BW050007, Eleventh Refueling Outage Steam Generator Inservice Inspection Summary Report

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Eleventh Refueling Outage Steam Generator Inservice Inspection Summary Report
ML050280208
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 01/20/2005
From: Polson K
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW050007
Download: ML050280208 (67)
v • d • e


Text

Exekln..

Exelon Generation Company, LLC Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel. 815-417-2000 www.exelonCoTp.C0Tn Nuclear January 20, 2005 BW050007 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 Eleventh 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 eleventh refueling outage (Al Ri 1).

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 Xl, "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."

Please direct any questions you may have regarding this submittal to Mr. Dale Ambler, Regulatory Assurance Manager, at (815) 417-2800.

Sincerely, ePo

/

Keith J. Polson Site Vice President Braidwood Station

Attachment:

Exelon Braidwood Station, Unit 1 Eleventh Refueling Outage Steam Generator Inservice Inspection Summary Report cc:

Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Braidwood Station

 C)H

Exelon Nuclear BRAIDWOOD STATION UNIT 1 351 00 South Rte. 53, Suite 84 Braceville, IL 60407 COMMERCIAL OPERATION: July 29,1988 STEAM GENERATOR EDDY CURRENT INSPECTION REPORT ELEVENTH REFUELING OUTAGE (Al RI1)

October 2004 Exelon Generation Co., LLC 300 Exelon Way Kennett Square PA 19348

TABLE OF CONTENTS

1.0 INTRODUCTION

2.0

SUMMARY

3.0 CERTIFICATIONS 3.1 Procedures/Examinations/Equipment 3.2 Personnel 4.0 EXAMINATION TECHNIQUES AND EXAMINATION SCOPE 4.1 Examination Techniques 4.2 Steam Generator Inspection Scope 4.3 Recording of Examination Data 4.4 Witness and Verification of Examination 5.0 EXAMINATION RESULTS 5.1 Eddy Current Inspection 5.2 Other Inspection Results 6.0 REPAIR

SUMMARY

7.0 DOCUMENTATION 8.0 FIGURES/TABLES/ATTACHMENTS

1.0 INTRODUCTION

Braidwood Station, 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 PI 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 Fall 1998.

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 Xl 1989 Edition, IWB 2500-1, Examination Category B-Q, Item Bi 6.20, SG eddy current examinations were performed during the Braidwood Station Unit 1 eleventh refueling outage (Al RI 1). The inspections were performed consistent with the Electric Power Research Institute (EPRI) "PWR Steam Generator Examination Guidelines," Revision 6, and Nuclear Energy Institute NEI 97-06, "Steam Generator Program Guidelines," Revision 1. The inspections were conducted from October 8, 2004 through October 18, 2004 by the Westinghouse Electric Company (Westinghouse). The following inspections were performed during this outage.

100% Full Length Bobbin Coil in SG 1B Approximately 22% Bobbin Coil of the hot leg tubing straight sections in SGs IA, 1C, and iD Approximately 15.5% Bobbin Coil of the cold leg tubing straight sections in SGs 1 A, iC, and 1D 25% +PointTM probe inspection of hot leg dents and dings > 5.0 volts in bobbin coil signal strength Diagnostic +PointTM 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 6 of the EPRI PWR Steam Generator Examination Guidelines (i.e., EPRI Guidelines) along with Interim Guidance as provided by EPRI, were implemented during this inspection. A degradation assessment was performed prior to the inspection to ensure the proper EPRI Guidelines 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 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.

The modes of tube degradation found during Al R 1I were fan bar wear, lattice grid wear and foreign object wear.

As a result of the eddy current inspection of the SGs, a total of 5 tubes were removed from service by mechanical tube plugging. The 5 tubes were removed from service due to having wear associated with secondary side foreign objects located at the lattice grid support structures. One tube in SG 1 B had tube wear greater than the TS plugging limit of > 40%. Pursuant to TS 5.5.9.c, "Inspection Results Classification," the I B SG was classified as inspection category C-2. Scope expansion into the remaining three SGs was not required per TS requirements, but was recommended per the EPRI Guidelines.

A scope expansion plan consisting of approximately 22% of the hot leg straight section tubing and 15.5% of the cold leg straight section tubing in each of the remaining three SGs was developed and implemented in accordance with the EPRI Guidelines. The inspection results for the 1A, 1 C and 1 D were classified in accordance with TS 5.5.9.c as inspection category C-1. There were no scanning limitations during the eddy current examinations. Table 2.1, 'Equivalent Tube Plugging Level," 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 i__ Hi v_____

SG A SG B SG C SG D Total Tubes Plugged at Factory 1

2 0

0 3

Tubes Plugged in Al R08 1

0 0

0 1

Tubes Plugged in Ai RI0 8

10 3

0 21 Tubes Plugged in Al RI0 2

2 1

5 Total Tubes Plugged 10 14 5

1 30 Total Tubes Plugged (%)

0.15%

0.21%

0.08%

0.02%

0.11%

Note: Steam Generator Inspections Were Not Performed During Al R09.

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 IlIl in accordance with the 1984 Edition of SNT-TC-IA, "Personnel Qualification and Certification in Nondestructive Testing." Exelon Generation Company, LLC (i.e., Exelon) Procedure ER-AP-335-039, "Multifrequency Eddy Current Data Acquisition of Steam Generator Tubing," Revision 2 and Exelon Procedure ER-AP-335-040, "Evaluation of Eddy Current Data for Steam Generator Tubing," Revision 1, 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 TS 5.5.9; 1989 Edition of ASME Boiler and Pressure Vessel Code Sections Xl, "Rules for Inservice Inspection of Nuclear power Plant Components," and Section V, "Nondestructive Examination;" EPRI PWR SG Examination Guidelirjns, Revision 6; 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 R/D 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 8.4.2 Rev 4 computer software. Secondary analysis was performed with CoreStar Eddyvision 32, Release 5.7.1 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 +PointTM 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 +PointTM coil.

3.2 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-1A. The Level I personnel performed the inspections under the direct supervision of Level II or Level IlIl 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 Xl, 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 +PointTM inspection data analysis. Resolution analysts were also trained and tested specifically for the performance of data resolution. All analysts were required to achieve a > 80% probability of detection at a 90%

confidence level on the practical examination and a > 80% score on the written examination 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 the EPRI Guidelines, Revision 6. The analysis systems were operated in the manual interactive mode. Each system successfully passed the EPRI Automated Analysis Performance Demonstration Database (AAPDD).

Each system also was required to successfully pass the site specific performance demonstration practical examination prior to analyzing field data. Discrepancies between the two parties required Level IlIl concurrence between both parties for final resolution.

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

4.0 EXAMINATION TECHNIQUES AND EXAMINATION SCOPE All SG eddy current examination techniques used were qualified in accordance with Appendix H of the EPRI 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 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 for 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, 320 kHz, 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, 650/320 kHz differential mix and a 650/320/160 kHz differential mix.

4.1.2 Diagnostic examinations were performed on non-quantifiable indications and hot leg dents/dings greater than 5.0 volts detected by the bobbin coil examination. The diagnostic examinations utilized a +PointTM probe as described in Section 3.1.6. Maximum axial probe inspection speed was 0.6 inches per second for straight tubing, 0.35 inches per second for U-bend region of the tubing and 0.15 inches per second at dents and 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 for straight section tubing and dents/ding inspections were operated in the absolute test mode at frequencies of 300 kHz, 200 kHz, 100 kHz and 20 kHz. The rotating probes for U-bend section inspections were operated in the absolute test mode at frequencies of 400 kHz, 300 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 eddy current calibration standards used for the bobbin coil and

+PointTM inspections met the requirements of the EPRI Guidelines, Revision 6, and Sections V and Xl of the ASME Code, 1989 Edition.

4.1.4 The SG eddy current examination techniques used during this inspection were equivalent to the EPRI Guidelines Appendix H techniques listed in Table 4.1. Each ETSS was evaluated and determined to be applicable to site conditions.

I Table 4.1 EPRI Appendix H Techniques EPRI Technique Prbbe.

Description ETSSa 96004.3 Bobbin Fan Bar/Lattice Grid/Foreign Object Wear and Free 9600.3 Bbbin Span Flaws 96910.1

+PointTM Foreign Object Wear/Free Span Flaws (Wear Like 96910__1 Flaws) 21998.1

+PointTm Foreign Object Wear (Volumetric Like Flaws) 96703.1

+PintT Dents/Dings - Primary Water Stress Corrosion 960.1 +Cracking (PWSCC) 21409.1

+PointTM Outer Diameter Stress Corrosion Cracking (Axial 21409.1ODSCC) 21410.1

+PointTM Outer Diameter Stress Corrosion Cracking (Circumferential ODSCC) 205111

+PointTM Inside Diameter Stress Corrosion Cracking (Axial PWSCC) 205101 +PontTM Inside Diameter Stress Corrosion Cracking (Circumferential PWSCC) 96010.1 Bobbin Manufacturing Burnish Marks PWSCC - Primary Water Stress Corrosion Cracking ODSCC - Outside Diameter Stress Corrosion Cracking 4.2 Steam Generator Inspection Scope 4.2.1 The original inspection scope called for 100% full length bobbin inspection of the tubing in the 1 B SG. Two indications of foreign object wear were identified at the 6th lattice grid support structure. One indication was 27% through-wall (TW), and the other 42% TW. The 1 B SG inspection results were classified as inspection category C-2 in accordance with TS 5.5.9.c. Scope expansion into the remaining three SGs was not required per TS requirements, but was recommended per the EPRI Guidelines. A scope expansion plan consisting of approximately 22% of the hot leg straight section tubing and 15.5% of the cold leg straight section tubing in each of the remaining three SGs was developed and implemented in accordance with the EPRI Guidelines.

The inspection results for the 1 A, 1 C and 1 D were classified in accordance with TS 5.5.9.c as inspection category C-1.

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

+PointTm 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, uST2000" version, 1.14.01. 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 1 B and approximately 22% Bobbin Coil of the hot leg tubing straight sections and 15.5% Bobbin Coil of the cold leg tubing straight sections in SGs 1A, iC, and 1D.

In some instances the 1A, 1C and 1D tubing received full length bobbin inspection.

5.1.1 Fan Bar Wear - Of the tubes inspected through the Fan Bar region during Al RI 1, a total of 5 tubes showed indications of Fan Bar wear. The largest indication of Fan Bar wear was 7% 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.4 for detailed locations and sizing for all Fan Bar wear.

5.1.2 Lattice Grid Wear - Of the tubes inspected through the Lattice Grid regions during Al Ri 1, a total of 4 tubes showed indications of Lattice Grid wear. The largest indication of Lattice Grid wear was 10% 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.5 for detailed locations and sizing for all Lattice Grid wear.

5.1.3 Foreign Obiect Wear - A total of 5 tubes showed indications of secondary side foreign object wear at the lattice grid elevations. All tubes with indications of foreign object wear were removed from service by tube plugging regardless of percent through wall. One tube was also stabilized prior to tube plugging since the foreign object wear occurred at an area

I susceptible to higher secondary side cross flow. The largest indication of foreign object wear identified was 42% TW. The EPRI Appendix H

+PointTM technique 21988.1 was utilized in this inspection for depth sizing of all foreign object wear. Table 5.1.3 below provides a summary of the foreign object wear found during this SG inspection. Refer to Attachment B.3 for additional details.

Table 5.1.3 Foreign Object Wear Summary SG Row Col Elevation

+PointTm Call

%TW Plug Stabilize B

48 89 6H SVI*

27 Y

N B

1 116 6C SVI*

42 Y

N C

66 13 1H SVI*

17 Y

Y C

69 50 4H SVI*

9 Y

N D

70 41 2H SVI*

25 Y

N

  • SVI = Single Volumetric Indication 5.1.4 Tube to Tube Proximity - The condition of tube to tube being in close proximity was monitored as part of the 100% full length bobbin coil inspection in the 1 B SG. Scope expansion in the remaining unscheduled SGs (1 A,1 C and 1 D) did not include a sufficient population of tubes to monitor this condition. This condition will be monitored in all four SGs during the next SG inspection scheduled for Spring 2006 (Al R12). The 1 B SG inspection results for tube to tube proximity are provided in Table 5.1.4 below. No tube degradation was identified associated with tube to tube proximity. This condition will continue to be monitored during future scheduled SG inspections.

Table 5.1.4 Tube to Tube Proximity Summary 1 B Steam Generator Tubes Tubes Tubes Tubes No Tubes Tubes Total Identified Identified Identified Longer Identified Newly Tubes In-In-In-In-In-In-Identified Proximity Proximity Proximity Proximity Proximity Proximity In-Identified During During AlRlO AiR10to AIR10to Proximity in AlRl 1 Pre-Al R08 (Spring AlRll AlRl1 AiR11 Service (Spring 2003)

Inspection 1999) 122 26 36 2

34 5

39 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 Al Ri 1 eddy current inspection.

5.2 Other Inspection Results 5.2.1 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 were also visually inspected and the installation parameters were reviewed for acceptable installation.

No anomalies were found.

6.0 REPAIR

SUMMARY

Repairs were conducted in accordance with ASME Section Xl, 1989 Edition. All repairs were performed using Inconel-690 mechanical tube plugs. All repairs were performed in accordance with Westinghouse approved procedures. Table 6.0 summarizes the repairs performed during Al R11. No tube sleeving was performed.

Table 6.0 7.0 DOCUMENTATION All original data is stored on optical disks that 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, Eleventh Refueling Outage, and are also maintained at Braidwood Station.

NOTE: The ASME Section Xl NIS-1 Form. "Owner's Report for Inservice Inspections," for steam generator inspections performed during the Braidwood Unit 1 Eleventh Refueling Outage is contained in a separate transmittal : the "Braidwood Station, Unit 1 Inservice Inspection Summary Report."

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 +PointTM 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 Ri 1

Attachment A Personnel Certifications

TABLE A.1 A1R1i Data Acquisition Personnel Certifications No.

Name Company Level QDA (Y/N) 1 Estel, J.

Westinghouse ii N

2 Evering, D.

Westinghouse iI N

3 Fore, S.

Westinghouse Ii N

4 Gault, W Westinghouse Ii N

5 Glenn, W.

Westinghouse 1I N

6 Greenawalt, L. Westinghouse I

N 7

Hazlet, W.

Westinghouse 1I N

a Kintigh, B.

Westinghouse I

N 9

Mains, P.

Westinghouse If N

10 Mantich, S.

TMP/SPEC I

N 11 Mardell, D.

Westinghouse II N

12 Parris, J.

Westinghouse IA Y

13 Patton, B.

Westinghouse II N

14 Permuka, J.

Westinghouse II N

15 Provencher, C. Westinghouse I

N 16 Smith, A.

Westinghouse II N

17 Tedrick, J.

Westinghouse I

N 18 Vernon, D.

Westinghouse II N

TABLE A.2 A1R11 Data Analysis Personnel Certifications No.

Name Company Level ODA (Y/Nl),

I Bowser, C.

Corestar liI Y

2

  • Brown, M.

NDE Tech II Y

3 Case, J.

NDE Tech III Y

4 Croyle, R.

NDE Tech III Y

5 Gootz, T.

Westinghouse IIl Y

7 Grant, B.

NDE Tech ill Y

8 Haynes, W.

NDE Tech III Y

9 Ives, D.

Corestar III Y

10 Lewis, D.

NDE Tech IlIl Y

11 Lohner, E.

NDE Tech III Y

12 Lopper, R.

NDE Tech IlIl Y

13 Martin, A.

Corestar IIA Y

14 Mast, M.

NDE Tech III Y

15 Miller, H.

Corestar II Y

16 Moates, R.

Westinghouse IA Y

17 Pocratsky, R.

Westinghouse III Y

18 Popovich, R.

Westinghouse III Y

19 Richmond, M.

NDE Tech III Y

20 Siegal, R.

NDE Tech III Y

21 Skirpan, J.

NDE Tech IIA Y

22 Spake, C.

Corestar IlIl Y

23 Stokke, T.

NDE Tech IIl y

24 Visconti, C.

Corestar II Y

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Attachment B.1 As-tested Bobbin Inspection Maps AiRli

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+-

+---

+

I ROW COL VOLTS DES IND PER CHN LOCN INCHI INCH2 CRLEN CRWID CEG BEGT ENDT PDIA PTYPE CAL Li

+-

+-

+

+

+-_++_.+

1 3

40

.15 157 DFS 1 05C 2.10 O9C TEC

.560 ZBARH 4 Cl 1

3 46 NDD 69H TEH

.560 ZBARH 17 HI l

3 40 NOF 2

65C 2.10 06C 05C

.560 ZPSNM 30 CI I

I 2 109

.16 16 -

DFS 1

07H 33.23 69H TEH

.560 ZBARH 3 HI 2 109 NDD O9C TEC

.560 ZBARH 14 C I N2 109 OF 2 07H 33.23 07H 07H

.560 ZPSNM 29 HI

+

+

+

+-+-

+-

+

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

ROW COL VOLTS DEG IND PER CHN LOCN INCHi INCH2 CRLEN CRWID CEG BEGT ENDT PDIA PTYPE CAL LI 4-Tubes: 2 Records: 6 1

S CCE-B HOT LEG SPECIAL INTEREST +POINT INSPECTION PROGRAM Braidwood Al RI1 CCE 7720 X 53 TUBE TESTED FOR SPECIAL INTEREST IN THE HOT LEG -

SEE LIST OFR LOCATION(S) TESTED a 12 PLUGGED TUBE 140 135 130 125 126 115 116 165 106 95 99 o oo 85 86 75 76 65 6e 0

oOo°To.°o. o 0 O

fO°O oc 55 so 46 46 35 3e 26 26 16 1s 6

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115 11e 165 95 96 as Be 75 7s 65 6o 56 45 46 35 36 25 26 15 16 S

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0 00 146 135 136 125 126 115 116 166 166 95 90 85 86 75 76 65 66 55 56 45 46 35 36 25 26 15 16 5

Wmu*ngom. fta~k Co""w' LLC ST Mm IMMON 12OM.OS

SG -

B Hot Leg Special Interest +Polnt Inspection Results Braidwood 1 AlRll MCE 26041601 16/17/2004 68:31:02

+.......................................... *..

-+

I ROW COL VOLTS DEG IND PER CNN LOCN INCHI INCH2 CRLEN CRWID CEG BEGT ENDT PDIA PTYPE CAL LI t--.........

47 24

.19 0

PCT 3

P2 IsH

-1.66 TEH TEC

.560 ZBARH 56 CI 1

47 24

.12 54 VOL 2

esH

-1.47 esH OSH

.560 ZPSNM 57 HI

- I I

5 57 42

.19 0

PCT 3

P2 F05

-1.55 TEN TEC

.560 ZBARH 64 CI 57 42

.15 72 VOL 1

Fes

-1.69 FOG 69H

.52e ZPUNM 83 HI I

71 62

.34 0

PCT 7

P2 F04

.75 TEN TEC

.560 ZBARH 78 CI 1

71 62

.11 lo VOL 1

FU4

.71 FOS 09H

.526 ZPUNM 83 "I

I 52 63

.25 e

PCT 6

P2 FUs 1.13 TEN TEC

.566 ZBARH 78 CI D52 63 OF 1

FUs 1.13 F06 O9H

.520 ZPUNM 83 HI I

I 76 73

.19 O

PCT 5

P2 Fes

-1.69 TEC TEN

.566 ZBARH 31 HI I

76 73

.12 87 VOL 1

FUs

-1.34 FO6 OSH

.528 ZPUNM 83 HI 46 87 ROD TEC TEN

.566 ZBARH 47 HI 46 87 HOD 06H e6H

.560 ZPSNM 87 HI 48 87 NOD TEC TEH

.566 ZBARH 47 HI I

48 87 NOD e6H 06H

.560 ZPSNM 87 HI 50 87 NOD TEC TEH

.560 ZBARH 39 HI t5 87 NOD U6H 06H

.560 ZPSNM 87 HI NDD TEC TEH

.56e ZBARH 45 HI I

45 88 NOD eGH e6H

.56e ZPSNM 87 HI I

4O NOD TEC TEN

.560 ZBARH 45 HI I 47 88 NOD OeH 06H

.560 ZPSNM 87 HI 49 NOD TEC TEH

.566 ZBARH 45 HI 1 49 88 NOD 06 0

U6H

.560 ZPSNM 87 HI I4 89 NOD TEC TEH

.s66 ZBARH 39 HI 51 88 NOD 06H 06H

.560 ZPSNM 87 HI 14 89 NOD TEC TEH

.56e ZBARH 59 HI I 44 89 NOD 06H U6H

.560 ZPSNM 87 HI 46 8NOD TEC TEH

.5660 ZBARH 59 HI 46 6 NOD U6H UGH

.560 Z1PSNM 87 HI I

48 89

.58 124 DSI P1 U6H

-1.35 TEC TEH

.560 ZBARH 61 HI 48 89

.31 73 PCT 27 2

U6H

-1.42

.19

.49 82 U6H 06H

.560 ZPSNM 85 HI I

48 89

.30 71 SVI 2

e6H

-1.42 06H UGH

.56e ZPSNM 85 HI I

I s5 89 NOD TEC TEN

.566 ZBARH 43 HN 50 89 NOD 06H U6H

.560 ZPSNM 87 HI 52 89 NDD TEC TEH

.560 ZBARH 43 HI I

52 89 NOD U6H 06H

.56e ZPSNM 87 HI 45 ge NDD TEC TEN

.56e ZBARH 47 HI I

90 ND 06H 06H

.s60 ZPSNM 87 HI 47 N9D TEC TEN

.556 ZBARH 47 HI I 47 90 NOD U6H 06H

.560 ZPSNM 87 HN I 479 0s D

E E

.s B R I

91 NOD TEC TEN

.56e ZBARH 43 HI 49 90 NOD 06H 06H

.560 ZPSNM 87 HI NOD TEC TEN

.566 ZBARH 43 HI 51 90 NOD U6H e6H

.566 ZPSNM 87 HI H4 91 NOD TEC TEN

.566 ZBARH 61 HN 46 91 NOD U6H 06H

.566 ZPSNM 87 HN 48 91 NOD TEC TEN

.56e ZBARH 61 HI N8 91 NDO 06H U6H

.s66 ZPSNM 87 HN O9 NOD TEC TEN

.56e ZBARH 43 HI s5 91 NoD UGH UGH

.560 ZPSNM 87 HI 5 97NOD TEC TEN

.566 zBARH 49 HI 52 97 NOD TSH TSH

.5660 ZPSNM 57 NJ 52 ~

I 54 97 NOD TEC TEN

.566 ZBARH 51 HI N54 97 RD TSH TSH

.s66 ZPSNM 57 HI

-,4....-.-

I ROW CoL VOLTS DEG IND PER CNN LOCN INCH1 INCH2 CRLEN CRWIO CEG BEGT ENDT PDIA PTYPE CAL LI

+.

+

t.+..'+'+--

+'---'-'-'+----

SG -

B Hot Leg Special I riterest +Point Inspection Results Braidwood 1 AlRl1l CCE 2e041e11 10/17/2004 08:31:02

+-

+-+

-+......*...............+.....................

I ROW COL VOLTS DEG IND PER CNN LOCN INCHX JNCH2 CRLEN CRWID CEG BEGT ENOT PDIA PTYPE CAL LI

.1 98 NOD TEC TER

.566 ZBARH 49 Hi b

51 98 NOD TSH TSH

.560 ZPSNM 57 HI 53 98 NOD TEC TEN

.s6e ZBARH 49 Hj 53 98 NOD TSH TSH

.560 ZPSNM 57 HI 55 98 NOD TEC TEN

.560 ZBARH 49 Hi 55 98 NDD TSH TSH

.560 ZPSNM 57 HN 50 99 ROD TEC TEN

.560 ZBARH 49 HI I

99 NOD TSH TSH

.560 ZPSNM 57 HN 52 99 moD TEC TEN

.560 ZBARH 49 Hj 52 99 NOD TSH TSH

.560 ZPSNM 57 Hi 52 I

54 99 NOD TEC TEN

.560 ZBARH 51 HN 54 99 NOD TSH TSH

.560 ZPSNM 57 HN~I 56 99 NOD TEC TEN

.660 ZBARH 51 Hj 56 99 NOD TSH TSH

.560 ZPSNM 57 HI 49 100 NOD TSH TSH

.56e ZPSNM 57 Hj 49 100 NOD TEC TEN

.560 ZBARH 59 HN j51 le NOD TEC TEN

.56e ZBARH 49 HI 5l lee NOD TSH TSH

.560 ZPSNM 57 HN 53 100

.21 22 SLG 8

TSH 1.79 TEC TEN

.560 ZBARH 49 Hj 53 lee

.35 38 SLG 8

TSH 2.82 TEC TEN

.560 ZBARH 49 HN 53 100 NOF 2

TSH 1.79 TSH TSH

.560 ZPSNM 57 HN 53 100 NDF 2

TSH 2.82 TSH TSH

.560 ZPSNM 57 HN 55 l1a NOD TEC TEN

.560 ZBARH 49 Hj l 55 1 NOD TSH TSH

.560 ZPSNM 57 HN 57 106 NOD TEC TEN

.560 ZBARH 51 HN 57 100 NOD TSH TSH

.566 ZPSNM 57 HN 1

I NOD TEC TEN

.560 ZBARH 49 HN 50 101 NOD TSH TSH

.560 ZPSNM 57 HN 52 101 NOD TEC TEN

.560 ZBARH 49 HI 52 101 NOD TSH TSH

.560 ZPSNM 57 HN 54 101

.13 31 SLG 8

TSH 1.21 TEC TEN

.560 ZBARH 51 Hj 54 101 NDF 2

TSH 1.21 TSH TSH

.560 ZPSNM 57 HN 56 101 NOD TEC TEN

.560 ZBARH 51 Hi 1 56 1

NDD TSH TSH

.566 ZPSNM 57 HN 58 102 NOD TEC TEN

.568 ZBARH 49 Hj s5 101 NOD TSH TSH

.5660 ZPSNM 57 Hi 53 12 NOD TEC TEN

.560 ZBARH 49 HN 51 102 NOD TSH TSH

.561 ZPSNM 57 HN 53 102 NOD TEC TEN

.566 ZBARH 49 Hj 1

53 102 NDD TSH TSH

.560 ZPSNM 57 Nj i

57 102 NOD TEC TEN

.560 ZBARH 51 NJ 55 102 NOD TSH ISH

.561 ZPSNM 57 HN 155 102 D

S S

56 PN 7H 57 102 NDD TEC TEN

.560 ZBARH 51 Hi 57 102 NDD TSH TSH

.560 ZPSNM 57 HN 52 103 NOD TEC TEN

.560 ZBARH 49 HI 52 103 NOD TSH TSH

.566 ZPSNM 57 HI 5O 103 NOD TEC TEN

.561 ZBARH 51 Hj 54 103 NOD TSH TSN

.560 zPS;NM 57 Hi 5613NOD TEC TEN

.560 ZBARH S1 NJ 56 103 NOD TSH TSH

.560 ZPSNM 57 HN 53 104 NOD TEC TEN

.566 ZBARH 51 HN 63 104 NOD TSH TSH

.568 ZPSNM 57 Nj

~.J55 104 NOD TEC TEN

.566 zBARHi 51 HI 55 104 NDD TSH TSH

.568 ZPSNM 57 HN I ROW COL VOLTS DEG IND PER CNN LOCN INCHI INCH2 CRLEN CRWID CEG BEGT ENOT PDIA PTYPE CAL UL

...~e..

,..,e......

l

....+.. *.. o............................................,..,,,..

2

SG - B Hot Leg Special I rnterest +Polnt Inspection Results Bruidwood 1 AIRll CCE 20041001 10/17/2004 18:31:02

+

4,,,-,

4+..4 4-..

+...

I ROW COL VOLTS DEG IND PER CHN LOCH INCHI INCH2 CRLEN CRWID CEG BE6T ENDT POIA PTYPE CAL LI

+.

.,,+,,+,,,,

.+

II 99 167

.53 a

PCT 16 P2 06H

.69 TEC TEH

.560 ZBARH 51 HI 9 96 167

.21 55 VOL 2

67H

.45 67H 07H

.560 ZPSNM 57 HI

-+

,+,+

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

4-_

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

+

+

+

+

+

+

Tubes: 63 Records: 109

CCE-B COLD LEG SPECIAL INTEREST +POINT INSPECTION PROGRAM Braidwood Al RI I CCE 7720 X 15 TUBE TESTED FOR SPECIAL INTEREST IN THE COLD LEG -

SEE LIST FOR LOCATION(S)

TESTED a 12 PLUGGED TUBE 14 135 139 125 129 116 110 105 100 95 go 86 8O 75 70 65 60 65 50 45 4*

35 30 26 20 16 1s 0000 000 0

1 r

1 Ir 5

115 11l 1e5 lee 95 90 se 85 80 75 70 65 55 50 45 40 35 30 26 20 15 10

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135 130 125 120 115 110 105 in 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 16 10 5

W mdnghom

. E~le OevipuiLLC.9rM MA W2A06 1206169

SG -

B Cold Leg Special Interest +Point Inspection Results Braidwood 1 AiRII CCE 28841881 10/17/2004 18:32:31

+

+*

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

  • -.+.*............*....*.
  • -+

+-

I ROW CoL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 CRLEN CRWID CEG BEGT ENDT POIA PTYPE CAL Li

.................... ~...............

1 112 NOD 99H TEN

.566 ZBARH 9 HI 1

112 NOD O9H TEC

.54e ZBARH 22 CI 1

112 NOO 06C 06C

.568 ZPSNM 92 CI 2

113 NOD O9H TEH

.568 ZBARH 9 HI 2

113 NOD 69H TEC

.640 ZBARH 22 CI 2

113 NOD 06C 06C

.560 ZPSNM 92 CI I

I 1

114 NOD O9H TEH

.568 ZBARH 9

HI 1

114 NOD 09H TEC

.540 ZBARH 26 CI 1

114 NDD 06C 06C

.568 ZPSNM 92 CI 3

114 NOD O9H TEN

.560 ZBARH 11 HI 3

114 NOD O9H TEC

.540 ZBARH 22 CI 3

114 NDD 06C 06C

.56e ZPSNM 92 CI 2

115 NDD 69H TEN

.568 ZBARH 9

HI 2

115 NOD O9H TEC

.540 ZBARH 22 CI 2

115 NDOD 6C 06C

.568 ZPSNM 92 CI 4

115 NOD

  • 9H TEN

.s6e ZBARH 11 HI 4

115 NOD Q9H TEC

.54e ZBARH 22 CI 4

115 NDO 06C 06C

.56e ZPSNM 92 CI 1

116 NDOD 9H TEN

.56e ZBARH 9

HI 1 116 1.12 118 DSI P1 06C

.54 O9H TEC

.s46 ZBARH 20 CI 1

116 1.27 116 OSI P1 06C

.41 o9C TEC

.568 ZBARH 82 CI I1 116

.47 78 PCT 42 2

06C

.40

.37

.49 82 06C 06C

.568 ZPSNM 96 CI 1

116

.34 89 SVI 2

66C

.47 06C 06C

.56e ZPSNM 90 CI I

I 3

116 NOD 69H TEN

.568 ZBARH 9

HI 3

116 NOO 69H TEC

.540 ZBARH 22 CI 3

116 NoD 06C 06C

.568 ZPSNM 92 CI I

I 5

116 NOD 09H TEN

.560 ZBARH 9

HI 5

116 NoD 69H TEC

.548 ZBARH 18 C1 5

116 NOD 06C 06C

.560 ZPSNM 92 CI I

I 2

117 NOD 09H TEH

.56e ZBARH 9

HI 2

117 NOD O9H TEC

.548 ZBARH 26 CI 2

117 NDD 06C 06C

.56e ZPSNM 92 CI 4

117 NOD 09H TEN

.568 ZBARH 11 HI 4

117 NOD 69H TEC

.54e ZBARH 22 CI 4

117 NOD 06C 06C

.566 ZPSNM 92 CI 1

118 NOD 69H TEN

.568 ZBARH 9

HI 1

118 NOD 09H TEC

.s4e ZBARH 26 CI 1

118 NDD 06C 06C

.568 ZPSNM 92 CI 3

118 NOD O9H TEN

.566 ZBARH 11 HI 3

118 NOD 69H TEC

.s4u ZBARH 18 CI 3

118 NOD 06C 06C

.56e ZPSNM 92 Cl 2

119 NOD

  • 9H TEN

.560 ZBARH 9

HI 2

119 NOD O9H TEC

.540 ZBARH 26 CI 2

119 NDD 66C 06C

.566 ZPSNM 92 CI I

1 128 NOD 09H TEN

.568 ZBARH 9

HI I

1 128 NOO 09H TEC

.54s ZBARH 20 CI I

1 120 NOD 0SC 06C

.568 ZPSNM 92 CJ

.4.....*.....

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

I ROW CoL VOLTS DEG IND PER CNN LOCN INCHI INCH2 CRLEN CRWID CEG BEGT ENDT POIA PTYPE CAL LI

+

+

+

+

+......+..........

+

+

Tubes: 15 Records: 47 1

CCE-C SPECIAL INTEREST +POINT INSPECTION PROGRAM Braidwood Al RI1 CCE 7720 X 29 TUBE TESTED FOR SPECIAL INTEREST WITH +POINT PROBE -

SEE LIST FOR LOCATION(S)

TESTED a 3 PLUGGED TUBE 5

16 15 25 39 35 46 45 56 I

I I

I I

I I

I I

55 so 66 76 75 86 85 9e 95 1ee 185 116 115 126 125 136 135 146 A

lOo 0 0 0

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85 86 75 79 65 66 55 so 45 46 35 3,

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6 S 55 06 76 75 as8 99 "151916126 125 130 135 146 WesU.~houvoEMwbtcCxenpsnyLW

- SrMsc IOV202O I&M3S4

SG - C Special Interes t

+Point Inspection Results Bratdwood 1 AIRII CCE 20641601 10/20/2004 13:37:34 4.....+.4---

- -+-

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

+

.. +.

+--

63 12 NDO TEC TEH

.560 ZBARH 13 Hi 63 12 NOD 01H O1H

.560 ZPSNM 21 HI 2 HI 62 13 NOD TEC TEH

.560 ZBAPH 13 H

62 13 NOD O1H SIH

.5660 ZPSNM 21 Hi 64 13 NDD TEC TEN

.5660 ZBARH 15 HI 64 13 NOD 611 61H

.560 ZPSNH 21 HI 66 13

.27 124 DSI P1 61H

-. 61 TEC TEN

.560 ZBARH 13 HI 66 13

.17 76 SVI 2

e1m

-. 72

.23

.22 37 01H 61H

.560 ZPSNM 21 HI 66 13

.17 71 PCT 17 2

61H

-. 72 61H 1

1H

.560 ZPSNM 21 HI 63 14 NOD TEC TEH

.560 ZBARH 13 Hi 63 14 NOD

.O6

.68 6

61H 61H

.560 ZPSNM 21 HI 65 14 NOD TEC TEN

.5660 ZBARH 15 HI 65 14 N0D O1H 61H

.560 ZPSNM 21 HI 65 14 NODD E

E 5C ZM5H 67 14 NDD TEC TEN

.560 ZBARH 13 HI 66 11 NDD O1H 61H

.560 ZPSNM 21 Hi 64 15 NDD TEC TEN

.560 ZBARH 15 HI 64 15 NOD 61H 614

.560 ZPSNH 21 Hi 2 I l6 iS TDD OEC TEN

.560 ZBARH 13 Hi 66 15 ND 014H 014H

.560 ZPSNM 21 Hi 68 15 NDD TEC TEN

.560 ZBARH 15 HI 68 15 NDD 014H 014H

.560 ZPSNM 21 HI

@7 48 NOD O9H TEH

.560 ZBARH 3 Hi 67 48 NOD 04H 04H

.560 ZPSNM 21 Hi 69 48 NOD O9H TEN

.560 ZBARH 1

Hi 69 46 NDD 04H 04H

.560 ZPSNM 21 HI I7 48 NOD 69H TEN

.560 ZBARH 1 HI 710 48 ND1 H

717 48 N6D 4H 04H

.560 ZPSNM 21 HI 66 49 NOD 69H TEN

.560 ZBARH 3 HI 16 49 NOD 04H 04H

.560 ZPSNM 21 HI l68 4

NOD 69H TEH

.560 ZBARH 3

Hi 68 49 NOD 04H 04H

.660 ZPSNM 21 Hi 67 49 NDD 09H TEN

.560 ZBARH 1 HI 170 4

N6D 04H 04H

.560 ZPSNM 21 Hi 72 49 NOD

@9H TEN

.560 ZBARH 1 Hi 172 9

N6D 414H 04H

.560 ZPSNM 21 Hi l 5 so NOD 69H TEN

.560 ZBARH 3

HI 65 50 NOD 04H 04H

.560 ZPSNM 21 Hi 67 56 NOD O9H TEN

.560 ZBARH 3

Hi 67 56 NOD 04H 64H

.560 ZPSNM 21 HI 70144 OF 1

64H

-1.91 69H TEN

.560 ZBARH 1 Hi 69 50

.07 92 SY!

2 64H4

-1.71.

.18

.21 35 6414 64H

.560 ZPSNM4 21 Hi 69 51

.69 85 PCT 9

2 6414

-1.71 4

@4H

.560 ZPSNM 21 HN 71 56 NOD O9H TEN

.560 ZBARH 1 HI 71 51 NDD 04H 04H

.560 ZPSNM 21 Hi 736 D 914 TER

.560 ZBARH4 3 HI 73 50 NOD

@4H 6414

.560 ZPSNM 21 HI 66 51 NDD 6914 TEN

.560 ZPARP 3 HI 66 51 NOD 6414 6414

.560 ZPSNM 21 Hi 68 51 NO@914 TEN

.566 ZBARH 3

Hi1 68 1NOD6414 6414

.560 ZPSNM 21 HNI 76 51 NOD 6914 TEN

.560 ZeARH 1 HI 70 1NOD6414 6414

.560 ZPSNM4 21 Nj 72 51 NOD 0914 TEN

.560 ZBARH 1141 72 1ROD6414 6414

.560 ZPSNM 21 H I IROW CDL VOLTS DEG IND PER CNN LOCN INCH1 INCH2 CRLEN CRWID CEG BEGT ENOT PDIA PTYPE CAL LI 1

Sd - C Special Interes -c +Polnt Inspection Results Braldwood 1 A1RI1 CCE 20041001 l1/20/2004 13:37:34

+

+

+-

-+

- -+

+

+

+

I ROW COL VOLTS DEG IND PER CHN LOCN INCHI INCH2 CRLEN CRWID CEG BEGT ENDT PDIA PTYPE CAL Ll

++--------+

" ~---------

67 52 NDD 69H11 TEN

.560 ZBARH 3 Hi 67 52 NDD 04H 04H

.560 ZPSNH 21 Hl I 69 52 NDD 69H1 TEH

.560 ZBARH 1 H 1 69 52 NWo 0411 04H

.560 ZPSNM 21 HJ I

NDD 69H11 TEN

.560 ZBARH 1 HI 1 71 52 64H 604H

.560 ZPSNM 21 HI 171 52 ND!)

+

+----,-

+ ++ +_ ++

++

++

++

+.

++

+_

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

+

+

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

Tubes: 29 Records: 60 2

0 0

CCE-D SPECIAL INTEREST +POINT INSPECTION PROGRAM 0

Braidwood Al RI 1 CCE 7720 A 19 TUBE TESTED AT 02H WITH

+POINT PROBE FOR SPECIAL INTEREST 140 135 139 125 120 115 lie 105 100 95 99 85 8e 75 70 65 60 55 50 45 49 35 30 25 20 15 is I

1 10II II I

I 1

I I

I I

I I

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5 ls 110 1es lee 95 90 85 B0 75 70 65 s0 55 60 46 40 35 30 25 20 5

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S6 - D Special Interes t +Point Inspection Results Braidwood 1 AIRll CCE 20041001 10/20/2004 15:55:43

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I ROW COL VOLTS DEG IND PER CNN LOCN INCHI INCH2 CRLEN CRWID CEG BEGT ENDT PDIA PTYPE CAL Li

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Attachment B.4 Tubes Containing Fan Bar Wear AMRii

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SO - B Fan Bar Wear Indications Braidwood 1 AlRll CCE 20041001 10120/2004 89:36:51

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Attachment B.5 Tubes Containing Lattice Grid Wear A1R11

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Tubes: 2 Records: 2 1

CCE-B LATTICE GRID WEAR INDICATIONS Braidwood Al R 1I CCE 7720 A 1 TUBE WITH LATTICE GRID WEAR INDICATION OF 10 PERCENT AT 07H 8

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