Text

Tenth Refueling Outage Steam Generator Inservice Inspection Summary Report
	ML032190155
Person / Time
Site:	Braidwood
Issue date:	07/29/2003
From:	Pacilio M; Exelon Nuclear
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Bw030059
	Download: ML032190155 (76)
	v • d • e

Exek rnm Exelon Generation www.exeloncorp.com Nuclear Braidwood Generating Station 35100 South Route 53, Suite 84 Braceville, IL 60407-9619 Tel 815-458-2801 July 29, 2003 Bw030059 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. STN 50-456

Subject:

Braidwood Station, Unit 1 Tenth Refueling Outage Steam Generator Inservice Inspection Summary Report In accordance with Technical Specification 5.6.9, "Steam Generator (SG) Tube Inspection Reports,"

item b, Exelon Generation Company, LLC is reporting the results of the SG inspections, which were completed during the Braidwood Station Unit 1, Cycle 10 Refueling Outage. 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 1WA-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."

If there are any questions regarding this submittal, please contact Kelly Root, Regulatory Assurance Manager, at (815) 417-2800.

Respectfully, MichaJ.aio Site Vice President Braidwood Station

Attachment:

Exelon Braidwood Station, Unit 1 Tenth Refueling Outage Steam Generator Inservice Inspection Sunmary Report Cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Braidwood Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety 4 4j7

Exelon Nuclear BRAIDWOOD STATION UNIT 1 35100 South Rte. 53, Suite 84 Braceville, IL 60407 COMMERCIAL OPERATION: 07/29/88 STEAM GENERATOR EDDY CURRENT INSPECTION REPORT CYCLE 10 REFUELING OUTAGE (A1l10)

April 2003 Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 Document Completion Date: July 17,2003

TABLE OF CONTENTS

1.0 INTRODUCTION

2.0

SUMMARY

3.0 CERTIFICATIONS 3.1 Procedures/Examinations/Equipment 3.2 Personnel 4.0 EXAMINATION TECHNIQUE AND EXAMINATION SCOPE 4.1 Examination Techniques and Examination Scope 4.2 Recording of Examination Data 4.3 Witness and Verification of Examination 5.0 EXAMINATION RESULTS 5.1 Indications Found 5.2 Other Inspection Results 6.0 REPAIR

SUMMARY

7.0 DOCUMENTATION 8.0 FIGURES/TABLES/ATTACHMENTS

1.0 INTRODUCTION

Braidwood Unit 1 operates with four Babcock & Wilcox Replacement Steam Generators (SGs) in the four loop pressurized water reactor system. The SGs each contain 6633 thermally treated Inconel-690 U-tubes that have a nominal diameter of 0.6875 inches and a nominal thickness of 0.040 inches. The tubes are supported by stainless steel lattice grid structures and fan bars. The tubes are hydraulically expanded into the full depth of the tubesheet. Main Feedwater enters the SGs above the tube bundle through a feedring and J-tubes. The SG configuration is shown in Figures A. 1 and A.2. The replacement SGs were installed at the end of Cycle 7.

In compliance with Braidwood Station Technical Specification (TS) 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 Braidwood Station Unit 1 Cycle 10 refueling outage (AIR10). In addition, 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 inspections were conducted from April 17, 2003 through April 24, 2003 by Westinghouse Electric Co. Ltd. The following inspections were performed during this outage.

100% Full Length Bobbin Coil in SG A

54% Full Length Bobbin Coil in SGs B, C, ID (consisting of 100% of the peripheral tubes with the exception of tubes under the manipulator base plate and 50% of interior tubes)

100% Hot Leg Dents/Dings > 5.0 Volts Plus-Point

Diagnostic Plus-Point Inspections based on Bobbin Coil Results

100% Visual Inspection of Previously Installed Tube Plugs

100% Visual Inspection of Newly Installed Tube Plugs 2.0

SUMMARY

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

EPRI Guidelines) were implemented during this inspection. A degradation assessment was performed prior to the 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 Braidwood Station Unit 1 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 Guidelines (i.e., Qualified Data Analyst (QDA)). All data analyst and acquisition personnel satisfactorily completed site-specific training and testing prior to beginning examinations.

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.

As a result of the eddy current inspection of the SGs, a total of 21 tubes were removed from service by mechanical tube plugging. The 21 tubes were removed from service due to either having wear associated with secondary side foreign objects or were required to be removed from service in order to bound locations where the secondary side foreign object could not be retrieved. One tube in SG IA had tube wear greater than the Technical Specification Plugging Limit of > 40%. Pursuant to Technical Specification 5.5.9.c, "Inspection Results Classification," the LA SG was classified as inspection category C-2 and examination scope was increased from 54% full-length bobbin to 100%

full-length bobbin. The remaining SGs B, C, D were classified as inspection category C-I and the 54% full-length bobbin inspection was performed. There were no scanning limitations during the eddy current examinations. Table 2.1 provides the total tube plugging history and equivalent plugging levels to-date for the Braidwood Station Unit 1 SGs:

Table 2.1 Equivalent Tube Plugging Level SG A SG B SG C SG D Total Tubes Plugged at Factory 1 2 0 0 3 Tubes Plugged in AlRO8 1 0 0 0 1 Tubes Plugged in AlR1O 8 10 3 0 21 Total Tubes Plugged 10 12 3 0 25 Total Tubes Plugged (%) 0.15% 0.18% 0.045% 0% 0.094%

Note: Steam Generator Inspections Were Not Performed During AlRO9.

3.0 CERTIFICATIONS 3.1 Procedures/Examinations/Equipment 3.1.1 The examination and evaluation procedures used during the SG eddy current inspection were approved by personnel qualified to Level m in accordance with the 1984 Edition of SNT-TC-lA, "Personnel Qualification and Certification in Nondestructive Testing." Exelon Generation Company, LLC (i.e., Exelon) Special Process Procedures Manual (SPPM) NDT-E-2, "Multifrequency Eddy Current Data Acquisition of Steam Generator Tubing at Braidwood and Byron Nuclear Stations,"

Revision 4 and Exelon 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 Exelon and Westinghouse Quality Assurance Programs for Inservice Inspection, Braidwood Station Technical Specification 5.5.9, 1989 Edition of ASME Boiler and Pressure Vessel 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 Braidwood Station. Tables A.1 and A.2 of Attachment A lists all personnel who performed, supervised or evaluated the data during this SG Inservice inspection.

3.1.4 RID Tech Incorporated TC6700 Remote Data Acquisition Units (RDAUs) with Westinghouse ANSER computer software was used to acquire the eddy current data.

Analysis was performed with Westinghouse ANSER 8.3 Rev 94 computer software.

Secondary analysis was performed with CoreStar Eddyvision 32 Release 5.0 computer software.

3.1.5 The bobbin coil examinations of the SGs were performed with Westinghouse 0.560 inch diameter probes. For low row U-Bend tubing, a 0.540 inch diameter probe was utilized to achieve the complete full tube examination in tubes where there was difficulty using the 0.560 inch diameter probe.

3.1.6 The rotating coil examinations were performed with Zetec 0.560-inch diameter three coil plus-point probes. The coils within this probe were a 0.115-inch diameter pancake coil, a shielded 0.080-inch diameter pancake coil and a standard plus-point coil.

3.2 Personnel 3.2.1 The personnel who performed the SG eddy current inspections were qualified to Level I and Level II certification in accordance with the 1984 Edition of SNT-TC-IA.

The Level I personnel performed the inspections under the direct supervision of Level II or Level III personnel. A list of the certified eddy current personnel who performed data acquisition for the examination is contained in Table A. 1 of Attachment A.

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. A list of the certified eddy current personnel who performed data analysis for the examination is contained in Table A.2 of Attachment A.

3.2.3 All 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 and sub-contractors. An independent company, CoreStar International, performed the secondary analysis.

Primary and Secondary analysis was performed by an automated data screening analysis system as described in Section 6.3 of the EPRI PWR Steam Generator Examination Guidelines, Revision 5. The analysis systems were operated in the manual interactive mode. Each system was required to successfully pass the site specific performance demonstration practical examination prior to analyzing field data.

3.2.6 An independent SG eddy current Level III QDA was employed to serve as a process control reviewer, in accordance with EPRI Guidelines, Section 6.3.3.4, to randomly sample the data to ensure the resolution process was properly performed and that the field calls were properly reported. The Independent Level III 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.

EXAMINATION TECHNIQUES AND EXAMINATION SCOPE All SG eddy current examination techniques used were 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 Braidwood Station Unit 1 SGs.

4.1 Examination Techniques 4.1.1 The bobbin coil examinations performed during this inspection were performed with a 0.560-inch diameter probe as described in Section 3.1.5 of this report. For low row U-Bend regions where there was difficulty using the 0.560 inch diameter probe, a 0.540 inch diameter probe was utilized to achieve the full tube inspection. Nominal probe inspection speed was 40 inches per second for tubes in row 10 and higher and 24 inches per second low row tubes. Sufficient sampling rates were used to maintain a minimum digitizing rate of 30 samples per inch. The bobbin probes were operated in both the differential and absolute modes at frequencies of 650 kHz, 320kHz, 160 kHz, and 35 kHz. The following suppression mixes were used to enhance the inspection: 650/160 kHz differential mix, 320/160 kHz absolute mix, and a 650/320 kHz differential mix.

4.1.2 Diagnostic examinations were performed on non-quantifiable indications and hot leg dents/dings greater than 5.0 volts that may be detected by the bobbin coil examination. The diagnostic examinations were to utilize a plus-point probe as described in Section 3.1.6. Axial probe inspection speed was 0.5 inches per second for straight tubing and 0.15 inches per second for U-bend region of the tubing and dents/dings. Sample rates and rotation speeds were used to maintain a minimum digitizing rate of 30 samples per inch (i.e., 25 samples per inch for the axial direction and 30 samples per inch for the circumferential direction). The rotating probes were operated in the absolute test mode at frequencies of 300 kHz, 200kHz, 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 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.

4.1.4 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 site conditions.

Table 4.1 E PRI Appendix H Techniques EPRI Technique Probe Description ETSS 96004.3 Bobbin Fan Bar/Lattice Grid/Foreign Object Wear and Free Span Flaws 96910.1 Plus-Point Foreign Object Wear/Free Span Flaws (Wear Like 9691.1Pus-PintFlaws) 96703.1 Plus-Point kDents/Dings - Primary Water Stress Corrosion 9670.1Pus-PintCracking (PWSCC) 21998.1 Plus-Point Foreign Object Wear Sizing (Pit Like Flaws) 21409.1 Plus-Point Outer Diameter Stress Corrosion Cracking (Axial 2140.1 Plus-Point ODSCC) 21410.PlusPointOuter Diameter Stress Corrosion Cracking (Circ 2140.1Plu-PontODSCC) 20511.1 Plus-Point Inside Diameter Stress Corrosion Cracking (Axial 2051.1Plu-PontPWSCC) 20510.1 Plus-Point Inside Diameter Stress Corrosion Cracking (Cric 010.1 Plusint rPWSCC) 96010.1 Bobbin Manufacturing Burnish Marks

4.2 Steam Generator Inspection Scope 4.2.1 The original inspection scope called for approximately 54% full-length bobbin inspection of the tubing in all 4 SGs. The 54% was comprised of 100% of the peripheral tubes with the exception of tubes under the manipulator base plate and 50% of the interior tubes. In SG 1A the inspection scope was increased from 54% to 100% based upon the steam generator being classified as inspection category C-2 in accordance with Technical Specification 5.5.9.c, "Inspection Results Classification."

4.2.2 Diagnostic examinations were performed on all non-quantifiable indications, locations of foreign object wear, and hot leg dents/dings greater than 5.0 volts that were detected by the bobbin coil examination. Diagnostic examinations were also conducted in the vicinity of potential foreign objects to determine the extent of tubes potentially affected by the objects. These special examinations were performed with the three coil plus-point probe described in Section 4.1.2 above. See Section 5.1 for further detail. No hot leg dents or dings greater than 5.0 volts by the bobbin coil technique were detected.

4.2.3 See Attachment B for tubesheet maps detailing the inspection scope for each SG.

4.3 Recording of Examination Data Results of the SG eddy current data analysis were recorded on optical disks. The data was then loaded into a Westinghouse Eddy Current Data Management System, "ST2000" version 1.11.03. The system was used to track the completion of the examinations and was used to generate the final SG eddy current report summaries.

4.4 Witness and Verification of Examination SG eddy current inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors, Mr. L. Malabanan of the Hartford Steam Boiler Inspection and Insurance Company of Hartford Connecticut, Chicago Branch, 2443 Warrenville Road, Suite 500, Lisle, Illinois 60532-9871.

5.0 EXAMINATION RESULTS 5.1 Eddy Current Inspection Full-length bobbin coil examination was performed on 100% of the tubes in SG 1A and 54%

in SGs B, C, ID.

5.1.1 Fan Bar Wear - A total of 7 tubes showed indications of Fan Bar wear. The largest indication of Fan Bar wear was 10% through wall. The EPRI Appendix H bobbin coil technique 96004.3 was utilized in this inspection for depth sizing of all Fan Bar wear. Refer to Attachment B for detailed locations and sizing for all Fan Bar wear.

5.1.2 Lattice Grid Wear -A total of 5 tubes showed indications of Lattice Grid wear. The largest indication of Lattice Grid wear was 12% through wall. The EPRI Appendix H bobbin coil technique 96004.3 was utilized in this inspection for depth sizing of all Lattice Grid wear. Refer to Attachment B for detailed locations and sizing for all Lattice Grid wear.

5.1.3 Foreign Object Wear - A total of 15 tubes were plugged due to wear associated with 3 foreign objects. An additional 6 tubes which did not have any signs of tube wear were also plugged in order to bound foreign objects that were not able to be successfully removed from the SG. Of the 15 tubes with foreign object wear the largest was 48% through wall. The EPRI Appendix H plus-point technique 21988.1 was utilized in this inspection for depth sizing of all foreign object wear. All tubes with foreign object wear were removed from service by mechanical tube plugging regardless of percent through wall. Table 5.1.3 below provides a summary of the foreign object wear found during this SG inspection. Refer to Attachment B for additional details.

Table 5.1.3 Foreign Object Wear Summary ObjectSG Row Col +PT Call %TW P Stabilize 1 A 45 134 SVI 15 Y N 1 A 42 135 SVI 25 Y N 1 A 44 135 SVI 48 Y Y 1 A 46 135 SVI 12 Y Y 1 A 45 136 SVI 20 Y Y 1 A 44 137 SVI 5 Y Y 1 A 46 137 SVI 14 Y Y 2 B 90 29 SVI 7 Y Y 2 B 92 29 SVI 17 Y Y 2 B 93 30 SVI 7 Y Y 3 B 52 11 SVI 11 Y N 3 B 54 11 SVI 13 Y N 3 B 51 12 SVI 7 Y N 3 B 53 12 SVI 12 Y N 3 B 52 13 SVI 4 N 5.1.4 Visual Inspection of Installed Tube Plugs - All previously installed tube plugs were visually inspected for signs of degradation and leakage. In addition, all plugs installed during this outage (AlR1O) were also visually inspected and the installation parameters were reviewed for acceptable installation. No anomalies were found.

5.1.5 Attachment B contains tube lists with axial elevations of all imperfections that contain measurable through wall depth that were found during the AIRlO eddy current inspection.

6.0 REPAIR

SUMMARY

Repairs were conducted in accordance with ASME Section XI, 1989 Edition. All repairs were performed using Inconel-690 mechanical tube plugs. All repairs were performed in accordance with Westinghouse approved procedures. Tubes in locations where secondary side foreign objects could not be retrieved were stabilized prior to tube plugging. Table 6.0 summarizes the repairs performed during AlR10. No tube sleeving was performed.

Table 6.0 Summary of Al 0 Tube Plugging REPAIRS SG 1A SG B SG C SGlD TOTAL PERFORMED Tubes Plugged 8 10 3 0 21 Tubes 6 5 3 0 14 Stabilized 7.0 DOCUMENTATION All original optical disks have been provided to Exelon and are maintained at Braidwood Station. The final data sheets and pertinent tube sheet plots are contained in the Westinghouse Outage Report for Braidwood Unit 1, Tenth Refueling Outage, and are also maintained at Braidwood Station.

NOTE: The ASME Section XI NIS-1 Form. "Owner's Report for Inservice Inspections," for steam generator inspections performed during the Braidwood Unit 1 Tenth Refueling Outage is contained in the "Braidwood Station, Unit 1 Inservice Inspection Summary Report," letter number BW030057.

8.0 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 Babcock & Wilcox Replacement Steam Generator Braidwood Unit 1 Configuration Figure A.2 Babcock & Wilcox Replacement Steam Generator Braidwood Unit 1 Tubesheet Configuration

Attachment B Contents Attachment B. 1 As-tested Bobbin Inspection Maps Attachment B.2 As-tested Plus Point Special Interest Inspection Maps Attachment B.3 Tubes Damaged by Secondary Side Foreign Objects Attachment B.4 Tubes Containing Fan Bar Wear Attachment B.5 Tubes Containing Lattice Grid Wear Attachment B.6 Tubes Repaired During Al R10

Attachment A Personnel Certifications

TABLE A.1 A1R1O Data Acquisition Personnel Certifications No. Name Company Level QDA (YN 1 Atcheson, T. SpecfTMP I-T N 2 Schaffner, K SpecfTMP I N 3 Bolt, W. Westinghouse II N 4 Bradley, G. Westinghouse II N 5 Deguevy, J. Westinghouse I N 6 Evering, D. Westinghouse II N 7 Fore, S. Westinghouse II N 8 Gallik, M. Westinghouse I N 9 Gault, W. Westinghouse II N 10 Greenawalt, L. Westinghouse I N 11 Groh, T. Westinghouse I N 12 Hopper, J. Westinghouse II N 13 Jury, L. Westinghouse I N 14 Koeser, S. Westinghouse II N 15 Miller, G. Westinghouse H N 16 Organai, S. Westinghouse I N 17 Parris, J. Westinghouse II-A Y 18 Parris, T. Westinghouse II N 19 Patton, B. Westinghouse II N 20 Pope, W. Westinghouse I N 21 Shipley, E. Westinghouse II N 22 Stitt, A. Westinghouse H N 23 Vernon, D. Westinghouse II N 24 Walsh, M. Westinghouse II N

TABLE A.2 AlR1O Data Analysis Personnel Certifications No. Name Company Level QDA (YN) 1 Brack, M. Anatec III Y 2 Miller, M. Anatec III Y 3 Stanger, D. Anatec III Y 4 Bowser, C. Corestar III Y 5 Causby, G. Corestar III Y 6 Croyle, R. Corestar III Y 7 Humphery. R. Corestar III Y 8 Kirk, M. Corestar III Y 9 Martin, A. Corestar IIA Y 10 McChesney, D. Corestar III Y 11 Miller, H. Corestar III Y 12 Overly, E. Corestar IIA Y 13 Seutter, A. Corestar IIA Y 14 Smith, J. Corestar IIA Y 15 Stach, G. Corestar IIA Y 16 Stump, T. Corestar III Y 17 Thuilen, T. Corestar III Y 18 Turner, D. Corestar IIA Y 19 Zevchak, J. Corestar IIA Y 20 Anderson, D. NDE Tech IIA Y 21

Brown, M. NDE Tech III Y 22 Ethridge, G. NDE Tech III Y 23 Havnes, W. NDE Tech III Y 24 Lewis, C. NDE Tech IIA Y 25 Lewis, D. NDE Tech III Y 26 Lohner, E. NDE Tech III Y 27 Looper, R. NDE Tech III Y 28 Mast, M. NDE Tech III Y 29 Nelson, D. NDE Tech III Y 30 Sheldon, J. NDE Tech III Y 31 Siegel, R. NDE Tech III Y 32 Thompson, K NDE Tech IIA Y 33 Wheeler, C. NDE Tech III Y 34 Drumm, R Vern & James III Y 35 Hutchinson, J. Vern & James IIA Y 36 McLeod, E. Vern & James IIA Y 37 Moore, R. Vern & James IIA Y 38 Owens, S. Vern & James IIA Y 39 Schmitz, K Vern & James III Y 40 Wilkerson, B. Vern & James IIA Y 41 Gootz, T. Westinghouse III Y

Independent Qualified Data Analyst

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SG - D HOT LEG LOW ROW BOBBIN INSPECTION PROGRAM AS TESTED Braidwood AIRIO CCE 7720 9 458 TESTED 09H THROUGH TEH WITH n 9 TESTED 9H THROUGH TEH WITH

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Attachment B.2 As-tested Plus Point Special Interest Inspection Maps

0 SG - A COLD LEG SPECIAL INTEREST +POINT INSPECTION PROGRAM Braidwood Al RIO CCE 7720 X 38 TUBE TESTED IN THE COLD LEG WITH POINT PROBE FOR SPECIAL INTEREST a 2 PLUGGED TUBE 5 16 15 26 25 36 35 46 45 6 55 66 65 76 75 80 85 " 95 1N 105 116 115 120 125 136 135 146 I 1 1 1 1 1 1 1 1 j1 -.0 o o co oo + oooool[- j I I I I I I I I I I 115 115 00.. . . .0

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A SG - A HOT LEG SPECIAL INTEREST +POINT INSPECTION PROGRAM Braidwood Al RIO CCE 7720 X 3 TUBE TESTED IN HOT LEG WITH

+POINT PROBE FOR SPECIAL INTEREST a 2 PLUGGED TUBE 140 135 130 125 120 : 15 110 15 iLe 95 91 85 80 75 76 65 60 55 50 45 46 35 30 25 2S 15 1 5 115 I I I l I °< ° ° .° .°O "oo 2 lI I I I I I I I I 116

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*0 SG - A HOT LEG U-BEND +POINT SPECIAL INTEREST INSPECTION PROGRAM Braidwood AlRIO CCE 7720 X 1 TUBE TESTED IN THE U-BEND FROM THE HOT LEG WITH +POINT PROBE a 2 PLUGGED TUBE 148 135 138 125 120 115 118 185 10 95 90 85 89 75 70 65 60 55 50 45 48 35 38 25 20 15 10 5 115 I I I I I I I I I I1 - 1 I I I I I I I I I I 115 00.0~~~~~~~~~~0 0000.~~~~~~~~~~~0 ie 11 105 00

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0 SG - B HOT LEG SPECIAL INTEREST +POINT INSPECTION PROGRAM Braidwood Al RIO CCE 7720 X 75 TUBE TESTED IN THE HOT LEG WITH +POINT PROBE FOR SPECIAL INTEREST a 2 PLUGGED TUBE 146 135 136 125 126 115 116 165 1" 95 96 85 86 75 76 65 66 56 5 46 4 35 36 25 26 15 1 5 10o0o.T°. I5 .0.-. O 0.00-0

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SG - B HOT LEG U-BEND +POINT SPECIAL INTEREST INSPECTION PROGRAM Braidwood AlRIO CCE 7720 X 3 TUBE TESTED IN THE U-BEND FROM THE HOT LEG WITH POINT PROBE a 2 PLUGGED TUBE 146 135 136 125 120 115 116 165 166 95 96 a5 as 75 76 65 66 55 56 45 46 35 36 25 26 1s le 5 lb 0010 IDo 0oo O.0 115 o00 , * . * * *I. . *

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C 0 SG - C COLD LEG SPECIAL INTEREST POINT INSPECTION PROGRAM Braidwood AlR10 CCE 7720 X I TUBE TESTED IN THE COLD LEG WITH +POINT PROBE FOR SPECIAL INTEREST 5 16 15 26 25 36 35 46 45 56 55 60 65 76 75 86 85 9 95 1i 105 118 115 120 125 136 135 148 115 i l l l l l l l 1 i oJo~t.°°.°*t-.°-.°T.°-.°-t'.°-.°T°°.°°'O 00o I I I I I I I I I I 115 00.* * ~~~~~~~~000 11 o00 ~. 0 0 11 0 . . . . . . .

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SG - D HOT LEG U-BEND +POINT SPECIAL INTEREST INSPECTION PROGRAM Braidwood AlRIO CCE 7720 X I TUBE TESTED IN THE U-BEND FROM THE COLD LEG WITH +POINT PROBE 140 135 130 125 120 115 : 10 105 100 95 99 85 8e 75 70 65 60 55 5 45 4 35 30 25 20 15 1s 5 115 I I I I I I o oo D o ° 0. ..- l- I I I I I I I I I I 115 lie . 0.0 .0~~~~0.

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Attachment B.3 Tubes Damaged by Secondary Side Foreign Objects

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SG - A Tubes Damaged By Foreign Objects Bra Idwood I AIRIG CCE 20030401 64/25/2003 11:14:49

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I ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 I CRLEN CEG BEGT ENDT PDIA PTYPE CAL LI

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SG - D Lattice Grid Wear Indications Braidwood 1 AR10 CCE 20030401 04/25/2003 18:07:33

+ + -- ++ - +

++ - 4 - + -- + - - - + +----4---------4 I ROW COL VOLTS DEG IND PER CNN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL Li

+- +- + -_ - + -+ ++ -+ + + + + . + _ +- _ ---+ ,

++----4-----

ai 70 41 .26 0 PCT 6 P2 02H -1.57 TEC TEH .560 RBART 33 HI 70 41 .25 78 VOL 2 02H -1.64 02H 02H .560 ZPSNM 53 HI I ROW COL VOLTS DEG IND PER CNN LOCN INCHI INCH2 BEGT ENDT PDIA PTYPE CAL LI

+- - - -+ +----+----+

- - + + + + + + + + + +++--------- - --

Tubes: 1 Records: 2 1

Attachment B.6 Tubes Repaired During AlRlO

SG - A TUBES REPAIRED DURING Al RIO Braidwood Al R10 CCE 7720 X 8 TUBE STABILIZED AND PLUGGED IN THE COLD LEG: PLUGGED IN THE HOT LEG 14 135 130 125 120 116 110 106 100 96 " 86 80 76 70 65 6 55 68 45 40 35 39 25 2 15 10 5 (00 000 A Ao 10?0.o?0 ***T??-f LA 0

I I I I I I I I I I I 115 ----- -e-~~~---.-.--.---

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.9 .. .. .9 9 99 . . . 9 . . 9 9 9 9 . 9 9 .. . . . . .

15 15 1l 5 5 4- _4 3...,-. - 25 , 15 , 00.5 1400S .51 135 130 15I 125 12 115 .

110 165 I*

100_ 96 9 90 85 8..57 80G. 75 -

70 65 ._ *. 60 55 .. 50 45 40 35 30 20 15 16 Wdqouw EbceiCpoay LWC-NMU a72,O O4V25= X54:21

SG - A Tubes Repaired During AlR10 Braidwood 1 ARlO CCE 20030401 04/25/2003 10:42:26

+ + ++ ++- + +-++ + - + +-

+ +-

+ ++-------

I ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL LI

+ ,+ +--+ + + + ++++++ - + - + - ++----------

45 134 NDD TEC TEH .560 RBART 3 HI 45 134 .14 107 SVI P1 TSC .10 TSC TSC .560 ZPSNM 8 Cl 45 134 .15 0 PCT 15 2 TSC .28 TSC TSC .560 ZPSNM 8 CI 45 134 .13 106 PID P1 TSC .19 TSC TSC .560 ZPSNM 66 Cl 42 135 .28 0 PCT 25 2 TSC .48 TSC TSC .560 ZPSNM 8 Cl 42 135 .27 98 SVI P1 TSC .49 TSC TSC .560 ZPSNM 8 Cl 42 135 .26 120 DTI P1 TSC .56 TEC TEH .560 RBART 65 HI 42 135 .24 100 PID P1 TSC .60 TSC TSC .560 ZPSNM 66 Cl I

44 135 1.61 113 DTI P1 TSC .31 TEC TEH .560 RBART 3 HI 44 135 .76 82 SVI P1 TSC .26 TSC TSC .560 ZPSNM 8 Cl 44 135 .75 0 PID 2 TSC .31 TSC TSC .560 ZPSNM 8 Cl 44 135 .70 0 PCT 48 2 TSC .37 TSC TSC .560 ZPSNM 8 Cl 46 135 NOD TEC TEH .560 RBART 3 HI 46 135 .11 97 SVI 2 TSC .23 TSC TSC .560 ZPSNM 8 Cl 46 135 .11 0 PCT 12 2 TSC .23 TSC TSC .560 ZPSNM 8 Cl 46 135 .11 95 PID P1 TSC .23 TSC TSC .560 ZPSNM 66 Cl 45 136 NDD TEC TEH .560 RBART 3 HI 45 136 .21 0 PCT 20 2 TSC .09 TSC TSC .560 ZPSNM 8 Cl 45 136 .21 115 SVI 2 TSC .15 TSC TSC .560 ZPSNM 8 Cl 45 136 .18 115 PID P1 TSC .10 TSC TSC .560 ZPSNM 66 CJ 47 136 TBP TEC TEH .560 R8ART 3 HI 47 136 NDD TSC TSC .560 ZPSNM 8 Cl 44 137 NDD TEC TEH .560 RBART 3 H 44 137 .04 105 SVI 2 TSC .14 TSC TSC .560 ZPSNM C 44 137 .04 0 PCT 5 2 TSC .15 TSC TSC .560 ZPSNM 8 C 44 137 .04 101 PID P1 TSC .13 TSC TSC .560 ZPSNM 66 C 46 137 NDD TEC TSH .560 RBART 3 HI 46 137 .14 0 PCT 14 2 TSC .28 TSC TSC .560 ZPSNM a Cl 46 137 .12 99 SVI 2 TSC .31 TSC TSC .560 ZPSNM 8 Cl 46 137 NDD TEC TEH .560 RBART 65 HI 46 137 .12 106 PID 2 TSC .30 TSC TSC .560 ZPSNM 66 Cl

+ +---- +---- +---- +- +

- +

- -+

I ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL LI

-- -+ - - - - +----+-----------+-

- - - - - -- - - - - - +- - - - - +------- ---- + - - - - - -

Tubes: 8 Records: 31 1

S SG - B TUBES REPAIRED DURING AlRI0 Braidwood Al R10 CCE 7720 n 5 TUBE STABILIZED AND PLUGGED IN THE HOT LEG: PLUGGED IN THE COLD LEG X 5 TUBE PLUGGED IN BOTH LEGS a 2 EXISTING PLUGGED TUBE 146 135 136 125 126 115 11 115 1ee 95 96 85 86 75 76 65 6 55 66 45 46 35 36 25 26 15 1a 5 115 - - - -- - - --- e-e~~~~-

n A 0

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5, 0 0 00 0 00 000O 0, 0000 S 0 00 00 0 00 0 0000 0 0000 5 146 135 136 125 126 115 116 165 10 95 9 5 86 75 76 65 66 55 56 45 46 35 36 25 26 15 1s Wmeo.h.. Ebt cwsUmWu.NC- N8t) Sr2 04M252S MA1:M

SG - Tubes Repaired During AR10 Braidwood 1 AR10 CCE 20630401 64/251203 14:67:54

+_ _ _ _ +_ _ . _ _ - ---- -.- - - + 4..-.--.-----

- + + 4+ 4-.---+----+ -- -+- - . - +-

4 +

- - + . + . t-I ROW CoL VOLTS DEG IND PER CHN LOCN INCH1 INCH I CRLEN CEG BEGT ENDT PDIA PTYPE CAL Li

+- +---------+----+-------------------+----------------------------+----+-------+------ +------------+---------

52 11 .15 137 DFI 1 TSH .94 TEC TEH .560 RBART 5 Hi 1 52 11 .09 88 SVI P1 TSH .94 TSH TSH .560 ZPSNM 55 HI 52 11 .08 86 PID 2 TSH .94 TSH TSH .560 ZPSNM 59 HI 52 11 .69 e PCT 11 P1 TSH 1.39 o .344 71 TSH TSH .560 ZPSNM 59 HI 54 11 NOD TEC TEH .560 RBART 5 H 54 11 .13 77 SVI 2 TSH .87 TSH TSH .560 ZPSNM 61 H 54 11 .12 80 PID 2 TSH .81 TSH TSH .566 ZPSNM 63 H 54 11 .13 0 PCT 13 2 TSH .92 o .310 63 TSH TSH .560 ZPSNM 63 H 51 12 .05 87 SVI 2 TSH .95 TSH TSH .560 ZPSNM 61 HI 51 12 .10 71 PID 2 TSH 1.03 TSH TSH .566 ZPSNM 63 HI 51 12 .06 0 PCT 7 2 TSH 1.17 o .311 40 TSH TSH .566 ZPSNM 63 Hi 53 12 .11 81 SVI 2 TSH 1.56 TSH TSH .560 ZPSNM 61 Hi 53 12 .12 6 PCT 12 2 TSH 1.56 o .349 63 TSH TSH .560 ZPSNM 63 HI 53 12 .10 71 PID 2 TSH 1.54 TSH TSH .560 ZPSNM 63 HI 52 13 NDD TEC TEH .560 RBART 5 Hi 52 13 .04 67 SVI 2 TSH .34 TSH TSH .56 ZPSNM 61 HI 52 13 .03 40 PID 2 TSH .25 TSH TSH .560 ZPSNM 63 Hi 52 13 .03 6 PCT 4 2 TSH .38 o .156 31 TSH TSH .560 ZPSNM 63 HI I

91 28 NOD TEC TEH .560 RBART 7 Hi 91 28 NDD TSH TSH .560 ZPSNM 65 Hi 91 28 TBP TSH TSH .560 ZPSNM 65 HI I

96 29 NOD TEC TEH .566 RBART 1 HI 96 29 .05 106 SVI P1 TSH .23 TSH TSH .560 ZPSNM 65 Hi 96 29 .14 94 PLP 1 TSH .26 TSH TSH .560 ZPSNM 65 HI 96 29 .06 6 PCT 7 P1 TSH .26 o .288 85 TSH TSH .560 ZPSNM 65 HI 96 29 .04 120 PID P1 TSH .23 TSH TSH .560 ZPSNM 67 HI 92 29 NDD TEC TEH .560 RBART 1 Hi 92 29 .05 91 SVI P1 TSH .66 TSH TSH .560 ZPSNM 65 Hi 92 29 .16 93 PLP 1 TSH .64 TSH TSH .560 ZPSNM 65 HI 92 29 .17 6 PCT 17 P1 TSH .75 0 .674 140 TSH TSH .560 ZPSNM 65 Hi 92 29 .10 94 PID P1 TSH .60 TSH TSH .560 ZPSNM 67 Hi I

91 36 TBP TSH TSH .560 ZPSNM 65 HI 91 30 NDD TSH TSH .566 ZPSNM 65 HI I

93 30 NDD TEC TEH .560 RBART 11 Hi 93 30 .06 6 PCT 7 P1 TSH .49 0 .249 85 TSH TSH .560 ZPSNM 65 HI 93 30 .06 87 SVI P1 TSH .55 TSH TSH .560 ZPSNM 65 HI 93 30 .14 87 PLP 1 TSH .55 TSH TSH .560 ZPSNM 65 HI 93 30 .69 98 PID P1 TSH .55 TSH TSH .566 ZPSNM 67 Hi

+- +- + + -+-+-+-+ + +-+-+-+ .-.-. +++---- 4--4 - . - -4. + +----4..-.-- I ROW COL VOLTS DEG IND PER CNN LOCN INCH1 INCH2 I CRLEN CEG BEGT ENDT PDIA PTYPE CAL LI

+------- -- - - ++-++-+-+-+-+-+-+-+-.--+-+---+-+----------- - -

Tubes: 10 Records: 38 1

0 SG - C TUBES REPAIRED DURING AlRIO Braidwood Al R10 CCE 7720 X 3 TUBE STABILIZED AND PLUGGED IN THE HOT LEG; PLUGGED IN THE COLD LEG 140 136 130 125 120 115 110 105 160 95 9o 85 80 76 70 65 60 66 50 45 41 36 30 25 20 15 10 6 116 1,.,° 0 000°T°°°<f°°T°°°f°o° 0 -I 115 110 110 ~~~a-

- - - -- - - 0-105 105 1" 0 I**

.. .0 I ~~~~~~I I . I . I I I 00I II' 160 004I .... .. I ...

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I I II I I I . 00 . I I I III 0I. I I 96 - - - - -~~~~I- - -- - - ----- -I - I - - - - - -- - 95 0 .I .I II.I II.I 0 90 O, . . .,. I 90 I. I I I II .I II . I . . . . .. I I~.

B6 85 as 80 0;.

I I I . I I I I .~ I ~I I I I II.

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WM*VhIcgu Eacft CompmNLLC-NSOU 5TWO 0442M3 21:01:18

SG -C TUBES REPAIRED DURING AlRIO COLD LEG PERSPECTIVE Braidwood AlR10 CCE 7720 X 3 TUBE STABILIZED AND PLUGGED IN THE HOT LEG AND PLUGGED IN THE COLD LEG DURING AR10 5 1 15 20 25 30 35 40 45 so 5 60 65 70 75 80 85 se 95 1oe 105 1le 115 120 125 130 13S 140 InOn 00fio00 oTo.o f.o5TOooj.

115 .*.. .. 0 115 n~~~~~~ 0

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00 5 1e 15 20 25 30 35 40 45 6e 56 66 65 76 75 80 85 90 95 1N 1t 110 115 120 125 130 135 140 Weedrilghaum A cI Cm~puiti LLC NS ST2000O 04M20 13:57

SG - Tubes Repaired During AIR10 Braidwood 1 AlRlO CCE 20030401 04125/2003 16:57:12

+- -- --- -- --- -- -- --- -- --- -- --- -- --- +

-- --- -- 4.

-- _---_---+-______+

___ +__---_ - - _-

I ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL LI

+ + +-- --------. + + + ++ + + - + ++----4--+--

3 48 NOD 09H TEC .540 RBART 12 CI 3 48 NOD 09H TEH .560 RBART 37 HI 3 48 .12 238 PLP 7 TSH .21 TSH TSH .560 ZPSNM 57 HI 1 3 48 TBP TSH TSH .560 ZPSNM 59 HI 1 3 48 .11 111 PID 2 TSH .21 TSH TSH .560 ZPSNM 59 HI I I~~~~~~~~

I 2 49 NDD 09H TEC .540 RBART 10 CI I 2 49 NDD 09H TEH .560 RBART 41 HI 1 2 49 .04 224 PLP 7 TSH .07 TSH TSH .560 ZPSNM 57 HI I 2 49 TBP TSH TSH .560 ZPSNM 59 HI I 2 49 .03 106 PID 2 TSH .18 TSH TSH .560 ZPSNM 59 HI l~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

I 4 49 .11 235 PLP 7 TSH .07 TSH TSH .560 ZPSNM 57 HI I 4 49 TBP TSH TSH .560 ZPSNM 59 HI I 4 49 .09 122 PID 2 TSH .28 TSH TSH .560 ZPSNM 59 HI

+ --

+ + + + +-+ - 4 - 4 +-+-. +-. +-+-- . + +-----

I ROW COL VOLTS DEG IND PER CHN LOCN INCHI INCH2 BEGT ENDT PDIA PTYPE CAL LI

+ +- + ++-++--------+ - 4 - + - 4 --- +----+++------4 -

Tubes: 3 Records: 13 1

ML032190155

Text

Subject:

Attachment:

1.0 INTRODUCTION

SUMMARY

SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

0

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