LR-N04-0066, Transmittal of Technical Specification 6.9.1.5 Annual Reports

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Transmittal of Technical Specification 6.9.1.5 Annual Reports
ML040620694
Person / Time
Site: Salem, Hope Creek  PSEG icon.png
Issue date: 02/19/2004
From: Mannon S
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N04-0066
Download: ML040620694 (43)
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Text

PSEG Nuclear LLC

,- P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 FEB 1 9 2004 0 PSEG LR-N04-0066 NuclearLLC U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 TECHNICAL SPECIFICATION 6.9.1.5 ANNUAL REPORTS SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311, AND 50-354 PSEG Nuclear LLC hereby submits the enclosed Annual Reports for the Salem and Hope Creek Generating Stations, in accordance with Technical Specifications 6.9.1.5.a and 6.9.1.5.b of Appendix A to Facility Operating Licenses Nos. DPR-70, DPR-75, and NPF-57.

Pursuant to Technical Specification 6.9.1.5.a, Enclosures 1, 2, and 3 are submitted for Salem Unit 1, Salem Unit 2, and Hope Creek, respectively. These enclosures contain 2003 data on the number of station, utility, and other personnel receiving exposures greater than 100 mrem/year and the collective exposures according to work and job function for each unit.

Enclosure 4 provides information pursuant to the requirements of Technical Specification 6.9.1 .5.b of Appendix A to Facility Operating Licenses No. DPR-70 and

,DPR-75. The information pertains to the Salem Unit 1 and Unit 2 steam generator tube inspections completed in 2003.

Pursuant to the requirements of Technical Specification 6.9.1.5.b of Appendix A to Facility Operating License No. NPR-57, the following information is provided concerning the Hope Creek Safety/Relief Valves (SRVs). During 2003, the SRVs were not challenged by any overpressurization events or transients that would have required the valves to respond.

Pursuant to the requirements of Technical Specification 6.9.1.5.c of Appendix A to Facility Operating Licenses No. DPR-70 and DPR-75, the following information is provided concerning specific activity analyses in which the primary coolant exceeded the limits of Technical Specification 3.4.8. During 2003 there were no events in which the primary coolant exceeded the limits of Technical Specification 3.4.8.

95-2168 REV. 7/99

"*Document Control Desk 2 FEB 1 9 2004 LR-N04-0066 Should you have any questions or comments regarding this submittal, please contact Mr. Michael G. Mosier at 856-339-5434.

Sincerely, b nnon Manager -Licensing Enclosures (4)

Document Control Desk 3 FEB 1 9 2004 LR-N04-0066 C: Mr. H. J. Miller, Administrator- Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Fretz, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 08B2 Washington, DC 20555 Mr. J. Boska, Licensing Project Manager- Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555 USNRC Senior Resident Inspector Hope Creek (X24)

USNRC Senior Resident Inspector Salem (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P.O. Box 415 Trenton, NJ 08625

- , LR-N04-0066 Enclosure 1 ENCLOSURE I ANNUAL REPORT Salem 1 - Year of 2003 NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION

PUBLIC SERVICE ELECTRIC C GAS / SALEM/HOPE CREEK 02-19-2004 Page 1 ANNUAL REPORT Salem 1 - Year of 2003 NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION I I All Personnel (> 100 mrem) II Total Man-Rem I I I Station I Utility I Contractors I Station I Utility I Contractors I Work & Job Function I Employees I Employees I and Others II Employees I Employees I and Others RX OPERATION C SURVEILL

-MAINTENANCE 0 0 3 0.729 0.000 0.592

-OPERATIONS PERSONNEL 0 0 0 1.312 0.000 0.552

-HEALTH PHYSICS 0 0 0 0.968 0.000 0.029

-SUPERVISORY PERSONNEL 1 0 7 3.278 0.019 2.447

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 ROUTINE MAINTENANCE

-MAINTENANCE 0 0 0 0.000 0.000 0.000

-OPERATIONS PERSONNEL 0 0 0 0.000 0.000 0.000

-HEALTH PHYSICS 0 0 0 0.000 0.000 0.000

-SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.000

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 INSERVICE INSPECTION

-MAINTENANCE 0 0 0 0.000 0.000 0.000

-OPERATIONS PERSONNEL 0 0 0 0.000 0.000 0.000

-HEALTH PHYSICS 0 0 0 0.000 0.000 0.000

-SUPERVISORY PERSONNEL 0 0 0 0.085 0.002 0.013

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 SPECIAL MAINTENANCE

-MAINTENANCE 0 0 0 0.000 0.000 0.000

-OPERATIONS PERSONNEL 0 0 0 0.000 0.000 0.000

-HEALTH PHYSICS 0 0 0 0.000 0.000 0.000

-SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.094

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 WASTE PROCESSING

-MAINTENANCE 0 0 0 0.005 0.000 0.000

-OPERATIONS PERSONNEL 0 0 0 0.006 0.000 0.001

-HEALTH PHYSICS 2 0 0 0.653 0.000 0.000

-SUPERVISORY PERSONNEL 0 0 0 0.076 0.000 0.000

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 REFUELING

-MAINTENANCE 0 0 0 0.000 0.000 0.000

-OPERATIONS PERSONNEL 0 0 0 0.000 0.000 0.000

-HEALTH PHYSICS 0 0 0 0.000 0.000 0.000

-SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.000

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000

I, PUBLIC SERVICE ELECTRIC & GAS / SALEM/HOPE CREEK 02-19-2004 Page 2 ANNUAL REPORT Salem 1 - Year of 2003 NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION All Personnel (> 100 mrem) fl Total Man-Rem I Station l Utility I Contractors I Station I Utility I Contractors Work A Job Function l Employees I Employees I and Others II Employees I Employees I and Others TOTALS

-MAINTENANCE 0 0 3 0.733 0.000 0.593

-OPERATIONS PERSONNEL 0 0 0 1.319 0.000 0.552

-HEALTH PHYSICS 2 0 0 1.621 0.000 0.029

-SUPERVISORY PERSONNEL 1 0 7 3.439 0.022 2.555

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 GRAND TOTALS 3 0 10 7.111 0.022 3.729 TOTAL DOSE 10.862

a ; LR-N04-0066 Enclosure 2 ENCLOSURE 2 ANNUAL REPORT Salem 2 - Year of 2003 NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION

-I)

PUBLIC SERVICE ELECTRIC & GAS / SALEM/HOPE CREEK 02-19-2004 Page I ANNUAL REPORT Salem 2 - Year of 2003 NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION I All Personnel (> 100 mrem) II Total Man-Rem I I I Station I Utility I Contractors II Station I Utility I Contractors I Work & Job Function I Employees I Employees I and Others I Employees I Employees I and Others I RX OPERATION & SURVEILL

-MAINTENANCE 14 0 14 5.116 0.000 3.737

-OPERATIONS PERSONNEL 10 0 0 4.854 0.000 0.310

-HEALTH PHYSICS 17 0 25 4.331 0.000 6.223

-SUPERVISORY PERSONNEL 45 0 139 14.734 0.098 51.809

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.005 ROUTINE MAINTENANCE

-MAINTENANCE 0 0 0 0.000 0.000 0.000

-OPERATIONS PERSONNEL 0 0 0 0.000 0.000 0.000

-HEALTH PHYSICS 0 0 0 0.000 0.000 0.000

-SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.000

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 INSERVICE INSPECTION

-MAgINTENANCE 0 0 0 0.034 0.000 0.086

-OPERATIONS PERSONNEL 0 0 0 0.444 0.000 0.117

-HEALTH PHYSICS 0 0 1 0.089 0.000 0.110

-SUPERVISORY PERSONNEL 6 0 31 1.617 0.114 8.370

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 SPECIAL MAINTENANCE

-MAINTENANCE 0 0 0 0.000 0.000 0.002

-OPERATIONS PERSONNEL 0 0 0 0.000 0.000 0.000

-HEALTH PHYSICS 0 0 0 0.025 0.000 0.000

-SUPERVISORY PERSONNEL 0 0 12 0.013 0.000 3.967

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.003 WASTE PROCESSING

-MAINTENANCE 0 0 0 0.010 0.000 0.000

-OPERATIONS PERSONNEL 0 0 0 0.033 0.000 0.003

-HEALTH PHYSICS 3 0 3 0.846 0.000 0.826

-SUPERVISORY PERSONNEL 1 0 6 0.343 0.000 1.667

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 REFUELING

-MAINTENANCE 0 0 0 0.000 0.000 0.000

-OPERATIONS PERSONNEL 0 0 0 0.000 0.000 0.000

-HEALTH PHYSICS 0 0 0 0.000 0.000 0.000

-SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.000

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000

PUBLIC SERVICE ELECTRIC & GAS / SALEM/HOPE CREEK 02-19-2004 Page 2 ANNUAL REPORT Salem 2 - Year of 2003 NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION l I All Personnel (> 100 mrem) II Total Man-Rem I I Station I Utility I Contractors II Station I Utility I Contractors I Work & Job Function I Employees I Employees l and Others II Employees I Employees I and Others TOTALS

-MAINTENANCE 14 0 14 5.160 0.000 3.825

-OPERATIONS PERSONNEL 10 0 0 5.331 0.000 0.430

-HEALTH PHYSICS 20 0 29 5.291 0.000 7.159

-SUPERVISORY PERSONNEL 52 0 188 16.707 0.212 65.812

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.007 GRAND TOTALS 96 0 231 32.488 0.212 77.234 TOTAL DOSE 109.933

- ' LR-N04-0066 Enclosure3 ENCLOSURE 3 ANNUAL REPORT Hope Creek - Year of 2003 NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION

PUBLIC SERVICE ELECTRIC & GAS / SALEM/HOPE CREEK 02-19-2004 Page 1 ANNUAL REPORT Hope Creek - Year of 2003 NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION I I All Personnel (> 100 mrem) II Total Man-Rem I I I Station I Utility I Contractors II Station I Utility I Contractors I I Work & Job Function I Employees I Employees I and Others 1I Employees I Employees I and Others I RX OPERATION & SURVEILL

-MAINTENANCE 13 0 3 4.880 0.030 1.136

-OPERATIONS PERSONNEL 42 0 1 13.532 0.000 1.103

-HEALTH PHYSICS 22 0 32 9.421 0.000 7.985

-SUPERVISORY PERSONNEL 95 6 147 28.452 2.986 45.176

-ENGINEERING PERSONNEL 0 0 1 0.001 0.000 0.293 ROUTINE MAINTENANCE

-MAINTENANCE 0 0 0 0.000 0.000 0.000

-OPERATIONS PERSONNEL 0 0 0 0.000 0.000 0.000

-HEALTH PHYSICS 0 0 0 0.000 0.000 0.000

-SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.000

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 INSERVICE INSPECTION

-MAINTENANCE 0 0 1 0.000 0.000 0.377

-OPERATIONS PERSONNEL 3 0 0 0.869 0.000 0.000

-HEALTH PHYSICS 0 0 0 0.014 0.000 0.138

-SUPERVISORY PERSONNEL 4 0 43 1.114 0.017 15.870

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 SPECIAL MAINTENANCE

-MAINTENANCE 0 0 0 0.000 0.000 0.000

-OPERATIONS PERSONNEL 0 0 0 0.000 0.000 0.000

-HEALTH PHYSICS 0 0 0 0.000 0.000 0.000

-SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.000

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 WASTE PROCESSING

-MAINTENANCE 0 0 0 0.012 0.000 0.002

-OPERATIONS PERSONNEL 0 0 0 0.013 0.000 0.003

-HEALTH PHYSICS 3 0 1 0.851 0.000 0.291

-SUPERVISORY PERSONNEL 0 0 0 0.896 0.002 0.184

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 REFUELING

-MAINTENANCE 0 0 0 0.000 0.000 0.000

-OPERATIONS PERSONNEL 0 0 0 0.000 0.000 0.000

-HEALTH PHYSICS 0 0 0 0.000 0.000 0.000

-SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.000

-ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000

PUBLIC SERVICE ELECTRIC & GAS / SALEM/HOPE CREEK 02-19-2004 Page 2 ANNUAL REPORT Hope Creek - Year of 2003 NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION I I All Personnel (> 100 mrem) II Total Man-Rem Station I Utility I Contractors I Station I Utility I Contractors I Work C Job Function I Employees I Employees I and Others I Employees I Employees l and Others TOTALS

-MAINTENANCE 13 0 4 4.892 0.030 1.516

-OPERATIONS PERSONNEL 45 0 1 14.414 0.000 1.105

-HEALTH PHYSICS 25 0 33 10.286 0.000 8.414

-SUPERVISORY PERSONNEL 99 6 190 30.462 3.005 61.231

-ENGINEERING PERSONNEL 0 0 1 0.001 0.000 0.293 GRAND TOTALS 182 6 229 60.055 3.035 72.558 TOTAL DOSE 135.648

. LR-N04-0066 Enclosure 4 ENCLOSURE 4 Salem Unit 1 and Unit 2 2003 Steam Generator Tube ISI Report

LR-N04-0066 Enclosure 4 Salem Unit 1 and Unit 2 2003 Steam Generator Tube ISI Report In the fall of 2003 PSEG Nuclear conducted eddy current examinations on the Salem Unit 2 Steam Generators (SG) during the 13'h Refueling Outage (2R13). No inspections were performed on Salem Unit 1 during 2003. The next scheduled outage for Unit 1 is in April 2004 therefore; this report only addresses Salem Unit 2.

Overview Commissioned in October of 1981, Salem Unit Two has four Westinghouse Model 51 series steam generators. Each steam generator contains 3388 NiCrFe alloy (Inconel ASME-SB-163)

U-tubes with an outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches.

The tube support structures consist of seven equally spaced 0.750-inch thick carbon steel support plates which are drilled with 0.891 inch holes and two sets of anti-vibration bars (AVB) that are located in the U-bend region of the tubes. The AVB bars are made from 0.387 square cross-section straight length bar material (Nickel-Chromium iron Alloy 600, chrome plated subsequent to bending) that is bent to a vee form with a 5.00-inch radius at the apex. The tube sheet is 21 inches thick ASME-SA508 Class 2 steel forging with Inconel cladding on the primary side. The tube ends are rolled into the tube plate and welded to the tube plate cladding. All tubes are explosively expanded into the tube sheet holes (a.k.a. WEXTEX). The expansion includes the entire depth of the tube sheet for both the hot and cold leg sides.

The steam generator primary side serves as part of the Reactor Coolant Pressure Boundary for containing the reactor coolant and/or emergency core cooling flow and for limiting radiation release to the Reactor Containment (by limiting coolant leakage) during all plant operating conditions. In addition, the steam generators serve as part of the Reactor Coolant Pressure boundary to preclude leakage and radiation release and provide separation between the radioactive primary side and the non-radioactive secondary side/system, Main Steam system, and the outside atmosphere during all plant operating conditions.

Examinations Performed (Scope)

The base eddy current scope was delineated in the Engineering Evaluation No. S-2-RC-MEE-1790 "2R13 Steam Generator Tubing Degradation Assessment". This document identified the active and potential degradation mechanisms affecting the tubing in the Salem Unit 2 Steam Generators, identified the inspection plan and examination techniques to be used, and provided structural limits for each damage mechanism for assessing tube integrity requirements. The eddy current examination scope met Salem Unit 2 Technical Specification 3/4.4.6, "Steam Generators" Surveillance Requirements.

I

LR-N04-0066 Enclosure 4 The final scope performed (including expansions) is outlined below:

  • With the exception of those row 2 and row 3 u-bends inspected under rotating coil inspection program, a full-length bobbin coil inspection was performed on 100% of the in-service tubes in each steam generator.
  • 100% Rotating Coil (+ Point) exam of the rows 2 through 10 U-bends and 20% of the rows 13 through 17 U-bends (07C-07H or 07H - 07C) in steam generators 21, 22 and 24. In steam generator 23, 100% of rows 2 thru 20 were inspected with Rotating Coil (+ Point).
  • 100% Rotating Coil (+ Point) exam of the Hot Leg (HL) WEXTEX Top of Tubesheet (TTS) transition regions in each steam generator at an extent of +3 inches above/-8 inches below
  • 100% Rotating Coil (+ Point) exam of the >1-volt dented HL Tube Support Plate (TSP) intersections at O1H, 02H and 03H AND 20% of the >1-volt dented HL Tube Support Plate (TSP) intersections at 04H in each steam generator. In addition, any new dents > 1 volt dented TSP locations at O1H, 02H, 03H or 04H were inspected with rotating coil.
  • 25% Rotating Coil (+ Point) exam of the >5-volt dented HL TSP population at 04H, 05H, 06H and 07H in each steam generator.
  • 25% Rotating Coil (+ Point) exam of the >2 volt HL free span dings (TSH +0.5 inches to 07H +2.0 inches).
  • Rotating Coil (+ Point) examination of previous TSP ligament Indications identified from the 2R12 bobbin coil data and any new TSP ligament indications identified during 2R13.
  • 100% Rotating Coil (+ Point) of > 2 volt U-bends dings (07H to 07C) identified in 2R12 AND any new > 2 volt U-bend dings reported during the 2R13 inspection
  • 100% Rotating Coil (+Point) of > 1.0 volt dented Anti-Vibration Bar (AVB's) locations in each steam generator AND any new > 1 volt dented AVBs reported during 2R13.
  • 100% Rotating Coil (+ Point) of the freespan indications that were dispositioned in 2R12 as historical bobbin coil signals not related to in-service degradation when compared to the first In-service Inspection (ISI) bobbin coil data. In addition, all bobbin coil freespan indications identified during 2R1 3 that were dispositioned as historical bobbin coil signals not related to in-service degradation when compared to the first ISI bobbin coil data were inspected with rotating coil.
  • 100% Rotating Coil (+ Point) of Cold Leg Thinning (CLT) Indications in each steam generator excluding those inspected during 2Rl 1 and 2R12. In addition, new Cold Leg Thinning indications found in 2R13 were inspected with rotating coil.

Examination Results and Technical Specification Classification Consistent with the requirements specified in NEI 97-06, Steam Generator Program Guidelines, the Unit 2 steam generators met the structural integrity, accident induced leakage and operational leakage performance criteria specified in site procedure SC.SG-AP.ZZ-OOO1(Q), Steam Generator Management Program for 2R13. The following table summarizes the number of tubes repaired in each steam generator by degradation mechanism. Framatome designed Alloy 690 rolled plugs were used for these repairs. The table also provides the total number and percentage of tubes repaired to date and cumulative steam generator tube plugging levels:

2

- ;LR-N04-0066 Enclosure 4 Modes of Degradation SG21 SG22 SG23 SG24 TOTAL Axial Primary Water Stress Corrosion Cracking 3 110 15 (PWSCC) @ ITS US 1 Volumetric Outside Diameter (OD) Indication @TTS Cold leg (Historical volumetric loose part wear 0 2 0 0 2 indication that was preventatively plugged)

New volumetric indications associated with Loose Part 0 0 0 3 3 Wear Preventatively plugged based on loose part engineering 0 0 0 3 3 analysis Volumetric PWSCC @TTS 1 0 0 0 1 Circumferential PWSCC @1TS 0 0 0 0 0 Axial Outside Diameter Stress Corrosion Cracking (ODSCC) @ TTS 0 0 0 1 1 Volumetric ODSCC at HL TSP 0 0 0 1 1 Axial ODSCC @ TSP 0 0 0 0 0 Axial PWSCC @ TSP 1* 1 0 0 2*

Circ PWSCC @ TSP 1* 0 0 0 1*

Axial PWSCC (Low Row Bends) 0 0 0 0 0 Circ PWSCC (Low Row Bends) 0 0 0 0 0 Axial PWSCC (High Row Bends) 0 0 0 0 0 Circ PWSCC (High Row Bends) 0 0 46 0 46 Preventive Plug for U-bend anomalous Signals 0 0 9 0 9 Unacceptable Data Quality (PVN and Ubend Stall) 5 3 0 0 8 Axial Freespan Anomalies 1 1 0 0 2 Volumnetric Freespan Anomalies 0 1 0 2 3 Anti-Vibration Bar Wear 1 0 0 1 2 Cold Leg Thinning Indications 1 2 6 3 12 TOTAL TUBES PLUGGED 13 11 62 24 110*

TOTAL TUBES PLUGGED CUMULATIVE 224 235 233 330 1022 CUMULATIVE TUBE PLUGGING % 6.61 6.94 6.88 9.74 7.54

  • One tube in 21 SG has an Axial and Circumferential PWSCC indication at the same TSP.

Although both indications are reported, the tube is only counted once for the purposes of reporting total tubes plugged.

The Technical Specification categorization of each steam generator is listed in the table below and takes into consideration both the bobbin coil and Rotating Coil inspection results.

3

LR-N04-0066 Enclosure 4 WEXTEX Tubesheet Inspections The WEXTEX transition is the region of the tube where the tube transitions from the expanded tube diameter to the nominal tube diameter and is typically located near the top of the tubesheet. The bottom of the WEXTEX transition is the first point of contact between the tube and the tubesheet. In this region, both PWSCC and ODSCC have been observed with PWSCC being the prominent damage mechanism at Salem Unit 2.

During 2R13, 100% rotating coil (+ Point) inspections of the HL TTS WEXTEX transition region were performed in each steam generator at an extent of +3 inches above TTS to - 8 inches below the TTS. The table below lists all tubesheet indications repaired during 2R13. All indications were sized for tube integrity assessment. Sixteen tubes were plugged for axial PWSCC located below the TTS. One axial ODSCC indication was detected at the TTS region in steam generator 24.

SG Tube ID Indication Location Damage Mechanism 21 R2C20 SAI TSH -2.22" PWSCC 21 R15C27 SAI TSH - 9.88" PWSCC 21 R6C70 SAI TSH - 0.70" PWSCC 21 R30C79 SVI TSH - 0.65" PWSCC 22 R25C72 SAI TSH -1.53" PWSCC 23 R25C61 SAI TSH -8.44" PWSCC 24 R3C51 SAI TSH -0.90" PWSCC 24 R9C36 SAI TSH -1.32" PWSCC 24 R14C17 SA TSH -0.37" PWSCC 24 R14C41 SA TSH -1.01" PWSCC 24 R16C39 SA TSH -0.28" ODSCC 24 R20C35 SA TSH -2.22" PWSCC 24 R24C52 SAI TSH -0.16 PWSCC 24 R3_C52 SAI TSH -0.29 PWSCC 24 R31C54 SAI TSH -0.34 PWSCC 24 R31C58 SAI TSH -0.24 PWSCC 24 R33C44 SAI TSH -0.41 PWSCC Dented Hot Leg (HL) Tube Support Plate (TSP) Intersection Inspections About 6259 > 1 volt dented TSP's intersections were inspected as part of the base scope rotating coil inspection program. In addition, approximately 286 newly reported dents were examined with a rotating coil technique. A total of 2 axial PWSCC indications and 1 circumferential indication were detected at the hot leg dented TSP intersections, affecting 2 of the steam generators (SG 21 and 22). The location in SG 21 (R19C18) had the axial and circumferential indication at the same TSP; 02H TSP. The flaws were approximately 120 to 180 degrees apart on the tube wall (opposite sides of tube) and separated axially within the TSP, thus flaw interaction is not probable and burst capability is not reduced. All indications were within the TSP.

4

LR-N04-0066 Enclosure 4 The tubes repaired for PWSCC at dented HL TSP locations are shown in the table below:

These indications were not detected during the bobbin coil examination.

SG Tube ID Indication TSP Location 2R13 Bobbin Damage Dent Voltage Mechanism 21 R19C18 SAI/SCI 02H 4.74 PWSCC 22 R4C77 SAI 01H 2.49 PWSCC ODSCC at the Tube Support Plate (TSP) Intersections One Outside Diameter Single Volumetric Indication was detected in SG 24 at the 01H TSP in tube R35C18. This indication was identified during the bobbin coil examination and reported as a non-quantifiable indication. Subsequent rotating coil examination sized the volumetric indication with a maximum depth of approximately 22% through-wall (TW), 0.4 volts, and is possibly attributed to intergranular attack corrosion (IGA). This tube was removed from service (plugged).

Anti-vibration Bar (AVB) Wear AVB wear indications are plugged if bobbin indicates a depth > 40% TW. Tubes with degradation less than 40% TW may be left in service or removed from service depending on the observed growth rate of the degradation. A population of bobbin coil AVB wear indications were inspected with rotating coil that verified the reported indications displayed a volumetric response and were not crack like.

A total of two tubes were repaired for this damage mechanism. The table below lists the tubes plugged for AVB wear during 2R13:

SG Tube ID Indication TSP Location 21 R27C47 40% AV3 24 R33C47 42% AV4 Appendix 1 provides a listing of the AVB percent through-wall indications reported during 2R13.

Cold Leg Thinning (CLT)

Cold leg thinning (CLT) is caused by surface wastage (corrosion) and occurs principally within the confines of the lower cold leg tube support plates on the periphery of the tube bundle. CLT indications are plugged if bobbin indicates a depth of > 40% TW. Tubes with degradation less than 40% TW may be left in service or removed from service depending on the observed growth rate of the degradation. A population of bobbin coil CLT indications were inspected with rotating coil and the results of those inspections verified the indications displayed a volumetric response and were not crack like.

5

LR-N04-0066 Enclosure 4 A total of eleven tubes were plugged for this damage mechanism as shown in the table below:

SG Tube ID Indication TSP Location 21 R43C31 19%* O1C 22 R33C16 43% 03C 22 R33C77 55% OlC 23 R9C3 43% O1C 23 R12C3 53% OIC 23 R25C8 48% OlC 23 R29C12 51% 02C 23 R31C15 46% OIC 23 R44C33 48% O1C 24 R42C33 43% 02C 24 R43C35 42% 02C 24 R33C79 46% OIC

  • Low voltage (0.35 volts) bobbin coil DSI that via rotating coil produces a volumetric response typical of cold leg thinning. The percent through wall depth could not be accurately determined with the bobbin coil technique due to the influence of tube support plate residual on the signal. The indication was sized with a rotating coil technique using an ASME calibration standard. This sizing technique was judged to be more representative of the actual depth based on indication voltage.

Appendix 2 provides a listing of the CLT percent through-wall indications reported during 2R1 3.

Rotating Coil Inspection of U-bends 100 % of the Row 2 and Row 3 (Row 1 plugged) low row u-bend in each SG were inspected with either a dual coil + Point probe (The probe contained both mid frequency and high frequency coils spaced 18 inches apart) or a single coil + Point probe. No degradation was reported during this inspection.

In response to operating experience from Diablo Canyon and Beaver Valley, additional u-bend inspections were performed following the guidance provided in Westinghouse report SG-SGDA-03-33, "Generic Evaluation of U-Bend PWSCC Susceptibility for Model 51 SGs with Mill Annealed Alloy 600 Tubing". The inspections performed are outlined below:

  • 100% of the Row 4 thru Row 10 tubes in each steam generator were inspected with a single coil + Point probe in the u-bend region.
  • 20% of Row 13 through Row 17 tubes each steam generator were inspected with a single coil +Point probe in the u-bend region.

Additional inspections were performed in 23 SG due to indications reported during the base scope inspections as outlined in the previous two bullets. PSEG followed the 6

LR-N04-0066 Enclosure 4 recommendations provided in Westinghouse report SG-SGDA-03-33 for this expansion. In summary, for 23 SG, 100% of the Row 2 through Row 20 tubes were inspected with a +Point probe in the u-bend region. No additional indications were reported.

One ID axial anomaly was reported in the apex (extrados) area of tube SG 21, R14C90 that appeared to be axial PWSCC based on phase angle, phase relationship (rotation) between the frequencies and the voltage drop across those frequencies.

PSEG concluded that this indication was not PWSCC, rather some sort of manufacturing anomaly in the tube. The specifics for reaching this conclusion are discussed in the "Freespan Indications" section of this report.

46 tubes were repaired (plugged and stabilized) in 23 SG attributed to circumferentially oriented PWSCC in the flank area of the tube, that were determined to be similar to those reported during the Diablo Canyon 2R1 1 outage. 7 of the 46 tubes were in-situ pressure tested (proof and leak tested). No burst or leakage was observed during the test. Therefore both structural and leakage performance criteria were demonstrated for this degradation at end of cycle (EOC) 13.

A listing of the tubes repaired (plugged and stabilized) is shown in the table below:

SG Tube ID Indication U-bend Location 23 R6C14 SO 7H +28.89 23 MRC17 SCI 7H +24.82 23 R6C18 SCI 7H +29.02 23 R9C19 MULTSCI 7H +41.25 23 R9C20 MULT SCI 7H +41.14 23 R9C21 MULT SCI 7H +41.25 23 R9C22 MULT SCI 7H + 41.23 23 R9C23 MULT SCI 71 +39.93 23 R5C26 SCI 7H + 25.79 23 R6C26 SCI 7H +29.25 23 RMC27 SCI 7H +25.39 23 RMC28 SCI 7H +25.95 23 R5C29 SCI 7H + 25.60 23 R5C32 SCI 7H +25.73 23 R5C33 SCI 7H +25.80 23 R5C34 SCI 7H +25.40 23 R5C38 SCI 7H +25.56 23 R5C40 SCI 7H +25.83 23 R5C41 SCI 7H +25.90 23 R5C42 SCI 7H +25.90 23 R5C47 SCI 7H + 25.96 23 R6C48 SCI 7H +4.92 23 R6C49 SCI 7H +4.56 23 R9C49 SCO 7H +4.36 23 R6C54 SCI 7H +4.77 7

LR-N04-0066 Enclosure 4 SG Tube ID Indication U-bend Location 23 R5C59 SO 7H + 4.67 23 R5C65 SCI 7H + 4.57 23 R5C68 SCI 7H +4.48 23 R5C69 SCI 7H + 4.37 23 R5C71 SCI 7H +4.46 23 R5C73 SCI 7H + 4.49 23 R5C74 SCI 7H + 4.67 23 R5C75 SCI 7H +4.59 23 RSC78 SCI 7H + 4.43 23 R5C80 SCI 7H +4.55 23 R8C80 SCI 7H +4.22 23 R5C81 SCI 7H +4.56 23 R5C83 SCI 7H +4.54 23 R5C87 SO 7H + 4.55 23 R5C88 SCI 7H +4.73 23 R5C89 SCI 7H + 4.44 23 R5C91 SCI 7H +4.81 23 R6C92 SCI 7H + 5.08 23 R8C92 SCI 7H +4.54 23 R5C93 SCI 7H +4.65 23 R6C94 SCI 7H +5.15 Nine additional tubes in 23 SG were preventatively plugged due to small anomalous signals that were difficult to discern from the ridge lift-off signals present in the tubes. It was not clear that these signals were truly flaw-like therefore PSEG preventatively plugged and stabilized these tubes. These locations are listed below:

SG Tube ID Indication Location 24 R9C52 Preventatively plugged Ubend 23 R6C56 Preventatively plugged Ubend 23 R6C61 Preventatively plugged Ubend 23 R6C62 Preventatively plugged Ubend 23 R7C63 Preventatively plugged Ubend 23 R6C65 Preventatively plugged Ubend 23 R6C66 Preventatively plugged Ubend 23 R6C74 Preventatively plugged Ubend 23 R9C74 Preventatively plugged Ubend Loose Parts During outage 2R13, 100% of the bobbin and rotating coil data was reviewed for possible loose part indications. A total of eight tubes were repaired for suspected loose part indications, wear associated with loose parts and/or preventatively plugged based on engineering evaluations performed.

8

LR-N04-0066 Enclosure 4 SG 24 tube locations R39C52 (21% TW wear, 43 degree arc, 0.14 inch axial extent), R40 C51 (30% TW wear, 64 degree arc, 0.37 inch axial extent), and R41C50 (21% TW wear, 56 degree arc, 0.26 inch axial extent); had indications of wear (PLI). These tubes were plugged and stabilized. SG 24 tube locations R40C52, R39C51, and R40C50 were also preventatively plugged and stabilized in accordance with engineering evaluations performed.

In addition, two tubes in 22 SG, R45C53 and R46C53, were plugged for loose part wear (less that 25% TW) indications at the cold leg TTS. These indications were originally identified during 2R9. During 2R13, these locations were preventatively plugged even though there was no change in the reported through-wall depth since 2R9.

Data Quality Data quality is an important parameter influencing the overall performance of a steam generator tube examination system as it has an effect on probability of detection and sizing uncertainties. The following list reflects the tubes repaired for Data Quality Concerns:

SG Tube ID Indication 21 R13C44 Permeability Variation 21 R19C47 Permeability Variation 21 RIOC56 Permeability Variation 21 R28C57 Permeability Variation 21 R27C80 Permeability Variation 22 R21C15 Permeability Variation 22 R5C73 Ubend - Probe Stalled 22 R4C84 Ubend - Probe Stalled Freespan Indications When reported during the outage inspection, freespan bobbin coil indications are compared to the 1983 first ISI data to determine if change has occurred. As documented in the bobbin coil Examination Technique Specification Sheet (ETSS), change was defined as 10 degrees towards the flaw plane, or greater than 0.5-volt difference when compared to historical (1983) data, new indications, or the indication exhibits a distinctive change in shape or character. In response to the Comanche Peak Operating Experience, during 2R13 a rotating coil inspection was performed on all freespan indications that were dispositioned during 2R12 as not meeting the bobbin coil change criterion. These inspections were performed in an effort to quantify the source of the bobbin coil signals and in an attempt to validate the stations change criterion.

9

LR-N04-0066 Enclosure 4 A total of 5 tubes were repaired due to freespan anomalies reported during the outage as described below:

Axial Anomalies

  • One ID axial anomaly was reported in the apex (extrados) area of tube SG 21, R14C90 that appeared to be axial PWSCC based on phase angle, phase relationship (rotation) between the frequencies and the voltage drop across those frequencies. The indication was very uniform along its length of 1.47 inches, approximately 40% deep from end to end and was very similar to that reported by another utility (series 51 SG) in a higher row u-bend during the spring 2003 outage season. Based on the length of this indication, in-situ pressure testing (proof and leak test) was performed. The testing, while demonstrating that tube integrity was met at EOC 13, was also used to verify that this indication is not actual tube degradation. The length of the indications is such that an in-situ pressure test would be expected to open up true PWSCC degradation. The tube was in-situ pressure tested and then re-inspected with the Plus-point probe afterwards with no significant changes detected in the Non Destructive Examination (NDE) characteristics.

The bobbin coil data was reviewed for this area in the current outage and previous outages, including the first ISI. It was determined that the indication although present in the 2R13 data, could not be expected to be reliably detected with the bobbin coil. The historical review revealed that the indication was present in the first ISI and had not changed significantly in 13 cycles of operation. Based on the NDE data after in-situ pressure testing and the historical review of the bobbin coil data, PSEG concluded that this indication is not PWSCC, rather appears to be some sort of manufacturing anomaly in the tube. This tube was removed from service (plugged).

  • The other axial indication, SG 22 (R19C71), was detected during the Plus-Point inspection of the historical freespan indications from 2R12. Location R19C71 was determined to have an axial indication approximately 8 inches below the 5h TSP on the cold leg side. The indication was somewhat similar to the indication in the unbend but was not as consistent in depth across its -1 inch length. Based on the length of this indication, in-situ pressure testing (proof and leak test) was performed. The testing, while demonstrating that tube integrity was met at EOC 13, was also used to verify that this indication is not actual tube degradation. The length of the indications is such that an in-situ pressure test would be expected to open up true PWSCC degradation. The tube was in-situ pressure tested and then re-inspected with the Plus-point probe afterwards with no significant changes detected in the NDE characteristics.

10

LR-N04-0066 Enclosure 4 Based on the NDE data after in-situ pressure testing and the historical review of the bobbin coil data, PSEG concluded that this indication is not PWSCC, rather appears to be some sort of manufacturing anomaly in the tube. This tube was removed from service (plugged).

The table below lists the specifics associated with the axial anomalies reported:

2R13 DATA 2 POST D13 INSITU Change

_____ ___ DATA _ _

SG IND R C I I TSP/INCH I LEN.

MD% +PT

~~~VOLTS LEN.

MD M%

TO

+TVLSLN D V

21 14 90 SAI 711+ 36.26 1.47 41 2.01 1.45 41 2.01 -0.02 0 0 22 19 71 SAI 5C - 8.28 0.92 38 1.38 0.8 35 1.43 -0.12 -3 0.05 Volumetric Anomalies As a result of the axial anomalies that were found during the base scope examination (discussed above), the rotating coil inspection program was conservatively expanded to include 100% of the current outage freespan indications that were dispositioned as not meeting the 2R13 change criterion.

Therefore, regardless if change was apparent (or not) when compared to the first ISI, these locations were inspected with a rotating coil. This resulted in another 156 indications being inspected with rotating coil. Three additional indications (all volumetric) were reported during this inspection. The details are provided in the table below. The fact that these indications are present in the first ISI inspection provides the basis that they are not active degradation, but likely manufacturing related. These indications were not significant as shown by their Plus-point responses (voltage) and comparison to the stations in-situ pressure testing screening document. These tubes were removed from service (plugged).

SG R C IND ED/OD TSP/INCH ARC LEN. M VOPLTS BCBBLN VOLTS 22 40 52 SVI OD TSC + 2.02 44 0.29 13 0.22 FSH 0.50 24 3 75 SVI OD (4) 4H-5H 42 0.16 6 0.12 FSH 0.33 24 27 80 SVI OD 2H + 24.96 39 0.18 5 0.11 i FSH 0.32 11

LR-N04-0066 Enclosure 4 Tube Support Plate Integrity Inspections During outage 2R13 approximately 40 tube support plate ligament (TSP) indications were detected. All previously identified indications, and any new suspected TSP ligament indications that were detected during 2R13 bobbin coil inspection, were Plus-point inspected. Data for TSP ligament indications is presented in the table below:

SG Tube ID CHN IND LOCATION SIZING

___ INFORMATION 21 R14C6 7 SLC 06H +0.04 SINGLE 21 R20C53 7 SLC OSH +0.03 SINGLE 21 R31C79 7 SLC 06H +0.00 SINGLE 21 R36C40 7 SLC 06H -0.02 SINGLE 21 R37C40 7 SLC 06H +0.08 SINGLE 7 SLC 05H +0.18 SINGLE 21 R42C34 7 SLC 06H -0.22 SINGLE 21 R42C36 7 SLC 06H -0.15 SINGLE 21 R43C40 7 SLC 06H -0.03 SINGLE 21 R45C41 7 SLC 06H -0.16 SINGLE 22 R37C54 7 SLC 03H +0.01 SINGLE 22 R41C54 7 SLC 03H +0.00 SINGLE 23 R3C56 7 SLC 06C +0.01 55DEG 23 R6C27 7 SLC 04H +0.00 47DEG 23 R9C40 7 SLC 06C +0.00 46DEG 23 R9C55 7 SLC 02H -0.02 56DEG 7 SLC 03H -0.09 116DEG 23 R14C37 7 SLC 04H +0.01 32DEG 23 R14C38 7 SLC 04H +0.00 56DEG 23 R14C57 7 SLC 05C +0.20 58DEG 23 R17C27 7 SLC 04H +0.01 70DEG 23 R22C75 7 SLC 01H +0.00 43DEG 7 SLC 07H +0.00 104DEG 23 R25C87 7 SLC 07C -0.12 SINGLE 23 R29C81 7 SLC 07C -0.02 64DEG 7 SLC 01C +0.00 50DEG 23 R39C56 7 SLC 07H -0.22 SINGLE 23 R42C59 7 SLC 04H -0.18 SINGLE 23 R45C54 7 SLC 07H -0.01 SINGLE 23 R46C54 7 SLC 07H -0.19 SINGLE 24 R20C29 7 SLC 07C -0.09 SINGLE 24 R26C9 7 SLC 05C +0.36 SINGLE 24 R34C46 7 SLC 02C -0.06 SINGLE 24 R41C39 7 SLC 02C -0.04 SINGLE 24 R45C41 7 SLC 07H +0.13 SINGLE 12

LR-N04-0066 Enclosure 4 SG Tube ID CHN IND LOCATION SIZING

______ ___INFORMATION 24 R45C57 7 SLC 01H +0.14 32DEG 24 R46C41 7 SLC 07H -0.17 SINGLE 7 SLC I01H -0.01 SINGLE 24 R46C54 7 SLC 07H +0.24 DOUBLE Only 1 "new" indication of ligament cracking was identified, which was detected via bobbin. As with the previously detected ligament indications, this indication is not necessarily new, but most likely a result of bobbin coil POD. However, the TSP locations that have been visually verified and are in fact missing a piece of ligament (gap), have been demonstrated as readily detectable via the bobbin technique. In addition no significant growth or change could be inferred in the data considering analyst variability and technique utilized. Visual inspections of historical ligament gap locations were performed following chemical cleaning in 2R10 and it was determined that the flow hole and tube holes intersected as a result of misdrilling during manufacture. No indication of true service induced TSP degradation has been detected or visually verified in the Salem 2 SGs.

One indication from 2R12 was determined as NDD by Plus-point in 2R13, and is likely a result of a conservative analyst call in 2R12. All indications were returned to service since the criteria of ligament cracking below 145 degree threshold gap was not exceeded.

Free Span Ding Inspections Rotating Coil inspections were performed on a 25% sample of the HL > 2-volt free span dings to identify potential PWSCC and/or ODSCC. The 25% sample included free span dings reported from the TSH +0.5 inches to 07H +2.0 inches. In addition to this scope and in response to Comanche Peak Operating Experience, 100% of then U-bend > 2-volt dings in each steam generator were inspected with rotating coil. Approximately 271 dings were inspected as part of the base scope and 104 new dings were examined. No degradation was reported.

13

LR-N04-0066 Enclosure 4 Appendix 1 Anti-Vibration Bar Wear Percent Through-Wall Indications I

.LR-N04-0066 Enclosure 4 SG Row Column %TW Location 21 16 24 11 AVI -0.04 21 16 66 15 AV4 -0.42 21 17 25 13 AV3 +0.04 21 17 35 9 AVI +0.12 21 17 37 13 AV4 -0.59 21 17 39 18 AVI -0.23 21 17 39 16 AV2 +0.03 21 17 39 17 AV3 -0.09 21 17 52 12 AVI +0.17 21 17 52 9 AV2 -0.83 21 17 52 8 AV2 +0.97 21 17 52 9 AV3 -0.85 21 17 52 12 AV3 +0.95 21 17 52 13 AV4 -0.34 21 17 56 19 AV2 +0.07 21 17 56 11 AV3 +0.26 21 17 63 14 AV2 +0.09 21 17 63 11 AV3 -0.23 21 17 63 12 AV3 +0.31 21 18 67 12 AVI -1.10 21 18 67 10 AV4 +0.78 21 19 30 18 AVI +0.08 21 19 30 22 AV2 +0.30 21 19 30 30 AV3 -0.08 21 19 30 14 AV2 -0.26 21 19 58 26 AV2 +0.51 21 19 58 19 AV4 +0.51 21 19 66 17 AVI -0.45 21 19 66 25 AV2 +0.23 21 19 66 27 AV3 +0.23 21 19 66 5 AV4 -0.96 21 21 29 11 AV3 +0.24 21 21 29 19 AV4 -0.49 21 21 60 16 AV2 -0.21 21 21 60 20 AV3 -0.43 21 22 60 17 AV2 -0.15 21 23 64 15 AV2 +0.06 21 23 64 18 AV3 +0.16 21 23 67 21 A"I -0.96 21 23 67 26 AV2 -0.31 21 23 67 23 AV3 -0.11 21 23 68 15 AV4 -0.13 21 23 68 25 AV3 -0.02 21 23 68 39 AV2 -0.45 21 23 70 13 AV4 +1.26 21 24 41 6 AVI -1.64 21 24 52 12 AVI -1.99 2

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 21 24 52 20 AV2 +1.25 21 24 52 8 AV3 +1.16 21 24 52 16 AV4 +0.49 21 24 67 19 AV2 -0.27 21 24 68 29 AV2 +0.81 21 24 68 29 AV3 +0.13 21 24 70 9 AVI +0.40 21 26 46 11 AV2 +0.36 21 26 56 26 AVI +0.32 21 26 56 22 AV2 +0.06 21 26 56 28 AV3 +0.15 21 26 56 32 AV4 -0.78 21 26 58 15 AV2 -0.59 21 26 58 24 AV3 -0.72 21 26 59 12 AV2 +0.11 21 26 59 15 AV3 +0.42 21 26 59 12 AV4 -0.38 21 26 63 12 AV4 -0.59 21 26 64 22 AVI -0.16 21 26 64 12 AV2 +0.11 21 26 64 13 AV3 +0.21 21 26 67 .25 AVI -0.75 21 26 67 12 AV2 -0.23 21 27 44 16 AVI -0.51 21 27 44 32 AV2 -0.06 21 27 44 32 AV3 +0.25 21 27 44 25 AV4 +0.83 21 27 45 18 AV4 +0.55 21 27 46 25 AV4 -0.41 21 27 46 33 AV2 +0.28 21 27 46 15 AV2 -0.24 21 27 46 34 AV3 +0.30 21 27 47 32 AV4 -1.40 21 27 47 18 AV2 -0.88 21 27 47 40 AV3 -0.75 21 27 50 11 AV2 -1.31 21 27 50 22 AV3 -1.58 21 27 56 23 AVI +0.32 21 27 56 30 AV2 +0.04 21 27 56 33 AV3 +0.06 21 27 56 25 AV4 -0.64 21 27 56 12 AV4 +0.49 21 27 59 21 AV4 -0.38 21 27 64 37 AV3 +0.19 21 27 64 27 AV2 +0.13 21 27 64 21 AVI -0.02 21 29 46 10 AV4 -0.17 3

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 21 29 46 38 AV3 +0.35 21 29 46 25 AV2 +0.37 21 29 46 16 AVI -0.57 21 29 57 21 AV2 +0.02 21 29 57 22 AV3 -0.11 21 29 57 20 AV4 -0.08 21 29 65 15 AV3 +0.59 21 29 65 28 AV4 -0.38 21 31 64 27 AV2 -0.04 21 31 67 19 AV2 +0.51 21 32 39 11 AV4 +0.02 21 32 48 24 AV2 -0.08 21 32 48 30 AV3 +0.17 21 32 49 14 AV3 +1.29 21 32 49 12 AV4 -0.42 21 32 51 12 AV2 +1.35 21 32 51 25 AV3 -1.20 21 32 51 27 AV3 +1.49 21 32 51 19 AV4 +1.75 21 32 54 12 AV3 -0.21 21 33 41 9 AV2 -0.04 21 33 41 7 AV3 -0.11 21 33 41 14 AV4 +0.75 21 33 55 14 AV3 +0.19 21 33 60 27 AVI +0.30 21 33 60 29 AV3 +0.42 21 34 36 14 AVI -0.33 21 34 36 14 AVI +0.28 21 34 36 29 AV2 -0.45 21 34 36 16 AV3 -0.27 21 34 37 10 AVI +0.32 21 34 37 21 AV3 +0.24 21 34 37 10 AV4 +0.06 21 34 37 25 AV2 +0.26 21 34 44 36 AV3 +0.11 21 34 44 24 AV2 -0.15 21 34 44 10 AVI +0.30 21 34 45 12 AVI +0.19 21 34 45 15 AV2 -0.02 21 34 45 27 AV3 -0.49 21 34 45 20 AV4 -0.24 21 34 49 11 AV2 +1.25 21 34 49 13 AV3 +1.41 21 34 51 22 AV2 +1.23 21 34 51 21 AV3 +1.20 21 34 51 25 AVI -0.26 21 34 52 14 AV2 +0.95 4

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 21 34 65 29 AV3 -0.15 21 34 65 27 AV4 -0.40 21 35 63 12 AVI +0.04 21 35 63 16 AV2 +0.01 21 35 68 17 AVI -0.51 21 35 68 18 AV2 -0.10 21 35 68 11 AV3 +0.04 21 36 41 24 AV3 +0.06 21 36 43 16 AV3 -0.28 21 36 43 10 AV4 +0.21 21 36 50 10 AV2 +0.94 21 36 52 37 AV2 -0.82 21 36 53 13 AV2 +0.55 21 36 53 11 AVI -0.56 21 36 56 24 AV2 +0.02 21 36 58 22 AVI +0.32 21 36 58 28 AV2 -0.42 21 36 58 13 AV2 +0.49 21 36 58 29 AV3 -0.32 21 39 37 32 AV2 +0.02 21 39 37 17 AVI +0.30 21 39 37 12 AVI -0.19 21 39 54 14 AVI -0.19 21 39 61 24 AVI -0.64 21 39 61 30 AV2 -0.45 21 40 58 17 AV2 -0.31 21 41 50 12 AVI +0.04 21 41 53 11 AVI +0.34 21 41 53 17 AV2 -0.19 21 41 58 13 AVI +0.15 21 41 58 11 AV4 +0.06 21 42 31 11 AV3 -0.02 21 42 34 10 AV4 -0.26 22 16 68 12 AV4 +0.64 22 16 68 16 AV3 +0.30 22 16 68 19 AV2 -0.26 22 18 65 21 AV4 -0.83 22 18 65 11 AV4 +0.77 22 18 65 30 AV3 +0.06 22 18 65 20 AV2 -0.62 22 18 65 25 AV2 +0.85 22 18 65 24 AVI -1.17 22 18 65 15 AVI +1.69 22 22 62 25 AV3 -0.19 22 22 62 11 AV2 -0.17 22 23 71 13 AV4 +0.28 22 23 71 18 AV3 +0.30 5

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 22 23 71 9 AV2 +0.11 22 23 71 16 AVI -0.91 22 23 74 13 AV2 -0.10 22 23 74 14 AV4 -0.40 22 25 9 10 AV2 +0.38 22 25 9 17 AV3 +0.04 22 25 30 19 AVI +1.72 22 25 30 22 AV2 +0.06 22 25 30 30 AV3 +0.23 22 25 55 14 AVI +0.86 22 25 63 13 AV3 -0.38 22 25 69 31 AV3 +0.15 22 25 69 18 AV2 +0.41 22 25 69 17 AV2 -0.38 22 25 71 19 AV3 +0.36 22 26 23 15 AV3 -0.02 22 26 62 9 AV4 +0.41 22 26 62 24 AV3 -0.15 22 26 62 26 AV2 +0.15 22 26 62 28 AVI +0.62 22 27 28 14 AV2 -0.12 22 27 28 12 AV3 +0.21 22 31 27 21 AV2 -0.02 22 31 28 23 AV2 +0.25 22 31 28 15 AVI +0.59 22 32 52 14 AV3 -0.21 22 33 67 15 AV2 +0.34 22 33 67 13 AV2 -0.21 22 34 32 28 AVI +0.04 22 34 32 31 AV2 +0.39 22 34 32 28 AV3 +0.04 22 34 39 13 AV3 -0.15 22 34 41 11 AV3 +0.06 22 34 46 13 AV3 -0.02 22 34 47 13 AV3 -0.04 22 34 49 34 AV4 -0.56 22 34 50 18 AV4 +0.82 22 34 50 28 AV3 +0.24 22 34 50 15 AV2 -0.07 22 34 50 8 AVI +0.95 22 34 58 18 AV2 +0.06 22 34 70 13 AV4 -0.06 22 35 26 10 AVI +0.10 22 35 26 10 AV2 +0.08 22 35 53 11 AV3 -0.09 22 35 53 15 AV2 +0.02 22 36 34 27 AV3 +0.19 6

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 22 36 51 12 AV2 +0.08 22 40 36 28 AV4 -0.12 22 40 37 17 AVI +0.09 22 40 37 22 AV2 +0.11 22 40 44 20 AVI +0.43 22 40 44 31 AV2 +0.02 22 40 52 13 AVI -0.19 22 40 52 17 AV2 -0.08 22 41 32 11 AV3 -0.02 23 15 77 15 AV2 +0.38 23 16 57 22 AVI +0.49 23 16 57 15 AV2 -0.16 23 16 57 23 AV3 -0.41 23 16 57 19 AV4 -1.05 23 20 31 14 AVI +1.18 23 20 56 10 AV4 -1.62 23 20 58 14 AVI +0.20 23 20 64 12 AV4 +0.06 23 20 67 15 AVI -0.94 23 20 67 12 AV2 -0.12 23 21 22 10 AV2 +0.03 23 21 32 13 AVI -0.06 23 21 44 17 AV2 +0.06 23 21 44 12 AVI +0.60 23 23 40 15 AV3 +0.25 23 23 44 10 AV2 +0.10 23 23 49 11 AVI -0.81 23 23 53 12 AVI +0.60 23 23 53 18 AV2 -0.17 23 23 53 15 AV2 +0.27 23 23 53 27 AV3 -0.06 23 23 53 10 AV4 -0.17 23 23 58 9 AVI -0.16 23 23 58 19 AV2 -0.16 23 23 58 9 AV2 +0.39 23 23 58 30 AV3 +0.02 23 23 58 8 AV4 +0.31 23 24 46 15 AV3 +0.48 23 24 48 19 AV2 -0.51 23 24 48 16 AVI -0.47 23 24 53 10 AV3 +0.12 23 24 55 18 AVI +1.11 23 24 55 10 AVI -1.01 23 24 55 11 AV4 -3.30 23 24 56 17 AV4 -1.63 23 24 56 27 AV3 +0.73 23 24 56 24 AV3 -0.89 7

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 23 24 56 18 AV2 +1.26 23 24 56 20 AV2 -1.24 23 24 56 24 AVI -0.76 23 24 60 12 AV2 +0.26 23 25 44 10 AV2 +0.11 23 25 57 13 AV2 -0.16 23 25 57 12 AVI +0.30 23 26 44 16 AV4 -0.02 23 26 44 23 AV3 +0.10 23 26 44 25 AV2 +0.10 23 26 45 26 AVI -0.14 23 26 45 24 AV2 -0.04 23 26 45 16 AV4 +0.67 23 26 55 15 AV3 +0.04 23 26 55 22 AVI -1.11 23 26 55 26 AV2 +0.57 23 26 63 12 AV2 -0.04 23 26 63 11 AVI -1.03 23 27 49 16 AV3 -0.10 23 27 49 14 AV2 -0.21 23 27 51 20 AVI -0.96 23 27 51 36 AV2 +0.04 23 27 51 31 AV3 +0.02 23 27 51 27 AV4 -0.23 23 27 59 16 AV4 +0.43 23 27 59 17 AV3 +0.34 23 27 59 19 AV2 +0.39 23 27 59 27 AVI +0.39 23 27 63 34 AV2 +0.21 23 27 63 19 AV3 +0.35 23 27 63 14 AV4 -0.64 23 27 63 22 AVI +1.48 23 27 64 9 AV2 +0.08 23 27 64 14 AVI -0.76 23 27 65 19 AV4 +1.13 23 27 65 17 AV2 +0.01 23 27 65 18 AV3 -0.08 23 27 65 14 AV3 +0.42 23 28 45 19 AV2 -0.08 23 30 27 15 AV4 +0.02 23 30 35 37 AV2 -0.08 23 30 35 13 AV3 -0.29 23 30 35 19 AV4 +0.92 23 30 57 15 AVI +0.04 23 30 57 14 AV2 -0.14 23 31 63 14 AV2 -0.06 23 32 41 33 AV3 -0.19 8

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 23 32 41 16 AV2 +0.13 23 32 45 27 AV4 +0.59 23 32 45 37 AV3 +0.06 23 32 45 35 AV2 -0.13 23 32 45 26 AVI -0.04 23 32 45 8 AV4 -0.54 23 32 59 20 AV4 +0.34 23 32 59 28 AV3 +0.13 23 32 61 22 AV3 -0.22 23 32 61 17 AVI +0.34 23 33 26 20 AV3 -0.32 23 33 26 20 AV2 -0.04 23 33 26 11 AVI +0.06 23 33 50 14 AVI +0.31 23 33 51 10 AV2 +0.08 23 33 51 10 AV3 -0.02 23 33 52 16 AVI +0.08 23 34 38 12 AV3 -0.02 23 34 38 10 AV -0.02 23 34 41 13 AV3 -0.16 23 34 52 18 AV4 +0.08 23 34 54 13 AV4 +2.00 23 35 53 20 AV4 +0.06 23 35 53 16 AV3 -0.06 23 35 54 17 AV4 +0.06 23 36 44 22 AV4 -0.10 23 36 45 16 AV3 +0.11 23 36 45 17 AV4 -0.40 23 36 45 12 AV4 +0.63 23 36 58 22 AV4 +0.02 23 36 63 20 AV2 +0.02 23 36 63 17 AVI -0.63 23 36 63 11 AVI +0.80 23 36 66 12 AV4 -0.57 23 36 71 12 AV2 +0.16 23 37 42 19 AV3 +0.25 23 37 42 21 AV4 -0.35 23 37 45 26 AV4 -0.31 23 37 45 18 AV3 +0.08 23 37 52 32 AV4 +0.10 23 38 41 13 AV2 +0.06 23 38 46 13 AV3 +0.29 23 38 46 14 AV4 -0.06 23 38 47 25 AV3 +0.10 23 38 47 22 AV4 -0.02 23 38 48 32 AV3 -0.40 23 39 50 18 AVI -0.08 9

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 23 39 50 20 AV2 +0.34 23 39 51 13 AV3 +0.02 23 39 51 18 AVI +0.24 23 39 52 27 AVI +0.10 23 39 52 24 AV2 +0.02 23 39 58 26 AVI +0.06 23 39 58 30 AV2 +0.22 23 39 60 18 AV4 -0.46 23 39 60 11 AV3 +0.24 23 39 60 12 AV4 +0.10 23 40 42 33 AV2 +0.29 23 40 42 10 AVI +0.06 23 40 43 14 AV2 -0.18 23 40 43 17 AV3 +0.08 23 40 50 28 AV2 +0.12 23 40 50 13 AV3 +0.06 23 40 51 20 AVI -0.37 23 40 51 31 AV2 +0.06 23 40 51 15 AV3 +0.02 23 40 54 37 AVI +0.06 23 40 54 33 AV2 +0.10 23 40 54 18 AV3 +0.12 23 40 54 35 AV4 -1.19 23 40 56 16 AVI -0.12 23 40 56 12 AVI +0.34 23 40 62 12 AVI +0.08 23 40 66 23 AV2 +0.14 23 41 29 10 AV3 -0.24 23 41 52 22 AV3 -0.10 23 41 52 18 AV2 +0.02 23 41 55 29 AVI -0.63 23 41 55 13 AVI +0.59 23 41 55 9 AV2 -0.20 23 41 55 21 AV2 +0.21 23 41 60 17 AV2 +0.02 23 41 61 15 AVI +0.02 23 41 63 10 AV3 +0.04 23 41 65 16 AV2 +0.14 23 42 52 15 AVI +0.18 23 42 60 11 AV3 -0.04 23 42 65 22 AV2 +0.04 23 42 66 7 AV3 -0.04 23 42 66 6 AV2 +0.18 23 42 67 27 AVI +0.03 23 42 67 21 AV2 +0.22 23 42 67 35 AV3 -0.13 23 43 34 15 AV4 +0.04 10

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 23 43 63 18 AV2 +0.02 23 44 40 13 AV4 -0.04 23 45 58 21 AV4 -0.02 23 45 58 11 AV3 +0.02 24 15 33 15 AV3 -0.02 24 17 32 12 AV2 +0.12 24 17 32 18 AV3 -0.29 24 17 65 28 AV2 -0.14 24 17 65 10 AV3 -0.17 24 17 65 19 AV4 -1.31 24 17 78 13 AV2 +0.34 24 18 23 26 AV4 -0.21 24 18 55 14 AVI +0.14 24 18 55 15 AV2 +0.12 24 18 55 16 AV3 +0.18 24 18 55 12 AV4 +0.69 24 21 28 16 AVI -0.47 24 21 28 21 AV2 +0.10 24 21 28 25 AV3 -0.16 24 21 28 13 AV4 +0.52 24 21 30 11 AVI -0.07 24 21 30 19 AV2 +0.31 24 21 30 11 AV3 -0.86 24 21 30 16 AV3 +0.86 24 21 72 25 AV4 -0.59 24 22 72 32 AV2 +0.22 24 23 28 37 AV3 +0.16 24 23 33 16 AVI -0.03 24 23 33 29 AV2 -0.15 24 23 33 14 AV2 +0.22 24 23 33 28 AV3 +0.12 24 23 33 11 AV4 +0.20 24 23 53 19 AV4 -0.03 24 23 56 13 AV3 +0.46 24 23 56 21 AV4 +0.34 24 23 57 7 AVI +0.19 24 23 57 11 AV2 -0.38 24 23 57 10 AV2 +0.36 24 23 57 30 AV3 -0.58 24 23 57 33 AV4 -0.12 24 23 59 24 AVI +1.08 24 23 59 29 AV2 +0.33 24 23 59 16 AV3 -0.31 24 23 59 17 AV3 +0.35 24 23 62 12 AVI +0.87 24 23 62 21 AV2 -0.17 24 23 62 29 AV3 -0.14 11

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 24 23 62 18 AV4 +0.99 24 23 72 13 AV2 +0.20 24 23 72 30 AV4 -0.50 24 24 34 27 AV2 -0.02 24 24 34 25 AV3 +0.07 24 24 34 21 AV4 -0.73 24 24 35 18 AV3 +0.05 24 26 34 21 AVI +0.38 24 26 34 23 AV2 -0.04 24 26 34 20 AV3 +0.03 24 26 34 12 AV4 +0.51 24 26 58 22 AVI -0.30 24 26 58 29 AV2 +0.67 24 26 58 30 AV3 +0.43 24 26 58 18 AV4 +1.37 24 26 62 20 AV4 +0.89 24 26 67 20 AV2 +0.03 24 26 67 19 AVI +0.14 24 27 62 12 AVI +0.84 24 27 62 14 AV2 -0.63 24 27 68 34 AV3 -0.21 24 27 68 28 AV4 -0.07 24 28 59 23 AV2 +0.54 24 28 59 16 AVI +0.87 24 31 31 35 AV3 -0.02 24 31 48 7 AV3 +0.09 24 32 64 17 AV2 -0.05 24 33 29 19 AV2 +0.07 24 33 29 19 AVI +0.17 24 33 41 16 AVI -0.16 24 33 47 13 AV2 +0.76 24 33 47 46 AV3 -0.63 24 33 47 42 AV4 +0.13 24 33 48 12 AV2 +0.05 24 33 48 10 AVI +0.53 24 33 50 11 AV4 +0.16 24 33 50 6 AV3 +0.09 24 33 51 6 AVI -0.39 24 33 51 29 AV2 -0.47 24 33 51 6 AV3 -0.49 24 33 57 13 AVI +0.23 24 33 57 11 AV2 -0.14 24 33 57 17 AV3 +0.48 24 33 57 24 AV4 -0.02 24 33 58 26 AV3 -0.34 24 33 58 12 AV4 -0.69 24 33 65 13 AV3 -0.38 12

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 24 33 66 31 AV2 -0.05 24 33 66 7 AV3 -0.02 24 33 67 23 AV] +0.12 24 34 63 18 AV4 +0.36 24 34 63 32 AV3 +0.02 24 34 63 31 AV2 -0.02 24 34 65 27 AV4 +0.43 24 34 65 34 AV3 -0.34 24 36 63 26 AV3 -0.05 24 38 39 16 AV3 -0.22 24 38 39 23 AV4 -0.24 24 38 52 29 AV4 +0.31 24 38 52 16 AV3 -0.33 24 38 67 25 AV2 +0.07 24 38 67 34 AV3 -0.27 24 38 68 29 AV2 +0.14 24 38 68 36 AV3 -0.04 24 38 68 35 AV4 -0.04 24 39 42 13 AV4 +0.30 24 39 42 11 AV3 +0.21 24 39 49 10 AV3 +0.19 24 39 49 33 AV4 -0.28 24 39 65 34 AVI -0.04 24 39 65 19 AV2 +0.05 24 40 37 25 AV2 -0.22 24 40 37 31 AVI +0.15 24 40 56 24 AVI +0.17 24 40 56 19 AV2 -0.15 24 40 57 14 AV4 +0.12 24 41 35 13 AVI -0.02 24 41 35 12 AV2 -0.02 24 41 53 18 AVI -0.16 24 41 53 32 AV2 -0.02 24 41 53 31 AV3 -0.26 24 41 53 25 AV3 +0.29 24 41 53 26 AV4 +0.12 24 41 57 10 AVI +0.03 24 41 59 24 AV4 +0.22 24 42 53 16 AV2 +0.19 24 42 53 15 AVI +0.07 24 42 55 37 AVI -0.03 24 42 55 14 AV2 +0.07 24 44 35 6 AV2 +0.05 24 44 35 10 AV3 -0.04 24 44 35 27 AVI +0.11 24 44 55 11 AV4 +0.21 24 45 54 18 AVI +0.03 13

LR-N04-0066 Enclosure 4 Appendix 2 Cold Leg Thinning Percent through-wall Indications 14

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 21 43 31 19 OIC +0.30 21 34. 79 13 O1C -0.12 21 35 76 30 02C -0.06 21 44 59 3 03C -0.30 21 45 58 13 04C -0.25 21 46 48 28 OIC +0.36 22 6 2 6 01C +0.00 22 22 87 9 01C +0.13 22 32 78 22 02C +0.02 22 32 79 18 02C -0.06 22 32 79 16 03C -0.16 22 33 16 43 03C +0.04 22 33 76 1 O1C -0.22 22 33 77 55 O1C -0.04 22 34 17 33 O1C +0.34 22 34 18 9 03C -0.20 22 36 18 5 01C -0.11 22 36 18 12 02C -0.22 22 37 19 8 O1C -0.04 22 40 67 1 02C +0.19 22 41 62 25 02C +0.15 22 41 67 1 02C -0.09 22 42 41 38 02C +0.00 22 42 61 19 02C -0.09 22 42 62 19 02C -0.04 22 42 65 25 O1C +0.38 22 42 67 8 O1C +0.12 22 43 37 23 02C -0.06 22 43 58 13 02C +0.00 22 43 60 31 02C -0.08 22 43 61 7 02C -0.08 22 43 64 25 02C +0.04 22 43 65 27 02C +0.06 22 44 37 1 02C -0.15 22 44 38 16 O1C +0.04 22 44 39 10 OIC +0.15 22 44 46 9 02C +0.18 22 44 47 1 02C +0.18 22 44 56 35 02C +0.10 22 44 58 10 02C -0.17 22 44 59 15 02C -0.09 22 44 60 19 02C +0.06 22 45 41 2 02C +0.17 22 45 48 15 01C -0.09 22 45 50 17 02C +0.22 22 45 52 1 02C +0.20 22 45 53 6 02C +0.21 15

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 22 45 55 18 02C +0.15 22 45 56 1 02C +0.15 22 45 58 5 O1C +0.17 22 46 47 11 02C +0.06 22 46 51 1 02C +0.14 22 46 52 24 02C +0.23 22 46 53 12 02C -0.11 22 46 54 1 O1C +0.19 23 3 1 21 OIC -0.04 23 5 3 19 OIC +0.22 23 6 3 19 OIC +0.23 23 8 3 22 OIC +0.06 23 9 3 43 O1C +0.09 23 11 2 29 OIC +0.14 23 11 3 14 OIC -0.05 23 12 3 53 O1C +0.00 23 12 4 25 O1C -0.05 23 25 8 48 O1C +0.04 23 25 9 26 OIC +0.22 23 29 12 51 O1C +0.21 23 31 14 30 OIC -0.02 23 31 15 46 O1C -0.14 23 34 17 30 O1C +0.00 23 34 18 27 O1C +0.05 23 37 19 34 02C -0.14 23 44 33 48 O1C -0.06 23 44 36 17 O1C -0.17 24 2 94 13 O1C +0.12 24 25 87 19 OIC +0.02 24 27 83 1 O1C -0.19 24 28 83 8 OIC -0.12 24 28 85 21 O1C +0.18 24 29 82 37 O1C -0.06 24 30 83 25 O1C -0.16 24 31 78 1 02C +0.18 24 31 79 20 02C +0.16 24 31 82 23 O1C -0.02 24 33 78 33 02C +0.08 24 33 79 19 03C -0.18 24 33 79 46 O1C +0.06 24 33 79 15 O1C +0.34 24 36 76 5 OIC -0.04 24 37 75 9 O1C -0.08 24 38 23 26 02C +0.02 24 38 73 9 O1C -0.08 24 39 71 21 OIC -0.15 24 41 59 19 OIC -0.07 16

LR-N04-0066 Enclosure 4 SG Row Column %TW Location 24 42 33 43 02C -0.16 24 42 59 19 02C -0.05 24 43 34 29 03C -0.09 24 43 34 26 02C +0.02 24 43 35 43 02C +0.05 24 43 58 17 02C +0.26 24 43 59 19 02C +0.10 24 43 59 16 O1C -0.03 24 43 62 3 02C +0.21 24 43 62 12 O1C +0.16 24 44 36 3 03C +0.05 24 44 58 8 02C -0.24 24 44 58 32 OIC -0.02 24 44 59 21 02C +0.21 24 44 59 8 OIC -0.12 24 44 62 21 02C +0.00 24 45 57 18 O1C -0.23 24 45 59 3 02C -0.24 17

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