Text

Generator Inservice Inspection Summary Report
	ML023520084
Person / Time
Site:	Byron
Issue date:	12/10/2002
From:	Lopriore R; Exelon Generation Co, Exelon Nuclear
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	3.11.0320, BYRON 2002-0129, IWA-6000
	Download: ML023520084 (80)
	v • d • e

Exelon Generation Company, LLC wwwexeloncorpcom Exelkn,.

Nuclear Byron Station 4450 North German Church Road Byron, IL61010-9794 ASME Section Xl, IWA-6000 December 10, 2002 LTR: BYRON 2002-0129 File: 3.11.0320 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Byron Nuclear Power Station, Unit 2 Facility Operating License NPF-66 NRC Docket No. 50-455

Subject:

Byron Station Unit 2 Steam Generator Inservice Inspection Summary Report In accordance with Technical Specification 5.6.9, "Steam Generator (SG) Tube Inspection Reports," Item b, we are reporting the results of the steam generator inspections which were completed during the Byron Station Unit 2, Cycle 10 Refueling Outage (ie., B2R10). The attached report is also being submitted in accordance with the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, 1989 Edition,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Article IWA-6000, "Records and Reports," and Article IV-7000, "Report of Examination," of Mandatory Appendix IV, "Eddy Current Examination of Non Ferromagnetic Steam Generator Heat Exchanger Tubing." Also included in this report are the results from the forced outage (B2F23) SG inspection conducted in June of 2002.

If there are any questions regarding this report, please contact W. Grundmann, Regulatory Assurance Manager, at (815) 406-2800.

-ichard *Lopr/

P. re*

Site Vice President Byron Nuclear Generating Station

Attachment:

Steam Generator Eddy Current Inspection Report (B2R10)

RUJS/DD/rah cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector- Byron Station NRC Project Manager - NRR - Byron Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety

bcc: Manager of Energy Practice - Winston & Strawn Site Vice President - Byron Station Vice President - Licensing and Regulatory Affairs Director, Licensing Manager, Licensing & Compliance - Braidwood and Byron Stations Regulatory Assurance Manager - Byron Station I J. R. Smith - Engineering Programs - Byron Station Exelon Document Control Desk Licensing (Hard Copy)

Exelon Document Control Desk Licensing ( Electronic Copy)

Exelon Generation Company, LLC BYRON STATION UNIT 2 4450 North German Church Road Byron, Illinois 61010 COMMERCIAL OPERATION: 08121187 STEAM GENERATOR EDDY CURRENT INSPECTION REPORT CYCLE 10 REFUELING OUTAGE (B2R10)

September 2002 Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 Documentation Completed Date: December 3, 2002 Page 1 of 78

TABLE OF CONTENTS

1.0 INTRODUCTION

....................................................................... 3 2.0 SUM MARY ................................................................................ 3 3.0 CERTIFICATIONS ..................................................................... 5 3.1 Procedures/Examinations/Equipment .............................. 5 3.2 Personnel ......................................................................... 6 4.0 EXAMINATION TECHNIQUE AND EXAMINATION SCOPE ..... 7 4.1 Examination Techniques .................................................. 7 4.2 Inspection Scope ............................................................ 8 4.3 Recording of Examination Data ........................................ 9 4.4 Witness and Verification of Examination ........................... 9 5.0 EXAMINATION RESULTS ......................................................... 10 5.1 Indications Found ............................................................ 10 5.1 Other Results ................................................................... 12 6.0 REPAIR

SUMMARY

................................................................... 12 7.0 DOCUMENTATION ................................................................... 13 8.0 FIGURES/TABLES/ATTACHMENTS ......................................... 14 Page 2 of 78

1.0 INTRODUCTION

Byron Station 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. The tubes are hydraulically expanded into the full depth of the tubesheet. The tubes are supported by stainless steel quatrefoil support plates (TSP's) and chrome plated Inconel-600 anti-vibration bars (AVB's). See Figure A.1 for a diagram of the D-5 steam generator configuration.

In compliance with Byron Station Technical Specification 5.5.9, "Steam Generator Tube Surveillance Program," and American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code Section XI 1989 Edition, IWB 2500-1, Examination Category B-Q, Item B16.20, SG eddy current examinations were performed during the Byron Station Unit 2 Cycle 10 refueling outage (i.e., B2R10).

The inspections were performed consistent with the Electric Power Research Institute (EPRI)

"PWR Steam Generator Examination Guidelines: Revision 5" and Nuclear Energy Institute (NEI) 97-06, "Steam Generator Program Guidelines." The field inspection activities were conducted September 20 through September 25, 2002, by Westinghouse Electric Company Ltd. The following inspections were performed during this outage.

- 100% Full Length Bobbin Coil in all four SGs

- 75% Hot Leg Top of Tubesheet Plus-Point in all four SGs

- 75% Row I and Row 2 U-bend Plus-Point in all four SGs

- Hot Leg Dents/Dings >5.0 volts Plus-Point as follows:

- 25% in SGs A/B

- 100% in SGs C/D

- 25% Pre-heater baffle expansion Plus-Point in SGs B/C/D

- 100% Visual Inspection of Previously Installed Welded Tube Plugs in all SGs

- 100% Visual Inspection of Previously Installed Mechanical Tube Plugs in all SGs

- 100% Visual Inspection of Newly Installed Tube Plugs in all SGs In addition, eddy current inspections were conducted on June 24 through June 25, 2002, during a forced outage (B2F23) caused by a primary to secondary leak in SG C. The primary to secondary leak was attributed to tube wear caused by a foreign object. The B2F23 inspections were limited to the leaking tube and the tubes surrounding the leaking tube. The tubes were inspected with a bobbin coil probe and a plus-point probe. The inspections were performed consistent with the EPRI "PWR Steam Generator Examination Guidelines: Revision 5" and Nuclear Energy Institute (NEI) 97-06, "Steam Generator Program Guidelines." Westinghouse Electric Company Ltd conducted the field inspection activities.

2.0

SUMMARY

The guidance in Revision 5 of the EPRI "PWR Steam Generator Examination Guidelines" (i.e.,

EPRI Guidelines) was used during this inspection. A degradation assessment was performed prior to each inspection to ensure the proper EPRI Appendix H, "Performance Demonstration for Eddy current Examination," qualified inspection techniques were used to detect any existing and potential modes of degradation. Each technique was evaluated to ensure that the detection and sizing capabilities are applicable to the Byron Station Unit 2 site specific condition in accordance with Section 6.2.4 of the EPRI Guidelines. All data analysts were qualified to Appendix G, "Qualification of Nondestructive Examination Personnel for Analysis of NDE Data," of the EPRI Page 3 of 78

Guidelines (i.e., Qualified Data Analyst (QDA)). All data analyst and acquisition personnel satisfactorily completed site specific performance training and testing. An independent QDA process control review was employed to randomly sample the data to ensure that the analysis resolution process was properly performed and that the field calls were properly reported. An analysis feedback process was implemented that required the data analysts to review their missed calls and overcalls on a daily basis.

The modes of tube degradation found during the B2R1O inspection were anti-vibration bar wear, foreign object wear, and pre-heater wear. Pursuant to Technical Specification 5.5.9.c, "Inspection Results Classification," the results of the inspection were classified as inspection category C-1 for SGs B/C/D and C-2 for SG A. There were no scanning limitations during the examinations.

As a result of the B2R10 eddy current inspections, a total of fourteen (14) tubes were repaired by tube plugging. During B2F23, three (3) tubes were repaired by tube stabilization and tube plugging. Table 2.1 provides the tube plugging levels for each SG. Table 2.2 and Table 2.3 provides the total number of tubes plugged in B2R1 0 and B2F23 by degradation mode.

TABLE 2.1 Equivalent Tube Plugging Level

~SG-A S GB' SG C 'SGD KTOTAL Tubes Previously Plugged 50 113 41 19 223 Tubes Plugged in B2F23 0 0 3 0 3 Tubes Plugged in B2R1O 2 0 9 3 14 Total Tubes Plugged 52 113 53 22 240 Total Tubes Plugged (%) 1.14% 2.47% 1.16% 0.48% 1.31%

TABLE 2.2 Tubes Repaired During B2R1 0 Modd'of Degradationi SG A SB SG'C'< SGDV, To6talI Foreign Object Wear 0 0 8 3 11 Anti-Vibration Bar Wear 2 0 0 0 2 Pre-heater Wear 0 0 1 0 1 B2R1l0 Ttals

.Plug.g 2093

.,,,,,20,14 TABLE 2.3 Tubes Repaired During B2F23 Modreif Dbegadatioa A, BC S3 Foreign Object Wear 0 0 I 3 I 0 I 3 B2RIO PIu ginE Totals 0" 0, 3 V 3 Page 4 of 78

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 III in accordance with the 1984 Edition of the American Society for Nondestructive Testing Recommended Practice SNT-TC-1A, "Personnel Qualification and Certification in Nondestructive Testing." Exelon Special Process Procedures Manual procedure NDT-E-2, "Multifrequency Eddy Current Data Acquisition of Steam generator Tubing at Braidwood and Byron Nuclear Stations," Revision 4 and procedure ER-AP-335-040, "Evaluation of Eddy Current Data for Steam Generator Tubing," Revision 0, were used for data acquisition and analysis.

3.1.2 The examinations, equipment, and personnel were in compliance with the requirements of the Exelon and Westinghouse Quality Assurance Programs for Inservice Inspection, Byron Station Technical Specification 5.5.9, 1989 Edition of the ASME B&PV Code Sections XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," and V, "Nondestructive Examination," Revision 5 of the EPRI PWR SG Examination Guidelines, and NEI 97-06, "Steam Generator Program Guidelines," Revision 1.

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 the B2R10 inspection.

Table A.3 lists all personnel who performed, supervised, or evaluated the data during the B2F23 inspection.

3.1.4 R/D Tech Incorporated Model TC6700 Remote Data Acquisition Units (RDAUs) with ANSER Versions 01.2.2 (B2F23/B2R1 0) and ANSER Version 0.1.2.4 (B2R10) software was used to acquire the eddy current data. Analysis was performed with Westinghouse ANSER-ANALYSIS

-- -Version 01.2.3 (B2F23) and ANSER-ANALYSIS Version 01.2.4 (B2R10) computer software.

3.1.5 The bobbin coil examinations were performed with a 0.610 inch diameter bobbin coil eddy current probe. For low row U-Bend tubing, a 0.590 inch diameter bobbin probe was utilized to achieve the complete full tube examination in tubes where there was difficulty using the 0.610 inch diameter probe.

3.1.6 The top of tubesheet, baffle plate expansion, dent/ding and special interest rotating coil examinations were performed with a 0.610 inch diameter three coil rotating plus-point probe that contains a plus-point coil, a 0.115 inch diameter pancake coil and a 0.080 inch diameter high frequency pancake coil.

3.1.7 The row 1 and row 2 rotating coil examinations were performed with a 0.580 inch diameter high frequency plus-point coil probe.

Page 5 of 78

3.2 Personnel 3.2.1 The personnel who performed the eddy current inspections were qualified to Level I and Level II in accordance with SNT-TC-1A, 1984 Edition. The Level I personnel performed the inspections under the direct supervision of Level II or Level III personnel.

3.2.2 The personnel who performed the SG eddy current data analysis were qualified to a minimum of Level II, with special analysis training (i.e.,

Level IIA) in accordance with the 1984 Edition of SNT-TC-1A and Article IV-2000 of ASME Section XI, 1989 Edition.

3.2.3 All SG eddy current data analysts were qualified in accordance with EPRI Appendix G for Qualified Data Analysts (QDAs). In addition, all data analysts were trained and tested in accordance with a site specific performance demonstration program in both the bobbin coil and plus point inspection data analysis. Resolution analysts were also trained and tested specifically for the performance of data resolution. All analysts were required to achieve a score of 80% or greater on both the written and practical examinations prior to analyzing data.

3.2.4 All SG eddy current data acquisition personnel were trained and tested in accordance with a site specific performance demonstration program.

The data acquisition operators were required to achieve a written test score of 80% or greater prior to acquiring data.

3.2.5 The SG eddy current analysis was subject to two independent analyses.

Primary analysis of all data was performed by Westinghouse, Anatec, NDE Technologies, Verner & James and Quantum. An independent company, CoreStar, performed the secondary analysis. Discrepancies between the two parties required Level III concurrence between both parties for the final resolution.

.... . 3.2.6 An independent SG eddy current Level III QDA who was not part of the resolution team was employed to serve as a process control reviewer, in accordance with EPRI Guidelines, Section 6.3.3.4. The Independent Level III QDA randomly sampled the data to ensure the resolution process was properly performed and that the field calls were properly reported. The Independent Level Ill QDA also provided data acquisition oversight to ensure that the data collection process was in compliance with appropriate procedures, that all essential variables were set in accordance with the applicable Examination Technique Specification Sheet (ETSS) and to provide a data quality check of acquired data. The Independent Level III QDA reported directly to the Exelon Level III inspector.

3.2.7 Personnel from Westinghouse performed data acquisition.

Page 6 of 78

4.0 EXAMINATION TECHNIQUE AND EXAMINATION SCOPE All eddy current examination techniques used are qualified in accordance with Appendix H of the EPRI PWR SG Examination Guidelines. Each examination technique was evaluated to be applicable to the tubing and conditions of the Byron Unit 2 SGs.

4.1 Examination Techniques 4.1.1 The bobbin coil examinations were performed with a 0.610 inch diameter bobbin coil eddy current probe described in Section 3.1.5. For low row U Bend regions where there was difficulty using the 0.610 inch diameter probe, a 0.590 inch diameter bobbin probe was utilized to achieve the complete full tube inspection. Nominal probe inspection speed was 40 inches per second for rows 5 through 49 and 24 inches per second for rows 1 through 4 U-bend region. 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, and a 300/130 kHz absolute mix for flat wear and a 300/130 kHz absolute mix for tapered wear.

4.1.2 The plus-point examinations at top of tubesheet and pre-heater baffle plate expansion transition regions, dents/dings and special interest locations were performed with a 0.610 inch diameter three coil plus-point eddy current probe described in Section 3.1.6. Nominal probe speed was 0.5 inches per second and 0.15 inches per second for the examination of dent and dings. A sampling rate was used to maintain a minimum of 30 samples per inch in the circumferential direction and 25 samples per inch in the axial direction. The rotating probes were operated at frequencies of 300 kHz, 200 kHz, 100 kHz and 20 kHz. In addition to the four base frequencies, three process channels were used to display axial indications

-in the positive trace. . ... .. .... .. .. ...

4.1.3 The plus-point examinations at row 1 and row 2 U-bend regions were performed with a 0.580 inch diameter plus-point eddy current probe described in Section 3.1.7. Nominal probe speed was 0.15 inches per second. A sampling rate was used to maintain a minimum of 30 samples per inch in the circumferential direction and 25 samples per inch in the axial direction. The rotating probes were operated at frequencies of 400 kHz, 300 kHz, 150 kHz and 20 kHz. In addition to the four base frequencies, three process channels were used to display axial indications in the positive trace.

4.1.4 Non-quantifiable bobbin coil indications identified by an "I-Code" were examined with a three coil rotating plus-point probe that contains a plus point coil, a 0.115 inch diameter pancake coil and a 0.080 inch diameter high frequency 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. Three process channels were created to display axial indications in a positive trace.

Page 7 of 78

4.1.5 The eddy current calibration standards used for the bobbin coil and plus point inspections met the requirements of Section 6.2.7 of the EPRI PWR Steam Generator Examination Guidelines, Revision 5 and Sections V and XI of the ASME B&PV Code, 1989 Edition.

4.1.6 The SG eddy current examination techniques used during this inspection were equivalent to the EPRI Appendix H techniques listed in Table 4.1.

Each Examination Technique Specification Sheet (ETSS) was evaluated and determined to be applicable to the site conditions.

Table 4.1 EPRI Appendix H Techniques EPRI Probe KDescription Technique 96004.3 Bobbin AVB/Pre-Heater/TSP/Foreign Object Wear, Freespan Flaws 96007.1 Bobbin Tube Support Plate Outer Diameter Stress Corrosion Cracking 96511.1 Plus-Point Low Row U-bend Primary Water Stress Corrosion Cracking 96703.1 Plus-Point Dent/Ding Primary Water Stress Corrosion Cracking 96910.1 Plus-Point Foreign Object Wear/Freespan Flaw Sizing 21409.1 Plus-Point Sludge Pile Outer Diameter Stress Corrosion Cracking 21410.1 Plus-Point Expansion Transition Circumferential Stress Corrosion Cracking 20510.1 Plus-Point Expansion Transition Axial Outer Diameter Stress Corrosion Cracking 20511.1 Plus-Point Expansion Transition Axial Primary Water Stress Corrosion Cracking 4.2 Steam Generator Inspection Scope 4.2.1 (B2R10) 100% of the tubes in all SGs were inspected full length, tube end to tube end, with a bobbin coil probe described in Section 4.1.1 above.

4.2.2 (B2R1 0) 75% of the tubes in all SGs were inspected at the hot leg top of tubesheet expansion transition region (+/- 3 inches) with a plus-point probe described in Section 4.1.2.

4.2.3 (B2R1 0) 75% of the tubes in all SGs were inspected in the Row I and Row 2 U-bend region with a plus-point probe described in Section 4.1.3.

4.2.4 (B2R10) 25% of the pre-heater baffle plate expansion transitions (+/- 2 inches) in SGs B/C/D were inspected with a plus-point probe described in Section 4.1.2.

4.2.5 (B2R10) 75% of the hot leg dents/dings that were greater than 5.0 volts were inspected with a plus-point probe described in Section 4.1.2. The SG distribution of the inspection was 25% in SGs A/B and 100% in SGs C/D.

4.2.6 (B2R10) Diagnostic examinations were conducted on non-quantifiable indications that were detected by the bobbin coil examination. Diagnostic examinations were also conducted on tubes in the vicinity of potential foreign objects in order to determine the extent of tubes potentially Page 8 of 78

affected by the objects. These examinations were performed with the three coil plus-point probe described in Section 4.1.4 above. A total of 141 tubes were inspected as a result of these diagnostic examinations.

4.2.7 (B2F23) A total of 8 tubes in SG C were inspected with a bobbin coil probe described in Section 4.1.1. The leaking tube R43-C23 was inspected full-length and the surrounding 7 tubes were tested from the cold leg tube end through to the 03C tube support plate.

4.2.8 (B2F23) A total of 11 tubes in SG C were inspected with a plus-point probe described in Section 4.1.4. Eight (8) tubes were inspected at the 02C and 03C tube support plates (+/- 2 inches) and three (3) tubes were inspected at the 02C tube support plate (+/- 2 inches).

4.2.9 Figures A.2 through A.24 contain tube sheet maps indicating the tube inspections that were performed during B2R1 0.

4.2.10 Figure A.25 and A.26 contains the tubesheet map indicating the tube inspections that were performed during B2F23.

4.3 Recording of Examination Data The raw eddy current data and analysis results were recorded on optical disks.

The data was then loaded into the Westinghouse Eddy Current Data Management System, "ST2000," version 1.09.01 (B2F23) and version 1.10.00 (B2R10). This system was used to track the proper examination of all tubes and itwas also used to generate the final eddy current report summaries.

4.4 Witness and Verification of Examination Eddy current inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors, Mr. Jeff Hendricks and Mr. Robert Ward, of the Hartford Steam Boiler of CT of Hartford Connecticut, Chicago Branch, 2443 Warrenville Road, Suite 500, Lisle, Illinois 60532-9871.

The B2R1 0 ASME Form NIS-1, "Owners Report for Inservice Inspections," is contained in Attachment A.6. The B2F23 ASME Form NIS-1 is contained in Attachment A.7.

Page 9 of 78

5.0 EXAMINATION RESULTS 5.1 Indications Found 5.1.1 Anti-Vibration Bar (AVB) Wear - Tube degradation was found by the B2R1 0 bobbin coil examination in the U-bend region due to fretting of the Anti-Vibration Bars on the tube. A total of 757 indications in 453 tubes were reported. The EPRI Appendix H bobbin coil examination technique 96004.3 was utilized in this inspection for the depth sizing of AVB wear.

The largest indication found was 40% through wall (TW) and was found in two tubes. Both tubes were subsequently plugged. Table 5.1.1 provides a summary of AVB Wear degradation.

Table 5.1.1

_B2RIO AVB Wear Summary SG A SGB'13 SG C SG D,

Tubes '. Tubes ld. Tubes ld. Tubes ld,

<20% TW* 66 77 98 121 80 101 52 59 20-39% TW* 76 116 112 170 50 61 39 50

>= 40% TW* 2 2 0 0 0 0 0 0 TOTAL* 111 195 165 291 102 162 75 109

Tubes may contain indications in more than one category.

5.1.2 Foreign Obiect Wear - Tube degradation was found in eleven (11) tubes that was attributed to foreign object wear during the B2R10 inspection.

The indications ranged from 3% TW to 32% TW. The EPRI Appendix H plus point qualified examination technique 96910.1 was applied to'size the indications. All 11 tubes that contained indications of foreign object wear were removed from service. No indications of foreign object wear were left inservice. All foreign objects that caused the tube damage were removed from the SGs. Tube R34-C59 in SG C contained an indication at the top of the tubesheet that was indicative of a foreign object wear scar. Visual inspection did not identify any foreign objects in the vicinity. The location of this tube is in a region where the object may have been removed by the sludge lancing operation. Table 5.1.2a provides a summary of the tubes that contained foreign object wear during B2R1 0.

A forced outage B2F23 was a result of a 75 gallon per day primary to secondary leakage in the 2C SG. Pressure testing and eddy current identified the leak source as foreign object wear in tube R43-C23 at the second TSP on the cold leg side (TSP 02C). Subsequent eddy current examinations identified two additional adjacent tubes that contained foreign object wear. The foreign object that caused this damage was removed from the SG during B2R10. Table 5.1.2b provides a summary of the tubes that contained foreign object wear during B2F23.

Page 10 of 78

Table 5.1.2a B2R10 Foreign Object Wear Summar SG Row Column Depth L " 6ocation 2C 17 25 22% 01H+0.42" 2C 22 30 4% 01 H+0.42" 2C 23 30 30% 01 H+0.46" 2C 23 31 11% 01H+0.41" 2C 24 33 3% 01H+0.41" 2C 25 33 15% 01H+0.47" 2C 34 59 8% TSH+0.12" 2C 49 34 24% 02C+0.41" 2D 35 99 32% 02C+0.48" 2D 36 99 14% 02C+0.41" 2D 37 99 8% 02C+1.09" Table 5.1.2b B2F23 Foreign Object Wear SG Row *Column> Depth Location 2C 43 22 37% 02C+0.49" 2C 43 23 71%* 02C+0.53" 2C 43 24 11%/13% 02C+0.46"/+0.85"

Tube confirmed by pressure testing to contain a through-wall indication.

5.1.3 Pre-Heater Wear- Fifteen (15) tubes were found that contained signals of pre-heater wear. The depth of the pre-heater wear ranged from 6% TW to 19% TW as measured by the EPRI Appendix H qualified bobbin coil examination technique 96004.3. Tube R48-C36 in SG C was preventatively removed from service. Table 5.1.3 below provides a summary of tubes that contain Pre-Heater wear.

TABLE 5.1.3

.. B2R1O Pre-heater-Wear Summary

`7-SG Row** Columni-i I'Depth Lc*'ation`-!,

2B 47 75 6% 02C+0.31" 2B 48 50 13% 07C+0.34" 2B 48 53 12% 07C+0.40" 2B 48 54 8% 07C+0.34" 2B 48 55 10% 07C+0.40" 2B 48 59 12% 07C-0.46" 2B 49 50 15% 07C+0.25" 2B 49 53 16% 07C+0.15" 2B 49 63 9% 07C+0.40" 2C 48 36 17% 02C+0.5" 2C 49 48 14% 07C-0.5" 2C 49 62 18% 07C-0.08" 2C 49 63 19% 07C-0.05" 2C 49 73 7% 07C-0.41" 2D 49 52 8% 07C+0.36" Page 11 of 78

5.2 Other Results 5.2.1 Visual Inspection of Installed Tube Plugs - All previously installed welded plugs and previously installed mechanical plugs were visually inspected for signs of degradation and leakage. A total of 25 welded plugs and 491 mechanical plugs were visually inspected. In addition, all plugs installed during this outage (i.e., 28 mechanical plugs in 14 tubes) were also visually inspected and the installation parameters were reviewed for acceptable installation. No anomalies were found.

5.2.2 Attachments A.1 through A.5 contain tube lists with axial elevations of all imperfections that contain measurable through wall depth that were found during the B2R10 eddy current inspection.

5.2.3 Attachment A.5 contains a tube list with axial elevations of all imperfections that contain measurable through wall depth that were found during the B2F23 eddy current inspection.

6.0 REPAIR

SUMMARY

Repairs were conducted in accordance with ASME Section XI, 1989 Edition. All tube plugging was performed by Westinghouse using Inconel-690 mechanical tube plugs. All repairs were performed in accordance with approved Westinghouse procedures. Table 6.1 depicts the repairs conducted during B2R10. Table 6.2 lists the tube locations that were repaired in B2R10. Table 6.3 depicts the repairs conducted during B2F23. Table 6.4 lists the tube locations that were repaired in B2F23.

TABLE 6.1 Summary of B2R10 Tube Plugging REPAIRS PERFORMED S"G A-, -SGB 'ý"SG'C ,ý. *iSGD. , TOTAL",

Tubes Plugged* 2 0 9 3 14 Tubes Stabilized 0 0 0 0 0

Includes number of tubes stabilized and plugged.

Page 12 of 78

TABLE 6.2 SG Tubes Repaired During B2R10 SG 6 Row Cl. Repir** <DepthL Volts .Chael Phaseý f Location 2A 40 21 Plug 40% 4.68 P2 0 AV2+0.00" 2A 41 93 Plug 40% 4.87 P2 0 AV2+0.00" 2C 17 25 Plug 22% 0.32 P4 0 01H+0.42" 2C 22 30 Plug 4% 0.08 P4 0 01H+0.42" 2C 23 30 Plug 30% 0.43 P4 0 01H+0.46" 2C 23 31 Plug 11% 0.15 P4 0 01H+0.41" 2C 24 33 Plug 3% 0.07 P4 0 01H+0.41" 2C 25 33 Plug 15% 0.21 P4 0 01H+0.47" 2C 34 59 Plug 8% 0.11 P4 0 TSH+0.12" 2C 48 36 Plug 17% 0.99 P3 0 02C+0.5" 2C 49 34 Plug 24% 0.34 P4 0 02C+0.41" 2D 35 99 Plug 32% 0.5 P4 0 02C+0.48" 2D 36 99 Plug 14% 0.16 P4 0 02C+0.41" 2D 37 99 Plug 19% 0.23 P4 0 02C+1.09" P4 - Suppression Mix 300/100 kHz - Plus-Point P3 - Suppression Mix 300/130 kHz - Bobbin Absolute - TSP Wear Scar P2 - Suppression Mix 300/130 kHz - Bobbin Absolute - AVB Wear Scar TABLE 6.3 Summary of B2F23 Tube Plugging REPAIRS PERFORMED SG A' SG B 'SG*Ci - SGVD TOTAL Tubes Plugged* 0 0 3 0 3 Tubes Stabilized 0 0 3 0 3

Includes number of tubes stabilized and plugged.

TABLE 6.4 SG Tubes Repaired During B2F23

R0W' ý'Col.", Repair 4,-Stabilizera "lndicati6on' _Volts>' 'Ch-annel

,SGRýýo' Phase6"'Location 2C 43 22 Plug Cold Leg 37% 0.42 P4 0 02C+0.49" 2C 43 23 Plug Cold Leg 71%* 2.02 P4 0 02C+0.53" 2C 43 24 Plug Cold Leg 11% 0.07 P4 0 02C+0.46" 13% 0.08 P4 0 02C+0.85"

As sized by eddy current. Pressure Testing confirmed flaw to be 100% throughwall.

7.0 DOCUMENTATION All original optical disks have been provided to Exelon and are maintained at Byron Station. The final data sheets and pertinent tube sheet plots are contained in the Westinghouse Final Outage Reports for Byron Station Unit 2, B2R10 and B2F23. The reports are also maintained at Byron Station.

Page 13 of 78

8.0 FIG URESITABLES/ATTACHMENTS Table A.1 B2R10 Data Acquisition Personnel Certification List Table A.2 B2R1 0 Data Analysis Personnel Certification List Table A.3 B2F23 Data Analysis/Acquisition Personnel Certification List Figure A.1 Westinghouse Model D-5 Tube Support Configuration Figure A.2 B2R10 SG A Cold Leg Bobbin Coil Inspection Scope Figure A.3 B2R10 SG A Hot Leg Bobbin Coil Inspection Scope Figure A.4 B2R10 SG A Hot Leg Top of Tubesheet Plus-Point Inspection Scope Figure A.5 B2R10 SG A Row 1 & Row 2 Plus-Point Inspection Scope Figure A.6 B2R10 SG A Hot Leg Dent/Ding Plus-Point Inspection Scope Figure A.7 B2R10 SG A Hot Leg Special Interest Plus-Point Inspection Scope Figure A.8 B2R10 SG A Cold Leg Special Interest Plus-Point Inspection Scope Figure A.9 B2R10 SG B Cold Leg Bobbin Coil Inspection Scope Figure A.10 B2R10 SG B Hot Leg Bobbin Coil Inspection Scope Figure A.11 B2R10 SG B Hot Leg Top of Tubesheet Plus-Point Inspection Scope Figure A.12 B2R10 SG B Row 1 & Row 2 Plus-Point Inspection Scope Figure A.13 B2R10 SG B Baffle Plate Expansion Plus-Point Inspection Scope Figure A.14 B2R10 SG B Hot Leg Dent/Ding Plus-Point Inspection Scope Figure A.15 B2R10 SG B Hot Leg Special Interest Plus-Point Inspection Scope Figure A.16 B2R10 SG B Cold Leg Special Interest Plus-Point Inspection Scope Figure A.17 B2R10 SG C Cold Leg Bobbin Coil Inspection Scope Figure A.18 B2R10 SG C Hot Leg Bobbin Coil Inspection Scope Figure A.19 B2R10 SG C Hot Leg Top of Tubesheet Plus-Point Inspection Scope Figure A.20 B2R10 SG C Row 1 & Row 2 Plus-Point Inspection Scope I Figure A.21 B2R10 SG C Baffle Plate Expansion Plus-Point Inspection Scope Figure A.22 B2R10 SG C Hot Leg Dent/Ding Plus-Point Inspection Scope Figure A.23 B2R10 SG C Hot Special Interest Plus-Point Inspection Scope Figure A.24 B2R10 SG C Cold Leg Special Interest Plus-Point Inspection Scope Figure A.25 B2R10 SG D Cold Leg Bobbin Coil Inspection Scope '

Figure A.26 B2R10 SG D Hot Leg Bobbin Coil Inspection Scope Figure A.27 B2R10 SG D Hot Leg Top of Tubesheet Plus-Point Inspection Scope Figure A.28 B2R10 SG D Row 1 & Row 2 Plus-Point Inspection Scope Figure A.29 B2R10 SG D Baffle Plate Expansion Plus-Point Inspection Scope Figure A.30 B2R10 SG D Hot Leg Dent/Ding Plus-Point Inspection Scope Figure A.31 B2R10 SG D Hot Leg Special Interest Plus-Point Inspection Scope Figure A.32 B2R10 SG D Cold Leg Special Interest Plus-Point Inspection Scope Figure A.33 B2F23 SG C Bobbin Coil Inspection Scope Figure A.34 B2F23 SG C Special Interest Plus-Point Inspection Scope Attachment A.1 SG A ASME Form NIS-BB for B2R10 Attachment A.2 SG B ASME Form NIS-BB for B2R10 Attachment A.3 SG C ASME Form NIS-BB for B2R10 Attachment A.4 SG D ASME Form NIS-BB for B2R10 Attachment A.5 SG C ASME Form NIS-BB for B2F23 Attachment A.6 B2R1 0 ASME Form NIS-1, "Owners Report for Inservice Inspections" Attachment A.7 B2F23 ASME Form NIS-1, "Owners Report for Inservice Inspections" Page 14 of 78

TABLE A.1 B2RIO DATA ACQUISITION PERSONNEL CERTIFICATIONS

-No. Name Company 'L*evel QDA

__ _ ____ (YIN) 1 Bradley, GD Westinghouse II N 2 Chiplasky, GA Westinghouse II N 3 Conner, MG Westinghouse II N 4 Dvorak, DJ Spec/TMP I N 5 Estel, JW Westinghouse II N 6 Evering, DP Westinghouse II N 7 Groh, TA Westinghouse II N 8 Hopper, JM Westinghouse II N 9 Mains, PJ Westinghouse II N 10 Mardell, DM Westinghouse II N 11 McElhinny, JW Westinghouse II N 12 Provencher, C Westinghouse II N 13 Reif, DL Westinghouse I1 N 14 Schachte, DM Westinghouse II N 15 Schaffner, KR Spec/TMP I N 16 Scott, AW Westinghouse II N 17 Scott, KL Westinghouse II N 18 Shipley, EB Westinghouse II N 19 Smith, AO Westinghouse II N 20 Smith, DR Westinghouse II N 21 Stitt, AL Westinghouse II N 22 Tedrick, JE Westinghouse I N 23 Whalen, DJ Westinghouse II N 24 Young, JA Westinghouse II N Page 15 of 78

TABLE A.2 B2R10 DATA ANALYSIS PERSONNEL CERTIFICATIONS (Page 1 of 2)

No., Namfe, Comnapany Level QDA'

_________________(YIN) 1 Anderson, DA NDE Tech IIA Y 2 Beehner Westinghouse III Y 3 Bowser, GC CoreStar III Y 4 Breuel, K Verner & James lilA Y 5 Brown, ME NDE Tech lilA Y 6 Causby, GW CoreStar lilA Y 7 Croyle, RJ CoreStar III Y 8 DeLaPintiere, L Anatec III Y 9 Ethridge, GJ NDE Tech lilA Y 10 Herold, MJ V&J IIA Y 11 Himmelspach, R* Anatec III Y 12 Hover, L Verner & James 1liA Y 13 Humphrey, RA CoreStar III Y 14 Ingenthron, GJ V &J IIA Y 15 Ingraham, RH NDE Tech lilA Y 16 Ives, DH CoreStar III Y 17 Jerina, FJ NDE Tech lilA Y 18 Johnson, JR CoreStar IIA Y 19 Kirk, MB CoreStar III Y 20 Lewis, CL NDE Tech IIA Y 21 Lohner, ET NDE Tech lilA Y 22 Maben, DE Anatec III Y 23 Martin, AP CoreStar IIA Y 24 McChesney, WD CoreStar III Y 25 Miller, HN CoreStar III Y 26 Overly, ES CoreStar IIA Y 27 Pocratsky, RJ Westinghouse III Y 28 Popovich, RA Westinghouse III Y 29 Prentice, RV Quantum IIA Y 30 Radovanic, JI Anatec III Y 31 Raper, U Anatec III Y 32 Richmond, MA NDE Tech IliA Y 33 Roberts, CJ Anatec IIA Y 34 Robertson, RR CoreStar IIA Y 35 Rogers, GF Quantum III Y 36 Seutter, AE CoreStar IIA Y 37 Sheldon, JT NDE Tech lilA Y 38 Smith, JS CoreStar IIA Y 39 Spake, CD CoreStar III Y 40 Stach, GJ CoreStar IIA Y Independent Qualified DataAnalyst Page 16 of 78

TABLE A.2 B2R10 DATA ANALYSIS PERSONNEL CERTIFICATIONS (Page 2 of 2)

N6o. Name *i ComPany L:* el, QDA,

_ _ ___ (YIN):

41 Stokke, TF NDE Tech lilA Y 42 Stump, TJ CoreStar III Y 43 Thompson, KA NDE Tech IIA Y 44 Thompson, VA NDE Tech IliA Y 45 Thulien, TA CoreStar III Y 46 Tobin, RJ Westinghouse III Y 47 Traves, DJ CoreStar IIA Y 48 Turner, DG CoreStar IIA Y 49 Visconti, CG CoreStar IIA Y 50 Welch, LC V&J lilA Y 51 Wieber, JA Anatec IIA Y 52 Williamson, LR Anatec III Y 53 Zevchak, JJ CoreStar IIA Y Page 17 of 78

TABLE A.3 B2F23 DATA ANALYSISIACQUISITION PERSONNEL CERTIFICATIONS AN - Analysis AQ - Acquisition No. Na-me Comipany Level CrewQD

________________ (Y/N)~

1 Akerlind, Bruce NDE Tech III AN Y 2 Barnes, Robert* Anatec III AN Y 3 Bowser, Craig Corestar III AN Y 4 Bradley, George West. II AQ N 5 Case, John NDE Tech III AN Y 6 Croyle, Rodney Corestar III AN Y 7 Dvorak, Douglas Spec I AQ N 8 Ethridge, Gary NDE Tech III AN Y 9 Gootz, Timothy West. III AN Y 10 Mains, Phillip West. II AQ N 11 Nelson, David NDE Tech III AN Y 12 Popovich, Roy West. Ill AN Y 13 Richmond, Mark NDE Tech III AN Y 14 Scott, Allen West. II AQ N 15 Skirpan, James NDE Tech IIA AN Y 16 Smith, Anthony West. II AQ N 17 Spence, William West. III AN Y 18 Stitt, Alan West. II AQ N 19 Taylor, Scott West. III AN Y 20 Terning, Gary West. III AN Y

Independent Qualified Data Analyst Page 18 of 78

FIGURE A.1 Westinghouse Model D-5 Tube Support Configuration SAV-2 AV3 1 r11 I* Anti-vibration bars 11H zzz z*11C 43- 3 10H 10C 43- 43 09H ------- 09C 43" 43" W =+ 08C 43- 3 07H zz- 1 07C 36- =06c 05H1 05C I Is- Inlet 03H1 03C j4" 01H 02C 01c*

TSH 24 TSC TEH TEC Outlet MInlet Nozzle - Manway Page 19 of 78

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ATTACHMENT A.1 ASME SECTION XI FORM NIS-BB 2A Steam Generator Page 1 of 5 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - 13211I Site: Byron Station, Unit 2 Steam Generator: 2RCOIBA Test Frequency: 20, 130, 300, 550 kHz Date: 0912512002

% Tube Wall Row Column Penetration Origin Location Inch 20 64 22 OD AV1 022 22 109 15 OD AV4 0 23 109 21 OD AV4 0 25 8 24 OD AV3 0.03 26 106 16 OD AV1 011 26 106 15 OD AV3 -0.06 26 107 18 OD AV2 006 26 107 21 OD AV3 -0.14 27 18 17 OD AVI -0.12 27 85 29 0D0 AV2 0 27 104 19 OD AV2 -008 27 106 26 OD AV1 0 27 106 21 OD AV2 0 27 106 29 OD AV3 0 28 104 16 OD AV4 -0.03 28 105 20 OD AV3 0.17 28 105 21 OD AV4 0 29 10 35 OD AV3 0 29 11 16 OD AV3 0 29 12 17 OD AV2 0.29 29 12 19 OD AV3 0 29 13 22 OD AV3 0.22 29 104 15 OD AV3 -0.14 30 68 17 OD AV2 0 30 69 23 OD AV2 0 30 69 17 OD AV3 0 30 70 16 OD AV2 0 30 103 22 OD AV2 0 30 104 15 OD AV2 0.06 31 12 19 OD AV3 0 31 12 15 OD AV4 0.03 31 14 16 OD AV3 0 31 14 17 OD AV4 0 31 67 25 OD AV4 0 31 101 22 OD AV2 0 31 101 24 OD AV3 0 31 103 21 OD AV2 0 31 103 21 OD AV3 0 32 76 22 OD AV3 -0.05 32 79 23 OD AV4 0 34 14 22 00 AV2 0.03 Page 53 of 78

ATTACHMENT A.1 ASME SECTION XI FORM NIS-BB 2A Steam Generator Page 2 of 5 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2R10 Site: Byron Station, Unit 2 Steam Generator: 2RC01BA Test Frequency: 20, 130, 300, 550 kHz Date: 09125/2002

% Tube Wall Row Column Penetration Origin Location Inch 34 90 21 OD AV3 0.03 35 15 23 OD AV3 0 35 15 16 OD AV4 0 35 16 23 OD AV2 006 35 16 22 OD AV3 0.05 35 100 20 OD AV3 0.03 36 15 15 OD AV3 -0.11 36 15 20 OD AV4 0 36 18 18 OD AV2 003 36 18 18 OD AV3 0.14 36 21 22 OD AV3 0.11 36 21 16 OD AV4 006 36 96 22 OD AV2 003 37 17 27 OD AV3 0 37 18 15 OD AV2 003 37 19 20 OD AV1 0.23 37 19 24 OD AV3 0.06 37 19 17 OD AV4 0 37 20 19 OD AV3 -0.05 37 21 17 OD AV3 0.03 37 23 28 OD AV2 0 37 23 26 OD AV3 0.09 37 23 15 OD AV4 0 37 98 31 OD AV2 0.11 37 98 29 OD AV3 006 37 99 18 OD AV3 0.03 38 16 24 OD AV3 0.03 38 16 22 OD AV4 0 38 19 24 OD AV3 0.17 38 19 25 OD AV4 0.03 38 20 26 OD AVI 0.11 38 20 27 OD AV2 0.14 38 20 15 OD AV3 0.11 38 20 19 OD AV4 0 38 21 18 OD AV1 0.06 38 21 17 OD AV3 -0.05 38 22 21 OD AV2 0.06 38 23 22 OD AVI 0.06 38 23 15 OD AV2 -0.03 38 23 30 OD AV3 0 38 23 24 OD AV4 0 Page 54 of 78

ATTACHMENT A.1 ASME SECTION XI FORM NIS-BB 2A Steam Generator Page 3 of 5 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2R10 Site: Byron Station, Unit 2 Steam Generator: 2RC01BA Test Frequency: 20, 130, 300, 550 kHz Date: 09125/2002

% Tube Wall Row Column Penetration Origin Location Inch 38 24 23 OD AV2 0 38 24 17 OD AV3 0.17 38 26 17 OD AV2 0 38 27 20 OD AV3 0 38 30 15 OD AV2 0 38 30 21 OD AV3 0 38 63 18 OD AV2 0.22 38 63 16 OD AV4 0.13 38 72 27 OD AV3 0 38 72 17 OD, AV4 0 38 73 15 OD AV2 0 38 73 27 OD AV3 0 38 98 22 OD AV1 03 38 98 30 OD AV2 008 38 98 17 OD' AV3 0 39 17 19 OD AV3 -0.05 39 21 31 OD AV3 008 39 21 16 OD AV4 -0.03 39 23 20 OD AV2 0 39 23 25 OD AV3 0 39 23 19 OD AV4 0 39 84 17 OD AV2 0 39 89 26 OD AV2 0 39 89 31 OD AV3 -0.31 39 89 18 OD AV4 0.06 39 94 22 OD AV1 0.08 39 94 33 OD AV3 0.03 39 96 19 OD AV3 0.03 39 96 16 OD AV4 0.17 39 97 15 OD AV4 -0.06 40 19 26 OD AV2 0.06 40 19 18 OD AV3 006 40 19 27 OD AV4 003 40 21 40 OD AV2 0 40 21 27 OD AV3 0.03 40 21 21 OD AV4 0 40 46 16 OD AV1 0 40 46 22 OD AV3 -003 40 64 17 OD AV1 -008 40 66 21 OD AV1 0 40 82 25 OD AV2 0.19 Page 55 of 78

ATTACHMENT A.1 ASME SECTION XI FORM NIS-BB 2A Steam Generator Page 4 of 5 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2R10 Site: Byron Station, Unit 2 Steam Generator: 2RC01BA Test Frequency: 20, 130, 300, 550 kHz Date: 09/25/2002

% Tube Wall Row Column Penetration Origin Location Inch 40 82 20 OD AV3 0 40 85 20 OD AV3 0 40 90 26 OD AV2 0.03 40 90 26 OD AV3 008 40 90 15 OD AV4 0 40 91 28 OD AV3 0 40 92 18 OD AV2 0 40 92 17 OD AV3 0 40 95 21 OD AV1 0 40 95 30 OD AV2 0 40 95 29 OD AV3 003 40 95 28 OD AV4 003 41 20 19 OD AV2 0 41 20 29 OD AV3 005 41 20 24 OD AV4 0.03 41 22 34 OD AV2 0 41 33 15 OD AV2 0.06 41 33 22 OD AV3 0.03 41 84 19 OD AV2 0 41 84 20 OD AV3 0 41 85 16 OD AV2 0 41 85 25 OD AV3 0 41 87 31 OD AV2 0.03 41 87 18 OD AV3 0 41 88 20 OD AV2 0 41 91 19 OD AV2 0 41 92 22 OD AV2 0 41 92 21 OD AV3 0.03 41 92 24 OD AV4 028 41 93 19 OD AV1 0.14 41 93 40 OD AV2 0 41 93 28 OD AV3 0 41 93 16 OD AV4 0 41 95 17 OD AV2 0.11 41 95 25 OD AV3 -006 41 95 26 OD AV4 0 42 21 16 OD AV4 003 42 25 20 OD AV1 0 42 25 18 OD AV2 0.06 42 25 35 OD AV3 0 42 25 22 OD AV4 003 Page 56 of 78

ATTACHMENT A.1 ASME SECTION XI FORM NIS-BB 2A Steam Generator Page 5 of 5 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2R10 Site: Byron Station, Unit 2 Steam Generator: 2RC01 BA Test Frequency: 20, 130, 300, 550 kHz Date: 0912512002

% Tube Wall Row Column Penetration Origin Location Inch 43 34 39 OD AV2 0 43 34 34 OD AV3 0 43 34 33 OD AV4 0 44 23 15 OD AV1 0.06 44 23 20 OD AV4 0 44 59 18 OD AV3 0 44 81 31 OD AV2 0 44 81 21 OD AV3 0 44 88 24 OD AV3 008 44 88 24 OD AV4 -0.11 44 90 26 OD AV2 006 44 90 32 OD AV3 006 45 24 18 OD AV3 0.03 45 24 21 OD AV4 0.11 45 25 20 OD AV3 011 45 25 20 OD AV4 0 45 28 38 OD AV3 0 45 28 34 OD AV4 -008 45 89 18 OD AV4 0 46 64 27 OD AV3 0 46 64 31 OD AV4 -0.03 46 89 17 OD AV4 -0.03 47 28 15 OD AV4 014 47 59 20 OD AVI 0 47 61 20 OD AV3 -0.19 47 61 19 OD AV4 -008 48 56 29 OD AV3 0 48 56 22 OD AV4 0 49 50 16 OD AV4 0 49 51 21 OD AV4 0 49 60 18 OD AV4 0.03

_PagI 7I o 78 Page 57 of 78

ATTACHMENT A.2 ASME SECTION XI FORM NIS-BB 2B Steam Generator Page 1 of 8 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - 132111 Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20,130, 300, 550 kHz Date: 0912512002

% Tube Wall Row Column Penetration Origin Location Inch 18 48 31 OD AVI -0.41 23 7 16 OD AV4 0 23 108 33 OD AV2 0.06 23 108 16 OD AV3 0.03 24 106 15 OD AV2 -0.06 24 107 19 OD AV2 0.08 24 107 17 OD AV3 -0.23 24 108 25 OD AV4 -0.11 25 91 16 OD AV3 0 25 103 21 OD AV2 -0.17 25 104 21 OD AV2 0.14 25 106 18 OD AV4 -0.06 25 107 20 OD AV2 048 25 107 24 OD AV3 -0.17 25 108 15 OD AV2 -02 25 108 30 OD AV4 -0.2 26 11 15 OD AV3 027 26 105 29 OD AV3 -0.14 26 107 17 OD AV2 0 27 10 21 OD AV2 0 27 29 19 OD AV3 009 27 31 23 OD AV4 0 27 105 19 OD AV1 0 27 105 28 OD AV2 -026 27 105 18 OD AV3 -0.17 27 105 16 OD AV4 -0.23 28 11 21 OD AV2 0.33 28 11 29 OD AV3 -0.12 28 11 23 OD AV4 0 28 12 20 OD AV2 0 28 27 18 OD AV2 012 28 27 20 OD AV3 0 28 29 21 OD AV2 0.18 28 29 21 OD AV3 0.12 28 32 22 OD AV2 0 28 37 20 OD AV3 0 28 79 17 OD AV3 -0.03 28 99 16 OD AV2 -023 28 102 24 OD AV3 -0.17 28 103 16 OD AVI 0.08 28 103 15 OD AV2 -0.11 Page 58 of 78

ATTACHMENT A.2 "ASMESECTION XI FORM NIS-BB 2B Steam Generator Page 2 of 8 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2RIO Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20,130, 300, 550 kHz Date: 09/25/2002

%Tube Wall Row Column Penetration Origin Location Inch 28 103 21 OD AV3 -0.2 28 104 16 OD AVI 0.28 28 104 24 OD AV2 0.23 28 104 16 OD AV3 0 29 13 18 OD AV3 0 29 15 17 OD AV2 0.18 29 15 16 OD AV4 0 29 98 16 OD AV2 0 29 100 17 OD AV2 0.14 29 105 21 OD AV2 -02 29 105 25 OD AV4 -0.25 30 13 18 OD AV3 0 30 14 18 OD AV3 0.12 30 99 21 OD AV3 0 30 101 19 OD AV1 0 30 102 28 OD AV2 0 30 102 18 OD AV3 -014 30 105 28 OD AV4 0 31 12 21 OD AVI 0.06 31 12 26 OD AV2 -0.06 31 12 31 OD AV3 -0.45 31 12 29 OD AV4 -018 31 13 17 OD AV1 0.06 31 13 15 OD AV2 0.12 31 13 16 OD AV3 -015 31 13 21 OD AV4 0 31 15 25 OD AV2 0 31 17 15 OD AV2 0 31 34 17 OD AV3 0 31 102 19 OD AV3 -0.06 32 12 27 OD AV2 0 32 28 31 OD AV2 0.34 32 28 23 OD AV3 0.12 32 28 18 OD AV4 -0.03 32 32 22 OD AV2 0 32 32 32 OD AV3 0 32 32 22 OD AV4 0.06 32 36 17 OD AV2 0 32 36 25 OD AV3 -0.06 32 40 17 OD AV2 0.16 32 40 21 OD AV3 0.12 Page 59 of 78

ATTACHMENT A.2 ASME SECTION XI FORM NIS-BB 2B Steam Generator Page 3 of 8 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2RIO Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20, 130, 300, 550 kHz Date: 09/25/2002

% Tube Wall Row Column Penetration Origin Location Inch 32 40 17 OD AV4 -0.09 32 98 19 OD AV3 0 32 99 15 OD AV3 0.06 33 13 20 OD AV1 0.09 33 14 34 OD AV1 -0.12 33 14 26 OD AV2 0 33 14 19 OD AV4 0 33 72 18 OD AV3 0.08 33 72 16 OD AV4 0 33 97 30 OD AV3 0 33 98 16 OD AV2 -0.03 33 98 22 OD AV3 0.03 33 99 20 OD AVI 0 33 99 25 OD AV2 0 33 99 23 OD AV3 0 33 99 15 OD AV4 -0.03 34 14 30 OD AV3 -0.03 34 14 15 OD AV4 0 34 17 19 OD AV3 003 34 19 17 OD AV3 0 34 26 24 OD AV3 -0.06 34 30 22 OD AV1 0.09 34 30 26 OD AV3 0.12 34 33 24 OD AV2 041 34 36 19 OD AV2 0 34 39 20 OD AV2 0.29 34 95 17 OD AV3 0.2 34 99 16 OD AV3 003 34 100 18 OD AV3 0.03 34 102 16 OD AV4 -003 35 14 18 OD AV2 0 35 14 23 OD AV3 0 35 15 31 OD AV2 0 35 16 18 OD AVI 006 35 16 21 OD AV3 -0.12 35 96 25 OD AV3 -0.06 35 97 15 OD AV2 -008 35 97 34 OD AV3 0 35 98 24 OD AVI 0 35 98 16 OD AV3 0.14 35 98 24 OD AV4 -0.08 Page 60 of 78

ATTACHMENT A.2 ASME SECTION XI FORM NIS-BB 2B Steam Generator Page 4 of 8 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2RIO Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20, 130, 300, 550 kHz Date: 09/25/2002

% Tube Wall Row Column Penetration Origin Location Inch 35 99 19 OD AV3 0.06 35 99 21 OD AV4 -0.06 35 100 27 OD AV2 -0.17 35 100 18 OD AV3 0 35 100 24 OD AV4 -003 35 101 35 OD AV3 0 35 101 29 OD AV4 0 36 16 18 OD AV2 0 36 16 27 OD AV3 -0.09 36 16 16 OD AV4 0 36 17 20 OD AV2 0.03 36 17 17 OD AV3 -0.03 36 18 16 OD AV2 0 36 20 18 OD AVi -009 36 20 24 OD AV2 -0.18 36 20 16 OD AV3 0 36 23 27 OD AV2 0 36 29 18 OD AV2 0.09 36 29 16 OD AV3 0 36 78 21 OD AV3 003 36 78 15 OD AV4 -011 36 88 20 OD AV3 -0.08 36 94 20 OD AV2 0.03 37 17 16 OD AV3 0.12 37 83 18 OD AV2 0 37 90 17 OD AV2 0 37 92 34 OD AV2 0 37 93 16 OD AV2 0 37 93 30 OD AV3 0 37 95 19 OD AV3 0 37 95 16 OD AV4 0 38 71 18 OD AVI 0 38 71 23 OD AV2 0.14 38 71 34 OD AV3 -0.06 38 93 16 OD AV2 0.08 38 93 17 OD AV3 003 38 93 16 OD AV4 0 38 95 33 OD AV1 0 38 95 23 OD AV2 0 38 95 23 01 AV3 0 38 95 26 OD AV4 0 Page 61 of 78

ATTACHMENT A.2 ASME SECTION XI FORM NIS-BB 2B Steam Generator Page 5 of 8 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2R10 Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20, 130, 300, 550 kHz Date: 09/2512002

% Tube Wall Row Column Penetration Origin Location Inch 38 96 30 OD AV1 -006 38 96 25 OD AV2 -0.09 38 96 18 0D AV3 003 38 96 29 OD AV4 0.06 39 19 32 OD AV2 -0.03 39 19 28 OD AV3 -003 39 19 15 OD AV4 0.09 39 20 20 OD AV2 0 39 21 17 OD AV2 0.06 39 21 18 OD AV3 -0.06 39 26 25 OD AV2 -0.12 39 26 18 OD AV3 -0.03 39 33 20 OD AV4 0 39 39 24 OD AV2 0.15 39 69 17 OD AV2 0 39 69 19 OD AV3 0.03 39 77 16 OD AV3 0 39 88 19 OD AV2 0 39 92 24 OD AV4 -006 39 93 22 OD AV3 0 39 93 17 OD AV4 0.17 39 94 18 OD AV2 -0.2 39 94 31 OD AV3 -006 39 94 19 OD AV4 0 39 95 22 OD AV2 -0.11 39 95 23 OD AV3 0 39 95 20 OD AV4 -0.03 39 96 19 OD AVI -0.06 39 96 39 OD AV2 0 39 96 17 OD AV4 -0.06 40 18 20 OD AV1 -006 40 18 39 OD AV2 0 40 18 38 OD AV3 0 40 20 24 OD AV2 0 40 20 28 OD AV3 0 40 24 24 OD AV2 0.12 40 26 24 OD AV2 0.18 40 27 25 OD AV3 0.09 40 34 28 OD AV2 0.22 40 41 19 OD AV2 0.15 40 45 17 OD AV2 0.24 Paae 62 of 78

ATTACHMENT A.2 ASME SECTION XI FORM NIS-BB 2B Steam Generator Page 6 of 8 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2R10 Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20, 130, 300, 550 kHz Date: 09125/2002

%Tube Wall Row Column Penetration Origin Location Inch 40 54 18 OD AV2 0 40 54 19 OD AV3 -0.18 40 59 22 OD AV3 0.09 40 59 16 OD AV4 0 40 91 21 OD AV2 0 40 92 29 OD AV3 0.11 40 94 15 OD AV1 0 40 94 32 OD AV2 0.03 40 95 15 OD AV3 0 40 95 18 OD AV4 0.03 41 43 24 OD AV1 0.12 41 43 28 OD AV2 0.15 41 43 35 OD AV3 003 41 79 18 OD AV3 006 41 85 18 OD AV2 0 41 87 22 OD AVI 0 41 87 27 OD AV2 0 41 87 21 OD AV3 0.03 41 87 16 OD AV4 0.06 41 93 23 OD AV2 -006 41 93 27 OD AV3 0 41 93 25 OD AV4 0 41 95 21 OD AV1 0 41 95 33 OD AV2 0 41 95 29 OD AV3 0 42 30 30 OD AV1 0 42 30 24 OD AV2 0.18 42 30 36 OD AV3 0 42 34 24 OD AV2 0 42 36 26 OD AV2 021 42 37 15 OD AVI 044 42 37 28 OD AV2 0.41 42 37 31 OD AV3 0.47 42 39 15 OD AV3 0.18 42 44 19 OD AV2 0.12 42 44 33 OD AV3 0 42 44 21 OD AV4 0.12 42 68 22 OD AV2 0 42 68 20 OD AV3 -0.06 42 84 19 OD AV2 0 42 84 17 OD AV3 0.14 Page 63 of 78

ATTACHMENT A.2 ASME SECTION XI FORM NIS-BB 2B Steam Generator Page 7 of 8 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B21111 Site: Byron Station, Unit 2 Steam Generator: 2RCOIBB Test Frequency: 20, 130, 300, 550 kHz Date: 09/2512002

% Tube Wall Row Column Penetration Origin Location Inch 42 86 21 OD AV2 0 42 89 34 OD AVI 0 42 89 33 OD AV2 0 42 89 24 OD AV3 -0.11 42 91 16 OD AV4 0.03 43 25 25 OD AV2 -0.09 43 25 20 OD AV3 0 43 25 17 OD AV4 0 43 29 21 OD AVI -0.12 43 29 37 OD AV2 0 43 29 16 OD AV3 0.03 43 91 24 OD AV3 0 43 92 23 OD AV3 006 43 93 16 OD AV4 003 44 26 35 OD AV2 0 44 26 18 OD AV3 0 44 45 18 OD AV2 0 44 45 25 OD AV3 0.12 44 76 25 OD AV2 0.03 44 76 17 OD AV3 -008 44 85 24 OD AV2 0 44 85 32 OD AV3 0 44 85 24 OD AV4 -0.08 44 90 33 OD AV3 0.06 44 90 19 OD AV4 0.03 45 26 33 OD AV2 0 45 26 38 OD AV3 0 45 26 28 OD AV4 0 45 29 19 OD AV4 -0.09 45 32 23 OD AV2 0.12 45 32 29 OD AV3 0.15 45 36 28 OD AV3 0.15 45 36 33 OD AV4 0 45 83 25 OD AV2 0 45 83 21 OD AV3 0 45 83 21 OD AV4 0.06 45 86 29 OD AV2 0.03 45 86 18 OD AV3 -017 45 89 31 OD AV2 0 45 89 22 OD AV3 0 47 27 35 OD AV2 0 Page 64 of 78

ATTACHMENT A.2

'ASME SECTION XI FORM NIS-BB 2B Steam Generator Page 8 of 8 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2R10 Site: Byron Station, Unit 2 Steam Generator: 2RC01BB Test Frequency: 20, 130, 300, 550 kHz Date: 09/25/2002

% Tube Wall Row Column Penetration Origin Location Inch 47 27 29 OD AV3 0 47 27 29 OD AV4 0 47 56 31 OD AV2 0 47 75 6 OD 02C 0.31 48 50 13 OD 07C 0.34 48 53 12 OD 07C 0.4 48 54 8 OD 07C 0.34 48 55 10 OD 07C 0.4 48 59 12 OD 07C -046 49 50 15 OD 07C 0.25 49 53 16 OD 07C 0.15 49 63 9 OD 07C 0.4 49 69 16 OD AV4 -0.06 4 1 4 + 9

+ I 4 4. t

.9. 9 1 4 I 4 9 4 4 9

.4. 9 4 .9. 9

+

4 .9. 4 9 1 4 4

______ 9 1. .4 4

.4. 9 4. 4 4 4 9 4. 4 4 4 9 1 I 4 I 4 I

.4. I 4. .4 4 Paqe 65 of 78

ATTACHMENT A.3 ASME SECTION XI FORM NIS-BB 2C Steam Generator Page 1 of 5 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - 132111 Site: Byron Station, Unit 2 Steam Generator: 2RC01BC Test Frequency: 20, 130, 300, 550 kHz Date: 0912512002

%Tube Wall Row Column Penetration Origin Location Inch 17 25 22 OD 01H 0.42 22 6 19 OD AVI 008 22 6 18 OD AV4 -0.22 22 30 4 OD 01H 0.42 23 6 22 OD AV4 0.08 23 30 30 OD 01H 0.46 23 31 11 OD 01H 041 24 33 3 OD 01H 041 25 33 15 OD 01H 047 25 105 17 OD AV2 0 25 106 21 OD AV1 009 25 107 17 OD AV4 -0.14 25 108 19 OD AV1 0.11 25 108 18 OD AV2 0 25 108 20 OD AV3 0.06 26 8 22 OD AV2 0 26 9 18 OD AV2 014 26 9 18 OD AV3 -0.03 26 9 26 OD AV4 -0.06 26 85 22 OD AV2 0.42 27 34 19 OD AV3 0 27 106 17 OD AV2 0 27 106 26 OD AV3 0 28 35 15 OD AV3 0.06 28 84 22 OD AV3 0 28 103 27 OD AV3 0 29 11 23 OD AV1 -0.08 29 29 19 OD AV2 0 29 29 18 OD AV3 -0.11 29 38 15 OD AV3 0 29 44 17 OD AV2 008 30 35 22 OD AV3 0.03 30 84 15 OD AV2 014 30 85 18 OD AV2 0 30 85 16 OD AV3 0 30 100 15 OD AV2 0 30 100 16 OD AV3 008 30 100 16 OD AV4 0.08 30 104 18 OD AV2 008 30 104 16 OD AV3 -011 31 14 17 OD AV3 0 Page 66 of 78

ATTACHMENT A.3 ASME SECTION XI FORM NIS-BB 2C Steam Generator Page 2 of 5 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2111O Site: Byron Station, Unit 2 Steam Generator: 2RC01 BC Test Frequency: 20, 130, 300, 550 kHz Date: 09/25/2002

% Tube Wall Row Column Penetration Origin Location Inch 31 82 17 OD AV3 0.14 32 13 17 OD AV2 0.22 32 13 22 OD AV3 0.16 32 28 16 OD AV3 0 32 74 15 OD AV3 0 32 82 21 OD AV2 -0.17 32 83 18 OD AV3 0 32 83 18 OD AV3 014 33 39 17 OD AV2 -0.08 33 39 16 OD AV3 -003 33 50 17 OD AV3 0 34 27 26 OD AV2 0 34 29 19 OD AV2 0.17 34 29 18 OD AV3 003 34 59 8 OD TSH 0.12 34 85 17 OD AV2 0 34 92 24 OD AV2 0.11 34 92 17 OD AV3 0 34 94 19 OD AV2 -011 34 94 16 OD AV3 0 34 95 16 OD AV2 0 35 19 15 OD AV2 0 35 22 20 OD AV3 0 35 25 22 OD AV2 0 35 25 20 OD AV3 -0.03 35 30 22 OD AV2 003 35 82 17 OD AV2 0.14 35 82 21 OD AV3 0.06 35 85 18 OD AV2 0.03 35 85 27 OD AV3 0 35 86 15 OD AV1 0.03 35 86 33 OD AV2 -0.2 35 87 17 OD AV3 0 35 88 19 OD AV3 -0.06 35 95 19 OD AV2 0 35 96 16 OD AV2 -0.2 35 96 16 OD AV4 0.03 36 17 17 OD AV3 -0.03 36 19 27 OD AV3 0.11 36 20 16 OD AV3 0 36 21 25 OD AV3 -0.08 Page 67 of 78

ATTACHMENT A.3 ASME SECTION XI FORM NIS-BB 2C Steam Generator Page 3 of 5 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2R10 Site: Byron Station, Unit 2 Steam Generator: 2RC01BC Test Frequency: 20, 130, 300, 550 kHz Date: 09125/2002

% Tube Wall Row Column Penetration Origin Location Inch 36 22 21 OD AV2 0 36 22 20 OD AV3 0 36 24 15 OD AVI -0.28 36 24 26 OD AV3 -0.22 36 25 16 OD AV2 031 36 27 17 OD AV3 003 36 80 16 OD AV1 0 36 80 18 OD AV3 -0.28 36 93 16 OD AV2 0 36 94 19 OD AV2 006 36 96 20 OD AV2 -0.14 36 96 17 OD AV3 0 37 17 19 OD AV1 -0.17 37 23 16 OD AV2 0 37 84 20 OD AV3 0 38 16 23 OD AVI 0 38 16 21 OD AV2 0 38 22 24 OD AV1 0.22 38 22 21 OD AV2 0 38 25 15 OD AVI 0.06 38 25 20 OD AV2 0.28 38 62 25 OD AV2 -009 38 62 18 OD AV3 -008 39 19 27 OD AV3 0.03 39 20 15 OD AV2 0 39 25 16 00 AVI -0.03 39 25 16 OD AV2 0 39 35 15 OD AVI 0 39 35 32 OD AV2 0 39 35 32 OD AV3 0 39 38 17 OD AV3 006 39 49 18 OD AV2 008 39 83 20 OD AV2 017 39 94 17 OD AV2 -0.14 39 94 16 OD AV3 0 40 21 29 OD AV2 0.03 40 21 16 OD AV3 0 40 82 16 OD AV2 0.06 40 83 24 OD AV2 -006 40 83 19 OD AV3 -0.11 40 90 19 OD AV2 006 Page 68 of 78

ATTACHMENT A.3 ASME SECTION XI FORM NIS-BB 2C Steam Generator Page 4 of 5 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - 13211I Site: Byron Station, Unit 2 Steam Generator: 2RC01BC Test Frequency: 20,130, 300,550 kHz Date: 09125/2002

% Tube Wall Row Column Penetration Origin Location Inch 40 90 18 OD AV3 0 40 93 16 OD AV1 0 40 93 22 OD AV3 0 40 95 15 OD AV1 0 40 95 23 OD AV3 0 41 26 15 OD AV2 017 41 26 17 OD AV3 0.28 41 63 19 OD AV1 -008 41 63 30 OD AV2 022 41 63 19 OD AV3 -0.03 41 84 15 OD AVI 0 41 84 18 OD AV3 0.03 41 88 21 OD AV2 0.08 41 88 25 OD AV3 -0.2 41 89 26 OD AVi 0 41 89 18 OD AV2 0 41 89 28 OD AV3 0 41 89 21 OD AV4 0 41 92 18 OD AV1 0 41 92 33 OD AV3 0.11 41 92 20 OD AV4 -0.03 42 25 18 OD AV3 008 42 29 18 OD AV2 006 42 29 26 OD AV3 006 42 86 19 OD AVI -006 42 86 26 OD AV2 0.08 42 86 28 OD AV3 -006 42 88 16 OD AV2 014 42 89 18 OD AV2 0 42 89 30 OD AV3 0 42 90 31 OD AV3 -0.2 42 90 19 OD AV4 0 42 93 25 OD AV1 0 42 93 15 OD AV2 0 42 93 27 OD AV3 0 42 94 18 OD AV2 0.06 42 94 29 OD AV3 0 42 94 16 OD AV4 -0.11 43 34 17 OD AV3 0.06 43 36 23 OD AV3 0.03 43 36 17 OD AV4 0.11 Page 69 of 78

ATTACHMENT A.3 ASME SECTION XI FORM NIS-BB 2C Steam Generator Page 5 of 5 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2R10 Site: Byron Station, Unit 2 Steam Generator: 2RCOIBC Test Frequency: 20, 130, 300, 550 kHz Date: 09125/2002

% Tube Wall Row Column Penetration Origin Location Inch 43 93 16 OD AV1 0 43 93 21 OD AV2 0 43 93 17 OD AV3 0 47 74 15 OD AV3 0 48 36 17 OD 02C 0.5 48 43 15 OD AV3 0 49 34 24 OD 02C 041 49 48 14 OD 07C -0.5 49 59 16 OD AV2 008 49 62 18 OD 07C -0.08 49 63 19 OD 07C -005 49 73 7 OD 07C -0.41 9 I. 9 1 9 J. 1 4 4 I 4 1 4 4 4 .1. I 4 9 + 9 1-I + I 1-1 4 9 4. 4 1 4 9 4. .9 4 4

1-4 4 9 .9 1 1 4 4 4. 4 4 4 4 4.

4 4 4 .9

4. 4. 4 .9 ¶ L .L 1 4. 4

4. 4 4 + 9

4. 4 4 4. 9

4. .9 1 .9 9

______ 1. 1 1 4. 9

4. 1 4. 4 9

4. 9 4. t

4. 9 4. 4. 9

+ 1 4 4. I

.9. 1 4. 4 4 4 4 4. 4 4 L -

Paqe 70 of 78

ATTACHMENT A.4 "ASMESECTION XI FORM NIS-BB 2D Steam Generator Page 1 of 3 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - 132111 Site: Byron Station, Unit 2 Steam Generator: 2RC01BD Test Frequency: 20, 130, 300, 550 kHz Date: 0912512002

% Tube Wall Row Column Penetration Origin Location Inch 20 5 18 OD AV4 0 21 57 18 OD AV1 0 25 50 27 OD AV2 0 25 108 20 OD AVI -006 25 108 19 OD AV4 0 26 70 21 OD AV2 -0.37 26 107 19 OD AV3 0 26 107 15 OD AV4 0.03 28 11 16 OD AV2 0 28 28 29 OD AV4 -0.34 28 36 28 OD AV2 -0.14 28 78 17 OD AV3 -0.03 28 102 16 OD AV3 -009 30 103 21 OD AV2 -0.09 31 13 17 OD AV1 009 31 13 22 OD AV3 0.03 31 14 16 OD AV4 -0.14 31 44 37 OD AV2 0 31 44 25 OD AV3 0 31 50 20 OD AV2 0.17 31 50 30 OD AV3 -014 31 50 19 OD AV4 0 31 84 25 OD AV2 0.09 31 84 18 OD AV3 0.06 31 103 22 OD AV2 -006 31 103 20 OD AV3 0 31 103 16 OD AV4 -0.06 31 104 18 OD AV3 -0.03 32 79 17 OD AV3 0.03 33 34 19 OD AV2 0.2 33 70 18 OD AV3 006 34 87 16 OD AV2 0 34 87 20 OD AV3 -0.06 34 95 16 OD AV3 0.06 34 97 17 OD AV1 -0.03 34 97 29 OD AV2 0.03 34 97 15 OD AV3 0.06 34 98 23 OD AV3 0.06 34 99 18 OD AV3 0 34 99 37 OD AV4 0 34 100 17' OD AV3 0 Paqe 71 of 78

ATTACHMENT A.4 ASME SECTION XI FORM NIS-BB 2D Steam Generator Page 2 of 3 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - 132111 Site: Byron Station, Unit 2 Steam Generator: 2RC01BD Test Frequency: 20, 130, 300, 550 kHz Date: 0912512002

% Tube Wall Row Column Penetration Origin Location Inch 35 14 19 OD AV4 0 35 17 28 OD AV2 0 35 17 15 OD AV3 -0.06 35 20 28 OD AV2 0 35 95 29 OD AV2 003 35 95 16 OD AV3 014 35 99 32 OD 02C 0.48 36 17 18 OD AV2 0 36 18 19 OD AV2 0.03 36 19 15 OD AV3 -0.03 36 21 23 OD AV2 0 36 37 31 OD AV2 0 36 37 25 OD AV3 0.06 36 62 17 OD AV2 0.08 36 82 28 OD AV2 0 36 82 17 OD AV3 0.03 36 82 18 OD AV4 0.03 36 83 23 OD AV2 0.14 36 84 16 OD AV2 0.17 36 95 18 OD AV3 009 36 99 14 OD 02C 041 37 33 16 OD AV1 0 37 33 25 OD AV2 0 37 33 27 OD AV3 -0.03 37 42 35 OD AV2 0 37 87 15 OD AV3 -0.03 37 99 19 OD 02C 1.09 38 25 18 OD AV3 0 39 27 18 OD AV3 0.17 39 72 19 OD AV2 0 39 72 23 OD AV3 0.14 39 80 15 OD AV2 0 39 80 23 OD AV3 006 39 90 26 OD AV4 0 40 22 16 OD AV4 -009 40 25 15 OD AV3 -0.17 40 26 17 OD AV3 0.03 40 28 19 OD AV3 0.09 40 29 29 OD AV2 0 40 29 22 OD AV3 0 40 33 20 OD AV2 031 Page 72 of 78

ATTACHMENT A.4

'ASME SECTION XI FORM NIS-BB 2D Steam Generator Page 3 of 3 FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS -B2R10 Site: Byron Station, Unit 2 Steam Generator: 2RC01BD Test Frequency: 20,130, 300, 550 kHz Date: 09125/2002

% Tube Wall Row Column Penetration Origin Location Inch 40 33 25 OD AV3 0.17 40 36 17 OD AV2 006 40 36 16 OD AV3 -0.06 40 73 23 OD AV2 017 40 76 25 OD AV2 003 40 90 20 OD AV3 0 40 92 16 OD AV3 -0.11 41 20 22 OD AVI 0.14 41 20 25 OD AV2 0 41 32 19 OD AV2 0 41 32 16 OD AV3 0 41 33 25 OD AV2 0.26 41 33 16 OD AV3 -011 41 60 19 OD AVI 0.14 41 60 17 OD AV2 0.06 41 80 22 OD AVI 0.17 41 86 17 OD AV2 006 41 86 35 OD AV3 0 42 36 34 OD AV2 0.11 42 36 23 OD AV3 -0.03 43 22 19 OD AVI 0 43 22 19 OD AV2 -0.14 43 85 16 OD AV3 0 46 80 17 OD AV4 0 46 89 16 OD AV4 003 47 56 20 GD AV3 008 47 56 31 OD AV4 0.11 48 59 27 OD AV3 0 48 59 20 OD AV4 0 48 59 16 OD AV4 -0.06 49 34 15 OD AV2 0 49 52 8 OD 07C 0.36 t t .t 6 6 J. 4 6 4.

4. 4 6 +

4. 4 6

4. 4. 9 1 6 4. 4. 1 t I J. .& 1 4.

I _________ .L .L _________ I _________ J.

Page 73 of 78

ATTACHMENT A.5 ASME SECTION XI FORM NIS-BB 2C Steam Generator Page 1 of I FORM NIS-BB TUBE EXAMINATION REPORT EDDY CURRENT EXAMINATION RESULTS - B2F23 Site: Byron Station, Unit 2 Steam Generator: 2RCOIBC Test Frequency: 20, 130, 300, 550 kHz Date: 0612512002

% Tube Wall Row Column Penetration Origin Location Inch 43 22 37 OD 02C 0.49 43 23 71 OD 02C 0.53 43 24 11 OD 02C 0.46 43 24 13 OD 02C 085 1 .4 4 4. 4

______ 1 .4 4 + 4 4 4 4 4. 4 4 4 4.

. 4 I 4. I

______ L .4 1 4 4

1. .4 4 4 4

4. 4 4. .4

4. .4 1. 4. 1

4. 1 4. 4. 1 J. 1 4. 4 4

4. 4 4. .4 4 4 4 4. .4 i i I 4I 4

+ I 4. 4. 1-

______ .4 4 4. I 4.

4 4 4. 4 4 4 4. 4 4.

4 1 + I 4.

______ .4 1 + 4 4.

______ .4 4 *I. 9 4 4. 4. 9 4.

4 4. 4 I t

______ .4 L .4 4 +

4 4. 4 4 4.

4 4. 4. 1 4.

1 4 4 I 4.

i 4. v. I 4 PaQe 74 of 78

Sized at 71 % TW by eddy current. 100% TW flaw confirmed by pressure test.

I __

ATTACHMENT A.6 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules

1. Owner: Exelon Generation Company, LLC, 200 Exelon Way, Kennett Square. PA, 19348 (Name and Address of Owner)

2. Plant: Byron Station, 4450 North German Church Road, Byron, Illinois, 61010 (Name and Address of Plant)

3. Plant Unit: Two (2) 4. Owner Certificate of Authorization (if required): N/A

5. Commercial Service Date: 08/21/87 6. National Board Number for Unit: N-200

7. Components Inspected: Steam Generator Eddy Current Inspection- B2RI0 Component or Manufacturer or Manufacturer or State or Province National Board No.

Appurtenance Installer Installer Serial No. No.

2RCO1BA Westinghouse 2095 U-201435 15 2RCO0BB Westinghouse 2096 U-201436 16 2RCOIBC Westinghouse 2097 U-201437 17 2RCO0BD Westinghouse 2098 U-201438 18

.4. .4. + +

+ +

+ 1* 4

.4. .4. + 4

.4. .4. .4. 4 4 4 +

4 4 + 1 4 .4. .4. .4.

.4. 4 4.

4 F F I

4. I. I. 4.

Page 75 of 78

FORM NIS-1 (Back)

8. Examination Dates 09/20/02 to 09/25/02 9. Inspection Interval from 08/21/98 (extended) to 08/21/07

10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

Refer to the Attached Report

11. Abstract of Conditions Noted Refer to the Attached Report

12. Abstract of Corrective Measures Recommended and Taken Refer to the Attached Report We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.

Certificate of Authorization No. (if applicable) Not Applicable Expiration Date Not Applicable Date /12-- 3 Oa_ Signed For Exelon Generating Company, LLC By Owner CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Z9 1 - and employed by 11%6 er of .oer - have inspected the components described in this Owner's Report during the period g to -4ý i54 , and state that to the best of my knowledge and belief, the Owner has performed examinations and aken corrective 6easures described in this Owner's Report 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 employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

_________, ___.._ Commissions i/t- /P*Q rinspector's Signature National Board, State, Province, and Endorsements Date 41fellý&3 *IWý Page 76 of 78

ATTACHMENT A.7 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules

1. Owner: Exelon Generation Company, LLC, 200 Exelon Way, Kennett Square, PA, 19348 (Name and Address of Owner)

2. Plant: Byron Station, 4450 North German Church Road, Byron, Illinois, 61010 (Name and Address of Plant)

3. Plant Unit: Two (2) 4. Owner Certificate of Authorization (if required): N/A

5. Commercial Service Date: 08/21/87 6. National Board Number for Unit: N-200

7. Components Inspected: Steam Generator Eddy Current Inspection - B2F23 Component or Manufacturer or Manufacturer or State or Province National Board No.

Appurtenance Installer Installer Serial No. No.

2RCO0BC Westinghouse 2097 U-201437 17 I 4 4 4 4 4 4 1 4 4 1 1 1 4 4 1 4- 4 1 1-4- 4- 1

+ 4- 1 4- 4- 1-4- 4- 4-4 4- 4- 4-

+ + 1- t 4- + 4- 4-4 + 1- -t 4 + 1- -t Page 77 of 78

FORM NIS-1 (Back)

8. Examination Dates 06/24/02 to 06/25/02 9. Inspection Interval from 08/21/98 (extended) to 08/21/07

10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

Refer to the Attached Report

11. Abstract of Conditions Noted Refer to the Attached Report

12. Abstract of Corrective Measures Recommended and Taken Refer to the Attached Report We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.

Certificate of Authorization No. (if applicable) Not Applicable Expiration Date Not Applicable Date 1.!t3// 2- Signed For Exelon Generating Company, LLC By A, Owner CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of V1;O1* and employed by Af ... of ,_/ have inspected the components described in this Owner's Report during the period to 5,d , and state that to the best of my knowledge and belief, the Owner has performed examinations and taknn corrective measures described in this Owner's Report 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 employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

_______________ Commissions ,I, -/Z-4 1 IW'ectoes Signature National Board, State, Province, and Endorsements Date 3 ,wd-Page 78 of 78

BYRON 2002-0129, Generator Inservice Inspection Summary Report

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BYRON 2002-0129, Generator Inservice Inspection Summary Report

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SUMMARY

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