 0.2" 251' N/A CIRC. PIPE SIDE 0.8" 15% N/A CIRC. PIPE SIDE 8.0" 24% N/A CIRC. PIPE SIDE O.6" NAI. N/A 5 AIIA!3 PIPE SIDE 1986 1.5" NAI. N/A 0.77" NIN. 4 CIRCS. PIPE SIDE BUILT-UP TO " STANDARD" OVERLAY 0.75" NAI. N/A 0.54' NIN. AIIAL PIPE SIDE 1987 3.2" N/A 0.50" CIRC. ELBOW SIDE l< 0.60" NAI. N/A 0.35" NIN. 4 AIIALS ELBOW SIDE l-l_ 1989 0.75" MAI. N/A 0.42" NIN. 4 AIIALS PIPE SIDE l

AIIAL FLAWS ASSUMED TO HAVE 1001 PIPE WALL DEPTH.

l l l 'XCE-42-250 A.18 nutech l Revision 0 l --

k Y \\ 4 PIPESI!E: 12' - - WELD No.: 02K $4-DIN. 'D": 4.49' WDR TYPE: 1 A!!Al SR.: 0.220"- UPSTREAR DNSTREkN CONFIGURAf!ON: -PIPE EIJ10W i PIPEWALLTE.(tp): 0.584' O.665" OVDLAYTE.(to): 0.315" 0.345' IDW DELTA FDRITE . FIRST lAYD HK.: N/A N/A DIN. 'A*: 2.0" N/A RENAINING OUTAGE LNGTB DEPTH LIGAMENT ORIElff. 10 CATION C0lOIElff 1984 0,25" NAI. N/A 2 AIIALS PIPESIDE " LIMIT E S D VICE" OV D LAY APPLI G I 1986

110T INSPECTED ----------------------

-i 1987-0.84" N/A 0.45' AIIAL E120W SIDE BUILT-UP 70 " STANDARD" OVERLAY - 0.64" NAI. N/A 0.37' NIN. 7AIIM PIPE SIDE .J -1989 0.35' NAI. N/A 0.36' NIN. 8AIIE PIPE SIDE l

AIIAL FLAWS ASSURED TO HAVE 1001 PIPE WALL DEPTH.

i l XCE-42-250 A.19 Revision 0 l1utech

PIPE S!!E:. 12" WELD NO.: 02L-S4 DIN.-"D": 4.90" WDR TYPE: 1 AIIAL S R.: 0.297"- UPSTREAN DNSTREAN CONTIGURATION: PIPE ELBOW PIPEWALL75.(tp): 0.605" 0.664" OVERLAT75.(to): 0.457" 0.447" 14WDELTAFERRITE i FIRST !.AYB TR.: N/A N/A DIN. "A": 2.18" N/A REAINING .OCTAGE LDCTB DEPTH LIGARElff ORIEllf. !DCATION COIOENT 1989

60 REPORTABLE INDICATIONS AFTER OVRLAT APPLICATION --- " STANDARD" OVERLAY APPLI G TO

-4 BALAllCE SYSTEN OVERLAT AIIAL SH I E AGE STRESSES .j i

A!!AL TLAWS ASSORD TO EAVE 1004 PIPE WALL DEPft.

1 b i l' XCE-42-250 A.20 Revision 0 l

h l PIPESI!!: 12". WELD NO.: ..... S3-02N l I DIN. "D":- 4.72" WDR ffPE: 1 [ -AIIAL SR.: 0.299" UPSTREAR DNSTREAR CONFIGURAf!0N: EIA0W PIPE PIPE WALL TR. (tp): 0.678' O.597* OVERLAT TR (to): 0.285" 0.376' IDW DELTA FERRItt FIRST LAfD 75 : N/A N/A DIN. 'A': N/A 2.22" RENAINING OCTAGE LDCTH DEPN LIGAMENT ORIErf. IDCATION 00557 1984 l' NAI. N/A 3 AIIA!3 PIPE $1DE ' LEAKAGE BARRIER" OV R LAY AND PIPE CLANPING DEVICE APPLItD 1986

NOT INSPEtttD ------------------

.1987 NOT INSPECTED ----- --------- --~-- - - - - - - - - ~ ~ - ~ - - ~ 1989 -- NO EZPORTABLE INDICATIONS AFTER OVERLAT APPLICATION --- BUILT-UP 70 " STANDARD" OVERLAY. PIPE CLAMPING DEVICE RD10VED.

AIIAL FLAWS ASSURED TO HAVE 100% PIPE WALL DEPfH.

1: - XCE-42-250 A.21 Revision 0 nutech

r a ? a, ,4> 'PIPESI!E: 12' WELD No.: 02N 54 DIN. 'D*: 3.9' WDR TYPE: 1 AIIALSB.: 0.265' UPSTRfAN DNSTREAR CONFIGURATION: PIPE Ela0W PIPEWA!.LTNK.(tp): 0.601' O.646' 's ' OVRIAY TE. (to): 0.321" 0.389' ..g 14W DELTA FDtRITE FIRST IATR TE.: N/A N/A DIN.'A*: 1.94* N/A RBIAINING OCTAGE LDCTB DEPTR LIGANWT ORIDT. IDCATION COINIDT 1984

NO REPORTABLE INDICATIONS - ------------ IRSI-TREATE 1986

NOT INSPECTE ---------- ----------

-1987 In e N/A AIIAL ELB0W SIDE ' LEAKAGE BARRIER" 0\\TRLAY APPLI E 1989

NO REPORTABLE INDICATIONS AFTR OVERLAT APPLICATION -- BUILT-UP TO ' STANDARD' OVERLAY

AIIAL FLAWS ASSUM E TO BAVE 1001 PIPE WALL DEPTH.

XCE-42-250 A.22 Revision 0 r1utech

1 i I-f i . PIPESI!E: 22' WELD NO.: ......F1 028 DIN. "D':- 5.52' WDR fYPE: 2 AIIAL SR.: 0.138' UPSftEAR - MSftF.AN 00NTIGURATION: VALVE PIPE PIPEWALL75.(tp): N/A 1.095" OVRLAf75.(to): N/A 0.559' 3 IAW DELTA FEttITE-FIRST LAY R 7 5.: _ N/A N/A DIN. 'A': N/A 3.69' RENAINING OUTAGE LNGTH DEPH LIGAENT ORINT. IDCAf!0N CORENT 1984

-- I.D. GE0Efti ----------------- IRSI-TREATED 1986

~---------------------- NOT INSPECTED ----------------------- -1987 3.0" 26% N/A CIRC. PIPESIDE " LEAKAGE BAtt!D' OVDIAY APPLIED - 0.25' W/A AIIAL PIPE SIDE 1989 -- 30 RDolfABLE INDICATIONS AFfD OVBLAY APPLICATION --- BOILT-UP TO "$fANDARD' OVERLAY

AIIAL FLAWS ASSUIED M IAVE 100% PIPE WALL DEPfB.

I' l l i l I 1 l XCE-42-250 A.23 1 ' Revision 0 nutech

pi( r, ')i' U. PIP! SIIt: 22' WELD NO.: .02B........ DIN.D*: 2.47' WDRfiP!: 2 AIIAL SR.: 0.110' UPSTREAR DNSTREAR CONFIGURATION: CROSS PIPE PIPE E LL T E. (tp): N/A 1.073' OVFRMYTE.(to): N/A 0.559' IDN DELTA FERRITE FIRST MIER 75.: N/A 0.102' DIM. 'A': N/A 1.94' -REMAINING OCTAGE LENGTB DEPfB LICARIN! ORIEN!. IDCATION

0) MENT

-.............. ~.. -..... 1984 0.125' . N/A AIIAL PIPE SIDE "LIRIfD SERVICE' MTRMY APPLIG 1966

...- ---.------- M0T INSPECTED --------------------

1987 0.92* N/A 0.56' AIIAL CRO6S SIDE BUILT-UP TO ' STANDARDS GTRLAY 1989 0.7' E !. N/A 0.6' RIN. 3 CIRCS. CROSS SIDE

AIIAL TMWS ASSUED TO HAVE 1001 PIPE WALL DEPfB.

XCE-42-250 A.24 Revision 0 nutech

li 4 - PIPESI!E: 22"- WELD NO.: 028 .....S10 i, ..... ~.. l' DIN. "D": 5.01"' WDR fYPE: 1 AIIALSER.:~ -0.030" DPSTREAN DNSTREAR CONFIGCRAf!0N: PIPE ENDCAP 1 PIPEWALL75.(tp): '1.070" 1.019" OVDIAY 75 (to): 0.471" 0.507" IDW DELTA FERRITE i FIRST LAfD 75.: N/A N/A DIN. "A": 2.9" N/A RENAINING 00fAGE LDGTH DEPTB LIGAMENT ORIDT. 14 CATION 001DIENT ..........e 1984 2" lot-N/A CIRC. E.C. SIDE " LIMITED SDVICE" OVDLAY APPLIED 0.5" 3 AIIALS E.C. SIDE 1986'

- ------------- IIQf INSPECTED - ---------- - - ~ ~

1987 1.12" NAI. N/A 0.45" NAI. 2 AIIAIS E.C. SIDE BUILT-UP 70 " STANDARD" OVDLAY-1989 0.10" N/A 0.42" AIIAL !.C. SIDE 0.35" NAI. N/A - 0.32" NIN. - 4 A!!ALS PIPE SIDE

AIIAL FLAWS ASSUMED TO HAVE 1001 PIPE WALL DEPfB.

l-I- XCE-42-250 A.25 Revision 0 nutech

v je j

lL ,s.,: l PIPE S!!E: 28' WElb No.: 02BS S$ DIR. 'D*: 3.25' WDR ffPE: 2 i A!!AL SR.:- 0.057' -j 1 1,j -. ,i CONFIGCRATION: PIPE-TEE-x PIPEWALLTE.(tp): 1.244' N/A OVERLAY 75.(to): 0.592' N/A IM DELTA FDRITE FIRST IAYS TE.: N/A N/A DIR. 'A": 3.01" N/A RENAINING -OUTAGE IDCTB DEPTB LIGARENT ORIENT. 14 CATION CORRENT 1934- .................... I.D. CBORETRY ----------------------- IISI-TREATED 1,u .................... N0,INSPECr m........- -........... 1 J l 1987 5' 15% N/A CIRC. PIPE SIDE ' LEAKAGE BARRIER' OVERLAY APPLIED 4' 25% N/A CIRC. PIPESIDP. 0.2" N/A AIIAL PIPE SIDE 0.3" N/A A!!AL PIPE SIDE 1989

NO REPORTABLE INDICATIONS AFT H OVERLAY APPLICATION --- BUILT-UP 70 ' STANDARD' OVERLAY

- AIIll FLAWS ASSUE D TO HAVE 100% PIPE WALL DEPTE.

XCE-42-250 A.26 Revision 0 nutech

R 4 I h t PIP! SI!!: 28" WELD No.: 02BS-S9 - DIN. *D": 9.18" -WDRfYPt: 1 -l A!!AL SR.: 0.106" UPSfttAR WSfttAR I j (XWFIGURATION: PIPE ELB0W l PIPEWALLTR.(tp): 1.232" 1.422" OVERLAYTE.(to): 0.609" 0.531" y IDW DELTA FDRIt! FIRST LAYB TR.: N/A N/A I DIN. 'A": 4.51" N/A .t IRAINING ] OUTAGE LNGTB DEPfB LIGANENT ORIENT. IDCATION: C0557 1984 4.0" 0.05" N/A CIRC. ELB0WSIDE IRSI-fttATED 1.5" 18% N/A CIRC. PIPE SIDE- 'O.5" 15% N/A CIRC. PIPE SIM 1986 1" 23% N/A CIRC. Ela0W SIDE 1" 151 N/A CIRC. !!a0W SIDE { 2.5" 20%- N/A CIRC. ELBOW SIDE' l' 15% N/A CIRC. PIPE SIM 1.5" 24% N/A CIRC. PIPE SIDE 1987 3" 404 N/A CInc. ELB0W SIDE " LEAKAGE BARRI D" OVERLAY APPLIED 2" 35% N/A CItc. ELB0W SIM 1.5" 30% N/A CIRC. EL%W SIDE 2.5" 44% N/A CItc. 2120W SIDE 3.25" 351 N/A CIRC. Ela0W SIDE 3.5" 35% N/A CItc. PIPE SIDE 6" 404 N/A CIRC. PIPE SIDE 1.5" 20% N/A CItc. PIPE SIDE 0.25" N/A AIIAL E120W SIM 1989

NO REPORTABLE INDICATIONS AFfD OVELAY APPLICATION -- BUILT-UP TO " STANDARD" OVEP1AY

AIIAL FLAWS ASSUMED TO HAVE 1004 PIPE WALL DEPTH.

XCE-42-250 A.27 Revir, ion 0 nutech / i

. ~. - s'..A. ,3-.. " ei, t -b + PIPE Slit:' 10' WELD NO.: 14A ....F2 1 DIN.L"D":- 5.19" WDR TYPE: 1 = AIIAL SHR.: 0.255' I 1 >1 t UPSTREAR DISTREAR U CONFIGURATION: FIPE SAFE END PIPEWALLTE.(tp): 0.592" 0.59 i OVERLAYTR.(to): 0.347" .0.277' -14W DRLTA FERRITE FIRST LAY D TR.: N/A N/A DIN.'A': 2.30' - N/A 1 '1 I RENAINING 00TAGE. LNCTH DEPfH LIGAENT ORIENT. IhCATION CONER ............................................. n.......... 1934 ................. I. D. GE0NETRY -------------------- t 1986

I. D. GE0ETRY --------------------

1987-0.64" N/A AIIAL PIPE SIDE " LEAKAGE BARRIER" OV DLAY APPLIED l' 1989 ~~ NO REPORTABLE INDICATIONS AFTD OVDLAY APPLICATION -- BUILf-UP to ' STANDARD" OVDLAY

AIIAL FLAWS ASSUED TO HAVE 1004 PIPE WALL DEPfH.

I-l' t i 1 .XCE-42-250 A.28 ' Revision 0 nutech

r i r 1 n i 1 l-FIPE S!!!: 10' WILD NO.: 14A.T11 DIN,"D*:- 2.29' WDR fiPt: 2 A!!ALSR.: 0.139' l UPSTRIAN DNSfttAN CONFIG3ATION: VALVE Ela0N PIPI ELL TR. (tp): N/A 0.631' OVttLAI75.(to): N/A 0.352' LM DELYA Pttt!?! ElkST LAfD TE.: N/A N/A DI5. 'A*: N/A 1.44' l J RD&!NING OUfAct LINCTE DEPfB LIGANINT OtitNT. IhCAf!0N ONultNT 1964 NOT INSPtCf tD ----- --*--- -- - - 1986 ~~~ -- -- -------- NOT INSPECfD ---~~-----~~ --- 1987 0.3" N/A AIIAL ELbON $!Dt 'LLAKAGE MRID' M'tkLAY APPL!D 1989 ~~ N0 ftP0tfAEt INDICAf!0NS APfD MTRLAY APPLICAfl0N ~ KILT-UP 10 ' STANDARD' MTkLAY e AXIAL TLAWS ASSMED TO RAVE 1001 PIPE WALL DEPTR. T L i XCE-42-250 A.29 Revision 0 nutech

w PIPtS!!!: 10' WELD NO.: 14A.s6 DIN. *!f: -

3. H" Et TIPE:

1 A!!AL B R.: 0.192* UPSfttAN DNS?ttAR CONFIGCRAf!0N: P!Pt E130W PIPtWALLTE.(tp): 0.59' O.632' OVttLATfB.(to): 0.358' O.339' IDW DELTA PtttIft FIRST LAf tt TE.: N/A N/A DII.'A*: 1.62* N/A RENAINING 001Act LINCfN DEPfB LIGAENT Ot1ENT. IDCAf!0N COREWT 1964 ~~~~~~ ~~ B0! INSPECfD ~~~--~~~~~ 1966 --~~--~~~~ N7f INSPBCftD -~~~- -~------- 1967 1.5' 19% N/A CIRC. ELBOW SIDE ' STANDARD' OVERLAY APPLIED 0.3' N/A A!!AL E!A0WSIDE 1969

N0 ItMtfABLE INDICATIONS Arftt OVttLAT APPLICAf!0N ~

AXIAL FLAWS ASSU E D TO IAVE 1004 PIPE WALL DEPff, t

i XCE-42-250 A.30 Revision 0 nutech

PIPES!!!! 10' WELD NO.: 14A.$9 DIN. 'D*: 4.89' WDR TYPE: 1 l A!!AL SR.: 0.309' OPStktAN MSTREAN 00Nr!GCtAfl05: IIA 0W PIPE PIPE NALL 15. (tp): 0.600* 0.606' OVtkuY75.(to): 0.402' O.444' low DELTA FZttIft IIRST MYD TE.: N/A N/A DIN. 'A': N/A 2.21' RtilAINING OUTAGE LDCTI DEPfB LIGANENT Ot! TNT. IDCATION COEtWT 1944 - - ~~ -- Not INSPECfD -- ~ ~~--- - - -- ~--~~c-1966

----------- NOT INSPECfD ------ ----- ----~---

1987 0.3' N/A AIIAL PIPESIDE 'LEAKAGt BARRIER" OVERuf APPLIG 0.45' N/A A!!AL E!A0W SID' 1989 --~ NO REP 0tfABLE INDICATIONS AffD OVERuf APPLICAf!0N -~ BUILT-UP TO 'STAM MRD' OVERuf 8 A!!AL FuWS ASSURD M BAVE 1001 PIPE WALL DEPfl. l' 1 1 l XCE-42-250 A.31 Revision 0 nutech

7 PIPES!!!: 10' WELDNO.: 10 F2 .... ~. DIN. 'D': 5.01' WDRffPt: 1 AIIALSNR.: 0.319" UPSTREAN DNSTREAR 00NTICURAfl0N: PIPE SAPE RD PIPEWALL75.(tp): 0.57' O.566' OitRLAYTNK.(to): 0.405" 0.453* IDW DELTA FDRIft TIRST lAfD TE.: N/A N/A DIN.'A': 2.20' N/A RENAININC 00 FACE LINCTE DEPTE LICANNT ORIENT. IDCAf!0N COOtENT I 1964 ---~~~------- - I. D. CBONETR f -~~-~~----- i 1946

- ------- 307 INSPECitD - - - -----------------

1967 0.4' I/A AIIAL PIPE SIDE 'LEAKACE BARRID' OVERLAY APPLIED O.35' N/A AIIAL P!PESIDE i 1989 --- NO REPORTABLE INDICATIONS AFfD 0\\TRIAT APPLICAfl0N ~ BCILT-UP TO ' STANDARD' OVERLAY

A!!AL TIAWS ASSUlttD TO BAVE 1004 PIPE WALL DEPTE.

1 1 i l l XCE-42-250 A.32 Revision 0 nutech l t

1.- - PIPE $11t: 10' Wtlb No.: 148 .....-58 DIN. 'D*: 4.77' WDR fiPE: 1 A!!AL SR.: 0.264' UPSfttAN !ESfttAN GWTICURAf!0N: ELB0W EIA0W PIPEWALL75.(tp): 0.587' O.603' l OVButTE.(to): 0.367* 0.341' IIW DELTA Ftttlft litST M itt TE.: N/A N/A I DIN.'A': 2.29' N/A TRAINING OUTAGE LENGTN DEPfN LIGAENT OtitNT. IDCAf!0N C0lNWrf ......... ~...... ............. ~............ 1984 --~~- -------- NOT INSPECfD -~------ - -~-~ 1966 --- ~ ~ - - - WEIb CNOWN FINGtt DUIP - - -- ~ ~ ~ ~ 1987 0.6' N/A A!!AL UPST. SIDE ' LEAKAGE nutt!D' 0\\Ttui APPLIG 0.5' N/A AIIAL UPST. $1DE i-0.5" N/A AIIAL UPST SIDE 0.4* N/A AIIAL UPST. SIDE 1989 --- NO RD0RfABLt INDIC310N$ AffD OVERLAT APPLICATION ~ BUILT UP 70 ' STANDARD' OVERLAY

AXIAL fuWS ASSUED TO RA\\T 1001 PIPE WALL DEPfN.

i 'XCE-42-250 A.33 Revision 0 nutech

k ~. l p i i i:' i i l l 10bD l PIPt$111: 16' WELD NO.: ......$13 DIN. "D*: 5.36' WDRfiPE: 1 l AIIALSER.: 0.064* I 1 UPS R R R DNSftuN C0ff!GURATION: PIPt EIA0W PIPE NALL fBK (tp): 0.856' O.9998 j OVttuiTNK.(to): 0.389" 0.3818 i 14W DELTA FERRIf! FIRST LAftt TE.: N/A N/A DIR.'A': 2.43' N/A l RERAINING 00 FACE LNCTE DEPTE LIGAENI ORIENT. 10CAf!0N COMENT 1964 - ~~ ~~--- ~ *----- NOT IEPECf D *---- ~ --~ ~-~* -- i 1966 -~~~------ -~~~ N0f INSPECfD -- - ------- ------- 1987 1.5' 18% N/A CIRC. PIPE $1DE NSIP-fRuf2 l 4.75" 20% N/A CItc. PIPE SIDE 1989 - NO REPORTABLE INDICATIONS AffD OVERLAI APPLICAf!0N --- ' STANDARD

OVDLAY APPLIED
AIIAL FLAWS ASSUND M BAVE 100% PIPE WALL DEPM.

XCE-42-250 A.34 Revision 0 nutech

f b b i I t i Appendix B WELD OVERLAY DESIGN DRAWINGS l l r b I l t t 5 XCE-42-250 B.O nutech

i A s t ,,o y,u. = = = TYP. y %j,A u A eP%i' A 7////////f////k////////////////A, L -t Elbow pipe t WELD I WELD OVERLAY REPAlR DETAILS u s.,amt... uu.n i 1 1 l i 1 WELD NUMBER FLAW CHARACTER 12AT10N COMMENTS ^ t A B 02C-s3 1004 x 360' O.23" 2.25" 2.25" standard Weld overlay Repair I-l 5 l $4.s9 z /a /> e Oiro/>9 $$% $n 0 PREP SY/ CFK. BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./ V DESCRIM10N DATE DATE DATE DATE DATE JOB NO: PLANT: REV I XCE-42 Quad Cities Unit 1 SHT O FILE NO: OWG, NO: 1 0F XCE042.0103 XCE-42-103 ""0'" XCE-42-250 B.1 Revision 0 nutech

A e 3 45 MIN. L FLOW j 0 m TYP. p o j [I:)[ !*M sii:@ih%i!! !!!!k ] W//////////f4kf/f///f///////A Pipe Elbow -t (1) ) i ( WELD i WELD OVERLAY REPAIR DETAILS P.i.ni. i.e,or l NOTE: b

1) Design thickness, t, does not include low delta ferrite first layer thickness.

? DESIGN DIMENSIONS WELD NUMBER FLAW CHARACTERIZATION COMMENTS L t A B 1 m L 02C-S4 4". int. x 51% cire. .265" 2.0" 2.0" Design based on 100% x l 3 axi.als (l" max. 360' plus balance-of-length) plant life fatigue crack (all pipe side) growth flaw assumption. cwl "c cw/ rg.al c.w w.w 0 4 11*S(, t l1L7 flS n at1 44 g 21. % l'1T4 Initial I* sue PREP. BY/ CHK. BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./ REV. DESCRIPTION DATE DATE DATE DATE DATE JOB NO: PLANT: REV. SHT. 1 CEC-47 Quad Cities Unit 1 FILE NO: OWG. NO: OF 1 CEC 047.0202 CEC-4 7-202 XCE-42-250 B.2 Revision 0 nutech

t i' A B 460 MIN. TYP p o /> '!!!!9%s >s V///////////////A/////f//////////A, t Elbow pipe -t G. WELD l WELD OVERLAY REPAIR DETAILS u.s.,a m a.....u..n i ? i DEslGN DIMENSIONS WELO NUMBER FLAW CHARACTERIZATION COMME NTS t A B 1. 02D-s3 100% x 360' O.23" 2.25" 2.25" Standard Weld Overlay Repair Rgy 0 /24 Pf J/'7/f t 2//f? Q+M% 4M{g wie ac Issued f r construction REV. DESCRIPTION PREP. BY/ CHK. BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./ DATE DATE DATE DATE DATE JOB NO. PL ANT: REV XCE-42 Quad Cities Unit 1 SHT I O FILE NO: DWG. NO: 1 OF XCE04 2. 0104 XCE-42-104 j s w iss :i :: XCE-42-250 B.3 Revision 0 nutech y

1 I A 8 45 MIN. 0 TYP. p X J j L fi!!! M J:ii%%ii!!s i:e ji[h Vff/fffffff/h//////f/ffff//A i Elbow Pipe' _g ( WELO l WELD OVERLAY i REPAIR DETAILS U. S. Patent i Number 4,624,402 i r I DESIGN OlMENSIONS l WELO NUMBER FLAW CHARACTERIZATION COMYlNTS i I t A B 02D-S4 100% x 360 0.25" 2.0" 2.0" rull structural j. weld overlay l IW(9/'3*F7 b use &ge enG C4l)I87 J +A /6 7 94/87 AlSf87 + Initial Issue n PREP 8Y/ CHK. SY/ P.E. APPRJ E.M. APPRJ P.M. APPRJ REV. DATE DATE DATE DATE DATE DESCRIPTION JOB NO: PLANT: REV. l CEC-73 Quad Cities 1 SHT. 1 FILE NO: OWG. NO: OF CEC 073.0130 CEC-73-130 CWE015.0103 XCE-4 2-25 0 B.4 l Revision 0 nutech 1

i i 1 A e AS MIN _ B O TYP. p { u [$s:si$ese khkd i:!:::i::! !k Vlllllllllll//// A f///hllllllllllllb Elbow pipe i ( WELO i i WELD OVERLAY REPAIR DETAILS u.s. n t m........or i I f r I 4 DESIGN DIMENSIONS WELD NUMBER FLAW CHARACTERIZATION COMMENTS t A 8 i l 02E-S3 100% x 360' O.24" 2.25" 2.25" Standard Weld overlay Repair 1 0 4M tv/P9 4/P9 MB dM PREP. BY/ CHK. BY/ P.E. APPRJ l E.M. APPPI./ P.M. APPRJ REV DATE DATE DESCRIPTION DATE DATE DATE JOB NO: PLANT: REV XCE-42 Quad Cities Unit 1 SHT-1 0 FILE NO: OWG. NO: OF 1 XCE0 4 2. 010 5 XCE-42-105 r m tae a :: XCE-42-250 B.5 l Revision 0 nutech

a 2 8 45' MIN. x TYP., = n ' !l kl :::!:i:!:i i:} } s s Vffff/ffff//kfffff//ffff//A Elbow Pipe -t I q,WELO WELD OVERLAY REPAIR DETAILS U. S. Patent Number-4,624,402 l CESIGN DIMENSIONS WELO NUMBER FLAW CHARACTERIZATION COMMENTS t A B 02E-S4 100% x 360

0. I'4 " 2.0" 2.0" I'ull structural weld overlay

[ l

4c wec M

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/2/37 F/J/77 Abl&1 Dhl Initial Issue PREP. BY/

CHK. 8Y/ P.E. APPRJ E.M. APPRJ P.M. APPRJ E V. DATE DATE DATE DATE DATE DESCRIPTION JOB NO: PLANT: REV. CEC-73 Ouad Cities 1 1 0 FILE NO: OWG. NO: OF ~ CEC 073.0131 CEC-73-131 ) CWE015.0104 XCE-42-250 B.6 Revision 0 nutech L

4 B i A 4$o Miy. = } A @%l lA i V///////////////hf//////////////////////) E LBOW- ~ PIPE q WELD i i WELD OVERLAY REPAIR DETAILS l ratent wo. 4,624.402 I DESIGN DIMENSIONS WELO NUMBER FLAW CHARACTER 12ATION COMMENTS t A B 02r-S3 Circumferential, 0.21" 2.0" 2.0" rull Structural Weld 100% x 360' Overlay Repair L 1 l 9%($/

a'o e see /4/// c%) h,187

//81 W@l# SMD u sued r r const m tion l PREP. BY/ CHK. BY/ P.E. APPRJ E.M. APPR./ P.M. APPRJ REV. DESCRIPTtON DATE DATE DATE DATE DATE i JOB NO: PLANT: REV I XCE-42 Quad cities Unit 1 SHT. l l FILE NO: DWG, NO: ~ OF 1 0 XCE042.0114 XCE-42-114 8 YK 786 01 C; XCE-42-250 B.9 Revision 0 nutech 4 8 A + 45' MIN. 1 TYP. p \\\\ /ii: si $9%!ll w !?lA j f///////SS//////////Af//////////////////////////b, Elbow ~ Pipe t 1 i ( WELO I WELO OVERLAY REPAIR DETAILS U. S. Patent i Number 4,624,402 i r DESIGN DIMENSIONS WELO NUM8ER FLAW CHARACTERIZATION COMMENTS t A B 02G-S4 100% x 360 0.24" 2.0" 2.0" rull structural weld overlay l l l 1 @dy usc 44e cp9 lt1 R 0 fy.y,,g -) W/A/#7

/A/P7 4l5

+13/37 Initial Issue l PREP SY/ CHK, BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./ REV. DESCRIPTION l-DATE DATE DATE DATE DATE JO8 NO: PLANT: REV. I SHT. crc-73 Ound cition 1 FILE NO: DWG, NO: 1 0 l op l CEC 0 7 3. 0134 CEC-73-134 CWE015.0107 l XCE-42-250 B.10 l-Revision 0 nutech l l A el' MIN. e u /iiii is%N!:ii !!!k f Vf/f//////////Ar /////////////////A i Pipe. Elbow b t q WELO i WELD OVERLAY l REPAlR DETAILS I t U. S. Patent Number 4,624,402 WELO NUMSER FLAW CHARACTERIZATION COMMENTS t A B 02H-S3 100% x 360 3.25" 2.0" 2.0" rull structural weld overlay l l M

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4C CM}/3/87 4/3/87 Initia1 Issue C2$f 0

.J*,?e#7 +/2/O Ya/t/ + PREP. SY/ CHK, BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./ REV. DESCRIPTION DATE DATE DATE DATE DATE JOB NO: PLANT: REV. I CEC-73 Quad Cities 1 SHT. FILE NO: OWG. NO: 1 0 OF CEC 073.0135 CEC-73-135 l CWE015.0108 XCE-42-250 B.ll Revision 0 nutech i i-l A 8 4 al' MIN. = TYP. p { /s s spQ;s gg. l:jQ s 7)fj9j'7/ffffffffk ffffff/jfffffffA_ i i Elbow Pipe' q WELO ) WELD OVERLAY REPAHI DETAILS j U. S. Patent i Number 4,624,402 i s WELO NUMBER FLAW CHARACTERIZATION COMME NTS t A B t 0 02H-S4 100% x 360 0.24" 2.0" 2.0" I'ull structural l' weld overlay i L l 9(f/

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/JJe#7 9'/A/f 7 t/1/t? 4j5l87 4/3/57 Initial Issue PREP, SY/ CHK, 8Y/ P.E. APPR./ E.M. APPRJ P.M. APPRJ REV' DATE DATE DATE DATE DATE MSCRIPTION (- JOS NO: PLANT: REV y CEC-73 Quad Cities 1 SHT. FILE NO: OWG. NO: 1 0 OF CEC 073.0136 CEC-73-136 CWE015.0109 i XCE-42-250 B.12 Revision 0 nutech 1 l s A 0 45 MIN. o //////// ////// ///// //////////$b $weepolet pipe -t I q,WELO j i ) WELD OVERLAY REPAIR DETAILS U. S. Patent Number 4,624,402 (1) EXTEND OVERLAY A$ FAR AS PRACTICAL TOWARD SWEEPOLET, HOWEVER "A" DIMEN$10N NEED NOT EXCEED 2.0" h i DESIGN DIMENSIONS WELD NUMBER FLAW CHARACTERIZATION COMME NTS t A s 02J-F6 100% x 360 3.21" (1) 2.0" rull structural l weld overlay l 1 fo/fggy [o/es/py

hg7 se/g7 %*//'/D i

Added Note 1 i likt/ MC

4c CM+ /37 cQ 4/3

+pM7 Initia1 Issue l 0 r.y.y4.g y Wa/g > v/t/g */ '" IT b AT BAT BAT DESCRIPTION "K " ^ " ' ^" CEV. O TE l JOS NO: PLANT; R E V-1 CWE-15 Quad Cities 1 SHT. FILE NO: OWG. NO: 1 1 op CWE015.Ollo CEC-73-137 CEC 073.0137 XCE-42-250 B.13 Revision 0 nutech l 1 A 3 0 45 MIN. TYP. p 1 1 [iji s ' iiiikk$i -i!!ik i s Vfffff/////////h/////////////////4 i Pipe. Elbow -- t kWELD WELD OVERLAY REPAIR DETAILS U. S. Patent l Number 4,624,402 b l DESIGN DIMEN$lONS WELD NUMdER FLAW CHARACTERIZATION COMMENTS t A 8 1 02J-S3 100% x 360 0.24" 2.0" 2.0" rull structural weld overlay ( l I t' i klt C W l$1 CWlSlU Mc

4C kl3 0

J >c.3 y &/yg3 t/a/r7 4 Initial Issue PREP. BY/ CHK, BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./ REV. DESCRIPTION DATE DATE DATE DATE DATE JOS NO: PLANT: REV CEC-73 Ouad citiet 1 FILE NO: DWG NO: 1 0 OF CEC 073.0138 CEC-73-138 CWE015.0111 l XCE-42-250 B.14 Revision 0 nutech -v- A e B = = FLOW 460 ggy, TYP p [j!!

ii8:!!!!%%:s liiih s

Vf//f/////////Aff/////////////A, L r Pipe Elbow -t ( WELD WELD _0VERLAY REPA1R DETAILS P.i.ni. poi..a vo, NOTE:

1) Flaw characterization:

4.25" x 55% cire. 0.6" x 30% cire. 2.0" x 30% cire. 1.B" x 30% cire. 1.6" x 304 cire. 3.0" x 30% cire. 9 axials (1.1" max. length) (all pipe side) DESIGN DIMENSIONS WELD NUMBER FLAW CHARACTERIZATION COMMENTS t A B 02J-S4 See Note 1 .235" 2.0" 2.0" Design based on 100% x 360' plus balance-of-plant life fatigue crack growth flaw assumption. c4/ 44 C CWh/ g c64e c RMyf 0 l '11*9 b J/J7/P6 t-17.B b i. tg. to t-17-% Initial Issue PREP. BY/ CHK. BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./ REV. DESCRIPTION DATE DATE DATE DATE DATE JOB NO: PLANT: P 3 V. I SHT. crr-47 ouma cition twit 1 o FILE NO: DWG. NO: OF CEC 047.0203 CEC-47-?03 XCE-42-250 B.15 Revision 0 nutech 1 1 l A 45 MIN. g 0 = TYP. p fi:ii s iiipQil. 'ti;ih f/////////////Ah/////////// Aft 25A, -t Sweepolet

pip,

( Weld U S PATENT NUMBER WELD OVERLAY REPAIR DETAILS Note: (1) Blend smoothly into sweepolet contour. Length need not exceed 2,25". WELD NUMBER FLAW CHARACTERIZATION COMMENTS t A 8 02K-r6 100% x 360' O.24" (1) 2.25" Standard WOR Design Wirs)/ Mc a/t c. OW7 0 //v73 q t/es/t 9

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t Lwy//f/83 7/19/8 3 Initial Issue 7

PREP. BY/ CHK. BY/ P.E. APPRJ E.M. APPRJ P.M. APPRJ R E V. DESCRIPTION DATE DATE DATE DATE DATE JOB NO: PLANT: REV XCE 42 OUAD CmES UNIT 1 1 ggy. FILE NO: OWG. NO: 1 OF XCE042.0115 XCE 42115 1 8YK?86 0102 XCE-42-250 B.16 Revision 0 i nutech j --.,u,;.. A B FLOW 0 = 45 gig. -j-m. TYP g l k [i!!585s i:i:::!:!:

a:iNii:

ilik l

s s V,//M///////////MffkMf//M///////M///A. h -t Elbow hpe ( WELD WELD OVERLAY REPAIR DETAllS P,ioni.ooo.a io, NOTE:

1) Flaw characterization:

1.6" x 25% cire. 0.2" x 25s circ. 0.B" x 15% cire. 8.0" x 24% circ. 5 axials (5/B" max. length) (all pipe side) WELD NUMBER FLAW CHARACTERtZATION COMMENTS t A B 02K-S3 See Note 1 .235" 2.0" 2.0" Desse based on 100% x 360' plus balance-cf-plant life fatigue tack growth flaw assumptior.. WI/ 4C C.W CMS 5.,. gag / 0 i.gl e ,/ z r /t. g.ty, g g,gg g i.11-gd, Initial Issue PREP BY' CHK. BY/ PE APPR EM APPR. PM APPR, D E SC A IPTION DATE DATE DATE DATE DATE JOB NO PLANT AEV CEC-47 Quad Cities Unit 1 g FILE NO DWG NO OF CEC 047.0204 CEC-47-204 XCE-42-250 B.17 Revision 0 nutech 2 1 1 4$o y,y, TYP y h I fiii! Siiiiisi!:! ilip%s!!:iii:! ijg j s s i /////A///////////////////////////) h Elbow pipe -t kWELD WELD OVERLAY REPAIR DETAILS U. S. Patent Number 4,624,402 'AELD NUMBER FLAW CHARACTERIZATtDN COMM E NTS t A B 02F-54 100% x 360 0.24" 2.0" 2,0" rull structural weld overlay @tyP use we CMJ cW7 0 /JJa3? &/a/g;

/a/gy 4/3/97 4/3/87 Initia1 Issue PREP. BY/

CHK. BY/ P E. APPM./ E.M. APPR./ P.M. APPR./ REV. DESC R

TION DATE DATE DATE DATE DATE JOB NO-PLANT REV 1

CEC-73 Quad Cities 1 SHT FILE NO: DWG.NO. ^ OF ~ CEC 0 7 3. 0141 CEC 73-141 Ch'E 015. 0112 XCE-42-250 B.18 Revision 0 nutech A B e 0 MIN. 45 TYP. p 4 ll [$ iiihk!!! liik V///////////////k///////////////////////4} PIPE gggow -t ( WELO U S. PATENT NUMBER WELD OVERLAY REPAIR DETAILS DESIGN DIMEN510NS WELD NUMBER FLAW CHARACTERIZAT-lON COMMENTS t A B 02L-S4 100s x 360' O.24' 2.25" 2.25" Standard O R Design 5fPf7.jj,pg W W ovt c wt c /,p/g p T/fg/g3 7/jg/99 Initial Issue 0 ,f,,j,9 3 PREP.BY/ CHK. BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./ EV DESCRIPTION OATE DATE DATE DATE DATE JOB NO: PLANT: REv XCE 42 QUAD CITIES UNff 1 SHT FILE NO. OWG.NO-1 XCE042.0116 XCE 42116 XCE-42-250 B.19 Revision 0 nutech L A '= ~ B i j< 45' min. TYP y f fu ~:' a}Qiy Q V///////MMffAffffffff//////A, Elbow -t

pip, t WELD WELD OVERLAY REPAIR DETAILS us.,u m ~.. us..e WELO NUMBER FLAW CHARACTER 12ATION COMMENTS t

A B 0:M-s3 1004 x 360' O.24" 2.25" 2.25" standard Weld Overlay Repair 0 %.84 1/*7/E 9 1in//-9 4W%% '~ "~ PREP. B; CHK. BY/ P.E. APPR./ E.M. 'APPRJ P.M. APPRJ REV. DESCRIPTION DATE DATF DATE DATE DATE JOB NO-PLANT: REV XCE-42 Quad Cities Unit 1 $HT I FILE NO DWG.NO. 1 XCE042.0106 XCE-42-106

* '" ; ' 02 XCE-42-250 B.20 Revision 0 nutech L

A B C Ago y,q j TyP y 4 / l I fili l% i 1sp4%i ~ s V//////////////////////$9h///////////////////////////] ~' Pipe Elbow ( WELD WELD OVERLAY REPAIR DETAILS vs,avntu..u..a UESIGN DIMENSIONS AELD NUMBER FLAW CHAR ACTERIZATION COMME N T S 02M-S4 100% x 360' O.25" 2.00" 2.00* standard weld overlay Repair I' etc

4(

[ f., C#(( 4 Cdf 2hange5 Weld over.ay ,~ //-7-19 '//L/89 u/a/P9 ' u-2. $$ N. 2. If Length 1 ( %(M

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~ g&& $py& Issued for Ctr.struct. 0 fr.f.g s s tats > wr/n y PREP BY' CHK BY/ DE APPR EM APPR - P. M A PP R p p OATE DATE DATE DATE DATE JOB NO PLANT AEv XCE-42 Ouad Cities Unit 1 SHT -L-FILE NO DWG NO 1 OF XCE04 2. 010 7 XCE-42-107 s v. u XCE-42-250 B.21 Revision 0 nutech W - ;L ' t ^ I (1) c z l. {% 45' MIN - l g \\ ////AAk:YHffA' Valve Pipe -t q YALD c: L Efd.D 0VERLAY Patent No. 4.624.402 REPAIR DETAILS e. Notes (1) Toe of overlay to blend smoothly into valve transition DESIGN DIMENSIONS WELD NUM8ER FLAW CHARACTERIZATION COMMENTS A t 02B-F1 100% x 360* 3.5" 0.37" Standard Weld

J i

Overlay Repair L

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sec ~5c -g c A w @///77 & CN F Issued for o 3 Construction [f,,f g / 7/9 kg Issued for Bids A n.g PREP. SY/ CHK. BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./ REV. [._ DATE DATE DATE DATE DATE DESCRIPTION JOB NO: PLANT: R E V. XCE-42 Quad Cities Unit 1

SHT, l

n 1 FILE NO: DWO. NO: 1 XCE042.0100 XCE-4 2-2 00 FMKT66 0101 XCE-42-250 B.22 nutech Revision 0 t p 'l j O = ..P NOTE ) b A - 46' MIN. L v d CROSS PIPE L I WELD OVERLAY f * REPAIR DETAILS i U. S. Patent Number 4,624,402 NOTE: Overlay to extend and' blend smoothly into cross, i i DESIGN DIMENSIONS i ~ WELD NUMBER FLAW CHARACTERIZATION COMMENTS t A 02B-57 100% x 360 0.37" 2.0" Full structural weld overlay l' 2- /0//Wty $@6)t7 $e/ts gy (*$ h/of/& $ eof ^ M @($/ op(y(,, Nge, M my /g y f/tv/37 Revised Cross Detailc 1 t/i7/g7 g fy. g7 4/,9/gy y,y @df/.py ate wec CM9 C%t .r.2o F/a/97 fA/f7 Al3/f7 4/3/87 Initial Issue 0 PREP. BY/ CHK. BY/ P.E. APPRJ E.M. APPRJ P.M. APPR./ ~ EV. DESCRIPTION i s. DATE DATE DATE DATE DATE JOB NO: PLANT: REV. 1 CWE-15 Quad Cities 1 SHT. FILE NO: DWG. NO: OF l CWE015.0100 CEC-73-127 CEC 073.0127 I XCE-42-250 B.23 Revision 0 nutech o ? .i A 8 e 0 MIN. 45 TYP p /!!!! !!!!%%$I !sk T///////////////////////A//////////////////////////A End Cap. Pipe' t t ( WELO WELD OVERLAY REP AIR. DET AILS U. S. Patent Number 4,624,402 l: DESIGN DIMENSIONS WELO NUM8ER FLAW CHARACTER 12ATION COMMENTS t A B 028-510 100% x 360 0.37" 2.0" 3.0" Full structural weld overlay l l CN9 ffj-fj 89914e NGC CaG C>G 1 4/ofg7_ f,y,g7 4/n/g7 4/,y/y7 4f,7/g7 Revised Overlay length %f 0 J.Jo-g? W/M87 t/M67 C2b%~ blN Age 69c CET A 4' Initial Issue PREP. BY/ CHK. BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./ R W. DESCRIPTION DATE DATE DATE DATE DATE JOB NO: PLANT: REV-CEC-73 Quad Cities 1 SHT. 1 FILE NO: DWG NO: OF 1 CEC 073.0128 CEC-73-128 CWE015.0101 XCE-42-250 B.24 Revision 0 A 8 '//i 45 MIN. 1 FLOW 0 2 m TYP. p l EXISTING - ( PIPE CLAMP [b ih%- -- - -$$$s

-k iAWWEf7/////////////////h ///////////////////4 PIPE TEE g-(FOR INFO. ONLY)

WELD OVERLAY RERAIR DETAILS u s.,m.a....... NOTE: (1) BLEND OVERLAY SMOOTHLY INTO TEE CONTOUR. LENGTH NEED NOT EXCEED 426* ~ WELO NUMBER FLAW CHARACTERIZATION COMMENTS t A 8 02BS-SS 1006 x 360' O.46" 2.75" (1) Standard weld overlay [2\\ Repair gg /s/g3 ,,/,3/g3 ,,/o/#g 4 4 g /,5/se q /eAm Incorporated pipe to 2 ro so clamp detail $n.qq N/<e/ *, 7/a/rp Nl:4/96 shg/r) b$3!!! 'O 1 0 c,.g4 $npp 1/nfoy AW% M9

**"*e ter con struetzen PREP.' 8Y/

CHK. BY/ P.E. APPRJ E.M. APPRJ P.M. APPRJ OATE DATE DATE DATE DATE DESCRIPTION JOB NO. PLANT: REV 1 XCE-42 Quad Cities Unit 1 SHT. IlLE NO: OWG NO: ~ OF 1 XCE04 2. 010 8 XCE-42-108 "" #" 0 ' 02 -XCE-42-250 B.25 Revision 0 nutech L i fl; ' t -A B 0 46 MIN, TYP. g o /$ fi!!M%!!! !!!!h s s Vllllllll///////////////Al//////////////////////////A, h a Pipe' Elbow ~' ( WELD WELD OVERLAY REPAIR DETAILS v.s. u n ur.........o, DESIGN DIMENSIONS WELD NUMBER FLAW CHARACTERIZATION OMMENTS l-t A B r 02BS-59 100% x 360' O.49" 4.5" 4.5" Standard Weld overlay l Repair l [ l v/s9 t/er/sef MS Thf$ Issued for construction 0 4 39 2 PREP. BY/ CHK. SY/ P.E. APPR./ E.M. APPR / P.M. APPR./ Y' DESCRIPTION DATE DATE DATE DATE DATE JOB NO PLANT; REV 1 .XCE-42 Quad Cities Unit 1 SHT 0 FILE NO: DWG. NO: 1 OF XCE 04 2. 0109 XCE-42-109 CMK T&6 C1 y; XCE-42-250 B.26 Revision 0 nutech -i A i 8 0 46 MIN. i fi!! Eisi!!!!!%Qi!!!s !!!!.A 'Mff//Af////////////////////A Pipe safe-End -t i Q. WELD i WELD OVERLAY REPAlR DETAILS 1-u.a. em ur ~. 4.u...e 1' l-l-

r OESIGN DIMENSIONS WELD NUMBER FLAW CHARACTERl2ATION COMMENTS t

A B 14A-F2 100%'x 360' O.22" 2.25" 2.25" standard Weld Overlay Repair ( { 1 b WGC +GC l' 0 2+ 8T 2/'MO

N f NI$

hM Issued for construction PREP. BY/ CHK, BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./ REV. DESCRIPTION DATE DATE DATE DATE DATE JOB NO. PLANT: REV XCE-42 Quad Cities Unit 1 8HI' l 0 FILE NO: DWG, NO: I OF XCE04 2. 0110 XCE-42-110 XCE-42-250 B.27 Revision 0 nutech l '] l t OVERLAP 1 BEAD MAX. - 45' MIN. U) SOCKOLET u \\ MM k WELD VALVE ELBOW Patent No. 4.624.402 WELD OVERLAY REPAIR DETAILS NOTE: (1) TOE OF OVERLAY TO BLEND SMOOTHLY INTO VALVE TRANSfTION l-WELD NUMBER PLAW CHARACT&M12ATION COMMENTS j A t 14A-F11 100% x 360' N/A 0.22" Standard Weld k overlay Reps r i l. M A/G( 4 N M Incorporated sockolot '1 10/tS}83 w//3/$9 tofs3/93 'Cf!S/O 'O/43/8J details Skry ag e wed. 44s AC## @ /c/ Sir CHF" Issued for 0 '56 s1 3/4/49 1/4/ e t 2/6/M '3 yy Construction N ac +4c f Q A -8 7 d 'i J//1/ff F /'7 / f'r h + Issued for Bids PREP. SY/ CHK. SY/ P.E. APPR./ E.M. APPR./ P.M. APPR./ [ AIV' DATE DATE DATE DATE DATE DESCRIPTION JOS NO: PLANT: REV. 1 XCE-42 Quad Cities Unit 1 SHT. 1 FILE NO: OWG. NO: l OP XCE042.0101 XCE-42-101 Fw786 0101 i xes-42-250 nutech a.28 Revision 0 I y. t:.: "i LL-c .n$ ,9 A-i go MIN. 8 = c TYP. p u /@il s!Eisis@%%l!li !!!k fl////fll/////////A////////////////////////b PIPE ELBOW q WELD p:1 WELD' OVERLAY REPAIR DETAILS Patent No. 4,624,402 1 x

l

\\ DESIGN DIMENSIONS I WELD NUMBER FLAW CHARACTER 12ATION COMMENTS l t A B 't 14A-se circumferential 1.5" 0.21" 1.75" 1.75" standard weld Overlay l long by 19% with Repair Associated Axial Coarponent ' C#9 N89 /*//3/03 t o/t3/G) W

G C.

04f lC CN7 Issued for construction 'Clt 'WA IWO/D 0 PREP. BY/ CHK. BY/ P.E. APPR./ E.M. APPRJ P.M. APPR./ R E V-DESCRIPTION DATE DATE DATE DATE DATE JOB NO: PLANT: REV XCE-42 Quad Cities Unit 1 FILE NO: DWG. NO: 1 0 OF XCE042.0117 XCE-42-117 XCE-42-250 B.29 Revision 0 nutech i. t 1 e { 9:.: i i At e ,450 MIN. 8 s t 1 TYP; y i [ E'* s !!!p*%!!!; !!!$ Wii!!!!h N' '//////////bW/////////A /////////////////////////// [ ~' Pipe Elbow. q WELO' j WELD OVERLAY REPAIR DETAILS-u.. un u r........., y %. ,. 7 i DESIGN DIMENSIONS WELO NUMBER - FLAW CHARACTERIZATION COMMENTS ? t A B 14A-S9 100% x 360* 0.21" 2.25" 2.25" Standard weld overlay Repair l &gy( 8T /2-sh7/s9 a/" /f f @Mk g%$ Mc me. 5 Issued for constru:ticn 0 PREP. BY/ CHK. BY/ ' P E. APPR./ E.M. APPR./ P.M. APPR./ DESCRIPTION OATE DATE DATE DATE DATE JOB NO: PLANT: REV 1 XCE-42 Quad Cities Unit 1 SHT. FILE-NO: OWG. NO. OF XCE042.0111 XCE-42-111 'W f 66 Ci 02 XCE-42-250 B.30 Revision 0 nutech s1 7. kQi ' (c A B i 45 MIN. 0 ~ ~ ~ TYP. p /hlL Ijh%%!! $k V////////////////////////h//////////////////////////l, Pipe Safe-End -t ( WELD W5LD OVERLAY REPAIR DETAILS u.s. mm %...sa...or I l i q DESIGN OIMENSIONS i ', WELD NUMBER FLAW CHARACTERIZATION COMMENTS (~ t A B 14B-F2 100% x 360* 0.27" 2.25" 2.25" Standard Weld overlay d Repair age

nec, 096J Changedoverlaythk.fSjiyji[msedstreu 1

7 6.$T t/sp/et v//p/t 9 ifl$k f19[$ kg ^ Cc u G C. g g 0 /24 97 s /s7/f t 2// >/ # 7 Mg Mg Issued for construction ~ PREP. BY/ CHK. BY/ P.E. APPR./ E.M. APPH./ P.M'. APPR./ DESCRIPTION OATE DATE DATE DATE DATE JOB NO: PLANT - REV f-XCE-42 Quad Cities Unit 1 SHT 1 FILE NO: OWG. NO: 1 OF XCE042.Oll2 XCE-42-ll2 XCE-42-250 B.31 Revision 0 nutech v. I '8 A i 0 45 MIN, -TYP p n ' gj:)

is:si:ii4sii: jj!pQjj ;i;;;!;g sh.

T//////////////////////A//////////////////////////, ~' Elbod Elbow ( WELD + _ WELD OVERLAY u REPAIR DETAILS u. un ~r ~..-...:...o i I I 4 DESIGN DIMENSIONS WELD NUMBER FLAW CHARACTERIZATION COMMENTS t A B .14B-58 100% x 360' O.21" 2.25" 2.25" Standard Weld overlay-Repair 0 M 84 7/d 9 /0/G?

fW

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PREP. BY/ CHK. BY/ P.E. APPRJ E.M. APPRJ P.M. APPR./ DESCRIPTION DATE DATE DATE DATE DATE JOB NO: PLANT: REV I XCE-42 Quad Cities Unit 1 SHT FILE NO: DWG. NO: ~ OF 1 XCE04 2. 0113 XCE-42-113 svnfa6010; XCE-42-250 B.32 Revision 0 nutech k, i:: A_ L g i 0 = 7 3 45 MINJ n fijii

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!!!F ' :.::d@!;.. s. $!A i VS////////////////////A /)$$/////////////////E Pipe-Elbow -t ( WELD WELD OVERL A.Y REPAIR DETAIL 8 u s. u n ur ~.. u 24.e ( WELD NUMBER FLAW CHARACTER 12ATION COMME NTS I t A B 10BD-S13 100% x 360' O.27" 2.5" 2.5" Standard Weld overlay Repair 0 .#9 fe,/s, 2,,/#9 $N 34lS$ Isud f or constmtion PREP.BY/ CHK. BY/ P.E. APPR./ E.M. APPR./ P.M.' APPRJ REV. DESCRIPTION DATE DATE DATE DATE DATE JOB NO. PLANT: I REV 1 XCE-42 Quad Cities Unit 1 SHT. OC o FILE NO-OWG. NO: OF 1 XCE042.0102 XCE-42-102 sw rae ci a: XCE-42-250 B.33 Revision 0 nutech p r l Appendix C SUSTAINED STRESSES AT UNFLAWED WELD LOCATIONS o. l \\; l ( t XCE-42-250 C.0 Revision 0 nutech .------.-.-__--_~a-_-----u-._---,.--u- - - - - - - - - -.. - ~ _

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F Table C-1 .+ OUAD CITIES UNIT 1 SUSTAINED STRESSES REACTOR RECIRCULATION SYSTEM-C SUSTAINED RATIO WELD STRESS TO NO. PSI Sm i 02AS-F1 7042 0.42 02AS-F2' 7042 0.42 02AS-S3 6998 0.41 02AS-S4 6954 0.41 02AS-F5 6952 0.41 02AS-S6 6996 0.41 02AS-F8 6978 0.41 1 02AS-F9 6965 0.41 'l 02AS-S12 6761 0.40 I 02AS-F14-6733 0.40 -l 02AS-S15 6713 0.40 02AD-F12 6971' O.41 02AD-F9 7122 0.42 02AD-F8 6675 0.39 02AD-S6 6594 0.39 02AD-S2 6960 0.41 02AD-F1 7009 0.41 02BS-F1 12868l 0.76 02BS-F2 12868l 0.76 02BS-S3 11105l 0.66 b 02BS-F4 111031 0.66 i 02BS-F7 l 8921 1 0.53 02BS-S9 I 77431 0.46 02BS-S12 l 7567i 0.45 02BS-F14 i 76761 0.45 02BS-S15 I 8208I 0.48 .XCE-42-250 C.1 Revision 0 nutech V I 2 i Table C-1 OUAD CITIES UNIT 1 SUSTAINED STRESSES-REACTOR RECIRCULATION SYSTEM (Continued)- r SUSTAINED RATIO WELD STRESS TO l NO. PSI Sm 02BD-F12 8957 0.53 02BD-F9 9045 0.53 02BD-F8 8688 0.51 02BD-S6 8388 0.49 02BD-S2 11323 0.67 02BD-F1 11395 0.67 02B-F6 7922 0.47 02A-F1 8652 0.51 -02A-S3 l 9366 0.55 02A-F5 10551! 0.62 02A-S9 6290 0.37 02B-F5 l 13608 0.80 1 02-F1 8018 0.47 02-F1D 8303 0.49 02-F1E 8303 0.49 02-F2 1 8116 0.48 } f 02C-F1 1 7133 0.42 02C-F2 l 12569 0.74 (i. _02C-F6 l 13035 0.77 j l020-F1 i 9857i 0.58 l 020-F2 i 16608{ 0.98 j 020-F6 l 12789I 0.75 1 02E-F1 80241 0.47 02E-F2 14257I 0.84 02E-S3 l 11602i 0.68 02E-S4 i 8774i 0.52 I 02E-F6A I 11298I 0.67 02E-F6 i 129321 0.76 ( I XCE-42-250 C.2 1 Revision 0 l g Table C-1 OUAD CITIES UNIT 1 SUSTAINED STRESSES b REACTOR RECIRCULATION SY M (Concluded) a SUSTAINED RATIO WELD STRESS TO' NO. l PSI Sm 02F-F1 7007 0.41 02F-F2 12333 0.73 02F-F6 8320 0.49 02G-F1 7801 0.46 102G-F2 13836 0.82 10iG-F6 11385l 0.67 l 02H-F1 73241 0.43 02H-F2 12933 0.76 02H-F6 l 13913 0.82 02J-F1 l 7845-0.46 02J-F2 i 13918 0.82 02K-F1 8360 0.49 02K-F2 14892 l 0.88 02K-F6 14155i 0.84 02L-F1 4720 0.28 02L-F2 8001 0.47 02L-S3 - l 7262; 0.43 02L-S4 I 7340! 0.43l 102L-F6 I 9615: 0.57 l j02M-F1 1 6225i 0.37 l 02M-F2 I 108501 0.64 02M-F6 1 107321 -0.63 f 02M-F7 i 10732l 0.63 4031-5-A7I 41731 0.25 4031-5-A8I 41731 0.25 4031-5-A51 4173 i 0.25 4031-5-A6I 4173 i 0.25 l !4031-5-831 4173' O.25 ' !4013-5-B4i 4173l 0.25 ! 14031-5-B1l 41731 0.25 l l4031-5-B2l 41731 0.25 l XCE-42-250 C.3 Revision 0 nutech t Table C-2 OUAD CITIES UNIT 1 SUSTAINun STRESSES SHUTDOWN COOLING SYSTEM SUSTAINED RATIO WELD STRESS TO NO. PSI Sm 10S-F1 15697 0.92 10S-S3 14443 0.85 10S-S4 16122 0.95 10S-F5 15834 0.93 10S-F6 16641 0.98 10S-S7 16719 0.99 10S-F8 16948 1.00 10S-S9 15744 0.93 10S-S11 15568 0.92 10S-S12 16219 0.96 10S-F13 8930 0.53 [' I C 4 i XCE-42-250 C.4 Revision 0 nutech L i l. u Table C-3 OUAD CITIES UNIT 1 SUSTAINED STRESSES RHR LINES iSUSTAINED RATIO WELD STRESS TO NO. PSI Sm BLOOP PEN X-13B 12634 0.75 10BD-F16 9495 0.56 10BD-F15 8882 0.52 10BD-S13l 11186 0.66 10BD-S12 11363 0.67 10BD-F11 8308 0.49 10BD-S10 8292 0.49 10BD-F9 9811 0.58 10BD-S8 12106 0.71 .10BD-S7 12657 0.75 10BD-F6 11488 0.68 10BD-F5 12907 0.76 10BD-S4 14650 0.86 10BD-S3 15093' 'O.89 10BD-S2 15470 0.91 10BD-F1 16504 0.97 A LOOP 10AD-F1 17061 1.00 10AD-S3 14428 0.85 10AD-F4 14820 0.87 10AD-F5 l 14278 0.84 10AD-S6 l 16160l 0.95 10AD-S7 l 13916 0.82 10AD-S8 i 9941 0.59 10AD-F9 I 13626 0.80 10AD-S10l 11420 0.67 10AD-F12l 9250 0.55 10AD-F131 14503 0.86 PEN X-13Al 12569 0.74 l XCE-42-250 C.5 Revision 0 nutech a p o Table C-4 OUAD CITIES UNIT 1 SUSTAINED STRESS $S CORE SPRAY SYSTEM SUSTAINED RATIO WELD STRESS TO NO. PSI Sm 14 A-F1 16236 0.96 -l 14A-F3R 16097 0.95 14 A-F4AR 15311 0.90 14A-S4AR-15184 0.90 14A-S48R 15035 0.89 l 14 A-F4CR -15035 0.89 14A-S4DR 15035 0.89 14 A-F4ER 14604-0.86 14A-F6 13584 0.80 14A-F7 15612 0.92 14A-F12 12180 0.72 14A-F12A 12092 0.71 14A-S13 9101 0.54 14A-S14 8688 0.51 14A-S15 13007 0.77 l 14A-F17 14206- - 0.84 14 B-F1 16820 0.99 14B-F4R 16741 0.99 148-F5R 16442 0.97 14B-SSAR 16663 0.98 14B-FSBR 16745 0.99 i 14B-F6AR 15022 0.89 148-F7 16786 0.99 148-S9 12344 0.73 148-S10 9977 0.59 148-F12 10564 0.62 148-F13 10751 0.63 \\,. 148-S14 14672 0.87 14B-F15 15201 0.90 s I XCE-42-250 C.6 Revision 0 nutech g. I; m i Table C-5 OUAD CITIES UNIT 1 SUSTAINED STRESSES REACTOR MATER CLEAN-UP SYSTEM SUSTAINED RATIO WELD STRESS TO NO. PSI Sm I I 12S-S1 13581 0.80 12S-F3R-10666i 0.63 12S-F2R 10666 0.63 12S-F4R 10194 0.60 12S-F4 AR 10194 0.60 12S-F4CR 8080 0.48 12S-S4DR 6025 0.36 12S-SSR 6765 0.40 i 12S-F6R 9813 0.58 12S-S6AR 12717 0.75 12S-S7R 12804 0.76 i~ 12S-S8R 10724 0.63 12S-S9R 10614 0.63 l 12S-S9AR 10227 0.60 12S-F10R 8673-0.51 12S-S11R 8851 0.52 12S-S12R 8545 0.50 12S-S13R 9949 0.59 I. 12S-S14R 9918 0.59 12S-S15R 8108 0.48 12S-S16R 7765 0.46 12S-S17R 9328 0.55 12S-S18R 9049 I 0.53 12S-S19R 7624 0.45 -i I 12S-F20R 7162 0.42 1 12S-F21 R 7168 0.42 12S-F22R 7565 0.45 12S-F23R 7950 0.47 XCE-42-250 C7 i Revision 0 l d p- );. .s-- l[ Table C-6 r I ^ OUAb CITIES UNIT l_ SUSTAINED STRESSES CRD RETURN LINE t' 1; '/: SUSTAINED RATIO WELD STRESS TO _N O. PSI Srn 03-F8 5606 0.33 (: 03-F7-6659 0.39 03-F6 7000 0.41 03-F5 11974 0.71 k.- 03-F4 11974 0.71 03-S3 11490 0.68 03-S2 12304 0.73 5 03-F1 16191 0.96 03-F1A 16191 0.96 F \\ XCE-42-250 C.8 h Revision 0 nutech C u}}

ML20005E121

Contents

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