ML20210J001

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Non-proprietary Rev 1 to BAW-10219, Electrosleeving Qualification for PWR Recirculating SG Tube Repair
ML20210J001
Person / Time
Site: Callaway Ameren icon.png
Issue date: 03/31/1996
From:
BABCOCK & WILCOX CO.
To:
Shared Package
ML19317C595 List:
References
BAW-10219, BAW-10219-R01, BAW-10219-R1, NUDOCS 9708140300
Download: ML20210J001 (192)


Text

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l BAW 10219 ,

REV.01 MARCH 1996 ELECTROSLEEVING QUALIFICATION FOR PWR RECIRCULATING STEAM GENERATOR TUBE REPAIR l <

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NON-PROPRIETARY l

i FRAMATOME TECHNOLOGIES, INC.

P.O. BOX 10935 LYNCHBURG,VA 24506-0935 COPY NO.  !

l 9708140300 970800 l PDR ADOCK 05000483 1

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f FTl NON PROPRIETARY This document is the non-proprietary version of the proprietary document BAW-10219P-00. In order for this document to meet the non propri-tary criteria, certain blocks of information were with-held based on the following criteria.

(b) The information reveals data or material concerning FTl research or i development plans or programs of present or potential competitive advantage to FTI.

4 (c) The use of the information by a competitor would decrease his ,

expenditures, in time or resources, in designing, producing or. l marketing a similar product. '

(d) The informtion consists of test data or other similar data J concerning a process, method or component, the application of ,

which results in a competitive advantage to FTI.  ;

(e) The information reveals special aspects of a process method,

, component or the like, the exclusive use of which results in a '

1 competitive advantage to FTI. ,

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BAW 10219--

REV 1 MARCH 1996 l

ELECTROSLEEVING QUALIFICATION FOR PWR RECIRCULATING STEAM GENERATOR TUBE REPAIR i

a FRAMATOME TECHNOLOGIES, INC.

P.O. BOX 10935 LYNCHBURG, VA 24506-0935 g - ,- ,- -

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FTl NON PROPRIETARY This document is the non proprietary version of the proprietary document BAW-10219P-00. In order for this document to meet the non-proprietary critoria, certain blocks of information were with held based on the following criteria.

(b) The information reveals data or material concerning FTl research or development plans or programs of present or potential competitive advantage to FTI.

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-(c) The usa of the information by a competitor would decrease his expenditures, in time or resources, in designing, producing or .

marketing a similar product.

(d) The informtion consists of test data or other similar data concerning a process method or component, the application of which results in a competitive advantage to FTI. j (e) The information reveals special aspects of a process method, component or the like, the exclusive use of which results in a competitive advantaga to FTI.-

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i RECORD OF REVISION Heyision Dain Section Descriotion 00 11/95 All Original Issue 01 03/90 All Complete revision.

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TABLE OF CONTENTS PAGE

1,0l INTRODUCTION - 1-1 i

.2.0i- EXECUTIVE

SUMMARY

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' 3.0 - BACKGROUND. 31'

4.0L - DESIGN CRITERIA A-1' T

4.1 : - Qualification Methodology - 4 4.2 , Qualification Requirements ~ 4-3

4.3- Sleeve Design Conditions 4-3 5.0 -- SLEEVE DESIGN 51

-5.1- Design Description 51' 5.2- Process Description 51 1 6.0 _ DESIGN VERIFICATION - MATERIAL PROPERTIES - 6-1 6.1 Tensile Strength _ 61 6.2 Modulus of Elasticity '62 6.3y Ductility / Adhesion 62 6.4 Fatigue Life - 63 6.5 _ Thermal Stability 6-4 6.6 Creep Properties 6-5 6.7 Burst Strength 6-9 6.8, Thermodynamic Properties 69 z 7.0 DESIGN VERIFICATION - MECHANICAL PROPERTIES 7-1 Locked Tube Testing 7-1

- 7.1 27.2 Fatigue Testing 7-2

- 7.3 Testing of Degraded Sleeves 7-4

-7.4 Creep-Fatigue Experimental Analysis 7-6

. 7.5 Mechanical Testing Summary 7-7 8.0 DESIGN VERIFICATION - ANALYSES 8-1 s

8.1L Pressure Boundary Thickness 8-1 8.2- - Fatigue Test Loads 82 8.3 - - Flow-induced Vibration? 85 8.4- ' Thermal / Hydraulic -

8 L 8.5 Sleeve Plugging Criteria 86

, 8.6 Creep Analysis 8-7 i8.7. Design. Summary. ' 8 12 4 _

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IARLE_QF CONTENTS (Cont'dl PAGE 9.0 ~ DESIGN VERIFICATION - CORROSION 91 9.1 General Corrosion Properties 91

. 9.2 Primary Side Corrosion Evaluation 97 9.3 Secondary Side Corrosion Evaluation 9 17 9.4 Nickel Electroplating Operating Experience 9 31.

- 9.5 Corrosion Evaluetion Summary 9 32 10.0~ SLEEVE INSTALLATION 10 1 10.1 Installation Procedure 10-1 10.2 Process Verification 10 3 10.3 Instal'ation System / Tooling 10 3 10.4 ALARA 10-4 10.5 Sleeving Experience 10 5 11.0 NONDESTRUCTIVE EXAMINATION 11-1 11.1 Ultrasonic Testing Background 11 1 11.2 UT Defect Qualification Program 11-2 11.3 Eddy-Current Testing 11-8

12.0 REFERENCES

12 1 Appendix A PWR DESIGN INFORMATION A-1

-1 FRAMATOME TECHNOLOGIES, INC. ii

LIST OF TABLES PAGE 3.1 SG Nickel Plating and Electrosteeving Experience 3-4--

4.1 1 Summary of Applicable Codes and Standards - 4-5 5.1.1 Steam Generator Tube and Electrosleeve" Nominal Dimensions 54 6.1.1 ASME Code, Section lli Design Values 6 10 6.6.1 _ Creep Test Specimens 6 11 6.7.1 FTl Burst Test Results at Room Temperature 6 13 6.7.2 OHT Burst Test Results at 581*F - 6 14 7.3.1 - Plugging Criteria Fatigue Test Specimens 78 7.3.2 Plugging Criteria Burst Specimens 79 8.1.1 Primary Membrane Stress Intensity Range 8 14 8.2.1 Summary of Fatigue Test Load Ranges 8 15

. 8.2.2 Circumferential Defect Fatigue Test Loads 8 16 8.2.3 Axial Defect Fatigue Test Loads 8 19 8.3.1 Sleeve FIV Analyses Results 8 20 8.4.1 Thermal / Hydraulic Effects of Steeves in 3/4" Tubing 8-21 8.4.2 Thermal / Hydraulic Effects of Sleeves in 7/8" Tubing 8 22 8.5.1 Sleeve Plugging Limits 8-23 8.6.1 Total Creep Strain for Electrosteeve* Installed in the Tube Fres Span 8 25 8.6.2 Creep Strain for Electrosteeve Installed at Top of Tubesheet 8 27 9.1.1 Summary of Literature Survey Nickel and Alloy 600 General Corrosion Rates in Various Environments 9-34 9.2.1 Primary Side Matrix Chemistry 9-35 9.3.1 Secondary Side Matrix Chemistry 9 36 9.3.2 Secondary Side Capsule Test 9-37 FRAMATOME TECHNOLOGIES. INC. iii --

LlSI.OETABLESJCont'd)

PAGE 10.4.1 Sleeve ALARA Evaluation (100 sleeves) 10-8

-11.1 - Summarized UT Results of Bond /Unbond 11 5

' A.1 -- W D Design information A2 A.2- W E Design Information

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A.3-- CE SYS 80 Design Information A 10 -

A.4 Westinghouse 7/8" Tubing S/G Design Information A 13 A.5 ~ Combustion Engineering 3/4" x .048' S/G Tubing Design Information A 18 A-6 W F Design Information A 25 t

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t UST OF FIGUME PAGE (5.1.1' Typical RSG TSP and TS Sleeve Arrangement 5-3 6.1.1 Material Test Specimen Designs 6-15 6.1.2 Typical Tensile Properties vs Temperature 6 18 6.3.1 Reverse Bend Specimen 6-19  ;

6.4.1 Fatigue Test Data 6 20 6.5.1 Thermal Stability Test Result @ 650*F 6 21 6.6.1 Creep Tect Results 6 22 6.6.2 Typical Creep Fracture Surface Fractography 6 23 7.1.1 Mechanical Test Specimen Designs 7 10 1

-7.2.1 Typical Locked Tube Mockup Test Rig 7 13 8.6.1 Creep Strain v/s Time 8 28- ,

8.6.2 Tube Defects Modelled in Creep Analysis 8-29 8.6.3 ANSYS v/s Creep Test Data 8-00 8.6.4 Creep Rupture Time Predictions 8-31 8.7.1 Pressure Boundary 8-31 9.3.1 Secondary Side Capsule Tests 9 38 9.3.2' Capsule Furnace Setup 9-39 9.3.3 Capsule Testing For Faulted Secondary Side Environments d-40 9.3.4 Refreshed Autoclave Loop 9-41 9.3.5 Steam Generator Electrosteeved Tube Mockup For Sludge and Faulted Chemistry Tests 9-42

--9.4.1 Electroplated Tubes Pulled From Doel 2' 9-43 10.3.1 Electrosteeve* Ir stallation System Schematic 10-6 10.5.1 Electrosleeve* Installation Experience 10-7 FRAMATOME TECHNOLOGIES, INC. V-

LIST OF FIGURES (Cont.d.)

11.1 UT Wave VEE Path 11 6-11.2 Regions of a Nickel Sleeve for UT Qualification Testing 11 7-

-11.3 Detection of 20% Circumferential EDM Notch in Mid Sleeve 11 9 I

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GLOSSARY OF TERMS AECB Atomic Energy Control Board ANSI American National Standards institute ASTM American Society of Testing Materials ASME B&PV American Society of Mechanical Engineers, Boller and Pressure Vessel Code AVT All Volatile Treatment BOL Beginning of Life FTl Framatome Technologies, Inc.

CBH Contoured Bottom Hole CE SYS 80 Combustion Engineering System 80 RSG CSA Canadian Standards Association DBE Design Bases Event EC Eddy Current ECT Eddy Current Testing EDM Electrode Discharge Machining EOL End of Life FBH Flat Bottom Hole FIV Flow-induced Vibration FSM Fluid elastic Stability Margin FTl Framatome Technologies incorporated god Gallons Per Day HMA High Temperature Mill Annealed ID inside Diameter IGA Intergranular Attack IGSCC Intergranular Stress Corrosion Cracking LL Lower Loop (B&W Plant Design)

LMA Low Temperature Mill Anneal LOCA Loss of Coolant Accident  ;

LOW Lake Ontario Wate:

MCCR Ministry of Consumer and Commercial Relations MgCI, Magnesium Chloride MSLB Main Steam Line Break NaOH Sodium Hydroxide NDE Nondestructive Examination NDD No Detectable Degradation NGS Nuclear Generating Station nm nano-meter (104 meter)

OBE Operational Base Earthquake FRAM ATOME TECHNOLOGIES, INC. vii

b GLOSSARY OF TERMS (Cont'd) <

OD. Outside Diameter OTSG Once Through Steam Generator P Phosphorous .

Pw.c . Internal Butsi Pressure Pg., External Collapse Pressure PVT Process Verification Tube Pump Curve Relationship of Fump Volumetric Flow Rate and Discharge Head PWR Pressurized Water Reactor PWSCC Primary Water Stress Corrosion Cracking -

RL- Raised Loop (B&W Plant Design)

RPC Rotating Pancake Eddy Current inspection Coil RSG Recirculating Steam Generator .

RT Room Temperature SCC Stress Corrosion Cracking SI Safety injection S. Allowable Stress Intensity SSE Safe Shutdown Earthquake Su Ultimate Tensile Strength S, Yield Strength SPS Sleeve Procedure Specification TS Tubesheet TW Throughwall

-TSP Tube Support Plats TTS Top of Tubesheet UT= Ultrasonic Testing W D- Westinghouse Model D RSG W-E Westinghcuse Model E RSG WT Witness Tube

%TW_ Percent Through Wall l

- FRAMATOME TECHNOLOGIES, INC, viii S

h 1.0 '- - INTRODUCTION The quelificatini) program of an electroformed t.leeve for the repair of PWR Recirculating-4 Steam Generators (RSGs) with degradad Alloy 600 tubing is described in this report. The Electrosteeve*"' has been qualified for the major RSG designs, including Westinghouse Models D, E, F, 33, 44,' arid 51, and Combustion Engineering RSGs. This report documents the design analyses, mechanical testing,' corrosion evaluation, nondestructive examination, installation process, and ALARA aspects of the sleeve design. ,

Sleeving is a method used to repair defective steam generator tubes and thus keep the tubes !n service. Typically, sleeves have been designed with welded, brazed, rolled, ar.d/or hydraulically expanded sleeve-to tube joints. The design emphasis for sleeves is  ;

now focused on repair methods that impart minimal residual effects on the parent tube.

[ The electroformed sleevo is the next generation of SG repair which requires no " welding" or deformation of the parent tube, while providing the benefits of previous sleeve repair options.

E The nickel utilized in the repair process, once deposited, is referred to as a nanostructured 4 material. Nanostructured sleeve material consists of a grain structure having ine.tn diameters less than 300 nm, and as a result possesses unique properties, including enhanced corrosion and wear properties, along with enhanced hardness, strength and ductility. The ultra fine [ }" microalloyed grain structure of the (> 99.5%

pure) electroformed nickel provides outstanding mechanical properties that exceed conventional nickel plating.

An electroformed sleeve generically refers to the electrochemical deposition of ultra-fine grained nickel on the inner surface of a tube to form a structural repair of the degraded tube. The electrodeposition of nickel provides a continuous metallurgical bond between the tube and sleeve that eliminates allleak paths and macro-crevices. The electroformed slee'.e provides a structural,' leak tight seal, while minimizing residual stresses in the parent tube. It results in no parent tube deformation or microstructure changes._ Thus, the design does not require a post-installation stress relief. Since the e;ectroforming of the nickelimparts very low stresses on the parent tube, there is no need for stress relief, therefore installation into locked steam generator tubes is not a concern.

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(1)_ Electrosteeve is a registered trademark of Ontario Hydro Technologies.

FRAMATOME TECHNOLOGIES, INC. 11

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- Revisiori 01 of this document (this revision) is being issued to include qualification data

- on RSGs with 11/16" OD x 0.040" wall tubing.:> This revision also incorporates tbs latest =

testing and analysis information available on the Electrosleeve*, ,

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2.0 - . EXECUTIVE

SUMMARY

lThe material properties of the ultra-fine grained nickel sleeve have been characterized by testing as described in the ASME Section ill Appendices and ASTM specifications. The material properties established include tensile,-yield, modulus of elasticity, thermal stability, creep, ductility, and f atigue.- These properties were utilized during the sleeve analyses and mechanical qualification tests.

Mechanical _ testing was performed on the sleeve design to demonstrate its structural adequacy. This testing included axial f atigue, pressure, thermal, tensile tests, and primary hydrotests to burst pressure, in addition, sleeves with machined defects were put through fatigue tests and burst tests to show that a degraded sleeve still maintains structural  ;

integrity as a replacement for the parent tube.

Structural ana!yses performed included f atigue test loads (uniaxial and bending), ASME B&PV Code stress analysis, plugging criteria analysis, flow induced vibration analysis,

thermal / hydraulic analysis, and creep analysis.

Corrosion tests have been performed to evaluate the Electrosleeve* material's performance in primary and secondary water environments. Nickel plating has been utilized in operational applications as a means to repair and prevent PWSCC. Inservice experience in steam generators in Belgium, Sweden, and Canada, and in the pressurizer heater nozzles at Calvert Cliffs (12.37) reinforce the basis that electrodeposited nickel is resistant to corrosion and degradation in actual service environments.

Based on the testing and analysis documented in this report, the electroformed sleeve has been structurally qualified for application in PWR %cuculating steam generator designs.

Section 8.7 of this report provides a summary of key design aspects of the sleeve.

FRAMATOME TECHNOt.OGIES, INC. 21

3.0 BACKGROUND

Most early design PWR steam generators were fabGcated with tubing made of Ni-Cr ro Alloy 600. In general, the tubing in these steam generators is low mill annealed (LMA).

The tubes are typically expanded for Idngths ranging from 2" to the full thickness of the tubesheets (TS).

The cracking of LMA tubes due to high tensile stresses was identified in the late 1970s and early 1980s. Intergranular stress corrosion cracking (IGSCC) has occurred in Row 1 U-bends and in the expansion roll transitions of tubing expanded into the tubesheet. Shot peening (12.81 and U-bend stress relief [12.91 were developed as corrective measures for plants characterized as having high potential for IGSCC. The French and Belgians were the first to report that shot peening, as a corrective measure, was less effective on plants which had been in operation (12.101. This was attributed to the presence of small cracks (below the MDE detection capabilities) that had initiated prior to the peening operation.

Thus, other repair methods are required to keep tubes in service.

Subsequent to this, plants began experiencing degradation by ODSCC at both roll and explosive expansion transitions. There has also been the emergence of secondary side corrosion at the TSP intersections. The various degradation modes have expanded to now include high mill annealed (HMA) tubes as well.

These degradation mechanisms led to the development of numerous types and designs of sleeves in the industry. The overall objective of these designs is to provide a structural repair to the tube, spanning the degraded region of the tube. The typical sleeve design has been the tube-within-a-tube concept, with structural icints formed by various means at each end of the sleeve. Joints have been both nicchanical (leak limiting) and welded (leak tight) in these types of sleeves.

Since the original installation oi many of these sleeves, tubes have been found to be locked at the tube support plates, in some plants, due to the buildup of corrosion products or other mechanisms. This locked tube condition severely impacts the ability to perform an effective stress relief of tube-sleeve joints that have high installation residual stresses, and may lead to severe local yielding or buckling of the tube or a redistribution of residual stresses without expected reduction.

FitAMATOME TECHNOLOGIES, INC. 3-1

FTl, in cooperation with Ontario Hydro Technologies, has now developed an electroformed sleeve which offers an alternative solution to repairing Alloy 600 tubes experiencing degradation at the top of the TS, as well as the TSPs. This process deposits a layer of electroformed nickel on the inside diameter of degraded tubes in order to provide a structural, leak tight repair option that is simple to install and requires no stress relief.

This sleeve will span defects within the tube at the baffle plates, the tube support plates, at or_near the secondary face of the tubesheet and in freespan regions in PWR steam generators.

This repair process builds on previous experience with nickel plating and Electrosleeving.

Framatome (Europe) has been using nickel electroplating as a remedial technique for the repair of primary stress corrosion cracking (PWSCC) of steam generator tubing since 1985. The primary goal of this technique is to deposit a layer of nickel plating capable of bridging SCC in a SG tube, thereby arresting the degradation process of the tube wall.

This process has also been used to seal the roll transition area and thereby prevent the initiation of PWSCC; some of these repairs were performed over through wall flaws. EPRI has documented this successful repair of European steam generator tubes affected by PWSCC with electroplated nickel [12.12). Since 1985, Framatome has successfully installed electroplated nickelin more than 1,000 tubes at various plants in Europa As of today, over 95% of these electroplated nickel sleeves are still inservice and exhibit no compromising degradation or cracking. A small percentage of tubes have been plugged since the first large commercial application in 1988 at Doel 2, but none were due to any defect or degradation of the nickel sleeving, j Ontario Hydro (OHT) has also successfully installed Electrosleeves into various steam generators in the Pickering plants. Initially, sleeves were installed as part of the development phase and were either plugged or the tubes pulled for evaluation, in May

'1994, fourteen Electrosteeves" were installed in Pickering Unit 5 and left in service.

Subsequent inspection has indicated no degradation in these sleeves. Refer to Table 3.1 for a summary of Framatome nickel plating and Ontario Hydro Electrosteeving experience

. . In operating steam generators, in 1995, FTl installed S Electrosteeves"in one steam generator at Oconee Unit 1. These ,

sleeves were installed as part of the development program to gain experience with the sleeving equipment and field procedures. All of the sleeves were successfully installed.

Those tubes were subsequently plugged since the Electrosleeve* was not licensed at that

~ time.

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in regards to terminology, Efectrosteeve

. specifically refers to nanocrystalline

. microalloyed nickel electrochemical deposited sleeve material. Electrosteeving material has .

the high strength and thermal stability to qualify as-a structural repair. - Nickel plating refers to the process currently being used in Europe which utilizes a thin (~ 0.004 inch) layer to either prevent PWSCC or form a protective layer over existing PWSCC to inhibit further growth. Nickel plating is also high purity nickel, but is not nanocrystalline in nature, nor is it microalloyed for thermal stability. Nickel plating as currently used in Europe is not used for a structural repair.

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Table 3.1 Steam Generator Nickel Platina and Electrosfeevino Exnerience PLANTNENDOR YEAR TUBE TUBES ACTIONS COMMENTS NI-PLATED STILL TAKEN IN-SERVICE Doeb2 1985 to 1 3 plugged. 3 puned. R&D field basehrw program; tanye throughwas cracks; some leaked due to micro nickel pes; tab (Framatome) ] and 3 repa' red (1990) eram resutts' bndged craas, no intemat corresson Doeb2 1986 81 56 13 plugged 3 puFed. R&D reld casehne prog am; large throughwas cracks; some leaked due to ruckel hardness (nickel (Fierr60.. e) and 9 repared (1990) cracked over Alloy 600 cracks > 0 39 mch)

Doel-2' 1988 33 33 First commercial appiicaten; large throughwau cracks; visual bW,e en 1988,1989, and 1990 (Frarretome) with a 40X baiew; condusions: no leaks. no visNe corw. no erosson Doe 03" 19S8 11 11 Large throughwall cracks in parent tuting; UT inspected in 1988 (basehne).1989.1990, and 1991; (Framatome) condusion: cradts have not propagated into necuel p abng Reghals-3" 1990 10 10 UT (long. and circum.) basehne in 1990 to quady UT relatiec to ET; UT 1991 and 1992 (Framatome) cordusion cracks have not propagated Doel-2* 1990 345 337 8 plugged (not related Local rearxpansion (2 inches) in the tubesheet enbrety pro *ected by Ni-platmg on 4 inches (2 rnils (Framatome) to ndet plating) th ck); visual and ET inspected in 090 (basehne)

Tihange-2' 1992 602 602 Plating en parallel on all three S/Gs (Framatome)

Pickenng4 May 1 0 Trial run of Electrosleeve . Process not approved yet by AECB and MCCR so tubes plugged (OHT) 1993 Pdenng-8 October 9 0 9 Electrosleeves"instafled b BOS and B011, Process not approved yet by AEC8 and MCCR so (OHT) 1993 tubes plugged Pickenng-1 Nov 8 0 6 Electrosleeves" installed n 3 tubes. 3 sleeves unacceptable due to desbonded areas. Process (OHT) 1993 not approved ye* by AECB and MCCR so tubes plugged Pickenng-5 May 48 14 4 tubes pulled > 90% Electrosleeves" acceptable. 30 of 48 sleeves installed k mockup located on SG platform.

(OHT) 1994 Tihange-2 1993 -600 Exact number On att three S/Gs. More than 500 tubes ir 1993 + some repairs and new tubes in 1995.

(Framatome{ 1995 not available Tihange-2 1996 600 Preparationtplannmg for May 1996 outage (Framatome) (planned)

Oconee-1 1995 9 0 AR 9 plated. 9 Electrosleeves* insta!!ed, process not yet approved t:y NRC. 9 tubes plugged then plugged 1 Crocet stres at Doe +2- 0 2 to 0 3 we, frequersy up to 0 5 tre 5 Crack seres er TW2: o 35 to 0 4F we 2 Crack ares at Dost-3 0 4 ee 6 Steam genersear sepeacement was made at Doet 3 in 1993 and h W3 h 199s 3 Crack sizes at Ringhets-3' O 1 to 0.2 we 4 No crac$ts; twgh wortt hardened ares FRAMATOME TECHNOLOGIES, INC. 3-4

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4,0 DESIGN CRITERIA 4,1-- Qualification Methodology ,

The first step in the qualification of the Electrosleeve for use in repairing degraded PWR steam generator tubing consists of specifying the requirements, regulatory or others, that are imposed upon the sleeve in the installed condition, if the current standard does not explicitly apply to the Electrosfeeve , then it was still followed as a guideline. Next the material properties of the Electrosteeve were determined per ASME and ASTM guidelines.

The following methodology was used to qualify the Electrosteeve :

o Define the design requirements for the steam generator tube repair, o Develop the applicable material properties per the requiruments of the ASME Code, Section ill (12,2),

1 o Prepare a design analyses of the tube repair per the requirements of the ASME Code, Section 111 ( 1 2 , 2 ],

o Evaluate the tube repair to the requirements of NRC Regulatory Guide 1,121 i [12,6),

The design requirements for the Electrosfeeve* are defined in Section 4.2.

The determination of material properties is presented in Section 6.0, The material properties were developed per the following methodology:

o Determine the design stress intensity value (S.) per the methodo;ogy of ASME Code, Section Ill, Appendix lil 2110(b),

e Perform tensile testing per ASTM E8 and E21, [12,13,12,14),

Perform creep testing per ASTM E139112.22),

Perform bend testing per ASTM E290 [12.20).

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The design analyses for the Electrosteeve was performed using ASME Code, Section lli as a guideline. The following methodology was used:

o Determine the minimum required sleeve thickness using ASME Code, Section lil, Subsection NB as a guide. The design stress inMnsity value determined in Section 6.0 will be used, o Determine the structuralloading associated with the tube repair including repair of locked tubes and tubes with 100% through wall defects. Evaluate the structural loads and installed sleeve configurations per the stress and f atigue limits in ASME Code, Section lil.

- -c I Additional qualification evaluations included:

1 o Flow induced vibration o Corrosion (Primary and Secondary Side Environments) o Nondestructive Evaluation Techniques o Regulatory Guide 1.121 evaluation.

The purpose of this report is to show that the Electrosleeve* is cualified for the structural repair of the three major sizes of steam generator tubing (11/16",3/4", and 7/8") that are in most RSG designs in service today. Qualification testing and/or analysis was performed on all three of the sizes of tubing, in the cases where a bounding condition and size was determined, the results were expanded to envelope the other sizes of tubing. Material test results are also presented for 5/8" OD (OTSG) size tubing.

FRAMATOME TECHNOLOGIES, INC. 4-2

4.2 Qualification Requirements The electroformed sleeve is designed for application in PWR steam generators with nominal 3/4 inch OD x 0.042/0.043/0.048 inch walls,11/16 inch OD x 0.040 inch wall, .

7/8 inch OD x 0.050 inch wall tubing. The operating conditions of these steam generators foam the design basis for the sleeve operating conditions. Design requirements for the sleeve a'a:

- Span defects in tha parent tube at TTS and TSP locations in both the HL and CL regions of RSG's while maximizing tube access, t

- Provide a structurei repair for the parent tube at these locations,

- Provide a leak tight seal for primary to secondary sida water,

- Minimize residual stress in the parent tube in order to minirnize the possibility of primary and secondary side IGSCC.

The design and qualifiWon of the slerive utilized applicable industry codes and standards as summarized in T 4.1.1. The ASME B&PV Code is the basic governing document for numerous aspects of the design, including determining test loads, performing structural analyses, procuring material, establishing the slcovo procedura qualification, and preparing the Sleeving Procedure Specification.

At present, nickelis not identified as an approved materialin the Code for ASME Section 111 Class I systems. Also, electroformed sleeves are not identified in ASME Section XI as a sleeving method. Therefore, material testing has been performed per the guidance of ASME Section lli and ASTM to establish material design properties. Similarly, the sleeve proceduto qualification has been performed following the guidance of ASME Section XI for steam generator sleeving.

4.3 !leove Design Conditions .

The design and operating conditions for the steam generator become the design and operating conditions iniposed on the sleeves. The Tables contained in Appendix A detail the operatim cr>nditions for which the sleeve has been designed. Analysis and testing woro pertoin ed to the worst case bounding condi:lons. The sleeve was designed to encompass the following types of steam generators in service: Westinghouse Models D, E,F,33,44,51, CE Models 67,00,3410, and ANO 2, Ft. Calhoun, and Maine Yankee.

FRAMATOME TECHNOLOGIES. INC. 4 3~

Steam generator design transients were used to establish sleeve loading transients.

Section a discusses how these transients were used.to establish the sleeve loading transients and cycles. Operating pressure and thermal loading ranges were used to establish the worst case conditions. Both unfor:ked and locked tube conditions were considered. For the locked tube condition, the conservative assuniption that the tubes are !

-locked at all tube support plates was utilized. [

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TABLE 4.1.1

SUMMARY

OF APPLICABLE CODES AND STANDARD $d."

Application Criteria Structural Design ASME B&PV Code, of the Sleeve Section ill (12.2]

Sleeve / Tube Loads Analyses Sleeve Plugging NRC Reg. Guide 1.121 112.6)

Limit Material ASME B&PV Code, Procurement Sections 11 and lli (12.1,12.2)

Electroformed Sleeve ASME B&PV Code, Qualification Section XI [12.4)

ASTM Standards (12.1312.28]

r Sleeve NDE ASME B&PV Code, Sections V and XI [12.3,12.41 Code Case N 5041 (12.7)

Oualification EPRI Checklist 112.11)

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  • The ASME B&PV Code currently does not specifically identify electrochemical deposition of material for steam generator tube repair, nor nanocrystalline nickel material. Therefore, these Code sections were followed as a guideline for the development of the Electrosleeve .

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5.0 SLEEVE DESIGN 6.1 Design Description ,

An elect oformed sleeve is an electrochemical deposition of ultra fint grained nickel material on the inside diameter of a degraded steam generator tube tSat requires repair.  :

Table 6.1.1 contains a summary of the dimenolons of an installed Electrosteeve* In each f of the steam generator derigns. The approximate axiallength for all sizes of RSG tubing {

is 8" at the TTS, and 4" at a TSP Intersection (based on a 3/4" TSP). The actual stres of t an installed sleeve may vary, if a size change affects any of the structural properties of the sleeve, justification or testing will be performed, as required. For the purposes of the ,

qualification of this repair process, any reference to the length of a sleeve refers to the length between the tapered edges, including the minimum bond lengths, but not including i the tapered edges. The tapered transitions are not considered part of the pressure boundary region of the sleeve.  !

Figure 5.1.1 depicts a typical RSG Electrosleeve arrangernent. The sleeve is designed to repair degraded tubec by axially spanning the degraded region in order that they may t remain in service. The sleeve is designed to be installed at any straight section of tubing, including the top of the TS, all TSP intersections, and freespan areas. The electroformed repair is 100% leak tight because the nickel is bonded to the tube.

The material used for the sleeve is high purity nickel (>99.5%). Nickel is deposited relatively easily with excellent bonding characteristics to the alloy 600 base metal. The Electrostoeve" componition does not release activated species such as Cobalt. It also has excellent material properties and ductility as shown in Section 6 of this report.

The design of the sleeve is such that it acts as the primary pressure boundary and maintains its structuralintegrity in the event of a MSLB, OBE, or DBE. Installation of the sleeve has no effect on the parent tube material microstructure. Residual stresses generated in the tube are very low, such that post instatlation stress relief in not required.

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. S.2 Process Description-The operations required for Electrosleeve" installation are:

- Mechanically clean tube regions to be repaired

- Install electroforming probes into tubes

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FIGURE 5.1.1 IYEICALESG TSP and TS SLEEVE ARRANGEMEMI i

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TABl.E 5.1.1 3IEAM GENEBAIOR TURE AND ELECTROSLEEVE" NOMINALDIMENALONE Nominal Sleeve Sleeve >

$1tattLAaneratog Tube OD finch) Iube_ Wall rinc.hi Giv Wall rinchi Location Length finch)

W D2,D3,D4,DS,E 0.750 0.043 1 1 8

TS 8.0 and CE Sys 80 W D2,D3,D4,05,E 0.750 0.043 1 1 8

TSP 4.0 and CE Sys 80 CE 67, 3410 0.750 0.048 1 1 8

TS 8.0 ANO 2, Ft Calhoun, Maine Yankee CE 67, 3410 0.750 0.048 1 l' TSP 4.0 ANO 2, Ft Calhoun, Maine Yankee W 33,44,51 0.875 0.050 I l' TS 8.0 ,

W 33,44,51 0.875 0.050 ( l' TSP 4.0 WF 0.088 0.040 ( l' TS 8.0 WF 0.688 0.040 ( l' TSP 4.0 FRAMATOME TECHNOLOGIES,INC. 54

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6.0 DESIGN VERIFICATION MATERIAt. PROPERTIES The Electrosleeve'"is a nanocrystalline materialinstalled "in situ" on the tube inside surface using an electrochemical deposition process. The properties of the nanocrystaHhe nickel material are superior to those of regular nickel. This section describes the tests performed to establish the properties of the Electrostoeve'"

material. ASTM and ASME standards were utilized in the development and qualification of the material. For the purposes of this section and other design verification cactions of this report, a specimen is defined as a tube with an Electrosleeve'" installed on the inside diameter of the tube.

The material properties of the electrochemical deposited nickel material are independent of the host tube inside diameter and thickness. The supporting data is presented in the following sections.

6.1 Tensile Strength Tensile tests were performed to document yield strength, ultimate strength, and elongation of the electrochemical deposited nickel material. More than I l' specimens were tested in order to insure statistically significant results. I l' alloy 600 tube sizes with an installed Electrosteeve'" were tested by FTl:

_a The tensile tests were performed at the following temperatures: RT, I l' Additionally, OHT performed tensile tests of ultra fine grained nickel material installed into I l' The test specimens were fabricated as shown in Figure 6.1.1 and ASTM procedures (12.13,12.14) were utilized to perform the testing. The results of the tensile tests were tabulated for the each of the I l' temperatures tested by FTl and combined with the results of OHT test specimens. This data was evaluated per the ASME Code to establish the design properties for the nanocrystalline nickel material at the Electrosteeve'" design temperature of 650*F.

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, r The ASME Code minimum design strength values at the design temperature are tabulated in Table 6.1.1. The typical yield and ultimate strength versus temperature is l l

shown in Figure 6.1.2.

6.2 Modulus of Elasticity ,

[ l' specimens were utilized in testing to determine the modulus of elasticity for- ,

the material per ASTM procedure 112.15). The specimens were fabricated from; j

-e Electrosleeved tubes. The specimen design is illustrated in Figure 6,1,1.

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The results of the testing show the modulus of elasticity for the electrochemical i deposited nickel materialis independent of tube size. Figure 6.1.2 shows the design value for Young's Modulus versus temperature for all tube sizes.

6.3 Ductility / Adhesion 1

I l* specimens were tested per ASTM procedure [12.20,12.21] in order to verify the ductility and adhesion of the electrochemical deposited nickel material.

Specirrens were f abricated by Electrosleeving a tube then splitting it longitudinally in half. The specirnens were then bent with the nickel sleeve outside diameter in tension over a 1/4" mandrel as shown in Figure 6.3.1.

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The ductitity of the electrochemical deposited nickel materialis further demonstrated by the ductile f ailures the material exhibited during the tensile tests (Section 6,1), i creep tests (Section 6.6) cnd burst tests (Section 6,7).

6,4 Fatigue Life With the exception of t',a work presented in this document, there has yet to be undertaken a systematic study of the fatigue performance of nanostructured materials.  ;

A comprehensive review 112.45) of the literature regarding the effect of grain size (i.e.,  ;

a10 m) t,n the f atigue performance of conventional nickel and nickel based alloys ,

4 shows that in general, decreasing grain size results in; ,

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specimens using i 1

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9 l' specimens were fitted to a curve, obtained by applying a least squares fit. ASME Code safety factors were applied to the l normalized data. The bounding design f atigue curve is made by combining the results f of both of these adjusted curves into a single bounding curve, Figure 6.4.1 illustrates '

the fatigue data for the electrochemical deposited nickel riiaterial.

Fatigue testing of the Electrosleeve material has been conducted at both room and elevated temperatures. The results show that the material maintains its f atigue  ;

resistance in the temperature region tested.

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6.5 Thermal Stability I l' test specimens were utilized to verify the thermal stability of the l electrochemical deposited nickel material. The specimens were f abricated as shown in Figure 6.1.1. Vickers hardness measurements were performed in accordance with ASTM procedures (12.231.

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The results of the testing at the design temperature of 650'F are shown in Figure 6.6.1. This graph shows that hardness of an electroformed sleeve at the design temperature is stable, and thus the thermal stability of the material at lower operational temperatures is verified The results from the testing performed at [ l' also show that the rnatorial maintains thermal stability at that elevated temperature.

Realstance tc Strain induced Recrvatallization ,

As a renuit of the stored energy of cold work, strainod materials tend to undergo recrystallization accompanied by a commensurate decrease in mechanical strength, at temperatures well below those required for the onset of normal grain growth, in order to assess the susceptibility of Electrosleeve" material to strain induced recrystallization, [

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any of the specimens, since the hardness of recrystallized nickel would be expected to be less than i 18 The hardness values shown are consistent with the normal vallance in hardness noted with as plated material.

6.6^ Creep Proporties d' '

The effect of decreasing grain size on creep deformation has been well documented, with steady state creep rates generally increasing with decreasing grain size; however, with the exception of the work presented herein, to date, there have only been a few FRAMATOME TECHNOLOGIES, INC. 66

studies on the creep performance of nanostructured materials. !

l' Intrinsic intergranular creep cracking is the predominant mode of premature creep f ailure for engineering materials.1 l'

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A series of constant load creep tests were performed using ASTM E139 (12.22) as a guideline to determine the creep behavior of the Electrosleeve* material. Creep testing is a determination of deformation as a function of time and the time to fracture at an elevated temperature when sufficient load is present. Constant load creep testing is performed in a controlled environment at constant temperature, in the defined Cauge l length the strain versus time data presents the challenge of representing the creep phenomena by a mathematical equation. The literature on creep presents many l options to model creep (12.30,12.31,12.38) and finite element codes (12.321 have creep calculation capability for analysis. Evaluation of data and analysis is presented in Section 8.6. The test specimens for creep testing were fabricated as shown in Figure 6.1.1.

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l' Figure 6.6.1 presents typical creep test results [

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The creep fiacture f aces examined have some unique differences in loading conditions:

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6.7 Burt,t Strength Burst tests were performed on i l' sleeve specimens fabricated per Figure 7.1.1.

Each specimen had a machined gauge length in order to accurately test the burst characteristics of the electrochemical deposited nickel material.

The specimens were pressurized using a hydraulic presture generator at room temperature. The specimens were internally pressurized at a rate of 200 to 2000 psi por second, per EPRI guidelines. The data for the different sizes of specimens tested is co'itained in Table 6.7.1. For supplementalinformation, Table 6.7.2 also contains I

18 The data shows that the electroformed sleeve material burst pressure may be calculated by I je..

6.6 Thermodynamic Properties

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CftEEP TEST SPECIMENS i

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CREEP TEST SEECLMENh

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  • MAIESIAL TEST SPECIMEN DESIGNS TENSILE. FATIGUE. YOUNG'S MODULUS SPECIMENS ,

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7.0 DESIGN VERIFICATION MECHANICAL TESTING The Electrosleeve* qualification program combined analysis and mechanical testing to meet the sleeve qualification requirements presented in Section 4.0. The mechanical' testing is summarized in this section and the analysis results are presented in Section 8.0.

Sections 7.0 and 8.0 together demonstrate that the installed Electrosteeve is qualified for all RSG designs and their operating conditions.

-7.1 Locked Tube Testing Locked tube testing was performed in order to measure the loads induced on a locked parent tube as a result of the electrosleeving process.

The testing was performed on [

]d mockups. Each of the mockuns had tubes that were roll expanded and welded into the TS and TSP, reinforced into place with tie rods, instrumented with strain gages and thermocouples, and sleeved in the TS and freespan. Figure 7.2.1 depicts a typical mockup that was utilized in the locked tube testing.

The results c,1 the testing are summarized below for a 4" sleeve installation completely within the tube span:

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d Note that the axialload and associated axial stress ( ]* decreased as a result of the increased span. This effect would be observed for all tube sizes for any change in span length. The axial span load and stress may be ratioed by the actual length of the installed sleeve (s) within a particular tube span v/s the [ 18 length used to determine the effect of a differing sleeve length or numbers of installed sleeves within a particular span.

The axial tube stress is present in the parent tube after sleeving prior to startup. These stresses are considered extremely low and thus not significant.

7.2 Fatigue Testing Section ill of the ASME B&PV Code does not provide design rules for sleeves f abricated "in-situ" by electrochemical deposition of material, in such cases, the ASME B&PV Code, Section 111, 1 Appendix 11 (12.21 allows the use of experirpental stress analysis to substantiate the critical, or governing strecses. The-adequacy of the installed material and its bond to the tube to withstand operational pressure and thermal cyclic loadings was demonstrated by means of r fatigue testing per the ASME B&PV Code, Section Ill, Article 111500 (12.2].

The Electrosteeve* is designed to accommodate all loads that any steam generator tube'may

{ experience due to normal plant conditions and all anticipated transients specified for the steam generator. Appendix A summarizes the expected transient conditions which were used to qualify the Electrosleeve design. The f atigue testing loads associated with those transients are developed in Section 8.2. .The following is a discussion of the fatigue testing performed to i - qualify the Electrosleeve".

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-l The minimum bond specimen illustrated in Figur's 7.1.1 addresses the situstion where significant degradation and metalloss of the parent tube occurs (wastage, gross IGA, etc.). [

18 The testing described below verifies that the Electrosteeve and the minimum t Snd length will carry the loads irnposed in service for the various steam generator designs.

s The minimum bond fatigue test specimens were tested with loadings that represent the design life of an installed sleeve. The loads are given in Table 8.2.1.

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I l' The sleeve-to-tube joint was monitored after test completion by UT examination to verify de-bonding did not occur.

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l' This criteria applies to the exposed Electrosteeve!" material as well as the sleeve / tube band.

At the conclusion of the fatigue tests, the specimens were visually and UT examined for bond or sleeve failure. AllI _l* specimens were acceptable with no evidence of degradation. -

7.3 Testing of Degraded Sleeves A series of fatigue tests were performed on mechanically degraded sleeves in order to establish a plugging criteria per the guidelines of the NRC draft Regul story Guide 1,121 112.61. [ .

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The test loads were developed to allow testing to proceed in steps, with each step representing 2 years of operating life. The test steps were repeated until tho specimens f ailed or until 40 years of service life was reached. The f ailure point can thus be used to define the inspection intervel foi the defeenve sleeve. [

l' The results of the defective sleeve fatigue tests showed that an Electrosteeve with a i 18 has a maximum inspection interval of:

Fatigue Tube Size Driect Tvoe insoection Interval 7.3.2 Plugging Criteria Burst Testing Regulatory Guide 1.121 [12.61 requires that 3 times normal operating differential pressure or the worst case faulted differential pressure he less than the tube burst pressure. Burst tests were performed on sleeved tubes in order to demonstrate that this margin is available in sleeves with defects.

_ a The specimens, along with burst test results, are listed in Table 7.3.2.

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7.4 Creep Fatigue Experimental Analysis Testing was performed to determine the effect of creep fatigue interaction. [

18 were tested with the following results:

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7.5- - Mechanical Testing Summary

The mechanical design verification tests were performed to show that the Electrocleeve"is structurally capable of withstanding ' actual in-service loading conditions. The tests were
performed conservatively, in order to envelope worst case conditions.

The burst tests demonstrate that the Electrosleeve"is ductile [

]d The burst tests also show that a sleeved defective tube with a [- 18 throughwall defect in the sleeve will withstand faulted condition loadings.

The locked tube tests show that the electrosleeving process is unaffected by locked tubes.

Further, no significant loads are generated in the parent tube from the installation process.

The series of experimental f atigue tests confirm the structuralintegrity of the electrochemical deposited nickel sleeve material:

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ELUGGING CRITERULBillit. T_Sf1CJMENS  ;

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Mf:CHANICAL TEST SPECIMEN DESIGNS PLUGGING CRITERIA FATlGUE SPECIMENS

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FIGURE 7.1.1 (Cont'd)

MECHANICAL TEST SPECIMEN DESIGNS PLUGGING CRITERIA BURST SPECIMENS _ _

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l-8.0 DESIGN VERIFICATION ANALYSES 1

Design analyses were performed for the Electrosleeve* to verify it conforms to the l qualification requirements identified in Section 4.0. - The design analyses consist of; l l

o pressure boundary minimum thickness calculation; o analyses to support fatigue testing per Appendix ll of the ASME Code; j o analyses of flow-induced vibration of sleeved tubes; I o analyses of the effect of a sleeve on heat transfer and primary fluid flow; o analyses of a degraded sleeve for p:Jgging Criteria; and l o analysis of creep.

The analyses were performed on the different sizes of steam generator tubing outlined in Section 4.0. The results are presented in Sections 8.1 through 8.6.

8.1 Pressure Boundary Thickness The Electrosleeve pressure sizing calculation used the allowable stress based on the strength properties derived from tre material testing of the electrochemical deposited nickel material. [

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The structural adequacy of the various sizes of electroformed sleeves was evaluated for pressure thickness and external pressure in accordance with the ASME B&PV Code.

The minimum sleeve wall thicknesses per N8 3324 [12.21 for the sleeve, based on the primary side design pressure, are:

Electrosleeve" Electrosleeve* Electrosleeve" Tube Size Nominni OD Min. Thickness Nom. Thickness (inches) (inches) (inches) 11/16" OD x 0.040" wall 0.608 I l' ( l' 3/4" OD x 0.042" wall 0.666 i 1* I l' 3/4" OD x 0.043" wall 0.664 i 1* I l' 3/4" OD x 0.048" wall 0.656 I l' I l' 7/8" OD x 0.050" wall 0.775 t i 1* I 1*

FRAMATOME TECHNOLOGIES, INC. 81

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The allowable external pressure for the sleeve and tube was calculated per classical-collapse pressure equations for each of the sizes of tubes / sleeves. The results of the calculations show that the sleeve [ t l'

The' design primary stress intensity was calculated for the case of a tube completely removed from the sleeve. Stresses were calculated for each of the steam generator designs. All stresses in the sleeve satisfy the primary stress limits. The maximum stress intensities are listed in Table 8.1.1.

8.2 Fatigue Test Loads Section lli of the ASME B&PV Code does not provide design rules for sleeves f abricated by electrochemical deposition of material, in such cases, the ASME B&PV Code, Section 111, Appendix ll [12.2] allows the use of experimental stress analysis to substantiate the critical, or governing stresses. The adequacy of the installed material and its bond to the tube to withstand operational pressure and thermal cyclic loadings was demonstrated by means of fatigue testing per the ASME B&PV Code, Section lil, Article 111500[12.2].

(- )* different fatigue test specimens were used to demonstate the fatigue life of  !

the Electrosleeve* for the steam generator design transients listed in Appendix A. The specimens tested are:

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18 The Electrosleeve is designed to acccmmodate all loads that the steam generator tube may experience due to normal plant conditions and all anticipated transients specified for the steam generator. The tables presented in Appendix A summarize the 4-

. expected transient conditions which were used in the design of the sleeves for the different sizes of tubes.

Calculations were prepared for each sleeve design to determine a conservative maximum loading for a sleeve in any steam generator tube based on the transients listed in Appendix A. These calculations include both pressure and thermal gradient loading.

The loadings were evaluated for tubes either locked or unlocked at the tube support plates. The tube loading calculated for a locked tube enveloped the tube loads calculated for a tube in the unlocked condition. As a result, the fatigue loading evaluation considered the tubes to be locked at all tube support plates. Loads due to thermal and pressure transients were calculated for [ 18 cases using the transients listed in Appendix A. Where possible, transients were grouped together and the number of cycles adjusted accordingly. The structural model for each of these cases considered a tube with a sleeves installed at the [

]d The sleeved tube conditions considered are:

[

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t FRAMATOME TECHNOLOGIES, INC. 8-3

The loading analysis model for the priphery tube case considered the following boundary conditions:

I l'

The loading analysis model for the interior tube case considered the following boundary conditions:

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The specific combination of geometry and operating conditions which resulted in the highest load for a given transient grouping was used in the mechanical test program.

The load ranges were calculated base. > on the following conditions:

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The calculated axlal tube loads for all transients were combined into a set of test load ranges. The required number of test cycles was determined per [12.2) Appendix ll, and was based on the number of test assemblies and va-ious f actors relating the test conditions to the actual operating conditions.

The fatigue load testing sequence for specimen 1 is shown in Table 8.2.1 for the recirculating steam generctors considered. The load testing sequences were utilized in the tests described in Section 7.2.1.

FRAMATOME TECHNOLOGIES, INC. B-4

Fatigue testing was performed in Section 7.2.2 to determine the life of an Electrosiceve I l' These tpecimens were subjected to testing reprer.ntative of the design life of the Electrosteeve .

Fatigue test loads were calculated for these test specirnens to represent the op0ruting pressure and thermal stress ranges the sleeve would be wbjected to over its life. [

l' sleeved tube specimens were tested. The test loadings and total cycles required in the f atigue tests in Section 7.2.2 are listed in Tables 8.2.2 and 8.2.3.

8.3 Flow Induced Vibration The flow-induced vibration (FIV) analyses evaluated fluidelastic stability margins (FSM) and random vibration response for the nickel sleeve. I l' The Fluid-clestic Stability Margins and the respnnses to small scale turbulence were examined. [

l' The FIV analyses were performed using Conner's Constants, % damping and added mass coefficient as listed in Table 8.3.1.

l' The FlV tube model included the hot leg, U-bend, and cold leg tubing from tubesheet to tubesheet. This model ailows cross flow loads to be applied to the U-bend tubing for evaluating the tube support plate sleeves. The cases considered are for virgin and sleeved tubes. The results of all of the FlV analyses are presented in Table 8.3.1. The bounding cases for each similar design is presented in the table. (

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S bound all CE RSG designs. The analyses indicate that the Electrosleave is acceptable i for installation in RSGs based on FIV considerations.

6.4 Thermal / Hydraulic The effect of an Electrosleeve'" installation on steam generator performance was analyzed for heat transfer, flow restriction, and steam generation capacity. Several cases were considered in the evaluation, consisting of a single sleeve in a tube, as well as multiple sleeves in a single tube. All designs of steam generators were considered in these analyses. In addition, cases in which the sleeved tubes were distributed asymmetrically arnong the RsGs were considered.

The analyses show that the heat transfer affects of electrosleeving are minimal. The affects of installed Electrosleeves on primary flow are presented in Table 8.4.1 for each of the stearn generator designs. The results are presented as an equivalency number of sleeves installed having the same impact as plugging one tube. The results show that the installation of an Electrosleeve'" has minimal affects on plugging margin and RCS flow.

In summary, the thermal / hydraulic analysen show the advantages of an Electrosleeve*

over previous skeve designs as; o a smaller unrecoverable pressure drop from a larger ID of the sleeve, and o the negligible loss of heat transfer area since the sleeve is in direct contact with the tube.

8.5 Sleeve Plugging Criteria NRC Regulatory Guide 1.121 [12.6] provides guidelines for determining the degradation -

limits for PWR steam generator tubes, Since the sleeve replaces a portion of the original tube, these guidelines are used to determine the plugging limits for the cleeve.

Three criteria for normal operating condhions (level A) and four criteria for faulted conditions (level D) were evaluated in the sleeve / tube bonding joint and in the straight sleeve section. The burst plugging limits are based upon test results performed as part

. of the hiaterial Properties verification (Section 6.7).

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FRAMATOMNiCHNOLOGIES, INC. 6 .

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The required minimum sleeve wall thicknesse:, were calculated for the defined sleeve length only. The tapered sections of the sleeves e'e not included in the structural assessments. The allowable part throughwall defect in each of the sleeve sizes is summe ' zed in Table 8.5.1. The analysis results presented in Table 8.5.1 show that any sleeve [

l' The fatigue testing results from Section 7.3 show that any sleeve exhibiting a era .

like flaw [ ]d at a location where the tube also shows a defect greater than 100% throughwall meets the RG 1.121 criteria.

The plugging limits were also evaluated for the tube in the sleeve / tube joint region.

The existing tube plugging criteria for the tube still applies to this region [

8 1

The results of the analyses and fatigue testing of the sleeve and tuce with 100%

throughwall defects in the tube and [

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8.6 Creep Analysis ASME Code Case N 47 [12.51 established design rules for Section Ill, Class 1 components for the conditions when the metal temperature exceeds those established by Section Ill. The design rules in the code case are designed to guard against:

a) ductile rupture from short term loadings b) gross distortion c) creep rupture from long term loadings d) creep f atigue failure The analysis results presented in Section 8.1 and the mechanical testing in Section 7.0 demonstrate that ductile rupture from short term loadings are not a concern. The other design aspects are discussMi below.

FRAM ATOME TECHNOLOGIES, INC. 8-7

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I 8,6.1 Gross Distortion During creep, a specimen under load will undergo permanent deformation over

. time. The amount of deformation will vary based on stress, time, and

_. temperature. [

l' The creep respon:,e of.the Electrosleeve" material was modeled using an equation [

jb.c..

The material constants for the creep equation were determined by fitting the curve to the results from constant load tests (Figure 8.6.1). [

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ANSYS was then used to create a finite element model Figure 8.6.3 of various

-tube / defect geometries and the total creep strain calculated. The following

. cases were considered and are illustrated in Figure 8.6.2:

FRAMATOME TECHNOLOGIES, INC. 8-8

- With the' exception of cases [

l' The finite element analysis imposed the steady state loads generated during 100% power as well as transient fatigue loads. The transient loads included the loads generated under worst case locked tube scenario.

The analysis results for various times are summarized in Tables 8.6.1 and 8.6.2.

Converting the calculated creep strains into expected deformations in the steam generator demonstrates that the Electrosteeve is not subjected to any gross distortions.

8.6.2 Creep Rupture f

Considerable research and effort has been spent over the last half century developing methods to predict creep rupture. Many c' these techniques involve

~

time temperature parameters whereby short term tests at high temperature are used to predict long term' exposure to lower temperatures. Analysis of data for

- a variety of aluminum , iron , nickel , titanium , cobalt , and copper-based alloys I l' in a comparison between various extrapolative techniques, [

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Using the relationship illustrated in Figure 8.6.4, the ANSYS constants discussed earlier, normal operating temperature, and differential pressuro, a conservative time to rupture analysis for a sleeve with the tube removed can be performed: . -

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.The analysis summarized in the preceding table is conservative for the following reasons: _

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8.6.3 Creep Fatigue Failure Evaluation The ASME Section ill Appendices [12.2] contains rules for experimental stress ,

analysis to determine whether or not a component can withstand the cyclic -

loading required for its intended application. A specific requirement is for the test sample to have the same composition and to be subjected to identical mechanical working and heat treatment as the actual component The purpose 1- of identical processing is to produce mechanical properties equivalent to those of the materialin question.

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The testing summarized in Section 7.4 included the following safety margins:

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- FRAMATOME TECHNOLOGIES, INC. 8 11:

8.6.4 Creep Summary

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'8.7 Design Summary The results of material properties testing, mechanical tests and the analyses are combined to define the dessign definition of an installed sleeve. Key aspects of this design definition are summarized below.

The Electrosleeve* has been qualified for installation in the following steam generator designs:

Westinghouse Series 33,44,51, D, E, and F CE Models 67,3410 and System 80 CE SG at ANO 2, Ft. Calhoun and Maine Yankee 4 The Electrosteeve* is qualified for installation over a'l tube defect types, including IGA, circumferential cracks, axial cracks, pitting, and other similar defects. The Electrosleeve* is qualified for installation in tube freespan regions, at tube expansion 4 transitions, and at tube support plate regions. The sleeve is a complete structural repair of the parent tube. Instaliation of the Electrosleeve can be at all tube support plates without limitations.

FRAMATOME TECHNOLOGIES, INC. 8-12

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The minimum nd nominal sleeve wall thicknesses for installation are:

Installed Sleeve Installed Sleeve Minimum Wall Nominal Wall Thickness Thickness Tube Size (Inches) (Inches) 11/16" OD x 0.040" wall I l' l 3/4" OD x 0.042/0.043/0.048" [ l' I l' wall 7/8" OD x 0.050" wall 1 1* I l' Note that the field process is operated to obtain the nominal sleeve wall thickness on installation.

Testing showed that a [ 18 bond length between the sleeve and tube will carry all structuralloads. For conservatism, the bond length for field acceptance will be set at a i l'. Refer to Figure 8.7.1 for a sketch of the bond length and pressure boundary. The minimum bond length of I l' of tt.a sleeve provides adequato structural attachment to a degraded parent tube. If the Electrosleeve does not show bond to the parent tube, between the minimum bond lengths, and the quality of the thickness and material are acceptable, the installation meets all design requirements.

The plugging nit for the sleeve was established at [

. l' sleeve thickness based on je..

These will be documented when completed.

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TABLE 8.2.1  :

SUMMARY

OF FATlGUE TEST LOAD RANGES -

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ALLOY 800 - > -

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l 9.0 DESIGN VERIFICATION CORROSION The objectives of the corrosion evaluation are to determine the susceptibility of the Electrosleeve" material to known Alloy 600 degradstion mechanismt, such as stress corrosion cracking (SCC), and to evaluate the corrosion potential of the Electrosleeve*

materialin environments that might exist in an operating steam generator.

The corrosion evaluation was performed by addressing general corrosion characteristics first, followed by evaluation of primary side environments and secondary side ,

environments.

9.1 General Corrosion Properties The electroformed sleeve consists of high purity (>99.5%), ultra fine grained (nanocrystalline) nickel material. The corrosion resistance properties of high purB/ nick, have been thoroughly investigated and documented. Also, excellent material performance has been demonstrated in both testing and in actuci steam generator and reactor system In service applications.

9.1.1 Literature Survey of Nickel Corrosion A generalliterature review was performed comparing the corrosion behavior of Alloy 600 and pure nickel [12.40). The results are summarized in Table 9.1.1.

In general, both nickel and its alloys are very noble and are effectively resistant to corrosion in acid, neutral, and alkaline conditions. The presence of highly oxidizing species have been found to decrease this resistance in some chemical environments. For example, corrosion of both nickel and nickel alloys has been observed in an acidic and highly oxidizing environment containing sulfur species.

Galvanic attack between pure nickel and Alloy 600 or Monel 400 materia! will not occur in SG environments due to the very low potential difference generated by the formation of a couple of these two materials.

t FRAMATOME TECHNOLOGIES, INC. 91

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9,1.2 Comparison of Nickel Plating and Electrosleeve" Nickel plating has been used successfully to repair SG tubes since 1985 [12.39).

This experience is summarized in Section 3.0 (Table 3.1). The nickel plating utilized has been typleally thin walled (5-8 mils) compared to the thicker walled (>

25 mils) Electrosleeve repair method. The nickel plating is intended to be a corrosion resistant " patch" rather than a structural repair.

Both circumferential and axial SCC have been repaired with nickel plating. The nickel plating has also been Installed over alloy 600 tube cracks that are 100%

throughwall. Thus, the nickel plating has been exposed to primary olde environments as well as secondary side environments (via the tube cracks) [12.56].

This is exactly the same manner that the Electrosleeve will be exposed to the two environments. In plant performance of the nickel plating has been excellent in 10 years of service.

Both Electrosleeves and nickel plating are >99.5% pure nickel.

)" Nickel plating has a conventional polycrystalline grain structuro, whereas the Electrosleeving process produces a nanocrystalline microstructure. [

]'8 The corrosion properties of nonostructures was evaluated in a literature survey.

Most of the corrosion evaluations conducted to date have been laboratory studies

-involving potentiodynamic polarizallon techniques.

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I FRAMATOME TECHNOLOGIES. INC,. 9-2

jo The general conclusiori from this comparison is that the Electrosteeve* material will perform the same as SG nickel plating in regards to corrosion behavior. Specific tests to evaluate the Electrosleeve material's corrosion characteristics were performed as discussed below. -

9.1.3 General Corrosion Tests of Electrosteeve*

Corrosion tests were performed on Electrosteeves to confirm general corrosion properties for the material. The environments used are extremely severe and do not exist directly in the steam generators. However, the corrosion mechanisms which were tested for are known problems encountered with Alloy 600. Thus these tests are meant to show the characteristics of Electrosleeve material, not specifically to predict the life in a SG.

The corrosion mechanisms tested were IGA, SCC, pitting and crevice corrosion.

Standard ASTM test procedures were followed.

9.1.3.1 Boiling Sulfuric Acid IGA Test The boiling sulfuric acid ferric sulfate test [12.24)is a standard ASTM method to detect the susceptibility to IGA of wrought, nickel-rich, chromium bearing alloys. This method uses ferric chloride in 50%

boiling sulfuric acid. The test is very aggressive to nickel base materials with little or no chromium due to the oxidizing nature of the ferric lon.

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FRAMATOME TECHNOLOGIES, INC. 93

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9.1.3.2 Polythionic Acid SCC Test ,

The polythlonic acid test [12.25)is a standard ASTM method used to evaluate the relative resistance of stainless steels and related materials to SCC. The test is applied to wrought products, castings, and weld metals by immersing it in a solution containing polythlonic a::Id at room temperature. Cracking of austenitic stainless steels (Type 302 and 304) would be expected in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less in this solution. [ l 1

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After exposure to the corrosion environment, transverse cross sections were examined metallographically.

l' O.1.3.3 Magnesium Chloride CCC Test The boiling magnesium chloride test [12.26]is a standard ASTM method employed to evaluate the relative resistance of wrought, cast, and welded stainless steels and related alloys to SCC. The test can detect the effects of composition, heat treatment, surface finish, microstructure, and stress on the susceptibility of these materials to chloride SCC. The test is carried out in a solution of magnesium chloride (about 45%) which boils at 311'F (155'C) for a duration [ l' hours.

FRAMATOME TECHNOLOGIES, INC. 9-4

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y After exposure to the corrosion environment, transverse cross sections were examined metallographically. ,

y 9.1.3.4 Sodlum Chloride SCC Test The sodium chloride SCC test [12.27) Is a standard ASTM method used to characterize the SCC resistance of aluminum, ferrous, and other alloys exposed to altamate immersion or wetting and drying conditions.

This Icst is an eccelerated test to evaluate the resistance to SCC and is not intended to predict performance in specialized chemical environments.

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FRAMATOME TECHNOLOGIES, INC. - 95-

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t 9.1.3.5 Ferric Chloride Pitting and Crevice Corrosion Test i a  ;

The ferric chloride test [12.28} is a standard ASTM method used to evaluate the resistance of stainless steels, nickel base, chromium f

bearing and related alloys to pitting and crevice corrosion. This test is  ;

an accelerated test designed to cause the breakdown of type 304 {

stainless steel at room temperature. The test is carried out in two j 4

different steps, the first to evaluate pitting corrosion and the second to i

! evaluate crevice corrosion. i h

Pitting Corronlon 1

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, Standard ASTM tests were used to characterize the material's performance relative to corrosion mechanisms. [  ;

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9.2 Primary Side Corrosion Evaluation in general, corrosion in the primary system of a PWR is minimized by careful control of the environmental characteristics. The Reactor Coolant System (RCS)is a closed system that does not communicate with outside contaminant sources. The environment is further .

controlled by limiting the presence of contaminants to very low levels as required by Plant Technical Specifications. The RCS chemistry control parameters and expected limiting values for the various modes of operation are given in Table 9.2.1, [

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The evaluation of the corrosion performance of the Electrosteeve* in the primary side environment was done by addressing the following areas: ,

c FRAMATOME TECHNOLOOlES, INC, 9-7

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l' 9.2.1 Full Power Operating Conditions Corrosion testing 'vas performed on nickel plating in environments that included pure water, and primary water chemistry conditions [12.39). Highly stressed (hard rolled transition zones) or very highly stressed reverse U bends (" RUBS")

specimens were used in the testing. Also, samples were submitted to temperature and pressure cycling in pure water to induce deformations in the nickel layer, 9.2.1.1 Pure Water Testing The objective of this test was to determine the cracking resistance of highly stressed nickel plating in pure water and to compare it to Alloy 600.

RUB specimens were tested to evaluate the SCC susceptibility of nickel plated S/G tubing in pure water. The test were corried out in an autoclave at the following conditions:

FRAMATOME TECHNOLOGIES, INC. . 9-8

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9.2.1.2 Primary Water Testing The objective of't is test was to determine the cracking resistance of highly stressed nickel plating in primary water and to compare it to ,

Alloy 600.

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9.2.2 Shutdown Conditions The main corro*lon concern during primary side shutdown conditions is the presence of t,tw & M The effect of boric acid, at various temperatures and concentrations we :3 evaluated on nickel plating, in addition, oxioizing shutdown crud burst conditions were tested with Electrosleeves ,

9.2.22. - Boric Acid - Cold Shutdown -

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4 9.2.2.2- Boric Acid - Elevated Temperatures A group _of tests were performed on nickel plated Alloy 600 tubes in a boric acid environment at elevated temperatures [.

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FRAMATOME TECHNOLOGIES, INC. - 9-11.

b 9.2.2.3 Shutdown Crud Burst / Cleanup During a typical plant shutdown for a maintenance refueling outage, a RCS crud burst is induced through an adjustment to the coolant pH and oxidant level. For this, the plant is borated to the refueling concentration, the lithium and dissolved hydrogen removed, and hydrogen peroxide (up to 10 ppm) added when the temperature has decreased to less than 200*F, This condition is typically maintained for a period of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to reduce the crud inventory in the RCS prior to continuing the refueling -

activities. This condition was evaluated by testing Electrosleeve specimens at the following conditions:

FRAMATOME TECHNOLOGIES, INC. 9-12

. _ _ __1____

F 9.2.3 Parent Tube SCC Two tests have been performed to eva!uate SCC in the parent tube. The first test was performed with nickel plating to verify that the nickel layer would prevent SCC in the parent tube at highly stressed regions, i.e., provide a protective layer.

A test was also performed with Electrosleeves"in order to verify that high residual tensile stresses are not induced into the parent tube at the ends of the sleeve. This i has been a typical problem with standard, e.g., welded, sleeve designs.

9.2.3.1 Stress Corrosion Cracking Protection Testing in 10% NaOH (caustic) solution has been shown to rapidly induce stress corrosion cracking in PWSCC-susceptible Alloy 600 specimens containing stresses greater than about 30 to 35 ksi. Steam generator roll transition mockups were used to evaluate the effect of nickel plating on SCC [12.39). The Alloy 600 tubes were rolled in-place areas using a 5 step rolling process, providing two roll transition regions in each mockup. The specimens were tested at the following conditions:

FRAMATOME TECHNOLOGIES, INc, 9-13

9.2.3 : Parent Tube SCC Two tests have been performed to evaluate SCC in the parent tube. The first test was performed with nickel plating to verify that the nickel layer would prevent SCC

. In the parent tube at highly stressed regions, i.e., provide a protective layer.

A test was also performed with Electrosleeves" in order to verify that high residual tensile stresses are not induced into the parent tube at the ends of the sleeve. This has been a typical problem with standard, e.g., welded, sleeve designs. ,

9.2.3.1 Stress Corrosion Cracking Protection Testing in 10% NaOH (caustic) solution has been shown to rapidly induce stress corrosion cracking in PWSCC-susceptible Alloy 600 specimens containing stresses greater than about 30 to 35 ksi. Steam generator roll transition mockups were used to evaluate the effect of nickel plating on SCC [12.39). The Alloy 600 tubes were rolled in-place areas using a 5 step rolling process, providing two roll transition regions in each mockup. The specimens were tested at the following conditions:

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_d FRAMATOME TECHNOLOGIES, INC. 9

" ~d FRAMATOME TECHNOLOGIES, INC. 9-14.

t g.2.3.2 Stress Corrosion Cracking (Effect of Stress)

A prima (y concern with standard SG sleeving has been the introduction of residual tensile stresses into the alloy 600 parent tube due to the sleeving process, Such tensile stresses can lead to PWSCC in the parent tube, while the sleeve typically does not experience SCC, Electrosleeving has the advantage of not introducing these high residual tensile stresses in the tube.

The objective of this corrosion test is to demonstrate the absence of significant residual stresses imparted on the Alloy 600 tube after Electrosteeving. A second objective is to demonstrate the Electrosleeve's resistance to SCC.

The corrosion test environment was as follows:

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l' 9.3- Secondary Side Corrosion Evaluation Evaluating the corrosion performance of a material for secondary side environments is much more difficult than evaluating the primary side performance due to the wide range of chemistry conditions which may be encountered. Steam generator upset chemistry conditions may result of from condenser in leakage, ion exchange resin regenerant =

chemicals (caustic and acid) from condensate polishing and makeup domineralizer systems, acidic sulfur species from resin ingress, chlorides and corrosion product iron and copper.

The effect of these contaminants is further compounded by the concentrating mechanisms associated with heat transfer and boiling in the steam generators. The generally accepted steam generator and secondary system chemistry program is All Volatile Treatment (AVT).

In this program, no solids are intentionally added to the steam generators for chemistry control, Only volatile chemicals such as ammonia and hydrazine are used for corrosion control.

Corrosion of the Electrosleeve in the secondary side environment of a PWR is minimized by the following environmental characteristics:

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However, considering that the main reason to utilize Electrosleeves* is to arrest Alloy 600 cracking, the Electrosleeve has to be able to withstand the environment that locally forms )

at the tip of such cracks, Additionally, it is important to understand the behavior of the Electro $leeve" in transient (excursion) environments that may be prasont in localized  ;

regions in the SG; (

l The approach taken to the corrosion evaluation was to demonstrate first the capability of  ;

the Electrosleeve to arrest cracking at the Alloy 600/Electrosleeve interface. This was addressed by exposing [

l' The performance of the Electrosleeve"in possible secondary side localized environments was evaluated by exposing the sleeve to [

l' Evaluation of worst case conditions that may form in Alloy 600 cracks under sludge piles 1 was also tested. [

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conducted. The first test demonstrated the ability of nickel-plated steam generator FRAMATOME TECHNOLOGIES, INC. 9-18

tubes containing throughwall cracks to maintain their integrity in a secondary side

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environment (chemistry and pressure conditions). The second test demonstrated the ability of highly strained Electrosleeves" to arrest ODSCC in Alloy 600 tubing. l 4

-9.3.1.1 Precracked Steam Generator Tubing Test i l

Steam generator tubing, containing O.D. Initiated cracks (including throughwall cracks), was nickel plated and tested in a mockup. Refer to Figure 9.3.1. The purpose of the test is to determine whether  !

throughwall cracks in nickel-plated steam generator tubes will continue to propagate through the nickel plating when exposed to secondary side conditions [12.39].

I The test conditions were as follows:

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9.3.1.2 Crack Arresting C-Ring Test -

Alloy 600' steam generator tubing with and without Electrosleeves* in 1

the form of highly stressed C-rings were used to evaluate the ability of the Electrosleeve to arrest a crack propagating from the tube O.D.

FRAMATOME TECHNOLOGIES, INC. 9-19

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I Testing was performed in a 10% NaOH (caustic) environment which is known to cause SCC in susceptible Alloy 600 material.

The test conditions were as follows:

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'I 9.3.2 Capsule Tests -

The objective of this test was to characterize the corrosion performance of the

- Electrosleeve materialin confined conditions of extreme bulk water chemistry.

. Test conditions were as follows:

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9.3.3 Heat Transfer Sludge Corrosion Tests -

The objective of these corrosion tests was to assess the corrosion performance of an Electrosleeve when a large area of it is exposed to extreme chemistry .

- conditions under a sludge pile.

FRAMATOME TECHNOLOGIES, INC. 9-23 --

These tests address the formation of dynamic crevice environments of the type that form in operating EGs and yield information on the performance of the Electrosleeve material under these environments. Note, however, that in the SG the sleeve is not exposed to these environments over large areas. Typically the only portion of the sleeve exposed will be the tips of the cracks in the Alloy 600 tube.

Heat transfer corrosion tests allow the direct comparison of bulk water environmer.ts between the operating unit and the laboratory test. The test design used herein involved heat transfer of the same magnitude as in the hot leg of a SG and the simulation of a pile of corrosion products deposits (sludge piles) around the tube.

Accelerated conditions were chosen to assess the chemistry limits of the material performance. The three bulk water environments selected add.assed three different operating scenarios of feedwater contamination: condenter cooling water, sodium hydroxide and sulfuric acid. The latter species are used as lon exchange resin regeneranis and could be accidentally produced in the event of operational malfunctions in the water treatment or condensate polishing systems. Normally, these events are short lasting (in the order of a few hours). The present water chemistry specifications call for remedial action in such events which may even necessitate immediate unit shutdown.

1 Condenser cooling water in-leakage has afflicted many units in the past; however, the present practices are quite strict and call for prompt remedial action. Many units are equipped with full flow condensate polishers so that in the event of such leaks, the impurities do not reach the SG.

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i 9.3.3.2 Acid Ingress This test addresses the condition of a massive continuous acid ingress-in a SG during operation. Test parameters were as follows:

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9.3.3.3 ._ Caustic Ingress This test addresses the condition of a massive continuous caustic ingress in a SG during operation. The test parameters were as follows:

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9.4 h'ickel Electroplating Operating Experience 4- ' 9.4.1 Frematome Experience Since 1985, PWRs in Belgium and Sweden have utilized nickel plating as a repair metliod for steam generator tubes exhibiting cracking and degradation.' Section 3.0 (Table 3.1) summarizes the history of nickel plating of these Belgian plants. The repair method has been successfully used to prevent cracking, as well as to repair _

existing 100% throughwall cracks within the parent tube. These electropiated nickel sleeves have had excellent in service performance over the last 10 years.

Figure 9.4.1 provides a summary of examinations on pulled tubes exhibiting these

- results.

9.4.2 FTl Experience In 1993, FTl performed nickel plating of the Baltimore Gas & Electric Company's Calvert Cliffs Unit 1 pressurizer heater nozzles. Nickel plating was successfully 4

performed on 118 pressurizer heater sleeves to mitigate the potential occurrence of PWSCC in the Alloy 600 heater sleeves.

>  : In 1995, FTl successfully installed 9 Electrosleeves in Oconee-1.. All sleeves were installed at the 1st TSP. The objective was to demonstrate the tooling and -

procedures for Electrosleeving. Since the sleeves were not licensed, the tubes were removed from service.

9.4.3 Ontario Hydro Experience Ontario Hydro has utilized Electrosleeving to repair corrosion damaged tubes in the Pickering_ Units. Section 3.0 (Table 3.1) provides a summary of the OHT field -

experience with Electrosleeving.

FRAMATOME TECHNOLOGIES, INC. 9-31

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9.5 Corrosion Evaluation Summary j Qualification of the corrosion properties of the Electrosfeeve was performed using a three phased program. The first phase involved a literature review and selection of tests, including ASTM standard tests, to determine the susceptibility of the Electrosteeve to known forms of Alloy 600 damage, such as IGA and SCC. The second phase focused on  ;

corrosion testing in specific primary side environments that are known to be detrimental to Alloy 600 tubing. The third phase focused on secondary side environments including alkaline, neutral, and acidic, in the presence of oxidizing and reducing species, and in many cases at extreme conditions to accelerate the corrosion processes.

A comparative review of the general corrosion characteristics of nickel and Alloy 600 l

l' Testing was performed on Electrosleeves , including caustic and ASTM standard tests, to determine the susceptibility of the material to IGA and SCC. [

l' Corrosion testing was conducted on both nickel plating and Electrosleeves to evaluate the Electrosleeve material performance in primary and secondary environments. Primary side tests included pure water, primary water and boric acid. Secondary side tests included heat transfer conditions, sludge, and confined geometry (crevices) with the associated concentrating mechanisms evaluated. The following conclusions were reached based on the results of these tests and comparison to expected conditions:

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Electrosleeve material is not a concern in PWR environments.- The excellent in-service

- experience of electrodeposited nickel materials supports this conclusion.

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TABLE 9.1.1

SUMMARY

OF LITERATUR! SURVEY NICKEL AND ALLOY 600 GENERAL CORROSION RATES IN VARIOUS ENVIRONMENTS _,

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  • PRIMARY SIDE MATRIX CHEMISTRY .-

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STEAM GENERATOR ELECTROSLEEVED* TURE MOCKUP j

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10.1 Installation P,rocedure The Sleeve Procedure Specification (SPS) defines the generic requirements for fold  !

Installation of the Electrosleeves . The SPS has been prepared following the guidelines of  !

the ASME Code Section XI for steam generator tube sleeving. The essential and non- r essential verlables for the process are identified. The following is a summary of the j i installation procedure j I

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10.3 Installation System / Tooling The installation of the electroformed sleeve is a::complished remotely by tooling attachments mounted on a manipulator. Typical manipulators that may be used for -

sleeving include: ROGER", Cobra", and FLEXIVERA" manipulators, The sleeve installation tooling used minimizes the personnel radiation exposures in accordance with ALARA principles.

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The sleeving system utilizes a series of skids and trailers, each containing a different portion of the fluids and chemicals required to successfully perform the plating process.

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10.4 ALARA The Al. ARA evaluation has been prepared using the process steps for electrosleeving in conjunction with radiation dose fields representative of Se.ies D steam generators. The exposure estimate is based on sleeving 100 tubes in a single steam generator channel head. This quantity is representative of a typical sleeving campaign and provides a useful standard for comparison. Table 10.4.1 provides detailed information regarding the assumed radiation fields, as well as estimated exposures for the various sleeving activities and the total estimated process exposure.

Remote manipulators will be used for the electroformed sleeving process. The estimate provided does not include exposure associated with manipulator installation or removal, as the manipulator is typically installed at an earlier time in support of inspection or repair.

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Factors affecting process exposure include batch size, intensity of radiation fields, and sleeve placement locations. FTl Al. ARA Engineers prepare detailed estimates for each job and carefully consider all aspects of each activity in order to further minimize personnel exposure. The batch size and total quantity of sleeves installed play a significant role in the exposure received per unit. As the number of sleeves installed increases, the exposure per sleeve will decrease substantially since several tasks are performed only once for each sleeving job.

FRAMATOME TECHNOLOGIES, INC. 10-4

l 10.5 Sleeving Experience I

-i i As part of the qualdication process, a number of tube conditions were Electrosleeved* to demonstrate the process capabilities. The tube conditions in which sleeves were l successfully installed include:

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11.0 NONDESTRUCTIVE EXAMINATION NDE is performed on the sleeve and parent tube af ter installation in order to verify correct positioning, proper sleeve to tube bonding, sleeve thickness, and to provide a baseline  ;

inspection of the new primary pressure boundary. NDE is also performed during subsequent inspection outages to verify that the pressure boundary has not degraded.

Ultrasonic Testing (UT) la the primary NDE inspection technique for the sleeve and is

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described below. The UT is required for the installation examination to provide the sleeve thickness measurement and to provide verification of bond quality. I ji, 11.1 Ultrasonic Testing Background A UT examination is conducted by transmitting ultrasound into tne tubing wall and waiting for a returning echo from a reflective surface (i.e., tube outer diameter (OD) wall, Electrosfeeve* wall, crack corner trap, tube end, etc.). The time and amplitude of the returning echo yields information about the reflecting surface and its distance from the transducer. This process is analogous to sonar in that a " ping" of energy is released for the purpose of detecting and measuring the distance of objects that reflect some of the transmitted energy. I l'

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]* Tne qualification samples contained nickel sleeves which were Installed into parent tube ristorial as in the design verification sections of this report. A variety of flaws in different sleeve locations were made to test and define the UT capabilities.

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11.2.1 UT Detection /Longth Strin0 Capabilities I

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i TABLE 11.1 SUMMARIZED UT RESULTS OF BOND /UNBOND ,

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FIGURE 11.2 REGIONS OF A NICKEL St FFVE FOR UT QUALIFICATION TESTING s

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11.3 Eddy Current Testing

~ Historicolly, eddy current testing has not been widely used in the examination of nickel plated tube repairs due to the lock of penetration depth in the higher permeability of the nickel. Several eddy current probe designs were evaluated for- examination of the Electrosleeve". I p.

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I FIGURE 11,3 l DETECTION 0F 20% CIRCUMFERENTIAL EDM NOTCH IN MlD. SLEEVE 5

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12.0 REFERENCES

12.1 ASME Boiler and Pressure Vessel Code, Section 11,1989 Edition with 1989 Addenda.

-12.2 ASME Boiler and Pressure Vessel Code, Section 111 and Section til Appendices,1989 Edition with No Addenda.

12.3 ASME Boiler and Pressure Vessel Ccde,Section V,1D92 Edition with 1993 Addenda.

12.4 ASME Boller and Pressure Vessel Code,Section XI,1989 Edition with 1989 Addenda.

12.5 ASME Bolle: .md Pressure Vessel Code, Code Case N-47 33, " Class 1 Components in Elevated Temperature Service".

12.6 Regulatory Guide 1.121, " Bases for Plugging Degraded PWR Steam Generator Tubes."

12.7 ASME Code Case N 5041, " Alternative Rules for Repair of Class 1,2, and 3 Austenitic Stainless Steel Piping".

12.8 F.P. Vacaro, et al, " Remedial Measures for Stress Corrosion Cracking of Al!oy 600 Steam Generator Tubing," presented at Traverse City Third International Symposium on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, September 1987, 12.9 J.E. Outrwiller, S.W. Glass, "New Options for improved Steam Generator U Bend

'- Integrity," presented at the SMIRT 9, post conference seminar nn Assuring Structural Integrity of Steel Reactor Pressure Boundary Components, Davos, Switzerland, August, 1987.

12.10 EPRI Utility Experience Report, Electronucleaire Utility, Plants: Tihange 1,2,3, and Doel 1, 2, 3, 4, June,1987, 12.11 EPRI Steam Generator Tube Sleeving: Design, Specification and Procurement Checklist, Research Project S408 5, Topical Report December 1989, 12.12 LP91 TR 103824, Project 2859, Steam Generator Reference Book, Revision 1 December, 1994.

FRAMATOME TECHNOLOGIES. INC. 12 1 m

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12.13 ASTM E 8 95a, " Standard Test Methods for Tension Testing of Metallic Materials".

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l 12.14 ASTM E 2192, " Standard Test Methods for Elevated Temperature Tension Testing of l Metallic Materials". i 12.15 ASTM E 11182, " Standard Test Method for Young's Modulus, Tangent Modulus, and j Chord Modulus".  ;

i 12.16 ASTM E 606 92, " Standard Practice for Strain Controlled Fatigue Test". [

12.17 ASTM E 460 82, " Standard Practice for Conducting Constant Amplitude Axlal Fatigue

. Tests of Metallic Materials". l 12.18 ASTM E 467 90, " Standard Practice for Verification of Constant Amplitude Dynamic Loads on Displacements in an Axlal Load Fatigue Testing System".

.i 12.19 ASTM E 468 90, " Standard Practice for Presentation of Constant Amplitude Fatigue Test  ;

Results for Metallic Materials".

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12.20 ASTM E 290 92, " Standard Test Method for Semi Guided Bend Test for Ductility of ,.

Metallic Materials".

12.21 ASTM 8 489 85, " Standard Practice for Bend Test for Ductility of Electrodeposited and Autocatalytically Deposited Metal Coatings on Metals".

12.22 ASTM E 139 83, " Standard Practice for Conducting Creep, Creep Rupture, and Stress Rupture Tests of Metallic Materials".  ;

12.23 ASTM E 92, " Standard Test Method for Vickers Hardness of Metallic Materials".- ,

.12.24 ASTM. G 28, " Standard -Test Methods of Detecting Susceptibility to Intergranular Corrosion in Wrought, Nickel Rich; Chromium Bearing Alloys". --

i 12.25 ASTM G 35, " Standard Practice for Determining the Susceptibility of Stainless Stools and Related Nickel Chromium Iron Alloys to Stress Corrosion Cracking in Polythlonic Acids". ,

-12.26 ASTM G 36, "Starderd Practice for Evaluating Stress Corrosion Cracking Resistance of  ;

Metals and Alloys in a Boiling Magnesium Chloride Solution". .

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12.27 ASTM G 44, " Standard Practice for Evaluating Stress Corrosion Cracking Resistance of Metals and Alloys by Alternate immersion in 3.5% Sodium Chloride Solution".

12.28 ASTM G 48, " Standard Test Methods for Pitting and Crevice Corrosion Resistance of Stainless Steels and Related Alloys by Use of Ferric Chloride Solution".

12.29 ASME TJ290.A716,1976, " Criteria for Design of Elevated Temperature Class 1 Components in Section Ill, Division 1, of the ASME Boller and Pressure Vessel Code".

12.30 (

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12.32 ANSYS Finite Element Code, Version 5.2.

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12.37 D.B. Darling and J.A. Richards ill, " Nickel Plating of Pressurizer Heater Nozzles to Prevent PWSCC", Nuclear Plant Journal. November December 1994, 12.38 I l' FRAMATOME TECHNOLOGIES, INC. 12 3-

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October 9 13,1995, Airlie, VA.

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W D DESIGN INFORMATION ,_

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W D DESIGN INFORMATiON ~

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W D DESIGN INFORMATION e

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TABLE A.2 W E DESIGN INFORMATION _

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TABLE A.2 (Cont'd) .
  • W E DESIGN INFORMATION

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TABLE A.2 (Cont'd)

W:E DESIGN INFORMATION _

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- CERYS 80 DESIGN INFORMATlON T*

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TABLE A.3 (Cont'd)

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TABLE A,4

_- WESTINGHOUSE 7/8" TUBING S/GDESIGN INFORMATION ~

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TABLE A.4 (Cont'd)  ;

WESTINGHOUSE 7/8" TUBING SIG DESIGN INFORMATION a i t

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TABLE A,4 (Cont'd)

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WESTINGHOUSE 7/8" TUBING S/G DESIGN INFORMATION _ _

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TABLE A.4 (Cont'd)

_ WESTINGHOUSE 7/8" S/G TUBING DESIGN INFORMATlON _ ,

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.:i TABLE A.5 COMBUSTION ENGINEERING 3/4"x .048" TUBING S/G DESIGN INFORMATION -

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TABLE A.5 (Cont'd)

COMBUSTION ENGINFERING 3/4"x .048" TUBING S/G DESIGN INFORMATION ~

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_ COMBUSTION ENGINEERING 3/4"x .048" TUBING S/G DESIGN INFORMATION _  !

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TABLE A.5 (Cont'd)

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_ COMBUSTION ENGINEERING 3/4"x .048" TUBING S/G DESIGN INFORMATION _

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TABLE A.6 W F DESIGN INFORMATION

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TABLE A.6 (Cont'd)

W-F DESIGN INFORMATION ,

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TABLE A.8 (Cont'd)

WEDESIGGEORMATION ,

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