ML102440036

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Submittal of Steam Generator Examination Program Results 2010 Refueling Outage (2R19)
ML102440036
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 08/24/2010
From: Robert Walpole
Entergy Nuclear Northeast
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-1 0-079
Download: ML102440036 (17)


Text

EntertWl Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB Entergy L P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914)734-6710 Robert Walpole Manger Licensing NL-1 0-079 August 24, 2010 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Technical Specification 5.6.7 - IP2 Steam Generator Tube Inspection Report -

Spring 2010 Refueling Outage Indian Point Unit No. 2 Docket No. 50-247 License No. DPR-26

Dear Sir or Madam:

Technical Specification, 5.6.7, requires that a report be submitted to the NRC 180 days after the initial entry into Mode 4 following completion of a steam generator program inspection.

Enclosed as Attachment 1 is a report of the results of the Indian Point Unit 2 Steam Generator Examination Program conducted during the 2010 refueling outage, submitted pursuant to Technical Specification 5.6.7. Attachment 2 provides Steam Generator Landmark Information.

There are no new commitments contained in this letter. If you have any questions or require additional information, please contact me at 914-734-6710.

Sincerely, RW/mb cc: next page

  • 001

NL-10-079 Docket No. 50-247 Page 2 of 2 Attachments: 1. Steam Generator Examination Program Results, 2010 Refueling Outage (2R19)

2. Steam Generator Landmark Information cc: Mr. M. Dapas, Acting Regional Administrator, NRC Region 1 Mr. J. Boska, Senior Project Manager, NRC, NRR, DORL Mr. S. Aguilar, Material Control and Accounting Branch, NRC NRC Resident Inspectors Office, Indian Point Mr. Paul Eddy, NYS Dept. of Public Service Mr. Francis J. Murray, Jr., President and CEO, NYSERDA

ATTACHMENT 1 TO NL-10-079 Steam Generator Examination Program Results 2010 Refueling Outage (2R19)

Entergy Nuclear Operations, Inc.

INDIAN POINT NUCLEAR GENERATING UNIT 2 Docket No. 50-247

Attachment 1 NL-10-079 Docket No. 50-247 Page 1 of 11 Indian Point Unit 2 Steam Generator Examination Program Results 2010 Refueling Outage (2R19)

Examination Program Description At the time of the 2010 refueling outage (2R19) at Indian Point 2, the steam generators had accumulated approximately 83 effective full power months (EFPM) of operation since the first in-service inspection performed in 2002. The steam generators were replaced in 2000 and each have 3214 tubes made from thermally treated Alloy 600. The reactor coolant system operates with a hot leg temperature of 5990 F. Refueling outage 2R19 was the fourth of five refueling outages in the first inspection period of 120 EFPM as defined in section 5.5.7.d.2 of Technical Specifications and the last scheduled inspection of the period. The steam generator inspections were performed from March 21 through 26, 2010.

Indian Point 2 Steam Generator Primary Inspection Plan Outage Year EFPM since EFPM since Start Inspection Nominal SG of Inspection Period Inspection Replacement Period Scope 2R15 2002 20.6 N/A First ISI 100%

2R16 2004 42.7 22.1 First None 2R17 2006 59.3 38.7 Inspection 50%

2R18 2008 81.1 60.5 Period 120 None 2R19 2010 103.5 82.9 EFPM 50%

2R20 2012 126 est. 106 est. None 2R21 2014 149 est. 9 est. Second 50%

2R22 2016 172 est. 32 est. Inspection None 2R23 2018 195 est. 55 est. Period 90 50%

2R24 2020 217 est. 78 est. EFPM none The following information is provided as required in section 5.6.7 of Technical Specifications.

a. The scope of inspections performed on each SG,
b. Active degradation mechanisms found,
c. Nondestructive examination techniques utilized for each degradation mechanism,
d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,
e. Number of tubes plugged during the inspection outage for each active degradation mechanism,
f. Total number and percentage of tubes plugged to date,
g. The results of condition monitoring, including the results of tube pulls and in-situ testing, and
h. The effective plugging percentage for all plugging in each SG.

Attachment 1 NL-10-079 Docket No. 50-247 Page 2 of 11

2. Scope of Inspections Performed on each SG The primary side inspection consisted of bobbin and +PointTM Eddy current inspection as summarized in the table below. This inspection was the second of two SG tube inspections scheduled during the first inspection period for the replacement SGs. One hundred percent of the tube locations were inspected at least once between the 2R17 and 2R1 9 campaigns for those damage mechanisms considered existing or potential.

Tube wear at Anti-Vibration Bars (AVBs) is an existing damage mechanism. Tube wear at Tube Support Plates (TSPs), tube wear due to loose parts, and pitting are considered potential damage mechanisms.

Location Probe Extent Active tubes in rows 3 Bobbin 50% of tubes tube end to tube end and higher Tubes in rows 1 and 2 Bobbin 50% of straights sections, HL and CL

+PointTM 50% (same tubes as above) of row 1 and row 2 U-bends Previous wear Bobbin All indications Neighbors of previously Bobbin Adjacent tubes in the same row of tubes previously plugged tubes plugged for AVB wear.

Top of tubesheet +PointTM 9 Three tubes in from the annulus in the horizontal, Inspection for loose vertical and diagonal directions in the hot leg and parts detection and cold leg TTS (+/-3") in all SGs.

wear All row 1 & 2 tubes in the hot leg and cold leg TTS (+/-3") in all SGs.

& Location of loose parts observed in previous inspection and remaining in SGs.M')

All reported Bobbin +PointTM Special Interest Indications indications Dents/Dings +Point TM

  • 100% inspection of DNT/DNG >5V in HL, UB &

CL identified in 2R15 and 2R17

  • 20% sample of DNT/DNG between 2.0 and 4.99 V in HL, UB & CL identified in 2R15 and 2R17
  • Any new DNT/DNG >2V. New being defined below(2) which implies that it didn't meet the 2V threshold in 2R15 or 2R17 o DNR (Ding with rotation) will also be included in the sample plan

Attachment 1 NL-10-079 Docket No. 50-247 Page 3 of 11 Location Probe Extent

  • DNTs within the tubesheet are not required for inspection based upon PWSCC at BLG/OXP is not listed as potential for this inspection Top of Tubesheet hot +Point TM 20% sample TTS (+/-3") in all SGs not including leg sludge pile region peripheral loose parts inspection.
1. If historic loose part at TTS is not located, RPC plan should be expanded by two tubes in a bounding pattern to ensure part has not migrated.
2. "New" dents and dings as those which, by variances in repeatability of the eddy current process, not exhibit as amplitude response which is greater than the reporting threshold.

Scope Expansion: One tube in SG21 had AVB wear indications of 43 and 45% through wall prompting a full length bobbin inspection of an additional 20% of the tubes in that SG. This expansion resulted in 100% of the tubes in rows 22 through 45 being inspected, which are the rows most susceptible to AVB wear. In order to better characterize the AVB wear population for the purposes of the operational assessment, this expansion was also performed in SGs 22-24.

Summary of 2R19 SG Inspections (Number of Tests)

Inspection 21 SG 22 SG 23 SG 24 SG Total Bobbin - Full length bobbin 1617 1614 1612 1618 6457 (rows 3-45)

Bobbin - Hot leg & Cold leg straight section (rows 1 184 184 184 184 736

& 2)

Bobbin - Scope Expansion 670 675 677 665 2687 (Rows 22 and above)

Plus Pt.:- U-Bends (rows 1 92 92 92 92 368

& 2)

Plus Pt. - Hot leg TTS 1250 1212 1240 1238 4940 Plus Pt. - Cold leg TTS 696 700 699 696 2791 Plus Pt. - Special interest/ 65 72 303 DNT/DNG

3. Active Degradation Mechanisms Found The only tube degradation mechanism found during the SG inspection in 2R1 9 was tube wear at Anti-Vibration Bars (AVB).The largest wear indication was measured at 45%

throughwall in Steam Generator 21 tube Row 35 Column 49.

Attachment 1 NL-1 0-079 Docket No. 50-247 Page 4 of 11

4. Nondestructive Examination Techniques Utilized NDE Techniques used for Existing Degradation Mechanisms Detection Detection Sizing Sizing Probe ETSS Probe ETSS Wear at AVB supports Bobbin 96004.1 Bobbin 96004.1 NDE Techniques used for Potential Degradation Mechanisms Detection Detection Sizing Sizing Probe ETSS Probe ETSS Wear at tube support plates and Bobbin 96004.1 +Point 96910.1 flow distribution baffle plate Mechanical wear, and wear due Bobbin 27091.2 +Point 21998.1 to loose parts +Point 21998.1 Pitting Bobbin 96005.2 +Point 21998.1 NDE Techniques used for Information Purposes Only Detection Detection Sizing Sizing Probe ETSS Probe ETSS(1)

U-bend axial ODSCC +Point 21409.1 +Point 128431 U-bend circumferential ODSCC +Point 21410.1 +Point 128431 Axial ODSCC at expansion +Point 21409.1 +Point 128431 transitions Circumferential ODSCC at +Point 21410.1 +Point 128431 expansion transitions Axial ODSCC in dents/ding Bobbin 24013.1 +Point 128431

+Point 22841.3 Circumferential ODSCC in Bobbin 24013.1 +Point 128431 dents/ding +Point 22842.3 U-bend circumferential PWSCC +Point 96511.2 +Point 99997.1 PWSCC at expansion transitions +Point 20510.1 +Point 20510.1 Note (1): ODSCC circumferential cracking measurements are provided in EPRI TR-107197

Attachment 1 NL-10-079 Docket No. 50-247 Page 5 of 11

5. Location, Orientation and Measured Sizes of Service Induced Indications The only service induced indications were those attributed to wear at the Anti-Vibration Bars (AVBs). There were 207 indications of tube wear at the AVBs in 127 tubes. These indications are listed in Section 10 and summarized below.

Category SG 21 SG22 SG23 SG24 Total Tubes with Max. Indication <20%. 28 12 18 18 76 Tubes with Max. Indication 20-39% 8 5 7 5 25 Tubes with Max. Indication >=40% 1 0 0 0 1 Total Tubes with Wear 37 17 25 23 102

6. Number of Tubes Plugged During 2R1 9 for each Active Degradation Mechanism Nine tubes were plugged during 2R1 9 for tube wear at Anti-Vibration Bars (AVBs). One was required per Section 5.5.7(c) of Technical Specifications for wear equal to or greater than 40% through wall. The remaining eight were plugged preemptively to support two cycles of operation before the next scheduled steam generator tube inspection. The tube plugging list from 2R1 9 is below.

Indication Degradation SG Tube Location Depth DetT %TW Reason for Plugging AVI +0.00 16 AV2 +0.00 43 21 R35 C49 Wear > Repair Limit of 40%

AV3 +0.00 45 AV4 +0.00 11 AVI +0.07 15 21 R37 C65 AV2 +0.00 36 Preemptively for AVB wear AV3 -0.07 14 AVI +0.00 17 21 R35 C47 AV2 +0.00 25 Preemptively for AVB wear AV3 +0.05 34 AVI -0.03 13 AV2 -0.07 21 21 R45 C41 Preemptively for AVB wear AV4 +0.00 27 22 R39 C47 AV1 +0.00 15 Preemptively for AVB wear

Attachment 1 NL-10-079 Docket No. 50-247 Page 6 of 11 SGIndication Degradation Reason for Plugging Location Depth %TW AV2 +0.00 39 AV3 +0.00 32 AV4 +0.00 24 AVI +0.00 17 AV2 +0.00 23 22 R35 C56 AV3 +0.00 Preemptively Prepivl5o for AVB ABwawear AV4 +0.00 17 AV2 -0.05 27 23 R32 C36 AV3 -0.02 35 Preemptively for AVB wear AV4 -0.19 15 AV1 -0.05 17 AV2 -0.10 28 23 R37 C39 AV3 -0.14 Preemptively Prepivl4o for AVB ABwawear AV4 +0.14 11 AVl +0.00 28 24 R41 C37 AV2 +0.00 32 Preemptively for AVB wear AV3 +0.00 23

7. Total Number and Percentage of Tubes Plugged to Date SG 21 SG 22 SG 23 SG 24 Total Total Number of Tubes 3214 3214 3214 3214 12856 Number of Plugged Tubes 14 5 5 10 34

% of Tubes Plugged to Date 0.44% 0.16% 1 0.16% 0.31% 0.26%

8. Results of Condition Monitoring A Condition Monitoring assessment was performed, on a defect-specific basis, to demonstrate compliance with integrity criteria by the comparison of 2R1 9 NDE measurements with calculated burst and leakage integrity limits. Calculated integrity limits, including consideration for appropriate uncertainties, burst and leak analytical correlations, material properties, NDE technique, and analyst uncertainties were provided in the degradation assessment report. All indications in this inspection were below the calculated integrity limits and, therefore, met integrity requirements without further testing. Based upon the inspection results, all four steam generators were found to be in compliance with Condition Monitoring requirements.

Attachment 1 NL-10-079 Docket No. 50-247 Page 7 of 11 All measured tube degradation was less than the condition monitoring limit. No in-situ pressure testing was required nor were any tubes pulled for examination.

9. Effective Plugging Percentage for all Plugging in each SG Note: Since there are no sleeves installed and the safety analyses credit plugged tubes with the same value regardless of location, the effective tube plugging is equivalent to the percentage of tubes plugged.

SG 31 'SG 32 SG 33 SG 34 Total Total Number of Tubes 3214 3214 3214 3214 12856 Number of Sleeved Tubes 0 0 0 0 0 Number of Plugged Tubes 14 5 5 10 34

% of Tubes Plugged to Date 0.44% 0.16% 0.16% 0.31% 0.26%

10. Listing of Service Induced Indications SG Row Col Volts Ind Depth %TW Locn Inch 1 21 41 28 0.19 WEAR 11 AVI -0.27 21 33 29 0.35 WEAR 17 AV3 0.12 21 33 29 0.26 WEAR 14 AV4 0 21 33 33 0.52 WEAR 20 AV2 0.17 21 33 33 0.28 WEAR 13 AV3 0.02 21 33 34 1.54 WEAR 28 AVI 0 21 33 34 0.95 WEAR 22 AV2 0 21 33 34 0.98 WEAR 23 AV3 0 21 33 34 0.32 WEAR 12 AV4 0 21 37 36 0.26 WEAR 11 AVI -0.02 21 37 36 0.21 WEAR 10 AV2 -0.07 21 33 37 0.23 WEAR 13 AV2 -0.12 21 33 38 0.29 WEAR 12 AV2 -0.05 21 33 38 0.27 WEAR 12 AV3 -0.05 21 32 39 0.18 WEAR 10 AVI -0.2 21 32 39 0.19 WEAR 10 AV2 -0.12 21 41 39 0.3 WEAR 14 AV3 0.07 21 42 40 0.26 WEAR 10 AV2 0 21 45 41 0.26 WEAR 13 AVI -0.03 21 45 41 0.6 WEAR 21 AV2 -0.07 21 45 41 1.22 WEAR 30 AV3 -0.05 21 45 41 0.97 WEAR 27 AV4 0 21 45 43 0.26 WEAR 14 AV2 -0.07 21 33 46 0.32 WEAR 15 AVI -0.05 21 33 46 0.24 WEAR 12 AV2 0.02 21 30 47 0.53 WEAR 18 AVI 0 21 30 47 0.65 WEAR 20 AV2 0

Attachment 1 NL-10-079 Docket No. 50-247 Page 8 of 11 SG Row Col Volts Ind Depth %TW Locn *Inch 1 21 30 47 1.18 WEAR 27 AV3 0 21 30 47 0.4 WEAR 15 AV4 0 21 34 47 0.31 WEAR 13 AVI 0 21 34 47 0.51 WEAR 18 AV2 0 21 34 47 0.32 WEAR 13 AV3 0 21 35 47 0.48 WEAR 17 AVI 0 21 35 47 0.96 WEAR 25 AV2 0 21 35 47 1.88 WEAR 34 AV3 0.05 21 37 47 0.34 WEAR 14 AVI 0 21 37 47 0.32 WEAR 13 AV3 0 21 45 48 0.23 WEAR 13 AVI -0.11 21 35 49 0.43 WEAR 16 AVI 0 21 35 49 3.57 WEAR 43 AV2 0 21 35 49 4.23 WEAR 45 AV3 0 21 35 49 0.24 WEAR 11 AV4 0 21 30 50 0.24 WEAR 13 AV3 0 21 45 52 0.27 WEAR 14 AV3 -0.12 21 45 52 0.28 WEAR 15 AV4 -0.25 21 27 54 0.2 WEAR 12 AV4 0 21 37 54 0.36 WEAR 17 AV3 -0.2 21 31 57 0.24 WEAR 11 AV1 0 21 31 57 0.38 WEAR 15 AV2 0.29 21 31 57 0.3 WEAR 12 AV3 0.48 21 40 57 0.32 WEAR 13 AV3 0 21 40 57 0.35 WEAR 14 AV4 0 21 41 57 0.23 WEAR 10 AV4 0 21 34 60 0.58 WEAR 22 AV1 0 21 34 60 0.45 WEAR 19 AV2 0 21 34 60 0.39 WEAR 18 AV4 0 21 42 60 0.24 WEAR 13 AVI -0.19 21 27 63 0.25 WEAR 11 AVI -0.02 21 27 63 0.31 WEAR 13 AV2 -0.12 21 27 63 0.23 WEAR 10 AV4 -0.12 21 26 64 0.25 WEAR 14 AV2 0.23 21 26 64 0.6 WEAR 23 AV3 0.37 21 29 64 0.23 WEAR 13 AV2 0.16 21 36 65 0.23 WEAR 10 AV3 0 21 37 65 0.4 WEAR 15 AV1 0.07 21 37 65 2.35 WEAR 36 AV2 0 21 37 65 0.37 WEAR 14 AV3 -0.07 21 40 67 0.27 WEAR 14 AV3 -0.05 21 38 68 0.22 WEAR 13 AV2 0.05 21 35 70 0.27 WEAR 14 AV2 -0.21 21 35 70 0.27 WEAR 14 AV3 -0.15 21 35 70 0.2 WEAR 12 AV4 -0.05 21 32 71 0.23 WEAR 10 AV2 0.05

Attachment 1 NL-10-079 Docket No. 50-247 Page 9 of 11 SG Row Col Volts Ind Depth %TW Locn Inch 1 22 30 35 0.25 WEAR 11 AVI 0 22 30 35 0.29 WEAR 12 AV2 -0.22 22 43 38 0.26 WEAR 12 AVI -0.14 22 36 41 0.37 WEAR 15 AVI -0.08 22 36 44 0.63 WEAR 20 AVI 0 22 36 44 1.03 WEAR 27 AV2 -0.12 22 36 44 0.51 WEAR 18 AV2 0.07 22 36 44 0.39 WEAR 15 AV3 -0.24 22 39 47 0.52 WEAR 15 AVI 0 22 39 47 2.91 WEAR 39 AV2 0 22 39 47 1.86 WEAR 32 AV3 0 22 39 47 1.13 WEAR 24 AV4 0 22 38 49 0.44 WEAR 13 AVI 0 22 38 49 0.5 WEAR 15 AV2 0 22 41 52 0.45 WEAR 15 AV2 0 22 23 54 0.42 WEAR 16 AV1 0 22 23 54 0.32 WEAR 13 AV2 0 22 23 54 0.4 WEAR 15 AV3 0 22 23 54 0.7 WEAR 22 AV4 0 22 37 54 0.34 WEAR 12 AVI 0 22 38 55 0.35 WEAR 13 AVI -0.16 22 38 55 0.59 WEAR 19 AV2 -0.21 22 35 56 0.44 WEAR 17 AVI 0 22 35 56 0.75 WEAR 23 AV2 0 22 35 56 1.8 WEAR 35 AV3 0 22 35 56 0.47 WEAR 17 AV4 0 22 40 57 1.06 WEAR 26 AV2 0 22 40 57 0.37 WEAR 14 AV3 0 22 36 62 0.46 WEAR 15 AV2 -0.29 22 42 62 0.29 WEAR 11 AV4 0 22 36 64 0.31 WEAR 14 AVI -0.1 22 36 64 0.31 WEAR 14 AV2 -0.1 22 30 67 0.28 WEAR 13 AV2 -0.02 22 37 73 0.25 WEAR 12 AVI -0.07 22 37 73 0.28 WEAR 13 AV3 0 23 30 22 0.24 WEAR 12 AV2 -0.08 23 32 36 1.04 WEAR 27 AV2 -0.05 23 32 36 1.89 WEAR 35 AV3 -0.02 23 32 36 0.33 WEAR 15 AV4 -0.19 23 35 38 0.35 WEAR 15 AV2 -0.08 23 37 39 0.49 WEAR 17 AVI -0.05 23 37 39 1.13 WEAR 28 AV2 -0.1 23 37 39 1.73 WEAR 34 AV3 -0.14 23 37 39 0.26 WEAR 11 AV4 0.14 23 41 40 0.26 WEAR 11 AVI -0.12 23 41 40 1.16 WEAR 28 AV2 -0.07

Attachment 1 NL-10-079 Docket No. 50-247 Page 10 of 11 SG Row Col Volts Ind Depth %TW Locn InchI 23 41 40 0.47 WEAR 17 AV3 -0.12 23 41 40 0.5 WEAR 17 AV4 -0.14 23 29 41 0.26 WEAR 13 AV2 -0.32 23 35 41 0.26 WEAR 13 AV2 -0.05 23 41 43 0.34 WEAR 15 AVI -0.15 23 34 44 0.29 WEAR 12 AV2 0 23 35 46 0.39 WEAR 15 AV2 -0.05 23 35 46 0.41 WEAR 15 AV3 -0.12 23 45 46 0.24 WEAR 10 AV3 -0.02 23 40 47 0.24 WEAR 12 AV3 -0.12 23 40 53 0.47 WEAR 18 AV4 -0.11 23 29 55 0.32 WEAR 15 AVI -0.24 23 29 55 0.31 WEAR 14 AV2 -0.05 23 29 55 0.4 WEAR 17 AV4 -0.02 23 39 56 0.71 WEAR 22 AVI -0.17 23 39 56 0.24 WEAR 12 AV2 -0.2 23 39 56 0.99 WEAR 26 AV3 -0.07 23 40 58 0.51 WEAR 17 AV2 -0.07 23 40 58 0.58 WEAR 19 AV3 -0.07 23 35 59 0.32 WEAR 14 AV2 -0.22 23 35 59 0.73 WEAR 23 AV3 -0.37 23 39 59 0.46 WEAR 18 AVI -0.2 23 39 59 0.81 WEAR 24 AV3 0 23 36 60 0.31 WEAR 12 AVI -0.07 23 32 62 0.32 WEAR 13 AVI -0.12 23 34 62 0.35 WEAR 13 AVI 0 23 34 62 0.52 WEAR 18 AV2 0 23 34 62 0.34 WEAR 13 AV3 -0.1 23 38 62 0.46 WEAR 16 AV2 -0.29 23 38 62 0.29 WEAR 12 AV3 -0.1 23 32 63 0.23 WEAR 12 AVI -0.05 23 32 63 0.25 WEAR 13 AV2 -0.05 23 34 64 0.51 WEAR 17 AVI -0.12 23 34 64 0.5 WEAR 17 AV2 0.07 23 34 64 0.96 WEAR 25 AV3 0 23 34 64 0.41 WEAR 15 AV4 -0.19 23 41 64 0.23 WEAR 10 AVI -0.11 23 41 64 0.39 WEAR 14 AV2 -0.1 23 34 65 0.37 WEAR 16 AVI -0.05 23 34 65 0.38 WEAR 17 AV2 -0.15 23 34 65 0.37 WEAR 16 AV3 -0.07 23 34 65 0.28 WEAR 14 AV4 -0.07 24 24 8 0.33 WEAR 10 AV3 -0.23 24 37 25 0.39 WEAR 13 AV1 -0.12 24 37 25 0.27 WEAR 10 AV2 0 24 36 32 0.77 WEAR 20 AV2 0

Attachment 1 NL-10-079 Docket No. 50-247 Page 11 of 11 SG Row Col Volts Ind Depth %TW Locn Inchl 24 37 33 0.3 WEAR 11 AVI -0.12 24 41 37 1.42 WEAR 28 AV1 0 24 41 37 1.88 WEAR 32 AV2 0 24 41 37 1.03 WEAR 23 AV3 0 24 43 39 0.43 WEAR 14 AVI -0.19 24 44 39 0.27 WEAR 10 AV3 -0.05 24 45 41 0.43 WEAR 15 AV2 -0.1 24 45 41 0.53 WEAR 17 AV3 -0.19 24 32 45 0.43 WEAR 13 AVI 0 24 32 45 0.37 WEAR 12 AV2 0 24 32 45 0.3 WEAR 10 AV3 0 24 36 47 0.25 WEAR 10 AVI -0.17 24 34 59 0.84 WEAR 22 AVI -0.15 24 34 59 0.65 WEAR 19 AV2 -0.05 24 34 59 0.4 WEAR 13 AV3 -0.25 24 38 60 0.34 WEAR 12 AV3 -0.19 24 33 63 0.48 WEAR 16 AV2 -0.17 24 33 63 0.44 WEAR 15 AV3 0.27 24 33 63 0.45 WEAR 15 AV4 0 24 28 64 0.34 WEAR 13 AV3 0 24 28 64 0.34 WEAR 13 AV4 0 24 33 64 0.28 WEAR 11 AVI 0 24 33 64 0.41 WEAR 14 AV2 0 24 33 64 0.58 WEAR 18 AV3 -0.2 24 33 64 0.69 WEAR 20 AV4 0.07 24 34 65 0.27 WEAR 10 AV2 -0.05 24 32 69 0.41 WEAR 13 AV2 -0.25 24 32 69 0.42 WEAR 14 AV3 -0.3 24 33 69 .0.5 WEAR 16 AV3 -0.07 24 37 70 0.39 WEAR 14 AV2 0 24 33 71 0.43 WEAR 15 AVI 0 24 33 71 0.43 WEAR 15 AV2 0.02 24 33 71 0.41 WEAR 15 AV3 0 24 33 71 0.49 WEAR 17 AV4 -0.02 24 36 71 0.42 WEAR 15 AV1 0 24 36 71 0.81 WEAR 23 AV2 -0.36 24 36 71 0.26 WEAR 11 AV3 0 24 37 71 0.34 WEAR 13 AV3 -0.22 24 35 73 0.29 WEAR 12 AVI 0 24 35 73 0.36 WEAR 14 AV2 0 24 35 73 0.34 WEAR 13 AV3 0 24 35 73 0.31 WEAR 12 AV4 0.05

ATTACHMENT 2 TO NL-10-079 Steam Generator Landmark Information Entergy Nuclear Operations, Inc.

INDIAN POINT NUCLEAR GENERATING UNIT 2 Docket No. 50-247

Attachment 2 N L-10-079 Docket No. 50-247 Page 1 of 2 Indian Point 2 Steam Generator Tubesheet Map 0

Col No.

2 1--

4 5-6-- -

72----

10 ----

14 -1 16 1----

18 1 20 1--

22- 21----

24-cu 26-- - -

28 -2 -- -

3232-a) 34 -

N 3 N 36-Z 38-3 40- 41 42 43-44/ 45-48- 49 50 51 52- 53

>ý54- 55 56 5

._ 85 9-t-60*

>,62 6633 3:64 65

(" 66 67 6869 70 7 72 7 76; 75-78( 79 82 8 84 83 86 85 8887 9089 92 9

Attachment 2 NL-10-079 Docket No. 50-247 Page 2 of 2 Indian Point 2 Steam Generator Location Landmarks AV2 AV3 AV1 AV4 6H 6C 5H 5C 4H 4C 3H 3C 2H 2C 1H 1C BPH BPC TSH 2 TSC TEH TEC Westinghouse Model 44F Steam Generator Legend AV = Anti-Vibration Bar (AVB)

C = cold leg H = hot leg

  1. = support plate (TSP)

BP = baffle plate (FDB)

TS = tubesheet TE = tube end