ML20096F299

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Non-proprietary Rev 0 to CEN-627-NP, Verification of Installation Process & Operating Performance of Abb Ceno SG Tube Sleeve for Use at Comm Ed Byron & Braidwood Units 1 & 2
ML20096F299
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 01/17/1996
From:
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:
Shared Package
ML19317C267 List:
References
CEN-627-NP, CEN-627-NP-R, CEN-627-NP-R00, NUDOCS 9601230313
Download: ML20096F299 (31)


Text

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i CEN-627-NP Revision 00-NP COMBUSTION ENGINEERING, INC.

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JANUARY 1996 VERIFICATION O{' THE INSTALLATION PROCESS AND OPERATING PERFORMANCE OF THE ABB CENO STEAM GENERATOR TUBE SLEEVE FOR USE AT COMMONWEALTH EDISON BYRON AND BRAIDWOOD UNITS 1 & 2 Combustion Engineering, Inc.

Nuclear Operations Windsor, Connecticut 9601230313 960117 PDR ADOCK 05000454 .

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4 TABLE OF CONTENTS Section Tillt Eags LO INTRODUCTION 3

i 2.0

SUMMARY

1 3.0 INSTALLATION PROCESS 1 3.1 SLEEVE DESIGN DESCRIFITON 1 3.2 SLEEVE-TUBE ASSEMBLY 2 3.3 SLEEVE INSTALLATION SEQUENCE - ETZ SLEEVE 4 3.4 SLEEVE INSTALLATION SEQUENCE - TS SLEEVE 7 5 3.5 SLEEVE INSTALLATION SEQUENCE - TSP SLEEVE 7 4.0 SI FFVE INSTALLATION VERIFICATION 8 4.1 WELD INTEGRITY B 4.2 ROLLED JOINT INTEGRITY 12 1 5.0 SI FFVE PERFORMANCE VERIFICATION 20 5.1 COMMERCIAL SLEEVE INSTALLATION 20 5.2 SLEEVE-TUBE CORROSION TEST PROGRAM 24 5.3 SLEEVE-TUBE INSPECTION 28 5.4

SUMMARY

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6.0 REFERENCES

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'l .1.0 PURPOSE -

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The purpose of tnis report is to provide information in support of technical i specification changes allowing installation of Combustbn Engineering repair sleeve in recirculating steam generators. This report supplements data that ABB i

j Combustion Engineering has provided in the topical report (Reference 6.1) oj of steam generator tubes using leak tight sleeves for Byron and Braidwood Units 1  !

& 2, demonstrating both the Sleeve Installation Verification and the Sleeve  :

Performance Verification.

2.0

SUMMARY

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Actual sleeve operating history, as well as the qualification test program described herein indicate that the ABB-CENO steam generator tube sleeve is capable of '

performing as well as, if not longer than the original tube in which it has been j

installed; The expected life of any particular installation depends a great deal on the specific physical condition of the steam generator, metallurgical condition of its tubing, the degradation mechanism originally experienced, and the environmental conditions expected to exist after sleeve installation.

It is reasonably clear, however, that the use of a post weld heat treatment, particularly on a limited number of applications within a given tube, increases the margin for sleeve joint life. In selecting the installation processes, specifically whether to utilize post weld heat treatment, all of these factors must be considered-in an attempt to provide a cost effective repair consistent with the long term operational plans for that particular steam generator. '

3.0 STERVE INSTAT T ATION PROCESS 3.1 SLEEVE DESIGN DESCRIPTION There are three (3) types of sleeves which may be installed in various combinations within a steam generator tube. Only two types, the roll transition and tube support plate, are being considered for installation in Byron and Braidwood. Each sleeve type has a nominal outside diameter of [

] and a nominal wall thickness of [ . ]. The sleeve material is thermally treated Inconel 690. Each' of the sleeve types includes a chamfer at both ends to prevent hang-up of equipment used to install the sleeve and to inspect the steam generator tube and sleeve.

The first type of sleeve spans the roll transition zone (RTZ) at the top of the -

tubesheet to a minimum height of 3.5 inches above the flow distribution baffle. This O

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sleeve is up to [' )long andincludes [r

]. A shorter sleeve (approximately [  :)) of the same design is used to span defective areas of a steam generator tube which exist just above the tubesheet.

The second type of sleeve spans the tubesheet (TS) and a portion of the tube to a maximum height of[ -

] above the tubesheet. This sleeve is designed for use only in steam ger:erators with parnal depth rolled tubes. The sleeve is chamfered at the upper end to prevent hang-up with equipment which is used to install or inspect the sleeve (or steam generator tube). [

-] .

The third type of sleeve spans a tube support plate (TSP). The sleeve is up to [.

] in length, although a shorter sleeve (approximately [  ;]) may be used.

The tube support plate sleeve is used at the first and/or second tube support plate elevation or on any free span section of the tube between the top of the tubesheet and the second support plate. One or two tube support plate sleeves may be used in a tube containing an roll transition or tubesheet sleeve.

3.2 SLEEVE-TUBE ASSEMBLY 3.2.1 Roll Transition Zone Sleeve The RTZ sleeve is up to [ ] in length. The upper end of the sleeve is located above the May face of the tubesheet, while the sleeve lower end is located near the neutral axis of the tuha*h~t. [ .

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The lower end of the RTZ sleeve is rolled into the tube within the tubesheet.

roll is torque controlled to provide a leak tight structural joint. A roll which does not meet the criteria can be repaired by rerolling at the same location.

3.2.2 Tubsheet Sleeve The tubesheet sleeve (not for use at Byron'or Braidwood) is up to [ ] inches long, with the bottom of the sleeve positioned flush with the bottom of the steam generator  !

tube.

The sleeve is expanded in the steam generator tube at the upper end in I preparation for weldmg. The steam generator tube is 6;--n*-i slightly because of steam generator tube springback after expansion so that the gap between the sleeve -

and tube is minimized.

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The lower end of the sleeve is tapered to an outside diameter that is larger than the -  !

inside diameter of the steam generator tube. The taper serves three purposes: The taper limits the insertion of the tube to the proper elevation during installation, i temporarily holds the sleeve in place and provides tight contact with the tube for j welding.

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1 3.2.3 Tube Suonort Pjsc i i

The TSP sleeve is up to [ ] inches in length. It is approximately centered at either the first and/or second support plate. [

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For all sleeve welds except for the lower edge weld of the TS sleeve, the weld joint may be given a post weld heat treatment in the range of [

.] This time and temperature combination is sufficient to reduce the level of residual stress in Alloy 600 without resulting in detrimental effects such as grain growth or sensitization. This treatment is similar to that utilized in some operating units to heat treat the tight radius U-bends.

3.3 SLEEVE INSTALLATION SEQUENCE - RTZ SLEEVE RTZ sleeves are installed in the following sequence of operations:

3.3.1 Tube I.D. Cleaning Prior to sleeve installation, the tube I.D. is mechanically cleaned with an abrasive wire brush. A motor rotates the tool head as it is inserted in the end of 3.3.2 Sleeve Installation /Exnansion The sleeve expansion equipment is used to deliver and to provide the required sleeve / tube fit-up prior to welding or rolling.

The sleeve is located on the sleeve expansion tool for positioning within the steam .

generator tube. The expansion tool functions to guide the sleeve into the tube and install the sleeve to the selected elevation within the tube. A tool hardstop is <

provided for proper sleeve vertical positioning. Once the sleeve is at the proper Page 4

elevation within the steam generator tube, it is hydraulically expanded.

He expansion tool consists of a mandrel and two bladders which contain the ,

t =.lized water which is used as the pressurization fluid. De sleeve is located over the two bladders prior to insertion in the steam generator tube. When the  !

hydraulic expansion tool is pressurized, the bladders act directly against the inside '

diameter of the sleeve causing expansion of the sleeve.

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3.3.3 Structural Weld Near Sleeve Unner End The welding equipment used for the sleeve to tube welds is comprised of two major .

components; the weld head assembly and the weld power supply. The welding head  !

contains a copper wand which is used to hold and conduct the power to the tungsten electrode. The werd head includes a stainless steel sheath to prevent damage during  ;

insertion of the weld head into the steam generator tube and sleeve. Passages within  !

the weld wand are provided for the shield gas to reach the weld torch area. l The weld head is rotated inside the sleeve when it is positioned at the proper elevation.

The current and shielding gas are provided to the weld tool tungsten  ;

' electrode by connections at the bottom end of the weld tool shaft. A maximum of l

[ ] welds can be made with each tungsten electrode.

P The Gas Tungsten Arc welding power source is pre-programmed to supply argon shielding gas and pulsating D.C. current in four distinct power output levels.

Current output from level one is set to initiate the arc and form the weld " puddle".

As weld heat build-up increases, current output from each subsequent level is decreased in order to maintain consistent weld penetration and height. Weld essential variables, such as; current, voltage, head speed and gas flow are outlined in the applicable Weld Procedure Specification (WPS).

3.3.4 Ultrasonic Framination of Sleeve Unner Weld Ultrasonic testing using an immersion technique with demineralized water as a ,

couplant is used to inspect the tube to sleeve weld. A one-quarter inch diameter focusing transducer is positioned in the weld area and rotated by the probe pusher or i

{

motor at the tool base to scan the weld. The pulse echo tester has the ability to l

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. . t interface with an on line data reduction computer to produce a display /hardco during radial and axial scanning. ,

t 3.3.5 Vimal Fr=mination of Sleeve Usar ' weld  !

Visual inspection of the sleeve upper weld is accomplished with the use of a micro camera system.

3.3.6 Post-Weld Femt Treatment Of Slave Unwr Weld i

The post weld heat treatment is performed with a resistance heater designed to heat ;

the weld, the weld heat affected zone, and the pressure boundary portion of the tube expanded, including the outboard transition, during sleeve installation. De  ;

temperature controlis accomplished by thermocouple measurement of the temperature l

of the resistance heater. The thermocouple readings are input to a controller which initiates the heat treatment process and maintains the heater at a pre-set tempera;

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3.3.7 Sleeve End Toroue Rolline The sleeve rolling equipment is used to expand the RTZ siceve into contact with the steam generator tube within the tubesheet, forming a strong leak tight joint.

i ne rolling equipment consists of the air motor, tube expander, torque read-out,j chart recorder and a torque calibration unit. The torque read-out and settings of the '

rolling tool are verified on the torque calibration unit prior to rolling of the sleeves.

The rolling toolis located within the portion of the sleeve which was hydraulical) expanded during sleeve installation.

The approximately 1-1/4 inch long roll is located at the nickel and chromium oxide bands on the lower end of th The sleeve is expanded to a torque which has been demonstrated by testing to p a leak tightjoint. A strip chart record of the rolling tool torque is taken for further evaluation of the rolling process on the individual sleeves. A rolled joint which fails to meet the acceptance criteria may be re-rolled.

3.3.8 Sleeve nataline Examination With ECT A multi-frequency eddy current method will be used to perform a base line l

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A examination of the installed sleeve for future reference. The ET fixture, with conduit, is used on the manipulator arm to position the probe.

3.4 SLEEVE INSTALLATION SEQUENCE - TS SLEEVE  ;

TS sleeves (not to be installed in Byron or Braidwood) ar:: installed in the follow sequence of operations performed as described in Section 3.3.  !

l 3.4.1 Tube I.D. Cleanmg i' 1

3'.4.2 Sleeve In=t=llation/Exnansion

  • 3.4.3 Stnictural Weld Near Sleeve Unner End 3.4.4 Ultrasonic Fr=mination Of Sleeve Uu- Weld 1

3.4.5 Visual Framination Of Sleeve Unoer Weld i i

i 3.4.6 Post-Weld Heat Treatment Of Sleeve Unser Weld j i

3.4.7 Structural Weld Near Sleeve Imwer End 3.4.8 Visual Framinatinn of Sleeve Iower Weld 3.4.9 Sleeve Raceline Examination With ECT i 3.5 SLEEVE INSTALLATION SEQUENCE - TSP SLEEVE TSP sleeves are installed in the following sequence of operations performed as described in Section 3.3.

3.5.1 Tube I.D. Clennine 3.5.2 Sleeve Installation /Exoansion 3.5.3 Structural Weld Near Sleeve udder End 3.5.4 Structural Weld Near Sleeve Imwer End 3.5.5 Ultrasonic Examination Of Sleeve udder And Iower Welds

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3.5.6 Visual Framination Of Sleeve Unner And lower Weldt 3.5.7 Post-Weld Heat Treatment Of Sleeve Unscr And Lower Welde i

3.5.8 Sleeve healine Examinatinn With ECT 4.0 SLEEVE INSTALI ATION VERIFICATION i 4.1 WELD INTEGRITY '

Initiated in 1983, Combustion Engineering has conducted a comprehensive  ;

development program to ensure the sleeve to tube weld joint integrity. Tube I.D. -

brushing tests, sleeve / tube expansion tests and weld parameter evaluation tests were all completed as part of the process verification. During this development, hundreds }!

of welds have been made, examined, and/or tested to establish the essential vanables associated with these processes. )

4.1.1 Tube Clennine Oualification In preparation for welding, any oxide layer must be removed from the tube I.D.

surface.and process Extensive tool. tests were performed to develop, qualify and improve the c The cleaning program that was completed resulted in the qualification of an air powered, expandable wire brush.

4.1.2 Sleeve / Tube Exnansion Qualificatian An extensive test program was performed to qualify the bladder expansion tool and process. A particular effort has been made to minimize the diametral expansion of the tube while providing a tight sleeve / tube fit up to ensure a sound sleeve to tube weld.

This program considered tubing with thick, thin and nominal walls as well as tu with different yield strengths.

4.1.3 Weld Oualification l

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4.1.4 Ultrasonic Testine Oualification Ultrasonic (U.T.) techniques are employed to confirm the presence of weld fusion into the tube. A test program was completed by C-E to qualify the ultrasonic examination of sleeve / tube upper welds. Fourteen sleeve / tube weld specimens were ympared for

  • this qualification program. Each weld was ultrasonically inspected and then l

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l hydrostatically tested to confirm U.T. results.

' Test results indicate complete correlation between ultrasonic and hydrostatic testing.

Further verification of the  ;

U.T. technique under field conditions was provided by the comparison of two unacceptable and six acceptable welds removed from the Ringhals 2 steam generators. '

4.1.5 Post Weld Heat Treatment Oualifiemtian j

l The tubing used in some steam generators has been shown to be highly susceptible !

Primary Water Stress Corrosion Cracking (PWSCC). As a result, the residual stress l

induced in the steam generator tubing associated with any repair process must be minimized. In these cases, a post weld heat treatment (PWHT) applied to the sleeve 1

to tube weld joint as well as the weld heat affected zone and primary pressure boundary portion of the tube expansion may be performed. The Electrical Power i Research Institute (EPRI) has documented evidence in support of the benefits of this process.

! Combustion Engineering has followed EPRI guidelines (Ref. 6.6) to determine the tube temperature and hold time required to maximize tube life.

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intended to measure the long range, macro stresses imparted to the tube prima when the tubes were locked at support plate or egg crate locations. {

t Accelerated Corrosion Tests The accelerated corrosion tests were used to verify the temperature / time parameters for the pwcess by determining the level of stress relief obtained. Initial tests were performed on a mockup consisting of a four by four array of .750 inch O.D. x 0.042 inch wall tubes arranged in a square pitch array. In all mockup installations sleeves  :

were installed using the standard procedures and sequences described above.  :

Additionally, the tubes were locked by wdding to the support location.

After installation these mockups were cut to remove the tube sections for testing. No provisions were made to simulate the long range residual stresses due to tube locki The resultant tube / sleeve assemblies were then fabricated into individual capsule .

corrosion specimens. The I.D. surface of the samples were exposed to a 10% solution I of dearerated sodium hydroxide at 660*F. At the same time, C-ring samples of the . -

Alloy 600 tube material were stressed to various levels and exposed to the same environment. In other tests, representative roll transition samples were also exposed. '

These control samples provided a measure of the stress levels at which the sleeve / tube i

joints would fail. Some of this work was performed by ABb-CENO and some by '

independent organizations. The results of the two most prominent tests are shown in Tables 4-1 and 4-2. l i

The conclusion of these tests was that the as-welded tube / sleeve joint (  ;

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Instrumented Analysis ofI.ocked Tubes 1

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A plot of the temperature profile and the axialload measured are shown in Figure 4-2.

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Th2 results of this test are shown in Table 4-3, Although no m..asurements were no abrupt changes in the tube diameter were observed along the length of the tube. It was concluded that the deformation experienced by the tube would not be detrimental either to the installation process, i.e.. in preventing the tool from being removed, or the long term performance of the sleeve / tube joint as described in Section 5.

A similar test was performed on a two by four array of.750 inch O.D. x .042 inch wall tubes arranged in a square pitch and supported as shown in Figure 4-3. This configuration replicates the first three hot leg supports of a typical Westinghouse D3 Series generator while conservatively simulating aspects of a CE unit. Four of the tubes were locked at their support (but not the FDB) location 'by tack welding in four locations. 'Ihe other four were free from the tubesheet to Support Plate No. 8. Two Tube Support Plate (TSP) sleeves and a. Roll Transition (RTZ) sleeve were installed in each tube as shown in the figure. The tubes were instrumented with strain gages to determine the strain in the outer fibers. During the heat treatment of each sleeve the strain in the tube was recorded. A load cell was used to determine the upper most section of tube. In the case of this mockup, the heat treatment commenced at the upper most weld and proceeded toward the tubesheet. Both sleeve welds (wh applicable) were treated prior to any strain gage rneasurements. A typical temperature / time plot is shown in Figure 4-4. The results of the test are shown in Table 4-4. As would be expected, the more times the tube segments expenences the heat treat cycle the greater the residual stress. Examination of the tube surfaces in the vicin the welds indicated [.

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j 4.1.6 Summary i In summary, C-E has conducted a comprehensive development and verification i to ensure weld integrity of its leak tight sleeves. Experience has shown that oxide layers as visually confirmed to exist on the steam generator secondary side do not a

' weld parameters and the abrasive cleaning method described in Section 3.3 is effective in preparing the tube for welding. Further, a method has been developed to stress relieve the welded sleeve to tubejoint to provide increased resistance to PWSCC.

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1 4.2 ROLLED JOINT INTEGRITY i A development program was conducted to ensure the rolled joint of the RTZ sleeve was

  • l leak tight and capable of withstanding the design loads. The sleeves were rolled into l

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mock-ups consisting of steam generator tubes which had been simulating the tubesheet. The sleeves were then tested to c j leak tight both before and after cyclic load testing. Tests of the j conducted where process parameters such as torque, tube diame

[

were varied.' A test matrix was ured to verify the sleeve inst

'is acceptable within the allowable rolling process to l.

j In someinsteadcases, tubes have been installed into steam genera expansion of rolling.

In this case, a slightly greater gap may exist between the tube and the tubesheet hole. The torque applied by ouldthe sle

( close that gap and cause the tube to contact the tubesheet hol j tool, either the tube would stay in placc or spring back. oIn the firs act as a rolled tube and in the second the spring back would provide holding force to the sleeve joint. For this reason thejoint is con

. application in this configuration as well as in a rolled tube.
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p Further verification of the acceptability of the rolled joint are the rolled steam generator tube plugs in service for up to ten (10) years. ,

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4 TABLE 4 ABB-CENO ACCELERATED PRIMARY SIDE SCC TESTS I l t

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WE TABLE 4-2 ENSA ACCELERATED PRIMARY SIDE SCC TEST (Reference 6.7) l 1

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TABLE 4-3  !

0.875 O.D. SLEEVED TUBE PWHT DATA i

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TABLE 4-4 1 0.750 O.D. SLEEVED TUBE PWHT DATA

__ TUBES LOCKED AT ALL SUPPORTS i

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MGURE 4-1 .

0.875 O.D. LOCKED TUBE TEST i t

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FIGURE 4-2 0.875 O.D. LOCKED TUBE TEST TEMPERATURE AND AXIAL LOAD PROFILE b

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,e MGURE 4-3 0.750 0.D. LOCKED TUBE MOCKUP 5

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0.750 0.D. TYPICAL TaiPERATURE PROFILES 3

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, 5.0 ST FFVE PERFORMANCE VERIFICATION _

5.1 COMMERCIAL SLEEVE INSTALLATION C-E's commercial sleeving experience is shown in Table 5-1.

This data is also compiled in Table 5-2 to indicate the number of EFPY of exposure sleeves in each of the specific plants have experienced. The steam generators in which sleeves have been installed have experienced various tube degradation mechanisms, primarily caustic secondary side attack and primary water stress corrosion cracking.

In one of these units, Ringhals 2, six (6) sleeved tubes which had seen up to three (3)

EFPY were removed when the steam generators were replaced in 1989 (Reference 6.4)

Examination of these sleeved tubes indicated weld heights consistent with ultrasonic inspection, acceptable weld penetration, and no evidence of any form of attack to the tube, sleeve, or the weld.

Recently over 1100 of these sleeved tubes at five plants have been inspected with one of two advanced eddy current probes (I-coil or Plus Point), which have been demonstrated highly effective in detecting cracks in sleeved tubes. Of these tubes,162 (62 with PWHT) have seen from 4 to 6.5 EFPY and the remaining 953 (523 with PWHT) from 1 to 2.5 EFPY (Table 4-2). These inspections revealed no service related defects.

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TABLE 5-1 INSTALLATIONS OF C-E'S WFT nED ST FFVE SLEEVE PLANT QUANTITY DAIE INSTALLFD =

ANO2 10/95 662 Zion 1 10/95 911 Zion 2 01/95 162 Prairie Island 1 05/94 117 Zion 1 11/93 61 KRSKO1 06/93 160 RTZ 14 TSP Ginna 04/93 51 Zion 2 12/92 172 Prairie Island 1 11/92 158 ASCO1 06/92 5 RTZ 49 TSP Ginna 04/92 175 63 curved Zion 1 04/92 124 Kewaunee 03/92 16 curved Ringhals 3 07/91 46 RTZ 22 TSP Ginna 04/90 192 .

1 48 curved {

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TABLE Sol INSTAT T ATIONS OF C-E'S WFT TTED ST FFVE (continued)

SLEEVE PLANT QUANTITY DATE INSTAT.T ED

  • Zion 2 04/90 83 Prairie Island 1 01/90 63 Zion 1 09/89 445 Ginna 04/89 395 107 curved Prairie Island 1 09/88 74 Ringhals 2 05/87 571 Ginna 02/87 105 Zion 1 10/86 128 '

Ringhals 2 05/86 599 Ginna  :

02/86 36 l

Ringhals 2 05/85 59 -

Ringhals 2

, 05/84 18

  • Straight sleeves unless otherwise noted I RTZ - Roll Transition Sleeve  :

TSP - Tube Support Plate Sleeve ,

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.m TABLE 5-2 Hot Leg Sleeve ABS-CENO SIG Sleeve 02:.ei;..s History fio July 19951 Plant Temp (F) Type (1) <t Es8 met,HI EFPY of Sleeve Opersson (2) t 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 T.01 Total t

Ringhals 2 6f0 STAW 16 600 STAW STI 599 59 16 1245 Ghne 601 STAW 51 178 183 198 400 104 PTAW 63 29 48 107

  • 36 1158 247 Prairie lsland(4) 590 STAW STHT ' 117 73 27 100 158 42 337 Kewaunee (4) 590 PTAW 16 16 I Zion 1 594 STAW 61 124 445 128 758 Zion 2 (4) 594 STAW 162 170 82 414 Rbghals 3 610 RTHT j 46 SPHT 46 22 22 '

KRSKO (4) 619 RTHT 164 l SPHT 16 164 +

16 4 '

Total Cumulegve Total 162 528 146 1014 0 866 262 0 577 120 0 177 I

0 63 4523 4523 4361 3833 3087 2073 2073 1207 945 945 368 240 240 63 l (3) 63

, Notes: i (1) Sleeve Type desipietons and heir totals are es fotows:

STAW Totals StandardTubesheet sleeves where the welds are h he As Welded comEgon PTAW 3737 STHT Per5heral(InlueIy Curved) Tubesheet sleeves where lhe welds are h he As Wek8ed condtlon i Stenderdiubesheet sleeves where the upper weld has been Post Wehl Hest Treated 263 RTHT i

roe Transigon sleeves where the weld het been Post Wold Heat Treeted 275 l SPHT 210 '

Support Plate sleeves where the welds have been Post Weld Heat Trested 38 (2) E?PY of operston is based either on date received from the plant or calculated from De load factor pt40shed h Hudeer Engineerhg Intemasonal for me period during which me sleeves have been h piece.

Operelhg Eme is rounded to he neares 0. I EFPY es of 1 July 1995 (3) 16 Sleeves which ran for a year et Ringhals 2 before T het was redaced are hebded h lotels for 600 F (4) Plants hopected wilh l<og or Plus Point ECT probe  !

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, 5.2 SLEEVE-TUBE CORROSION TEST-PROGRAM i

i In addition to the mechanical design described in Reference 6.1, the most signi aspect of a sleeved tube's performance is its resistance to the various corrosion mechanisms encountered in the steam generator. As described in Reference 6.1, i

has conducted a number of bench and autoclave tests to evaluate t

! resistance of the welded sleeve joint. 'Of particular interest is the effect of the i

mechanical expansion / weld residual stresses and the condition of the weld and weld heat affected zone. Various tests have been conducted under accel i assess the sleeve-tube joint performance under nominal and potential fault environmental conditions. Tests have been performed on welded joints with and

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without a post-weld heat treatment from which the relative margin afforded the sleeve life by applying such a process step can be estimated.

5.2.1 Primary Side i The life of the sleeved tube is mostly likely a function of the resistance of.the par!

tube area adjacent to the sleeve / tube joint to primary water stress corrosion cri (PWSCC). As is well documented elsewhere, this resistance will depend on three issues; the initial metallurgical condition of the tube, the stresses in the tube and the{ t temperature of thejoint. Barring operational changes, the temperature of thejoint will not differ from that of the parent tube nor in general will the metallurgical condition[ <

some cases, the grain growth and solution annealing that occurs in the weld heat affected zone may actually improve the resistance). Therefore, the single most  !

important difference in assessing the life of the sleeve /tubejoint from the priml is the state of stress associated with the installed sleeve.

ABB-CENO has performed analyses and tests, described above to evaluate the total stress state at the critical location of the tube I.D. surface immediately adjacent to the ,

weld. Preliminary tests confirmed that this location, as would be expected, contained  !

the highest residual stress and therefore the life determining area. The total stress stat associated with this area can be defined by its three components; the applied str;{

short range or micro residual stress, and long range or reaction stress.

Once the stress state for the specific plant conditions has been established, thi <

Arrhenius relation described by EPRI in Reference 6.5 can be used to make a relative assessment of the increased margin afforded by post weld heat treatment:

Lmrr / L4, = ( Smer / SAw)*

4 Page 24

. . , . . nn , -

.~

where:

Im = Life of the Post Weld Heat Treated sleeved joint Law = Life of the As Welded original tube S,wur = Stress in a Post Weld Heat Treated joint Saw = Stress in an As Welded Tube /Sleevejoint n = Empirically determined exponent (conservative value = 4) a) Sleeve Stress State Anolied Stmeae - The applied stresses were calculated using the finite element analysis of the tube / sleeve joint described in Reference 6.1 for the region immediately adjacent to the tube /sleevejoint. The combination of pressure and thernal stresses results in a low stress on the tube LD. surface. The compressive thermal stress is a result of the greater expansion of the sleeve relative to the tube due to its higher thermal expansion coefficient and higher temperature. This produi:es a bending moment on the I.D. surface and the corresponding.

compressive stress.

TABLE 5-3

- APPLIED SiRESSES IN BYRON /BRAIDWOOD TUBE SLEEVE JOINT

'W Micro Re=Uual Stre==as in the' Weld HAZ - The HAZ stresses due to t localized weld shrinkage have been determined from the accelerated corrosion tests, as described above. Under these conditions, stresses for the post weld heat treated joint were found to be on the order of [ . ].

Reaction Stre==e= in In+aA Tubes - When the tubes are locked at support locations due to denting or other mechanisms, the tube undergoes a compressive load during heating (whether by welding or PWHT) which shortens the tube and ,

causes some column buckling. During cooling the tube is putinto tension. The Pap M h

- - - - -~, _ . - - - - - -- - , - . . ~ , _ . - _ , . -

i magnitude of the resulting stresses depends on the am:unt of deformation which is a function of the temperature, length of the heated zone, and the time the tube is heated. In the case of the as-welded sleeve /tubejoint, the stresses are on the order of a few ksi. For the heat treated sleeve / tube joint the level of suess in a  ;

particular tube ranged considerably depending on the length of the locked tube span, the number of sleeves, and the location of the sleeves with respect to the -

tube section being measured. Although the worst case involves the installation of multiple sleeves in a single tube, the more common practice is to install only; a roll transition zone sleeve for which the stresses would be significantly less.

These stresses represent a worst case scenario and may not necessarily be present in all units. The locked condition described is less likely to be the case in a steam .

generator that has an open support structure design such as eggerates and/or-  !

where denting has not been experienced. However, inasmuch as it is difficult to  :

determine whether tubes are locked, the assumption is that they are locked.

+

TABLE 5-4 TOTAL AXIAL STRESS ASSOCIATED TUBE / SLEEVE JOINT m '

i i

1 l

\

n I

t I

M i

I

  • l

)

I l

Page 26

0 Using the above relationship and the stresses given in Table 5-4, the relative improvement in sleeve joint life for a post weld heat treated sleeve as compared to one in the as-welded condition is expected to range from [ ] depending on the number of sleeves installed in a particular tube.

[ ] i 5.2.2 Secondary Side The life of the sleeved tube from the steam generator secondary side environment depends on interactions at two locations on the sleeved tube. First with respect to j the tube at the location immediately above the weld on the O.D. surface. Second, if '

the original mode of tube failure was from the secondary side, in the annulus between the tube and the sleeve. '

By the very nature of the weld joint in both an RTZ, TS and TSP sleeve, it must be located outside a region where fault species are capable of concentrating, i.e..

tube / support intersections or sludge pile. Therefore the principle environment i i

experienced by the tube O.D. in the vicinity of the weld is the volatile secondary

)

side chemistry. His environment is similar to that of the primary side in that it j

consists of very pure water witho::t the aggravating factors of hydrogen and the i higher primary side temperature. Herefore, stress corrosion cracking from the tube O.D. due to secondary side environments is not considered likely at the weld location. ,

i In the annulus between the tube and the sleeve, it may be possible to concentrate '

whatever fault species had caused the initial failure of the tube. In this case the failure of the sleeve / tube combination would be dependent on the sleeve and sleeve weld's resistance to the concentrated species as well as the time it took for the environment in the annulus to develop. Corrosion testing performed on tube / sleeve assemblies as well as that performed on thermally treated Alloy 690 itself

.(Reference 6.1) shows that the sleeve and weld offer superior resistance to the typical fault environments which may form in this region. Any detrimental effect of the sleeve installation on the tube would result in only further degradation of the tube in that area where the sleeve has established the fluid boundary. Inasmuch as no credit is taken for the original tube in this region, the structural integrity of the assembly would not be degraded.

i I

Page 27 e

., -y+, ,- ,_ . . , - ~ - . . . - -

- . . ~ --. - - _

. e y

5.3 SLEEVE-TUBE INSPECTION -

i As described in Reference 6.1, the inspection of new sleeves is performed both ultrasonic (UT) and eddy current (ECT) examination methods.

Ultrasonic inspection is used only upon the initialinstallation of the sleeve. Subsequent t installation a multi frequency eddy current testing is performed on the sleeve and sleevejoint as a baseline for future in service examinations. At present, the ECT method being employed utilizes the Plus Point probe considered to be among I current state of the art.

I 5.4

SUMMARY

The operating performance of the welded tube sleeve has been shown to p acceptable service life in a variety of steam generators both in the as-welded and i

post weld heat treated condition. Corrosion testing and evaluation of sleevedi even under conditions of considerable tube restraint, have demonstrated the i

beneficial effects in stress corrosion cracking resistance associated with po heat treated joints. Further, inspection methods have been developed and that are sufficiently sensitive to detect tube and/or sleeve defects in accordance present industry standards.

As such, periodic inspection and leakage monitoring willidentified, be ensure that any premature degradation that may occur in the sleeved join i

Page 28

o

6.0 REFERENCES

6.1 i CEN-621-P, Commonwealth Edison Byron and Braidwood Unit 1 & 2 Steam Generator Tube Repair Using Leak Tight Sleeves, April 1995.

6.2 00000-ESE-881, Qualification of the Post Weld Heat Treatment Tool for

' Westinghouse "D" Series Steam Generators, September 1992.

6.3 i TR-MCC-153, Summary Repon, Combustion Engineering Steam Generator Tube  !

Sleeve Residual Stress Evaluation, November 1989.

6.4 Private Report, Laborelec Laboratory, Bruce 1<, Belgium,1990.

I i

6.5 EPRI NP-7493, Statistical Analysis of Steam Generator Tube Degradation, 1991.

6.6 EPRI NP-4364-LD, Specification for In-Situ Stress Relief of PWR Steam Generator

{

Tube U-bends and Roll Transitions, December 1985. '

6.7 Private S. A.,1992. Report, Sleeving Qualification Program Final Report, Equipos Nucleares, I

1 4

4 J

4 d

1 A

4 k

5 e

i 5 _

- . .