ML20236U475
| ML20236U475 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 07/23/1998 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20236U470 | List: |
| References | |
| NUDOCS 9807300185 | |
| Download: ML20236U475 (65) | |
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4 Comed BYRON STATION UNIT 2 COMMERCIAL OPERATION: 08/21/87 STEAM GENERATOR EDDY CURRENT INSPECTION REPORT CYCLE 7 REFUELING OUTAGE (B2R07)
April 1998 Comed P.O. Box 767 Chicago,IL 60690 Byron Nuclear Power Station 4450 North German Church Road Byron,liimois 61010 l
l Documentation Completed Date: July 23,1998
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TABLE OF CONTENTS 1.0 I INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0
SUMMARY
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l 3.0 CERTIFICATIONS .. . .. ... ... ... . .. . ... . . .. . . . . . . . . . . . . . . . . . . . .........2 ;
1 3.1 Procedures / Examinations / Equipment..... ......... ........ .... . .. 2 3.2 P e rso n n o l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4.0 EXAMINATION TECHNIQUE AND EXAMINATION SCOPE....... ........ 3 4.1 Examination Techniques.... .... .. . . ..... .. . . . . ...........3 4.2 Recording of Examination Data... . . ... ... ,. .. ... ... .... . .. .. . .... . 4 4.3 Witness and Verification of Examination... ............ ............ .. 4 5.0 EXAMINATION RESULTS...... .....................................4 5.1 Indications Found... ... . . .. . . .. .. ... ... ..........................4 5.2 Othe r R esu lts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . G 6.0 R EPA I R S U M MARY. . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 7.0 TUBE INTEGRITY ASSESSMENT
SUMMARY
.. ... .. .. ..... ..... . ... . 7 7.1 Insitu Pressure Testing... ... .... ... ... . . ... ... . .. ................7 7.2 Tube Pull Results. . . . ... . .. ... .. .. . . .. . . . . .. . .. . . .. . . . . . . . . ......8 7.3 Condition Monitoring / Operational Assessment....... ... .. .... ... 8 8.0 DOCU M ENTATI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . 10 9.0 FIGURES / TABLES / ATTACHMENTS... ... .. . ... ... .. . .. . . .. ... ... ... .10
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1.0 INTRODUCTION
Byron Unit 2 operates with four Westinghouse Model D-5 recirculating steam generators (SGs) in the four loop pressurized water reactor system. The steam generators contain thermally treated inconel-600 U-tubes that have a nominal outside diameter of 0.750 inches and a nominal thickness of 0.043 inches.
See Figure A.1 for a diagram of the D-5 Steam Generator configuration, in compilance with Byron Station Technical Specification 4.4.5 and ASME Section XI (lWB 2500-1, Exam Category B-Q, item B16.20),1983 Edition through the Summer 1983 Addenda, SG eddy current examinations were conducted by Framatome Technologies, Inc. (FTI) during the Byron Unit 2 Cycle 7 refueling outage. In addition, the inspections were performed in accordance with Revision 5 of the EPRI PWR SG Examination Guidelines. The inspections were conducted from April 15 through May 5,1998.
The following inspections were performed during this outage:
- 100% Full Lengtn Bobbin Coil in all 4 SGs
- 100% Top of Hot Leg Tubesheet Plus-Point in all 4 SGs
- 100% Row 1 and Row 2 U-Bend Plus-Point in all 4 SGs 25% Pre-Heater Baffle Expansions in SG A
- 100% Plus- Point of Hot Leg Dents >5.0 Volts
- Visual Inspection of Secondary Side of SG C
- Visual Inspection of Top of Tubesheet Region in all 4 SGs
- Visual inspection of Previously Installed Tube Plugs 2.0
SUMMARY
The requirements of Revision 5 of the EPRI PWR Steam Generator Examination Guidelines were implemented during this inspection. A degradation assessment was performed to ensure that only EPRI Appendix H qualified examination techniques were used. Each technique was evaluated to ensure that the detection and sizing capabilities are applicable to the Byron Unit 2 site specific condition. All data analysts were qualified to Appendix G of the EPRI SG Examination Guidelines. All data analyst and data acquisition personnel satisfactorily completed site spe::ific training and testing.
The major modes of active tube degradation found during this inspection were anti-vibration bar wear, circumferential indications at the hot leg expansion transition, loose part wear, pre-heater wear, and outer diameter volumetric freespan indications. This was the first inspection at Byron Unit 2 that circumferential indications at the top of the tubesheet had been f >und. Insitu pressure testing was performed on 4 of the circumferential indications and 3 of those tabes were removed for laboratory analysis to further characterize the indications.
As a result of the eddy current inspections, a total of 38 tubes were repaired by tube plugging. Table 2.1 provides the total number of tubes plugged by degradation mode. All tubes with circumferential indications were stabilized and plugged. Table 2.2 provides the equivalent tube plugging levels for each SG.
TABLE 2.1 Tubes Repaired during B2R07 Mode of Degradation e - SG A* u SG B L = SG C SG D : Total s
! Circumferential Indications si TTS 5 23 1 0 29 I
Anti-Vibration Bar Wear 1 0 0 0 1 Loose Pad kVear 0 2 1 0 3 Other 1 1 3 0 5 Totals / 7J 26^ '5 0: 138 1
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TABLE 2.2 Equivalent Tube Plugging a SO A* 780 Se 280 C4 5 SG D e aTotelH Previously Plugged 42 75 33 17 167 4 Plugged in B2R07 7 26 5 0 38 )
Total Plugged 49 101 38 17 205 j Total Plugged (%) 1.07 % 2.21 % 0.83% 0.37 % 1.12% l 3.0 CERTIFICATIONS 3.1 Procedures / Examinations / Equipment 3.1.1 The examination and evaluation procedures used during the eddy current-inspection were approved by personnel qualified to Level til in accordance with the 1984 Edition of SNT-TC-1A. Comed procedures NDT-E-2, Revision 1, and NDT-E-3, Revision 0, were used for data acquisition and analysis, respectively.
3.1.2 The examinations, equipment, and personnel were in compliance with the requirements of the Comed and FTl QA Manual for Inservice Inspection, Byron Technical Specification 4.4.5,1983 Edition through Summer of 1983 Addenda of Section XI of the ASME Boiler and Pressure Vessel Code, EPRI PWR SG l Examination Guidelines, Revision 5, and industry standards.
3.1.3 Certification packages for examiners, data analysts, and equipment are available at Byron Station. Table A.1 and Table A.2 lists all personnel who performed, supervised, or evaluated the data during this inspection.
3.1.4 MlZ-30 Remote Data Acquisition Units (RDAUs) with EddyNet 95 Version 4.28 software was used in the acq2ition of the eddy current data and EddyNet 95 Version 4.28 software was used in the analysis of the data.
3.2 Personnel 3.2.1 The personnel who performed the eddy current inspections were qualified to Level I and Level 11 in accordance with the 1984 Edition of SNT-TC-1A. The Level I personnel performed the inspections under the direct supervision of Level ll personnel.
3.2.2 The personnel who performed the data analysis were qualified to a minimum of Level 11, with special analysis training (llA) in accordance with the 1984 Edition of SNT-TC-1 A, FTl and Comed procedures, i1 .3.2.3 All eddy current data analysts analyzing data were qualified in accordance with L EPRI Appendix G for Qualified Data Analysts (QDA).
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}' 3.2.4 All eddy cunrent data analysts were trained and tested in accordance with a site specific performance demonstration program in both bobbin eddy current data 2
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and Rotating Pancake Coll (RPC)/Plus-Point data. The analysts were required to achieve a score of 80% or greater on this site specific demonstration exam.
3.2.5 All eddy current data acquisition operators were trained and tested to a site specific acquisition training program. The data acquisition operators were required to achieve a test score of 80% or greater.
3.2.6 The eddy current analysis was subject to two independent analyses. Primary analysis of all data was performed by FTl and Rockridge Technologies, Inc . An independent company, Zetec, performed the secondary analysis. Discrepancies l between the two parties required Level lli concurrence between both parties for l the final resolution.
3.2.7 An experienced eddy current Level lli QDA was employed to serve as a Process Control Reviewer to randomly sample the data to ensure the resolution process was properly performed and that the field calls were properly reported.
1 4.0 EXAMINATION TECHNIQUE AND EXAMINATION SCOPE i All eddy current examination techniques used are qualified in accordance with Appendix H of the EPRI SG Examination Guldelines. Each examination technique was evaluated to be applicable ,
to the tubing and conditions of the Byron Unit SGs.
4.1 Examination Techniques 4.1.1 All inservice tubes in each SG were inspected full length utilizing a 0.610 inch diameter M/ULC bobbin coil eddy current probe. For U-Bend regions and cold ,
leg tubing in rows 1 through 3, a 0.590 inch diameter spring flex bobbin probe !
was utilized to achieve the complete full tube inspection. Nominal probe inspection speed was 40 inches per second for rows 4 through 49 and 24 inches per second for rows 1 through 3. Sufficient sampling rates were used to maintain a minimum of 30 samples per inch. The bobbin coil probes were operated at frequencies of 550 kHz,300 kHz,130 kHz, and 20 kHz operating in the differential and absolute test modes. In addition, suppression mixes were used to enhance the inspection. These mixes were as follows: 550/130 kHz differential mix, 300/130 kHz absolute mix and a 550/300/130 kHz differential mix.
4.1.2 All inservice tubes in each SG were inspected at the top of the hot leg tubesheet expansion transition region with a 0.610 inch diameter three coil plus-point eddy current probe. The examinations were performed 2* sbove to 2" below the secondary tubesheet irferface. The probe contained a mid-rcnge plus-point coil, a 0.115 inch diameter pancake coil and a 0.080 inch diar,teter mid-range pancake coil. Nominal probe speed was 0.5 inches per second with a sampling rate to maintain a minimum of 30 samples per inch. The probe was operated at frequencies of 300 kHz,200 kHz,100 kHz and 20 kHz operating in the absolute test mode. Three process channels were created to disp!4 .sxial indications in a positive trace.
4.1.3 25% (34 tubes /68 baffle expansions ) of the tubes in the SG A pre-heater that were expanded into the baffle plates were inspected utilizing a 3 coil plus-point probe described in Section 4.1.2.
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l 4.1.4 All U-Bend regions of tubes in rows 1 and 2 in each SG were inspected utilizing a l 0.580 inch diameter magnetically biased U-Bend plus-point probe. Nominal probe speed was 0.15 inches per second with a sampling rate to maintain a minimum of 30 samples per inch. The probe was operated at frequencies of 400 kHz,300 kHz, 150 kHz and 20 kHz in the absolute test mode Three process channels were created to display axial indications in a positive trace.
, -4.1.5 Tubes containing dents at Hot Leg tube support plates that were sized greater than '
5.0 volts and non-quantifiable indications identified by an "!-Code" were examined with a rotating plus-point probe described in Sechon 4.1.2. The nominal probe speed for inspechon of dents was reduced to 0.15 inches per second while maintaining a minimum sampling rate of 30 samples per inch. l Note: See Figures B.1.1 through B.4.1 for tube sheet maps of the inspections
. performed during B2R07.
'4.2 Recording of Examination Data Results of tne eddy current data analysis were recorded on optical dins. The data was
- then loaded into the FTl Eddy Current Data Management System Tuban 11. This system was used to track the proper examination of all tubes and it was also used to generate the final eddy current report summaries.~ A Zetec dual data management system was also utilized as a second independent data management system.
4.3 Witness and Verification of Examination Eddy current inspechons were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors Mr. Jeff Hendricks and Mr. Greg Feigel of the Hartford Steam Boiler inspection and insurance Company of Hartford Connecticut, Chicago Branch,2443 Warrenville Road, l Suite 500, Lisle, Illinois 60532-9871.
5.0 EXAMINATION RESULTS 5.1 Indications Found l 5.1.1 Anti-Vibration Bar (AVB) Wear - Tube degradation was found by the 100% bobbin
!. coil examination in the U-bend region due to fretting of the Anti-Vibration Bars on the tube. A total of 467 tubes contained 776 indications of AVB wear. The bobbin coil examination technique utilized in this inspection was EPRI Appendix H qualified
- for the depth sizing of AVB wear. One tube (SG A , Row 36 Column 16) was removeo from service as a result of AVB wear. This tube contained a 43% through-
-wall (TW) wear indication at the second AVB. The table below provides a summary of AVB Wear degradation.
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<20% TW 83 94 133 162 102 117 66 73 384 446 1 20-39% TW 75 112 72 101 62 80 29 36 238 329
>= 40% TW 1 1 0 0 0 0 0 0 1 1 TOTAL
- 118 207 150 263 125 197 74 109 467 776
- Tubes may contain indications in more than one category.
5.1.2 Too of Tubesheet Circumferential Indications - Circumferential indications were found by the plus-point probe at the hot leg expansion transition during the 100%
top of tubesheet plus-point inspection. A total of 29 tubes contained q circumferential indications. Four indications were insitu pressure tested to verify structural integrity. . No leakage was measured up to a pressure of 3 times normal operating differential pressure. Three of these indications were removed for laboratory testing to determine the mode of degradation. All tubes with circumferential indications were conservatively stabilized and plugged. The three tubes that were removed had a welded plug installed on the hot leg tube I_ .end and a rolled plug installed on the cold leg. Preliminary tube pull results l indicate that the circumferential indications were not service induced cracking or corrosion, but a shallow groove that may have been caused during initial SG fabrication or first few cycles of operation. Burst testing of the indications showed that the indications have no impact on the structural integrity of tubes.
l Table 2.1 provides a summary of circumferential indications found and preventatively plugged.
5.1.3 Foreian Obiect . Pre-Heater Wear - Tube degradation was found on three tubes that was attributable to fretting from foreign objects. The objects (weld slag, gasket material and a fabrication part) were visually identified and removed in either this outage or during a previous outage. An EPRI Appendix H site qualified technique was not applied to size the indications, therefore, all three tubes were removed from service. Four tubes were found that contained indications of pre-heater wear. The depth of the pre-heater wear ranged from 3% TW to 20% TW as measured by the EPRI Appendix H qualified technique.
All four tubes had indications less than the Technical Specification pluggli,g limit of 40% TW and were consequently left inservice. Table 5.1.3 below l- provides a summary of tubes that contain Foreign object and Pre-Heater wear.
TABLE 5.1.3 S 8G A e - e SG 8s ( SG C " '
+ SG D '
e Totals Foreign Object Wear 0 2 1 0 3 Pre-Heater Wear 1 3 1 0 5 l' 5.1.4 Qther Indications - Four tubes were found that contained volumetric indications on the ou'er diameter near the top edge of tube support plates. The indications were initially detected by the bobbin coil examination and confirmed by a subsequent plus-point probe examination. Previous history and experience did not reveal the presence of foreign objects, however, the indications were very similar to wear scars left by foreign object wear. An EPRI Appendix H site 5
- qualified technique was not applied to size the indications, therefore, all four tubes were removed from service. One tube in SG B (Row 2 Column 57) contained a large geometry distortion in the U-bend region. No degradation was detected by the bobbin coil or plus-point probe examinations. This tube was
< removed from service as a preventative measure. Table 2.1 provides a summary of these indications.
6.2 Other Results 5.2.1 Low Row U-Bend Plus-Point insoection - All row 1 and row 2 U-bend regions ,
were inspected with a plus-point probe. No tube degradation was found. One tube was removed from service due to a large geometric distortion as described in Section 5.1.4.
1 5.2.2 . Pre-heater Exoansion Plus-Point inspection - A sample of 25% of the pre-heater baffle expansions in SG A were inspected with the plus-point probe. No degradaan was found.
5.2.3 Dents > 5.0 Volts Plus-Point inspection - All dents at hot leg tube support plates that were greater than or equa! to 5.0 volts (147 dents) as measured by the bobbin coil were inspected with a plus-point probe. No degradation was found.
5.2.4 Visual Inspection of Secondary Side - Secondary side visual inspections were performed in the upper tube bundle of SG C. Access was gained through inspection ports at the 11* (top) support plate and the 8* support plate. A video probe was used to inspect accessible portions of the divider lane, tube periphery lane and inner tube bundle. The video p* robe was also lowered through flow holes to inspect llmited portions of the 10 , 9*, 7* and 6* support plates. In addition, the top of the tubesheet region was inspected before and after sludge lancing. ' During these inspections, the following intemal components were inspected: 20 back-up bars,2 tube support plate anti-rotation blocks,6 wedges, 2 tie rod nuts,3 tie rod assemblies at the 8* support plate, 3 Jacking studs,6 i tube support plates, and 4 flow distribution baffles. No degradation was found.
5.2.5 Visual Inspection of Previousiv Install Pluas - All previously installed plugs on the hot leg and cold leg tube ends were visually inspected for signs of degradation and leakage. A total of 22 welded plugs and 376 mechanically )
rolled plugs were visually inspected. in addition, all plugs installed during this )
outage were also visually inspected. No degradation or abnormal leakage was found.
6.0 REPAIR
SUMMARY
Repairs were conducted in accostlance with ASME Section XI,1983 Edition through the Summer 1983
! Addenda. Attachment C of this report documents all repairs performed for each steam generator. All l repairs were performed using inconel-690 material. All iepairs were performed in accordance FTl L L approved procedures. Table 6.1 depicts the repairs conducted during B2R07. Table D.1 lists the tube locations thf vere repaired in B2R07.
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1 REPAIR 8 PERFORMED 4 <
r SG A7 r SG B c : SG C? 4 80 D 3 sTOTAL Tubes Plugged
- 7 26 5 0 38 Tubes Stabilized 5 20 1 0 26 Tubes Removed for Laboratory Analysis" 0 3 0 0 3 Includes number of tubes stabilized and tubes removed, j
" 'Three tubes were removed for indications at the hot leg expansion transition. These tubes were l plugged with a welded plug at the hot leg tube end and a mechanical plug at the cold leg tube end.
l' 7.0 TUBE INTEGRITY ASSESSMENT
SUMMARY
1 I
Tube integrity assessments were performed to demonstrate that SG performance for each mode of tube degradation met the required structural integnty requirements for the previous operating period, Cycle 7, and for the next operating period, Cycle 8. The assessment for the previous cycle is a condition monitoring assessment and the assessment for the next cycle is an operational assessment. Insitu pressure testing and tube pull testing results were used to L supplement the inspection results as input to these assessments. There was no primary to secondary leakage detected during Cycle 7 or upon shutdown for B2R07.
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7.1 Insitu Pressure Testing insitu pressure testing was performed on four tubes in SG B that contained circumferential indications at the expansion transition at the top of the hot leg tubesheet (TTS). The insitu pressure testing was performed by FTl using a localized insitu pressure testing probe. The test system design and tube selection were in accordance with the draft EPRI insitu Pressure Testing Guidelines. Testing was performed at differential pressures associated with normal operation (NOP), main steam line break (MSLB), and 3 times normal operating differential pressure (RG 1.121). The test pressures were corrected for temperature differences between test and operating conditions. The Regulatory Guide (RG) 1.121 pressure test is the most limiting to meet the Regulatory Guide 1.121 tube integrity requirements. No leakage was detected at any of the test pressures.
Table 7.1 summarizes the tubes tested and the leakage results.
Tab!e 7.1 Insitu Pressure Test Results s NOP Leak s : M8LB Leak x e RG 1.1214 cTestJ _ . . -. .
.. 2 Test t . f Test ? . . . ! Structural TestL tNot ?SG' 4Tubex vindication 0 L(1800 psig)J ..!(3000 psig) ? "(4700 psig)5 1 B 27-32 SCI at TTS No Leakage No Leakage No Leakage l 2 B 34-96 SCI at TTS No Leaktge No Leakage No Leakage
(. 3 8 37-89 SCI at TTS No Leakage No Leakage No Leakage 4 8 40-88 SCI at TTS No Leakage No Leakage No Leakage 1
7.2 Tube Pull Results
. Three tubes that contained circumferential indications at the hot leg expansion transition at the top of the tubesheet were removed from SG B. Two tubes were cut 3 inches below the 3"' support plate and one tube was cut 3 inches below the 5* support plate.
The tubes underwent laboratory testing in order to assess and characterize the mode of degradation and root cause. The testing included non-destructive testing, visual and dimensional examination, leak and burst testing, scanning electron microscope and energy dispersive spectroscopy examination and destructive metallurgical examination.
The laboratory.non-destructive and visual examinations confirmed that circumferential indications were present on the outer diameter of each tube at the expansion transition.
Each indication was characterized as a circumferentially oriented groove located undemeath deposits just above the top of the tubesheet.
Leakage and burst tests were performed on each tube section that contained a circumferential indication. The tubes were pressurized to pressures associated with normal operating, MSLB and the limiting RG 1.121 structural integrity conditions (1600 psi,3000 psi and 4700 psi, respectively). No leakage was observed. The tubes were ,
then pressurized to burst. Testing on two tubes ended when the extension portion of the support simulation burst at 10,200 psi and 11,300 psi. The tube samples did not burst. i One tube burst axially in a ductile manner at 11,100 psi at a location approximately 1 I inch from the top of the tubesheet. The burst location was not at the location of the circumferential indication. Post burst examinations revealed no evidcace of cracking.
Following the leakage and burst testing, the top of tubesheet region of each tube was sectioned for destructive examination. Examination results for each tube revealed evidence of a shallow circumferential groove with smeared metal on the outer diameter of the tube. There was no evidence of any type degradation such as wear, erosion, stress corrosion cracking, intergranular attack. The absence of degradation and the presence of smeared metal would indicate that the indications were caused by I mechanical daenage during initial fabrication or during the first few cycles of operation.
7.3 Condition Monitoring / Operational Assessment 7.3.1 Anti-Vibration Bar Wear The structural limit for AVB wear is 77% TW and the Technical Specification l repair limit is 40% TW. The deepest AVB wear indication found during B2R07 I was 43% TW, which is well below the structural limit, and this was the only indication greater than the repair limit. An indication of this size would r101 be expected to leak during accident conditions. This tube was removed from service. Cycle 7 condition monitoring for this mode of degradation is l
. acceptable.- ;
An operational assessment was performed to compare the largest predicted flaw '
- . at the end of Cycle 8 (1.412 effective full power years) to the structural limit. l l This was performed by combining the largest flaw left inservice with NDE uncertainty and an allowance for growth using the largest growth rate from previous inspection results over the expected-cycle length. The largest flaw predicted at the end of Cycle 8 is 56% TW, which is well below the structural limit of 77% for AVB wear. This results in an acceptable operational assessment.
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7.3.2 ~ ClaumferentialIndications The largest circumferential indications were insitu pressure teste;d up to pressures associated with the most limiting accident conditions and to the structural limit of Regulatory Guide 1.121. No leakage was observed. Three indications were removed for laboratory analysis and underwent burst testing.
The ir,dicetions did not burst up to pressures over 10,000 psi. All indications (29) found during B2R07 were repaired by tube stabilizing and plugging. The condition monitoring results are acceptable.
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h Based upon the tube pull results, this degradation mechanism is not service
!. Induced and therefore will not challenge structural Integrity at the end of C/cie 8.
! Therefore, resulting in an acceptable operational assessmerst.
l 7.3 3 Volumetric /Foreion Obiect Indications For the condition monitoring assessment, the largest flaw found of this l degradation mechanism was sized and found to be 41% TW. This is well below l
the 65% structural limit for uniform wall thinning. The use of a uniform wall thinning limit is very conservative when applied to localized volumetric flaws. All tubes that contained this type of degradation were removed from service upon
- ection, regardless of size. Due to the size of these flaws, no leakage would
, be ex,Mai e' accident mr.ditions. The results of condition monitoring for this
- j. degradation mechanism is acceptable.
All identified foreign objects were retrieved from the SGs and all tubes with this type of degradation were removed from service. Therefore, degradation due to foreign objects are not predicted to cause dama0e in excess the structural or leakage limits daring Cycle 8.
7.3.4 Pre-heater Wear The structural limit for pre-heater wear is 67% TW and the Technical Specification repair limit is 40% TW. A total of 5 tubes contained indications of pre-heater wear with the deepest flaw being 20% TW, which is well below the structural and repair !!mits. An indication of this size (20% TW) would not be expected to leak during accident conditions. All 5 tubes were left inservice.
Given the low growth rates experienced with the pre-heater wear and the low NDE sizing uncertainty, the end of Cycle 8 tube leakage and tube integrity are expected to be acceptable. Cycle 7 condition monitoring and Cycle 8 operational assessments for this mode of degradation are acceptable.
7.3.5 Secondary Side intemal Inteority inspection results found the condition of the SG secondary side intemals to be acceptable with no observations impacting tube integrity. No problems were encountered with inserting sludge lance equipment through the access ports, l
thus indicating that the wrapper remains in place. Eddy current analysis did not identify any missing or degraded support plates. No tube wear was found that could be attributable to loose parts from the pre-heater water box components.
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l 8.0 DOCUMENTATION All original optical disks have been provided to Comed and are maintained at f?yron Station. The l final data sheets and pertinent tube sheet plots are contained in the FTl Final Outage Report for Byron Unit 2, B2R07, and are also maintained at Byron Station.
9.0 FIGURES / TABLES / ATTACHMENTS ATTACHMENT A CONTENTS Table A.1 Data Acquisition Personnel Certification List Table A.2 Data Analysis Personnel Certification List Figure A.1 Westinghouse Model D-5 Tube Support Configuration ATTACHMENT B CONTENTS Figure B.1.1 SG A Bobbin Collinspection Scope
- Figure B.1.2 SG B Bobbin Coil Inspection Scope Figure B.1.3 SG C Bobbin Coll Inspection Scope Figure B.1.4 SG D Bobbin Coil Inspection Scope Figure B.2.1 SG A Hot-Leg Top of Tubesheet Plus-Point inspection Scope Figure B.2.2 SG B Hot-Leg Top of Tubesheet Plus-Point inspection Scope Figure B.2.3 SG C Hot-Leg Top of Tubesheet Plus-Point inspection Scope Figure B.2.4 SG D Hot-Leg Top of Tubesheet Plus-Point inspection Scope Figure 8.3.1 SG A Low Row U-Bend Plus-Point Inspection Scope Figure B.3.2 SG B Low Row U-Bend Plus-Point inspection Scope Figure B.3.3 SG C Low Row U-Bend Plus-Point inspection Scope Figure B.3.4 SG D Low Row U-Bend Plus-Point inspection Scope Figure B.4.1 SG A Pre-Heater Expansion Plus-Point inspection Scope ATTACHMENT C CONTENTS Figure C.1.1 SG A Anti-Vibration Bar Wear Indications l Figure C.1.2 SG B Anti-Vibration Bar Wear Indications l
l Figure C.1.3 SG C Anti-Vibration Bar Wear Indications l Figure C.1.4 SG D Anti-Vibration Bar Wear Indications Figure C.2.1 SG A Circumferential and Volumetric Indications Figure C.2.2 SG B Circumferential and Volumetric Indications Figure C.2.3 SG C Circumferential and Volumetric Indications {
Table C.3.1 SG A ASME Form NIS-BB Table C.3.2 SG B ASME Form NIS-BB i Table C.3.3 SG C ASME Form NIS-BB l Table C.3.4 SG D ASME Form NIS-BB 10 l
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, ATTACHMENT D CONTENTS Table D.1 Tubes Repaired During B2R07 I I
Figure D.2.1 SG A Tubes Repaired During B2R07 Figure D.2.2 SG B Tubes Repaired During B2R07 Figure D.2.3 SG C Tubes Repaired During B2R07 i
i Figure D.3.1 SG A ASME Form NIS-2 }
Figure D.3.2.a SG B ASME Form NIS-2 (Mechanical Plugging)
Figure D.3.2.b SG B ASME Form NIS-2 (Weld Plugging)
Figure D.3.3 SG C ASME Form NIS-2 t
l Figure D.4 ASME Form NIS-1 I
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TABLE A.1
. DATA ACQUISITION PERSONNEL CERTIFICATIONS rNo.s; q #awne F Co. s; Level 2 ; QDAt.
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FIGURE D.3.1 l SG A ASME FORM NIS-2 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT is L
- As Required by the Provisions of the ASME Code Section XI
- 1. Owner Commonwealth Edison Company Name Date _ - [
One First National Plaza, Chicago, II.
Address Sheet I of 2.
- 2. Plant Byron Nuclear Power Station Unit 2 Name 4450 N. German Church Road, Byron, II. Work Request No. 9(av///9/ 7 43 Address Repair Oigam2ation. P.O. No. Job No.. etc.
- 3. Work Performed by Framatome Technologies Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable j 155 Mill Ridge Road, Lynchburg, VA. Expiration Date Not Applicable Address
'.l J Identification of Systu, RC A 1 5, (a) App.'icable Construction Code Section III 19 71
$*YfY Edition, S72W74* Addenda, J355, ' !S : Code Case
~
' f 3, W^3-i 474-1 (b) Applicable Edition of Section XI Utilized for Repairs or Replacement Components 19 83/S83
- 6. Identification, of Com.3..ents Repaired or Replaced and Replacement Components hassonal Repaared.
Name of Name of Manufsen.rer ASME board Other Year Replaced.
. componene Manufacturer Cede. Sumped Serial No No idenisficanon 1 Built or Replacement (Yes or Noi Steam Generator Westinghouse i
g -
2RC0186 Yes 1980 Repa,i red
.\techamcal plug - Framatome SEE' i
Technologies S g p,SHeT T #.
- /// #// Repair No l
l i
l l
l' I
i l
~
7.
l DescriptionofWork Sir 5vFPLEMENTAL S#f(75 /d 193e5 PtoccED
- 8. Test Conducted: Hydrostat.ic 0 Pneumatic Nominal Operating Pressure O kd Other - Pressure psi Test Temp. 'F Note:
Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is 8 l/2 in. x 11 in.,
(2)information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. '
his form has been electronically generaud, 'W 14 applicable ror NB 2331(D). NB-2332(A)(2). NB4332. NB4334. NB-43341. 4334.2. NB4333.t.2. &3 f
- - . ~
KMb1 N1S-2 (Bick)
- 9. Remarks -
Apphcapie Manuta:ru et a usu Krports to De enactwa WR %0lllqJ7 l
l l
I.
I CERTIFICATE OF COMPLIANCE I
We certify'that the statements made in the report are correct and this L,mgconforms to the rules ofth: ASME Code, l Section Xt. '
w.- ,
i Type Code Symbol Stamp No[ A jlff/<
' Certi6cate of Authorization No.]o[ A p l ggt Expiration Date [o/ A pffadf Signed f- s yM-j- . _ fZ Date 1}y is' ,191 l
CERTIFICATE OF INSERVICE INSPECTION i
I, the undersigned, holding a valid com, mission issued by the National Board of Boiler and Pressure Vessel Inspeco State or P.7vince of j/4ap/S and employed by & ysy t*p of - MS/ M /d feee ed h j uf- __ have inspecte the j components described in this Owner's Re' port during the period 4/py to y j// , and state that to the best of my
' knowledge and belief, the 6w6er has performed examinations and t 'e corrective measures described in the O
. in accordance with the requirements of the ASME Code,Section XI.
By signing this certi6cate neither the inspectos nor his employer makes any wananty, expressed or implied, conc examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor shall be liable in any manner '
for any perscual injury or property damage or o loss of my kind arising from or connected with this inspection.
M .{
Commissions
/24w ./,E4/ . .=_
'{
- j i
' Date *'
M j.f , 19 pg !
/
Il l
i -
I
- ____________________.___________.m.__ _ _ . _ _ _ _ . . _ _
7,w,_ k -
g C
L(,; '
(.
FORM NIS-2 SUPPLEMENTAL SHEET -
P 1. Owner: Commonwealth Edison Company Sheet 1 of - 1 ,
One First National Plaza Date S'/g ju Chicago, Illinois 60690 Unit 2 2, Plant ' Byron Nuclear Power Station. Unit 2, 4450 N. Greman Church Road Byron, Illinois 61010 960111q17 P.O. No., WR No., etc.
- 3. ' Work Performed by: Fiamatome Technologies Type Code Symbol Stamp Not Applicable 1 Name Authorization No. Not Applicable 155 Mill Ridge Rd. Expiration Date
~
Not Applicable Address 4; Identification of Systen Reactor Coolant Sa.' Applicable Co truction Code Section Ill' 19 71 Edition S72 W74* Addenda Code Case $ g ' .' f ', ' !", ' f 2', ' T- P,474 1.
5.b A ppScable ' Edition of Section XI utilized 19 83 Edition S 83 Addenda
- 6. , Identification of Components Repaired or Replaced and Replacement Components.
Plugged steam generator tubes as listed below Tube location Tube location Hot or Cold leg Plug Serial . Year Built Repair ASME Code; Row' Column . Number Stamped 3 94 Hot leg EA64 3-0313' 19N Repair No 3 94 Cold leg EA64 3 0325 ' 199) Repair No 19 40 *% he EA64 3 0312 ' 1995 Repair No 19 40 Cold leg EA64 3 0372 / 1995 Repair No 24 38 Hot leg EA64 3-0314 / 1995 Repair No I4' 38 Cold leg EA64 3-0319 / 1995 Repair No 24 78 Hot leg EA64-3 0385 e 1995 Repair No 24 78 Cold les EA64-3 0320' 1995 Repair No
- I 3I. 38 Hot leg . EA64 3-0316 "' 1995 Repair No 31 38 Cold leg EA64-3-0371 ' 1995 Repair No 44 67 Hot leg EA64 3-0318 " 1995 Repair No 44 67 Cold leg EA64 3 0324 ' 1995 Repair No 36 16 Hot les EA64 %0317 / 1995 kepair No 36 16 Cold les EA64-3-0370 / 1995 Repair No j-I t
[.
l
.. This form has been elocuonically ponerated. *W74 applicable for NB.233 l(D).NB 2332(A)(2). NB 4332, NB-4334, NB 43341,4334.2. NB-1333.1. 2. &3 (Pinal)
_ - _ - _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - -- ~ - - - - - ~ - - - - -
'l- .,
FIGURE D.3.2.a SG B ASME FORM NI2-2 (MECHANICAL PLUGGING)
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisius of the ASME Code Section XI 1.' Owner Commonwealth Edison Company Narne Date ~[
f j j One First National Plaza, CL 8cago, II.
Adaress Sheet 1 of 4 #/
ME 2l'IMI
- 2. Plant . Byron Nuclear Power Station Unit 2 Name 4450 N. German Church Road, Byron,11. Work Request No. 960111923-03 Address Repair Organization. P.O. No.. Job No etc.
- 3. Work Performed by Framatome Technologies Type Code Symbol Stamp Not Applicable Name At!Sorization No.Not Applicable 155 Mill Ridge Road, Lynchburg, VA. Expiration Date Not Applicable Addrcss
- 4. Identification of System RC
- 5. (a) Applicable Construction Code Section III 19 71 Edit:on, S72W74' Addenda, 7%;, l404 Code Case Mist GO. ' l03 ! 4741 (b) Applicable Edition of Section XI Utilized for Repairs or Replacement Components 19 83/S83 -
6.
Identification of Components Repaired or Replaced and Rel acement l Components Nanon44 Aepaired.
Namee( Nameof Manufachter As%tE Component board othe' Year Replaced.
Manufumrer serial No Code. sumped No identicanon Built er_ Repluemem (Yes or Not Steam Generator Westinghouse 2RC0 t 85 .
Yes 2096 16 1980 Repaired Mechanical plug Frarnatorne See supplement -
fj Technologies sheet f ///rt 1993 Repair No {
- 7. -
Description of Work 3.uM6b TUGES /15 LMEb dd SUPPt EMEuT/lt 3P6TT
- 8. Test Conducted: ~ Hydrostatic Pneumatic 0 Nominal Operating Pressure O Other O . Pressure psi Test Temp. *F Note: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is 8-l/2 in. x !! in.,
(2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
4 Dt8 forfR ha$ been electronically genef8ted. 'W74 Sppl6 Cable for NB.233l(D). NB 2332(A)(2). NB-4332. NB4334. NB 4334.1. 4334.2, NB43351. 2. A3
---~---------------------l 3 *
' FORM NIS-2 (Back)
Apphcable ManufaCluf tf 5 Pata Keporu 10 De attEheu l
t
]
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this feph conforms to the rules of the ASME Code,Section XI. i,
.w--
- Type Code Symbol Stamp h kpol6 Mt Certificate of Authorization No. A[, / A = /,'d/<_ Expiration Date _ d -/ , mp Signed , , ,.
.o IM.,~.w.56C Date ,j,l ff- ,19y
'l .
CERTIFICATE OF INSERVICE INSPECTION
'l . 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel I State or Province of , .Z/~ /,)fpfs and employed by g/gg fy Ety,
'I of Mp//cd/ 6,,ff/r ///g./ ~ have inspected the components described in this Owner's Report
- during the period ~4/#///g to y//pjJ' , and state that to the best of my l' knowledge and belief, the Gwiter has performed examinations and' ta(en (orrective measures described in the in accordance whh the requirements of the ASME Code,Section XI.
~ By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his empl shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. '
m:4f M.s Commissions e
/22 /,rp/
- u.a. - c -
Date M /g ,
19 f/
V I ed -
0 0
-- - - j
FORM NIS-2 SUPPLEMENTAL SHEET
- 1. Owner: Commonwealth Edison Company Sheetof /y Iff Z h.19.1 4 shsbe One First National Plaza Chicago, Illinois 60690 Date (JWrd g/cjg Unit 2 2,' Plant . Byron Nuclear Power Station Unit f 4450 N. Greman Church Road Byron, Illinois 61010 960111923-03 P.O. No., WR No., etc.
'3. Work Performed by: Framatome Technologies Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 155 Mill Ridte Rd. Expiration Date Not Applicable Address
. 4. Identification of System Reactor Coolant
- Sa. Applicable Construction Code Section til 19 71 Edition S72, W74* Addenda Code Cases 0 55,'18!,'!28,1 0 3 4,474-1 3%5 Mkl%
5.b ' Applicable Edition of Section XI utilized 19 83 Edition S 83 Addenda -
- 6. Identification of Components Repaired or Replaced and Replacement Components.
Plugged steam generator tubes as listed belov>
Tube location Tube location Hot or Cold les PI , : rial Year Built Repair ASME Code; Row Column ,,ber stamped 2 57 Hot leg EA64-3 0625 1995 Repair No 2 57 Cold leg EA64 3-0606 1995 Repair No 6 12 Hot leg EA64-3-0083 1995 Repair No 6 12 Cold leg EA64 3 0617 1995 Repair No 15 25 Hot les EA64 3-0079 1995 Repair No 15 25 Cold leg EA64-3-0612 1995 Repair No 17 36 Hot les EA64 3-0080 1904 Repair No 17 36 Cold les EA64 3 0622 1995 Repair No 18 11 Hot leg EA64 3-0085 1995 Repair No
- 18- 1I Cold leg EA64-3-0098 1995 Repair No 20 6 Hot les EA64 3-0086 1995 Repair No 20 6 Cold leg EA64 3-0613 1995 Repair No 20 7 Hot leg EA64 3-0077 1995 Repair No 20 7 Cold leg EA64-3-0611 1995 Repair No 21 $$ Hot leg EA64-3-0624 1995 Repair No 21 55 Cold leg EA64-3-0614 1995 Repair No 27 32 Hot leg See WR 980014981 1995 Repair No
- 27 32 Colo leg EA64 M096 1995 Repair No 28 25 Hot leg EA64 3 062; 1995 Repair No 28 25 Cola leg EA64 3-0608 1995 Repair No I
- l. 1 This form has been electronically genwered. .*W14 applicable for NB 2331(D), NB-2332(A)(2), NB-4332, NB4334, NB-4334.1,4334.2, NB4335.1,2. A3 h
- (Final) h C ___ _ _ _ _ _ _ _ --_ ----_ ------- ---- - - -- -- - - - - -
. , , s- ,
'l ,
FORM NIS-2 SUPPLEMENTAL SHEET 3 d 4 %g.
- l. Owner: C0mmonwealth Edison Company One First National Plaza Shen [of #
Date OcMt,
} '
Chicago, Illinois 60690 Unit 2
- 2. Plant Byron Nuclear Power Station Unit 2. l t
4450 N. Greman Church Road Byron, Illinois 61010 960111923-03 P.O. No., WR No., etc.
- 3. Work Performed by: Framatome Technologies Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 155 Mill Ridge Rd. Expiration Date Not Applicable Address
- 4. Identification of System Reactor Coolant 5a. Applicable Construction Code Section lil 19 71 Edition S72, W74* Addenda Code Cases -! 355, ;454, i.uo, W&t,474-1 2 4 *71*5 l %
5.b Applicable Edition of Section XI utilized 19 83 Edition S 83 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components.
Plugged steam generator tubes as listed below Tube location Tube location Hot or Cold leg Plug Serial Year Built Repair ASME Code; Row Column Number Starnped 28 di Hot leg EA64-3-0090 1995 Repair No -
28 41 Cold leg 5A64-3 0620 1995 Repai- No 33 20 Hot leg EA64 3 0088 1995 Repair No 33 20 Cold leg EA64 3 0610 1995 Repair No 34 96 Hot leg See WR 980014981 1995 Repair No 34 96 Cold leg EA64-3-0095 1995 Repair No 1 35 33 Hot leg EA64 3-0087 1995 Repair No 35 33 Cold leg EA64 3-0619 1995 Repair No 37 78 Hot leg EA64 3 0082 1995
~
Repair No .
37 78 EA64-3-0621 Cold les 1995 Repair No 37 89 Hot les EA64 3-0081 1995 Repair No 37 89 Cold leg EA64 3 0604 1995 ,
Repair No 38 88 Hot leg EA64 3 0091 1995 Repair No 38 88 Cold leg EA64-3-Ov05 1995 Repair No 40 88 Hot leg See WR 980014981 1995 Repair No 40 88 Cold leg EA64 3-0097 1995 Repair No 41 89 Hot leg EA64-3-0089 1995 Repair No .
]
41 89 Cold leg EA64-3-0322 1995 Repair No 42 31 Hot leg EA64 3-0099 1595 Repair No 42 31 Cold leg EA64-3-0618 1995 Repair No l
This form has been electronically generwed.
- W74 applicable for NB.2331(D). NB-2232(A)(2) NB-4332. NB-4334. NB43341. 4334J. NB-4335.1. 2. &3 (Final) i
)
e s- >
1 ,
1 FORM NIS-2 SUPPLEMENTAL SHEET 4 44
- Mim \
- 1. Owner: Commonwealth Edison Company One First National Plaza Sheet df bk Date fjf/n Chicago, Illinois 60690 Unit '2
- I
- 2. Plant Byron Nuclear Power Station 2-Unit 4450 N. Greman Church Road Byron, Illinois 61010 960111923 03 P.O. No., WR No., etc.
- 3. Work Performed by: Framatome Technologies 4 Type Code Symbol Stamp Not Applicable Name Authorizati.m No. Not Applicable 155 Mill Ridge Rd. Expiration Date Not Applicable l Address 4 Identification of System Reactor Coolant I l
Sa. Applicable Construction Code Section 111 19 71 Edition S72, W74*
_ Addenda j Code Cases 4#5, u g 4, g33, j a 934, 474 1 _
>u ,psm 5.b Applicable Edition of Section XI utilized 19 83 Edition S 83 Addenda ,
)
- 6. Identification of Components Repaired or Replaced and Replacement Components. 1 I
Plugged steam generator tubes as listed below Tube location Tube location Hot or Cold leg Plug Serial Year Built Repair ASitE Code:
Row Column Number stamped
)
43 28 Hot leg EA64-3 0093 1995 Repair No 43 28 f
Cold leg EAM-3 0609 1995 Repair No 43 55 Hot leg EA64-3-0084 1995 Repair No 43 55 Cold leg EA64 3-0615 1995 Repair No i 46 28 Hot leg EA64-3-0076 1995 Repair No 46 28 Cold leg EA64-3-0603 1995 Repair No 46 45 Hot leg f
EA64 3-0078 1995 Repair No 46 45 Cold leg EA64-3-0616 1995 Repair No j 38 Hot leg EA64-34)092
{47 1995 Repair No j 47 31 Cold leg EA64 3 0601 1995 Repair No T 80 Hot leg EA64-3-0094 1995 Repair N 48 80 Cold leg EA64-3 0602 1995 Repair No j
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Tbs form has 'heen electromcally generated. 'W14 applicable for NB 2331(D) NB-2332(A)(2) NB-4332. NB4334. NB-4334.l. 4334.2 NB-4335.1:2, &3 (Final) l J
_ - _ _ . _ - - - _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~
FIGURE D 3.2.b 1)CC W Njd SG B.ASME FORM NIS-2 (WELD PLUGGING)
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FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT
, As Required by the Provisions of the ASME Code Section XI
- 1. Owner Commonwealth Edison Company Date T Name '
One First National Plaza, Chicago,11. Sheet i of /
~
Address
- 2. Plant Byron Nuclear Power Station Unit 2 Name 4450 N. German Church Road, Byron, II. Work Request No. DOINI-O/
Address Repair Organization. P.O. No Job No., etc.
- 3. Work Performed by . Framatome Technologies Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 155 Mill Ridge Rrad, Lynchburg, VA. _
Expiration Date, Not Applicable Address
- 4. Identification of System RC
- 5. (a) Applicable Construction Code Section Ill 19 71 Edition, S72W74* Addenda, 13%,1454 goCode
%/Ur Case
~ ~ ~
2, ; ;s3.i Tl4 -1 (b) Applicable Edition of Section XI Utilized for Repairs or Replacement Components 19 83/S83 #
- 6. Identification of Components Repaired or Replaced and Replacement Compenents
.Nateanal 8.spaired-Name of Name of Manufamrer ASNE board Other Year Replaced.
/
Commonent Manufauvrer Code, stamped Serial No No Idemiression bun or Replacement (Yes or Not Steam Generator Westinghouse 2RC018 B Tube plugs Framatome -w 3s,-2 38 Wnr EAyf-3 j44t, 5ts. knak e Technologies -co9o AvA' Repair No 1
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7.
Description of Work /2EAW/h SMMEu7X ME[5)TU6E5 Be A:srpoc rVE ADNvm. OFevuld1 J.//#E lt'g)dC,Eb 'J*ni WE'LD@ 44 ht8'ktAJ(CL PCLkS-
- 8. Test Conducted: Hydrostatic S EE* VJA % m 9ZS-o3 SeR n c+H. PetX*S.
Pneumatic 0 NominalOperating Pressure C iasWW m Mg !
! Pressure psi Other @ Test Temp. 'F Note: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is 8-1/2 in. x 11 in.,
(2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the sop of this form.
This form has been electronically generaisd. 'W74 app!icable for NB 233 t(D) NB-2332(A)(2). NB-4332, NB4334, NB-43341,4334.2. NS 433j.1,2, &3 L_ _ _ _ _ _ - - _ - _ - - - - - _ - - _ - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - --
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FORM NIS-2 (Back)
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95 Remarks $l1 Mrc EE NI M - -3. ITA...C N WR TIOD/Y%/
i jjdel Plac in<bi)<l ;n 44 /m CL #Mr v f a
GLt 2 *7-3 *L PL. Slu AA M 03 8 a
1~A/ 3 Y ~ A lc, PL S/2 EA /A 010 ,
YJSo Pl.J . s/a ND*8T EA 4 4-3 c35 \
CERTIFICATE OF COMPLIANCE We certify that the statements made in the repor: tre correct and this br conforms to the rules of the ASME Code,Section XI. b--
Type Code Symbol Stamp daf AMtAlc {
Certificate of Authorization No.
NofAg;Ja. I Expiration Date J[g/ 4gyd/c Signed k_ .- Date dly ,
/ L., ,19 9 7 CERTIFICATE OF INSERVICE !NSPECTION
- 1. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and t State or Province of I//sie/5 and employed by gffg gv y (c of MeM6/ 6so/ rec Ahrf
' have inspecjed th,e components described in this Owner's Report during the period 4/.///pf
/ to //jp//f , and state that to the best of my knowledge and belief, the Qwn6r has performed examinations and fakerfcorrective measures described in the Owner in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his empl shall be liable in any manner 'for any personal injury or property damage or a loss of any kind arising from or connected with !
this inspection.
M,,M ,.,,-
Commissions
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Date._ M pf0 ,
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FIGURE D.3.3 SG C ASME FORM NIS-2 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
- 1. Owner Commonwealth Edison Company Date 4 [
Name f f One First National Plaza Lnicago,11. Sheet 1 of _ 2, Address
- 2. Plant Byron Nuclear Power Station Unit 2 Name 4450 N. German Church Road, Byron,II. Work Request No. 960111926-03 Address Repair Organization, P.O. N6.. Job No., etc.
- 3. Work Performed by Framatome Technologies Type Code Symbol Stamp Not Applicable Nwne Authorization No. Not Applicable 155 Mill Ridge Road, Lynchburg, VA. Expiration Date Not Applicable Address 4, Identification of System RC Its 'Mh R
- 5. (a) Applicable Construction Code Section 111 19 71 Edition, S72 W74* Addenda. D55, so4 Code Case 123, i4 D-1474 1 (b) Applicable Edition of Section XI Utilized for Repairs or Replacement Components 19 83/S83
- 6. Identification of Components Repaired or Replaced and Replacement Components hawaal Reps. red.
Name of Name of Manufacturer ASME board other Year Component Manufamirer Resued. Code. 5:amped serial No No Ident4fication Budt or Replacement (Yes or Not Steam Generator Westinghouse 2RC0lBC. Yes 2097 17 1980 Repaired Mechanical plug Framatome See supplement Technologies sheet /V/M # Repair 1995 No l
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- 7. Description of Work 7/,0666I) n)GfiS AS Usf6b ad 50PPLEWEJAL WEET
- 8. Test Conducted: Hydrostatic Pneumatic 0 Nomint.! Operating Pressure O N/A-other O Pressure psi Test Temp. 'F Note: Supplemental sheets in form oflists, sketches, or drawings may be used, pro ided (1) size is 8-1/2 in. x 11 in.,
l (2) information in iNms I through 6 on this report is included on each sheet, and ( j each sheet is nurabered and the number 1 of sheets is recorded at the top of this form.
This form has been electroracally generated. *W74 applicable for NB.2331(D). NB 2332(A)(2), NB 4332, NB-4334. NB-433J 1. 4334 2. NB-43331,2. &3 j j
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FORM NIS-2 (Back) ype. u.a. . u.u.3,w rman- l b CERTIFICATE OF COMhlANCE !
We certify that the statements made in the report are correct and this f grug conforms to the rules of the ASME Code,:
Section XI. , , =
Type Code Symbol stamp of Aphf /4 Certificate of Authorization No. g,/ hlfuf/g Expiration Date _ Mp/ / J/g/ ;
Sig$d r M~ -
Date ,19 9 y g m - > -. % r.
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CERTIFICATE OF INSERVICE INSPM-I, the undersigned, holding a valid commission issued by the National Bo
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.,1 7N 4 and Pressure VesselInspectors and the ;
\ State or Province of - 7///ded and , ,:. .- vy jfs/J EyJ 6, of f$r/d/c/ (cact. d 66#/ have inspected the componeifts descri'ed in this Owner's Report
! during the period 4/p/p/ to *
, and state that to the best ormy knowledge and belief, the'06ner has performed examinations and ta en c6rrective measures described in the l O in accordance with the requirements of the AS ' Code,Section XI.
l By signing this certificate neither the Inspector nor his employer makes any'tvarranty, expressed or implied, con examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor hi{
shall be liable in any-manner for any personal injury or property damage or a loss of any kind arising f this inspection.
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Commissions
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FORM NIS-2 SUPPLE 41 ENTAL SilEET
- 1. Owner: Commonwealth Edison Company !
Sheet '7, of 1.
One First National Plaza Date g/g/4g {
Chicago, Illinois 60690 Unit 2~
- 2. Plant Byron Nuclear Power Statior. Unit 2.
4450 N. Greman Chmen Road ]
Byrer:,liiinois 61010 ;
960111926-035 i P.O. No., WR No., etc. l
- 3. Work Pe formed by: Framatome Technologies Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 155 Mill Ridge Rd.
Expiration Date Not Applicable Address
- 4. Identification of System Reactor Coolant 5a. Applicable Construction Code Section ill '9 71 Edition S72, W74* Addenda Code Cases U ss, i 4 G 4.y:0, ; 4 L i,- 474- 1
- V V !/4(
5.b Applicable Edition of Section XI utilized 19 83 Edition S 83 Addenda 6.
Identification, of Components Repaired or Replaced and Replacement Components.
P!ugged steam generator tubes ; s listed below Tube location Tube location Hot or Cold leg Plug Serial Year Built Repair ASME Code; Row Column Number Stamped 35 59 Hot leg EA64 3 0307 1995 Repair N 35 59 Cold leg EA64-3-0303 1995 Repair No 18 25 l Hot leg EA64-3 0311 194- Repair No !
18 25 Cold leg EA6J-3-0306 1995 Repair No 19 27
-l Hot leg EA64 3-0308 1995 Repair No 19 27 Cold leg EA64 3-0305 1995 Repair No 34 66 Hot leg EA64 34309 1995 Repair No ;
34 66 Cold les EA64-3-0302 1995 Repan N3 49 53 Hot leg EA64 3 0310 1995 49 Rep e j>
53 Cold leg EA64-3-0304 1995 Rephir~ tuo 1 I l
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This form has been electronicai'y gensated. ? W74 appbcable for NS 233 a(D). NB.2332(A)(2). NB-4332. NB-4314 h%I3341. 4334 2. NB4335.1.2. &3 (Final)
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& 8 I FIGURE D.4 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS i As Required by the Provisions of the ASME Code Rules l
1
- 1. Owner: Commonwealth Edison Comoany Chicago. Illinois i (Name and Address of Owner)
- 2. Plant: Byron Nuclear Power Station Byron. Illionois (Name and Address of Plant) i
- 3. Plant Unit: Two (2) 4. Owrer Certificate of Authorization (if required): N/A q
- 5. Commercial Service Date: 08/21/87 6. National Board Number for Unit: N-200
- 7. Components inspected: Steam Generator Eddy Current inspection Component or Manufacturer or Manufacturer or State or Province National Board No. .
Appurtenance Installer Installer Serial No. No.
2RC01BA Westinghouse 2095 U-201435 15 2RC01BB Westinghouse 2096 U-201436 16 2RC01BC Westinghouse 2097 U-201437 17
. 2RC01BD Westinghouse 2098 U-201438 18 l
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Note: This is a computer generated form f
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FORM NIS-1 (Back)
- 8. Framination Dates 4/15/98 to 5/5/98 9. Inspection Interval from 8/21/87 to 8/21/98 (Extended)
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current Refer to the Attached Eddy Current Report 11., Abstract of Conditions Noted.
Refer to the Attached Eddy Current Repon
- 12. Abstract of Corrective Measures Recommended and Taken Refer to the Attached Eddy Current Report We cenify that the restements made in this repon are cormt and the exammations and corrective measures taken conform to the rules of the ASME Code,Section XI.
Cenificate of Authorization No. (if applicable) Not AnolicaNe Expiration Date Not Anolicable Date dMy .23 193 Signed For Comed By s l
Owner CERTIFICATE OF INSERVICE INSPECTION j i
I, the undersigned, holding a valid commission 'ssued by the National Board of Boiler and Pressure Vessel Inspectors and l
the State or Province of f//mr5 and employed by M WJ fd. of Mro affreree%/#/
f have (
inspected the components described in this Owner's Report during the period 4/f/#y to 4/ffr# , and state that I to the best of my knowledge and belief, the Owner has performed examinations'and taken corre(uv6 measures described in this Owner's Report in accordance with the requireinents of the ASME Code,Section XI. '
By signing this cenificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the exammations and corrective measures described in this Owner's Repon. Funhermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or propeny damage or loss of any kind arising from or connected with this inspection.
dfund(dt/$ Commissions /// -//fY \
. Inspector's Signature National Board, State, Province, and Endorsements Date v M
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