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{{#Wiki_filter:SOUTHERN CALIFORNIA | {{#Wiki_filter:SOUTHERN CALIFORNIA EDISON0 An L:IS),O~N I V7TtR,*' g I'lI)\"'L Cotnpam* | ||
A 20004-018 (10/18/2010) | SONGS Unit 2 Return to Service Report ATTACHMENT 3 AREVA Document 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage Steam Generator Condition Monitoring Report | ||
AREVA AREVA NP Inc.Engineering Information Record Document No.: 51 -9180143 -001 SONGS Unit 3 February 2012 Leaker Outage -Steam Generator Condition Monitoring Report Supplier Status Stamp VPL 1814-AU651-MO 158 | [Proprietary Information Redacted] | ||
Drawings are reviewed and approved for arrangements and conformance to only. Approval does not retleve the submitter from the responrsibility of adequacy and suitability of design, materials, and/or equipment represented.APPROVED 2. APPROVED EXCEPT AS NOTED -Make changes and resubmit.I3. NOT APPROVED -Correct and resubmit for review. NOT for field use.APPROVAL: (PRINT SIGN I DATE)RE: E. GRIBBLE 10/01/12 FLS: Other SCE DE(123) 5 REV. 3 07111 | |||
A 20004-018 (10/18/2010) | |||
AREVA AREVA NP Inc. | |||
Engineering Information Record Document No.: 51 - 9180143 - 001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Supplier Status Stamp VPL 1814-AU651-MO 158 1M- 0-N/Al | |||
[DESIGN DOCUMENT XREFERENCE DOCUMENT-INFORMATION ONLY ORDER NO. 800918458A | |||
.IVIRPIOM MANUAL MFG MAY PROCEED: O]YES ONO Y]NIA STATUS - A status is required for design documents and is opbonal for reference documents. Drawings are reviewed and approved for arrangements and conformance to specif*ication only. Approval does not retleve the submitter from the responrsibility of adequacy and suitability of design, materials, and/or equipment represented. | |||
*-1. APPROVED | |||
: 2. APPROVED EXCEPT AS NOTED - Make changes and resubmit. | |||
I3.NOT APPROVED - Correct and resubmit for review. NOT for field use. | |||
APPROVAL: (PRINT SIGN I DATE) | |||
RE: E. GRIBBLE 10/01/12 FLS: | |||
Other SCE DE(123) 5 REV. 3 07111 | |||
==REFERENCE:== | ==REFERENCE:== | ||
S0123-XXIV-37.8.26 1814-AU651-MO158, REV. 0 Page 1 of 98 Page 1 of 98 | |||
A 20004-018 (10/18/2010) | |||
Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Safety Related? [K YES r] NO Does this document contain assumptions requiring verification? L] YES NO Does this document contain Customer Required Format? L YES g NO Signature Block PILP, R/LR, PageslSections Name and A/A-CRF, PreparedlReviewed/ | |||
Title/Discipline Signature AIA-CRI Date Approved or Comments t I I t L L d -L Note: P/LP designates Preparer (P), Lead Preparer (LP) | |||
R/LR designates Reviewer (R), Lead Reviewer (LR) | |||
A/A-CRF designates Approver (A), Approver of Customer Requested Format (A-CRF) | |||
A/A-CRI. designates Aipprover (A),Approver - Confirming Reviewer. Independence (A-CRI) | |||
Page 2 1814-AU651-M0158, REV. 0 Page 2 of 98 | |||
A 20004-018 (10/1 8/2010) | |||
Document No,: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Safety Related? K] YES r-D NO Does this document contain assumptions requiring verification? E-, YES [ NO Does this document contain Customer Required Format? D YES M NO Signature Block PILP, R/LR, PageslSections Name and AIA.CRF, Prepared/Reviewed/ | |||
Title/Discipline Signature NA-CRI Date Approved or Comments i 1 - I I. | |||
L | |||
-. ~ - *1 1- I. | |||
____ I ____ __ | |||
Note: P/LP designates Preparer (P), Lead Preparer (LP) | |||
I I _ _______ | |||
R/LR designates Reviewer (R), Lead Reviewer (LR) | |||
A/A-CRF designates Approver (A), Approver of Customer Requested Format (A-CRF) | |||
AIA-CRI-designates Approver (A), Approver - Confirming Reviewer-Independence (A-CRI) | |||
Page2. | |||
1814-AU651 -M01 58, REV. 0 Page 2 of 98 | |||
A 20004-018 (10/18/2010) | |||
Document No.: 51-9180143-001 | Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Record of Revision Revision Pages/Sections/ | ||
No. Paragraphs Changed Brief Description / Change Authorization 000 All Original Release 001 All Added Sections 2.0, 4.1, 4.2, 4.3, 7.2 and 7.3. Incorporated a significant number of editorial corrections and modifications throughout the document. | |||
Page 3 REV. 00 1814-AU651-M0158, REV. | |||
1814-AU651-MO158, Page 3of98 Page 3 of 98 Page 3 | |||
No. Paragraphs Changed Brief Description | |||
/ Change Authorization 000 All Original Release 001 All Added Sections 2.0, 4.1, 4.2, 4.3, 7.2 and 7.3. Incorporated a significant number of editorial corrections and modifications throughout the document.1814-AU651-M0158, REV. | |||
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table of Contents Page SIG NATURE BLOCK ................................................................................................................................ 2 RECO RD O F REVISIO N .......................................................................................................................... 3 LIST O F TABLES ..................................................................................................................................... 6 LIST O F FIG URES ................................................................................................................................... 7 1.0 PURPO SE ..................................................................................................................................... 9 2.0 ABBREVIATIO NS AND ACRO NYM S ..................................................................................... 10 3.0 SCO PE ........................................................................................................................................ 13 4.0 BACKG RO UND .......................................................................................................................... 13 4.1 Previous Operating Experience (OE) Related to Tube-to-Tube Wear ....................... 17 4.2 Previous Operating Experience Related to Tube-to-AVB Wear ..................... 18 4.3 Pre-Service Exam ination Results .............................................................................. 19 5.0 PERFO RMANCE CRITERIA ................................................................................................ 20 6.0 MID-CYCLE 16 O PERATIONAL LEAKAG E ......................................................................... 21 7.0 INSPECTIO N SUM MARY ...................................................................................................... 22 7.1 Eddy Current Inspections Perform ed ......................................................................... 23 7.2 Tube-to-Tube Wear Detection ................................................................................... 23 7.3 Tube-to-Tube Wear Sizing ......................................................................................... 24 7.4 Degradation Identified ................................................................................................ 25 7.5 Secondary Side Visual Exam ination Results .............................................................. 26 8.0 CONDITIO N MO NITO RING ASSESSM ENT .......................................................................... 50 8.1 Input Param eters ........................................................................................................ 51 8.2 Evaluation of Structural and Leakage Integrity ............................................................ 52 8.2.1 AVB Wear ................................................................................................. 52 8.2.2 TSP wear ................................................................................................... 55 8.2.3 Retainer Bar Wear ..................................................................................... 65 8.2.4 Tube-To-Tube Wear ................................................................................ 68 9.0 CO NDITIO N MO NITO RING CO NCLUSIO N.......................................................................... 75 | |||
............................................................................................................................ | ==10.0 REFERENCES== | ||
76 1814-AU651-M0158, REV. 0 Page 4 of 98 Page 4 A | ............................................................................................................................ 76 1814-AU651-M0158, REV. 0 Page 4 of 98 Page 4 | ||
Page A p | |||
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table of Contents (continued) | |||
Page A p pe n d ix A .............................................................................................................................................. 78 A p pe nd ix B .............................................................................................................................................. 89 Page 5 Page 5 Page 98 1814-AU651-MO1 58, REV. | |||
10 | 1814-AU651-MO158, REV. 0 0 5 ofof 98 Page 5 | ||
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report List of Tables Page TABLE 2-1: ABBREVIATIONS AND ACRONYMS ........................................................................... 10 TABLE 4-1: | |||
==SUMMARY== | ==SUMMARY== | ||
OF PRE-SERVICE INSPECTION RESULTS ............................................ | OF PRE-SERVICE INSPECTION RESULTS ............................................ 19 TABLE 7-1: STEAM GENERATOR TUBE INSPECTION SCOPE | ||
19 STEAM GENERATOR TUBE INSPECTION SCOPE | |||
==SUMMARY== | ==SUMMARY== | ||
................................. | ................................. 27 TABLE 7-2: WEAR INDICATION SUM MARY ................................................................................. 30 TABLE 7-3: PLU G G ING S UMMARY ................................................................................................. 31 TABLE 7-4: AVB WEAR DEPTHS (%TWV) (BOBBIN ETSS 96004.1) .............................................. 31 TABLE 7-5: TSP WEAR DEPTHS (%TW) (BOBBIN ETSS 96004.1) ............................................. 31 TABLE 7-6: RETAINER BAR WEAR (+POINT MT ETSS 27903.1) .................................................... 32 TABLE 7-7: TUBE-TO-TUBE WEAR (%TW) (+POINT M T | ||
27 | ETSS 27902.2) ....................................... 32 TABLE 8-1: SONGS UNIT-3 STEAM GENERATOR INPUT VALUES .............................................. 51 TABLE 8-2: EDDY CURRENT ETSS INPUT VALUES [51 .............................................................. 52 TABLE 8-3: INCOMPLETE PROOF TESTS OF TSP WEAR EXCEEDING CM LIMIT CURVE ..... 57 TABLE 8-4: IN-SITU TEST RESULT | ||
30 PLU G G | |||
31 AVB WEAR DEPTHS (%TWV) (BOBBIN ETSS 96004.1) .............................................. | |||
31 TSP WEAR DEPTHS (%TW) (BOBBIN ETSS 96004.1) ............................................. | |||
31 RETAINER BAR WEAR (+POINT | |||
32 TUBE-TO-TUBE WEAR (%TW) (+POINT T | |||
32 SONGS UNIT-3 STEAM GENERATOR INPUT VALUES .............................................. | |||
51 EDDY CURRENT ETSS INPUT VALUES [51 .............................................................. | |||
52 INCOMPLETE PROOF TESTS OF TSP WEAR EXCEEDING CM LIMIT CURVE ..... 57 IN-SITU TEST RESULT | |||
==SUMMARY== | ==SUMMARY== | ||
FOR TTW FLAWS .............................................. | FOR TTW FLAWS .............................................. 70 Page 6 of 98 Page 6 1814-AU651-MO158, REV. 00 1814-AU651-MO1 58, REV. Page 6 of 98 Page 6 | ||
70 | |||
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report List of Figures Page FIGURE 4-1: SONGS STEAM GENERATOR SUPPORT STRUCTURE LAYOUT .......................... 14 FIGURE 4-2: VIEW FROM ABOVE BUNDLE SHOWING RETAINER BAR LOCATIONS ............... 15 FIGURE 4-3: SKETCH SHOWING RETAINER/RETAINING BAR CONFIGURATION ..................... 16 FIGURE 7-1: UNIT 3 AVB WEAR DEPTH DISTRIBUTION (INDICATION COUNT) ....................... 33 FIGURE 7-2: COMPARISON OF UNIT 2 AND UNIT 3 AVB WEAR DEPTH DISTRIBUTION (IND ICA T IO N C O UNT) ......................................................................................................... 34 FIGURE 7-3: UNIT 3 TSP WEAR DEPTH DISTRIBUTION (INDICATION COUNT) ....................... 35 FIGURE 7-4: COMPARISON OF UNIT 2 AND UNIT 3 TSP WEAR DEPTH DISTRIBUTION (IND ICA T IO N C O UNT) ......................................................................................................... 36 FIGURE 7-5: UNIT 3 TTW DEPTH DISTRIBUTION (INDICATION COUNT) ................................... 37 FIG URE 7-6: SG 3E-088 AVB WEAR ............................................................................................... 38 FIG URE 7-7: SG 3E-089 AVB WEAR ............................................................................................... 39 FIGURE 7-8: SG 3E-088 TSP WEAR - HOT LEG ............................................................................ 40 FIGURE 7-9: SG 3E-088 TSP WEAR - COLD LEG ....................................................................... 41 FIGURE 7-10: SG 3E-089 TSP WEAR - HOT LEG .......................................................................... 42 FIGURE 7-11: SG 3E-089 TSP WEAR - COLD LEG ..................................................................... 43 FIGURE 7-12: SG 3E-088 RETAINER BAR W EAR .......................................................................... 44 FIGURE 7-13: SG 3E-089 RETAINER BAR W EAR .......................................................................... 45 FIGURE 7-14: SG 3E-088 TUBE-TO-TUBE WEAR .......................................................................... 46 FIGURE 7-15: SG 3E-089 TUBE-TO-TUBE WEAR .......................................................................... 47 FIGURE 7-16: SG 3E-088 TTW INDICATIONS WITH IN-SITU RESULTS ...................................... 48 FIGURE 7-17: SG 3E-089 TTW INDICATIONS WITH IN-SITU RESULTS ...................................... 49 FIGURE 8-1: CM LIMIT FOR AVB WEAR, BOTH SGS, ETSS 96004.1 .......................................... 54 FIGURE 8-2: CM LIMIT FOR TSP WEAR, BOTH SGS, ETSS 96004.1 ......................................... 58 FIGURE 8-3: CM LIMIT FOR SG 3E-088 TSP WEAR, ETSS 96910.1, STRUCTURAL DIMENSIONS59 FIGURE 8-4: CM LIMIT FOR SG 3E-089 TSP WEAR, ETSS 96910.1, STRUCTURAL DIMENSIONS60 FIGURE 8-5: IN-SITU TEST RESULTS FOR SG 3E-088 TSP WEAR, ETSS 96910.1, STRUCTURAL DIME NS IONS ....................................................................................................................... 61 FIGURE 8-6: IN-SITU TEST RESULTS FOR SG 3E-089 TSP WEAR, ETSS 96910.1, STRUCTURAL DIMENS IONS ....................................................................................................................... 62 FIGURE 8-7: AXIAL DEPTH PROFILE - SG 3E-088 R106 C78 07H-1 ............................................ 63 FIGURE 8-8: AXIAL POP-THROUGH LIMIT FOR TSP WEAR ...................................................... 64 1814-AU651-MO158, REV. 0 Page 7 of 98 Page 7 | |||
SONGS Unit 3 is a two loop Combustion Engineering (CE) PWR (Pressurized Water Reactor) plant which began commercial operation in 1984. The original CE steam generators were replaced in 2010-2011 with new SGs designed and manufactured by Mitsubishi Heavy Industries (MHI) [21]. The replacements, referred to by MHI as model 11 6TT-1, incorporate thermally treated Inconel Alloy 690 (I-690TT) tubing which has demonstrated, through laboratory testing and industry experience, superior resistance to stress corrosion cracking as compared with the 1-600 tubing used in the original SGs.Other design features include full tubesheet depth hydraulic tube expansion and seven stainless steel trefoil broach Tube Support Plates (TSPs); features chosen primarily to minimize the potential for tube corrosion. | A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report List of Figures (continued) | ||
Page FIGURE 8-9: CM LIMIT FOR RB W EAR, ETSS 27903.1 ................................................................ 67 FIGURE 8-10: CM LIMIT FOR SG 3E-088 TTW, ETSS 27902.2, STRUCTURAL DIMENSIONS ........ 71 FIGURE 8-11: CM LIMIT FOR SG 3E-089 TTW, ETSS 27902.2, STRUCTURAL DIMENSIONS ........ 72 FIGURE 8-12: IN-SITU TEST RESULTS FOR SG 3E-088 TTW, ETSS 27902.2, STRUCTURAL DIMENS IONS ....................................................................................................................... 73 FIGURE 8-13: IN-SITU TEST RESULTS FOR SG 3E-089 TTW, ETSS 27902.2, STRUCTURAL D IME NS IONS ....................................................................................................................... 74 1814-AU651-M01 58, REV. 0 Page 8 of 98 Page 8 | |||
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 1.0 PURPOSE In accordance with the EPRI Steam Generator Integrity Assessment Guidelines [2], a Condition Monitoring (CM) assessment must be performed at the conclusion of each steam generator eddy current examination. This process is described as "backward-looking," since its purpose is to determine whether Steam Generator (SG) integrity was maintained during the most recent operating period. It involves an evaluation of the as-found conditions of the SGs relative to established performance criteria for structural and leakage integrity. The performance criteria are defined in plant Technical Specifications [16] [17] and are based on NEI (Nuclear Energy Institute) 97-06 [1] (see Section 5.0 below). | |||
In late January 2012 during Cycle 16, SONGS (San Onofre Nuclear Generating Station) Unit 3 entered a forced outage due to a SG tube leak, prompting a comprehensive examination of the SGs. This report documents the required SG CM assessment following that examination, and concludes that the tube structural and leakage integrity performance criteria were not satisfied by Unit 3 during Cycle 16 operation. | |||
98 Page 9 REV. 00 1814-AU651-MOI 58, REV. | |||
1814-AU651-MO158, Page 99 of Page of 98 Page 9 | |||
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 2.0 ABBREVIATIONS AND ACRONYMS The following table provides a listing of abbreviations and acronyms used throughout this report. | |||
Table 2-1: Abbreviations and Acronyms Abbreviation or Definition Acronym 01C to 07C Tube Support Plate Designations for Cold Leg (7 Locations) 01 H to 07H Tube Support Plate Designations for Hot Leg (7 Locations) 2E-088 Unit 2 Steam Generator 88 2E-089 Unit 2 Steam Generator 89 3E-088 Unit 3 Steam Generator 88 3E-089 Unit 3 Steam Generator 89 3 NOPD 3 Times Normal Operating Pressure Differential 3AP 3 Times Normal Operating Pressure Differential ADI Absolute Drift Indication AILPC Accident Induced Leakage Performance Criterion ANO Arkansas Nuclear One ASME American Society of Mechanical Engineers AVB Anti-Vibration Bar B01 to B12 AVB Designations (12 Locations) | |||
BLG Bulge C Column CE Combustion Engineering CL or C/L Cold Leg CM Condition Monitoring DA Degradation Assessment DBE Design Basis Earthquake DNG Ding DNT Dent ECT Eddy Current Testing EFPD Effective Full Power Days EOC End of Operating Cycle EPRI Electric Power Research Institute ETSS Examination Technique Specification Sheet FOSAR Foreign Object Search and Retrieval GMD Geometric Distortion GPD Gallons per Day GPM Gallons per Minute 1814-AU651-M01 58, REV. 0 Page 10 of 98 Page 10 | |||
A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 2-1: Abbreviations and Acronyms Abbreviation or Definition Acronym HL or H/L Hot Leg INPO Institute of Nuclear Power Operators kHz Kilohertz KSI Thousand Pounds per Square Inch LER Licensee Event Report MBM Manufacturing Burnish Mark MHI Mitsubishi Heavy Industries MSLB Main Steam Line Break NDE Non Destructive Examination NEI Nuclear Energy Institute NN Nuclear Notification NOPD Normal Operating Pressure Differential NQI Non-Quantifiable Indication NRC Nuclear Regulatory Commission NSAL Nuclear Safety Advisory Letter OA Operational Assessment OE Operating Experience OTSG Once Through Steam Generator PDA Percent Degraded Area PLP Possible Loose Part POD Probability of Detection PRX Proximity Indication PSI Pounds per Square Inch PSIG Pounds per Square Inch Gage PST Pacific Standard Time PVN Permeability Variation PWR Pressurized Water Reactor QA Quality Assurance R Row RB Retainer Bar RCS Reactor Coolant System REPL Replacement ROLLED Rolled Plug Designation ROLLSTAB Rolled Plug with a Stabilizer RPC Rotating Probe Coil RSG Recirculating Steam Generator 1814-AU651-MO158, REV. 0 Page 11 of 98 Page 11 | |||
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 2-1: Abbreviations and Acronyms Abbreviation or Definition Acronym SCE Southern California Edison SG Steam Generator SIPC Structural Integrity Performance Criteria SL2 St. Lucie Unit 2 SLB Steam Line Break SONGS San Onofre Nuclear Generating Station SSA Secondary Side Anomaly SSI Secondary Side Inspection SVI Single Volumetric Indication TMI Three Mile Island TSP Tube Support Plate TTW Tube to Tube Wear TW Through Wall U3F16B Unit 3 Outage Designation UB U-bend Page 12 of 98 Page 12 1814-AU651-MO158, REV. 00 1814-AU651-MOI 58, REV. Page 12 of 98 Page 12 | |||
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 3.0 SCOPE This evaluation pertains to the SONGS Unit 3 replacement SGs, which are reactor coolant system components. The CM assessment is required to be completed prior to plant entry into Mode 4 during start up after a SG inspection. The operational assessment (OA) will be documented separately. | |||
==4.0 BACKGROUND== | |||
SONGS Unit 3 is a two loop Combustion Engineering (CE) PWR (Pressurized Water Reactor) plant which began commercial operation in 1984. The original CE steam generators were replaced in 2010-2011 with new SGs designed and manufactured by Mitsubishi Heavy Industries (MHI) [21]. The replacements, referred to by MHI as model 11 6TT-1, incorporate thermally treated Inconel Alloy 690 (I-690TT) tubing which has demonstrated, through laboratory testing and industry experience, superior resistance to stress corrosion cracking as compared with the 1-600 tubing used in the original SGs. | |||
Other design features include full tubesheet depth hydraulic tube expansion and seven stainless steel trefoil broach Tube Support Plates (TSPs); features chosen primarily to minimize the potential for tube corrosion. | |||
There are 9727 tubes in each SG, in 142 rows and 177 columns, in a triangular pitch arrangement. | There are 9727 tubes in each SG, in 142 rows and 177 columns, in a triangular pitch arrangement. | ||
The tubes in rows 1-13 are thermally stress-relieved to further minimize the potential for in-service stress corrosion cracking in the U-bends.The tube bundle U-bend region is supported by a floating Anti-Vibration Bar (AVB) structure consisting of six V-shaped AVBs between each tube column. The AVBs were fabricated from ASME (American Society of Mechanical Engineers) | The tubes in rows 1-13 are thermally stress-relieved to further minimize the potential for in-service stress corrosion cracking in the U-bends. | ||
SA-479, Type 405 ferritic stainless steel and are equipped with two Alloy 690 (ASME SB-168 UNS N06690) end caps. Each AVB end cap is welded to an Alloy 690 retaining bar. The retaining bars with AVBs attached are supported by twenty four chrome-plated Alloy 690 retainer bars that anchor the assembly to the tubes. Thirteen Alloy 690 bridges run perpendicular to the retaining bars, and hold the entire assembly together. | The tube bundle U-bend region is supported by a floating Anti-Vibration Bar (AVB) structure consisting of six V-shaped AVBs between each tube column. The AVBs were fabricated from ASME (American Society of Mechanical Engineers) SA-479, Type 405 ferritic stainless steel and are equipped with two Alloy 690 (ASME SB-168 UNS N06690) end caps. Each AVB end cap is welded to an Alloy 690 retaining bar. The retaining bars with AVBs attached are supported by twenty four chrome-plated Alloy 690 retainer bars that anchor the assembly to the tubes. Thirteen Alloy 690 bridges run perpendicular to the retaining bars, and hold the entire assembly together. The AVB structure is not attached to any steam generator component. Figure 4-1 illustrates the general layout of the tube support structures. | ||
The AVB structure is not attached to any steam generator component. | Figure 4-2 and Figure 4-3 illustrate the arrangements of the retainer bars and retaining bars. | ||
Figure 4-1 illustrates the general layout of the tube support structures. | of 98 Page 13 1814-AU651-MO158, REV. 0 1814-AU651-MOI 58, REV. 0 Page 13 Page 13 of 98 Page 13 | ||
Figure 4-2 and Figure 4-3 illustrate the arrangements of the retainer bars and retaining bars.1814-AU651- | |||
OE 34946 [18] was released. | A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 4-1: SONGS Steam Generator Support Structure Layout 98 of 98 Page 14 1814-AU651-MO158, REV. 0 1814-AU651-MQ1 58, REV. 0 Page 14 Page 14 of Page 14 | ||
This Operating Experience Report discusses experience at Three Mile Island Unit 1 (TMI-1). In July 2012, the NRC (Nuclear Regulatory Commission) released Information Notice 2012-07 [19]. This Information Notice contains information on the experience at TMI-1 as well as Oconee as well as ANO-1 (Arkansas Nuclear One -Unit 1).This section summarizes the experiences at these plants with OTSGs.TMI-1 completed replacement of its original OTSGs in 2010. The design of the OTSG differs from the recirculating SG design in that the tubes are straight. | |||
The tubes are supported by 15 tube support plates. The first inspection of the TMI-1 replacement SGs took place in the fall of 2011. During this examination, indications were detected on the absolute channel with no discernible response on the differential channel. The indications were designated as Absolute Drift Indications (ADIs). A comprehensive review of all of the ADIs identified tubes with long shallow wear signals between the eighth and ninth tube support plates. The indications were in adjacent tube combinations of either 2 or 3 tubes (the tube pattern is a triangular pitch). A more detailed investigation led to the conclusion that these wear indications were the result of tube-to-tube contact wear. The lengths ranged from 2 to 8 inches and from 1 to 21 percent through-wall. | A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 4-2: View From Above Bundle Showing Retainer Bar Locations | ||
As a result of the TMI-1 findings, and because TMI and ANO both have AREVA replacement steam generators, the licensee for Arkansas Nuclear One, Unit 1 (ANO-1) was notified. | -0 2E- 088 270 of 98 Page 15 REV. 00 1814-AU651-MO1 58, REV. | ||
Upon a review of previously recorded eddy current examination data, it was determined that ANO-1 also had similar indications of tube-to-tube wear. The depth and length of the ANO-1 indications were similar to those recorded at TM I-1 In the spring of 2012, the licensee for Oconee, also detected wear attributed to tube-to-tube contact in their Unit 3 replacement SGs. Because the design of the Oconee OTSG are built by BWI and are not the same as the TMI or ANO generators, the location of the tube-to-tube wear was different, but the characteristics were similar. The lengths ranged from 1 to 9 inches and the depths ranged up to 20 percent through-wall. | 1814-AU651-MO158, Page 15 Page 15 of 98 Page 15 | ||
A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 3: Sketch Showing Retainer/Retaining Bar Configuration 1814-AU651 -M01 58, REV. 0 Page 16 of 98 Page 16 | |||
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 4.1 Previous Operating Experience (OE) Related to Tube-to-Tube Wear Prior to the SONGS Unit 3 shutdown in January of 2012, the recent operating experience related to tub-to-tube wear was limited to once-through steam generators (OTSGs). In December 2011, INPO (Institute of Nuclear Power Operators) OE 34946 [18] was released. This Operating Experience Report discusses experience at Three Mile Island Unit 1 (TMI-1). In July 2012, the NRC (Nuclear Regulatory Commission) released Information Notice 2012-07 [19]. This Information Notice contains information on the experience at TMI-1 as well as Oconee as well as ANO-1 (Arkansas Nuclear One - Unit 1). | |||
This section summarizes the experiences at these plants with OTSGs. | |||
TMI-1 completed replacement of its original OTSGs in 2010. The design of the OTSG differs from the recirculating SG design in that the tubes are straight. The tubes are supported by 15 tube support plates. The first inspection of the TMI-1 replacement SGs took place in the fall of 2011. During this examination, indications were detected on the absolute channel with no discernible response on the differential channel. The indications were designated as Absolute Drift Indications (ADIs). A comprehensive review of all of the ADIs identified tubes with long shallow wear signals between the eighth and ninth tube support plates. The indications were in adjacent tube combinations of either 2 or 3 tubes (the tube pattern is a triangular pitch). A more detailed investigation led to the conclusion that these wear indications were the result of tube-to-tube contact wear. The lengths ranged from 2 to 8 inches and from 1 to 21 percent through-wall. | |||
As a result of the TMI-1 findings, and because TMI and ANO both have AREVA replacement steam generators, the licensee for Arkansas Nuclear One, Unit 1 (ANO-1) was notified. Upon a review of previously recorded eddy current examination data, it was determined that ANO-1 also had similar indications of tube-to-tube wear. The depth and length of the ANO-1 indications were similar to those recorded at TM I-1 In the spring of 2012, the licensee for Oconee, also detected wear attributed to tube-to-tube contact in their Unit 3 replacement SGs. Because the design of the Oconee OTSG are built by BWI and are not the same as the TMI or ANO generators, the location of the tube-to-tube wear was different, but the characteristics were similar. The lengths ranged from 1 to 9 inches and the depths ranged up to 20 percent through-wall. | |||
The severity of the replacement OTSG tube-to-tube wear was evaluated and was not found to compromise tube integrity. | The severity of the replacement OTSG tube-to-tube wear was evaluated and was not found to compromise tube integrity. | ||
1814-AU651-M0158, REV. 0 Page 17 of 98 Page 17 A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage -Steam Generator Condition Monitoring Report The combined experience from the above discussion demonstrated several significant points: " New or unexpected forms of degradation may be difficult to identify. | 1814-AU651-M0158, REV. 0 Page 17 of 98 Page 17 | ||
Robust inspection planning is an important part of identifying new degradation as well as properly characterizing known degradation." A comprehensive review of examination data from different perspectives is valuable. | |||
By considering the change in indications over time, responses to different channels or techniques, or the spatial distribution of the indications, important information may be found.* The reporting criteria are critical to proper identification of new or existing damage mechanisms." Comprehensive examination of new or replacement steam generators is necessary to ensure that performance is as expected.4.2 Previous Operating Experience Related to Tube-to-AVB Wear INPO OE 35359 [20] discusses the results of the first two inspections at St. Lucie Unit 2. The recirculating SGs at St. Lucie Unit 2 were replaced during 2007. During the Cycle 18 Refueling Outage (SL2-18, April 2009), eddy current testing of the replacement SGs reported over 5800 AVB wear indications in more than 2000 tubes. Fourteen tubes were plugged as a result of the wear indications. | A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report The combined experience from the above discussion demonstrated several significant points: | ||
None of the indications challenged the condition monitoring limits.Based on the high number of wear indications reported during the SL2-18 inspection, and to further establish growth rates, the St. Lucie Unit 2 SGs were examined again during the next refueling outage at SL2-19 in January 2011. Approximately 3000 new AVB wear indications were reported during the SL2-19 examination. | " New or unexpected forms of degradation may be difficult to identify. Robust inspection planning is an important part of identifying new degradation as well as properly characterizing known degradation. | ||
As a result of the SL2-19 inspection, an additional twenty-one (21) tubes were plugged, only one of which exceeded the Plant Technical Specification limit of > 40 %TW (throughwall). | " A comprehensive review of examination data from different perspectives is valuable. By considering the change in indications over time, responses to different channels or techniques, or the spatial distribution of the indications, important information may be found. | ||
None of the indications detected in SL2-19 challenged the condition monitoring limits.The OE reinforces the importance of inspecting replacement SGs with the bobbin coil at the end of the first cycle of operation, post-replacement. | * The reporting criteria are critical to proper identification of new or existing damage mechanisms. | ||
The diagnostic examinations performed with the +PointTM rotating coil concluded that the AVB wear indications could be flat or tapered, single or double sided.These wear characteristics are important to consider when selecting the proper depth-sizing technique(s). | " Comprehensive examination of new or replacement steam generators is necessary to ensure that performance is as expected. | ||
1814-AU651-MO158, REV. 0 Page 18 of 98 Page 18 A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage -Steam Generator Condition Monitoring Report 4.3 Pre-Service Examination Results The pre-service inspection of the Unit 3 replacement SGs was performed during June of 2010 at the MHI manufacturing facility in Kobe Japan. The examination consisted of 100 % bobbin coil inspection of all tubes (9727 tubes), 100 % inspection of the Hot Leg (HL) and Cold Leg (CL) Tubesheet region with the +PointTM probe (9727 tubes), and a 100 % inspection of the row 1-15 U-bend regions with the+PointTM probe (1314 tubes).No significant degradation was detected during this examination. | 4.2 Previous Operating Experience Related to Tube-to-AVB Wear INPO OE 35359 [20] discusses the results of the first two inspections at St. Lucie Unit 2. The recirculating SGs at St. Lucie Unit 2 were replaced during 2007. During the Cycle 18 Refueling Outage (SL2-18, April 2009), eddy current testing of the replacement SGs reported over 5800 AVB wear indications in more than 2000 tubes. Fourteen tubes were plugged as a result of the wear indications. | ||
There were a number of geometric type indications reported in each SG (dings, geometric distortions, proximity, bulge). The following table provides a count of the number of tubes and total number of indications for each Unit 3 SG.Table 4-1: Summary of Pre-Service Inspection Results SG 3E-088 SG 3E-089 Indication Code Tube Count Indication Count Tube Count Indication Count BLG (Bulge) 10 11 3 3 DNG (Ding) 364 395 706 831 GMD (Geometric 3 3 5 5 Distortion) | None of the indications challenged the condition monitoring limits. | ||
MBM (Manufacturing 0 0 0 0 Burnish Mark)NQI (Non-Quantifiable 0 0 0 0 Indication) | Based on the high number of wear indications reported during the SL2-18 inspection, and to further establish growth rates, the St. Lucie Unit 2 SGs were examined again during the next refueling outage at SL2-19 in January 2011. Approximately 3000 new AVB wear indications were reported during the SL2-19 examination. As a result of the SL2-19 inspection, an additional twenty-one (21) tubes were plugged, only one of which exceeded the Plant Technical Specification limit of > 40 %TW (throughwall). | ||
PLP (Possible 6 6 3 3 Loose Part)PRX (Proximity) 106 106 128 128 PVN (Permeability 0 0 0 0 Variation) | None of the indications detected in SL2-19 challenged the condition monitoring limits. | ||
The operational leakage criterion was taken from Section 3.4.13 [17]of the SONGS Technical Specifications. | The OE reinforces the importance of inspecting replacement SGs with the bobbin coil at the end of the first cycle of operation, post-replacement. The diagnostic examinations performed with the +PointTM rotating coil concluded that the AVB wear indications could be flat or tapered, single or double sided. | ||
These wear characteristics are important to consider when selecting the proper depth-sizing technique(s). | |||
All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cooldown, and all anticipated transients included in the design specification) and design basis accidents. | 1814-AU651-MO158, REV. 0 Page 18 of 98 Page 18 | ||
This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials. | |||
Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. | A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 4.3 Pre-Service Examination Results The pre-service inspection of the Unit 3 replacement SGs was performed during June of 2010 at the MHI manufacturing facility in Kobe Japan. The examination consisted of 100 % bobbin coil inspection of all tubes (9727 tubes), 100 % inspection of the Hot Leg (HL) and Cold Leg (CL) Tubesheet region with the +PointTM probe (9727 tubes), and a 100 % inspection of the row 1-15 U-bend regions with the | ||
In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.* Accident-Induced Leakage Performance Criterion: | +PointTM probe (1314 tubes). | ||
The primary to secondary accident-induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed 0.5 gpm per SG and 1 gpm through both SGs.* | No significant degradation was detected during this examination. There were a number of geometric type indications reported in each SG (dings, geometric distortions, proximity, bulge). The following table provides a count of the number of tubes and total number of indications for each Unit 3 SG. | ||
The leak location was confirmed by eddy current testing to be within the U-bend portion of the tube bundle, in the tube freespan. | Table 4-1: Summary of Pre-Service Inspection Results SG 3E-088 SG 3E-089 Indication Code Tube Count Indication Count Tube Count Indication Count BLG (Bulge) 10 11 3 3 DNG (Ding) 364 395 706 831 GMD (Geometric 3 3 5 5 Distortion) | ||
The tube degradation which resulted in the leak was tube-to-tube wear (TTW) caused by tube movement caused by fluid-elastic instability (FEI).Prior to the forced shutdown, the replaced Unit 3 SGs had been operated for approximately 338 EFPD (Effective Full Power Days) in fuel Cycle 16. The tube leak occurred in Unit 3 while Unit 2 was in the midst of a refueling outage. The utility designated the shutdown as U3F16B.1814-AU651-MO1 58, REV. | MBM (Manufacturing 0 0 0 0 Burnish Mark) | ||
NQI (Non-Quantifiable 0 0 0 0 Indication) | |||
PLP (Possible 6 6 3 3 Loose Part) | |||
PRX (Proximity) 106 106 128 128 PVN (Permeability 0 0 0 0 Variation) | |||
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 5.0 PERFORMANCE CRITERIA The SONGS Unit-3 performance criteria, based on NEI 97-06 [1], are shown below. The structural integrity and accident-induced leakage criteria were taken from Section 5.5.2.11 [16] from the SONGS Unit-3 Technical Specifications. The operational leakage criterion was taken from Section 3.4.13 [17] | |||
of the SONGS Technical Specifications. | |||
StructuralInte-grity Performance Criterion: All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cooldown, and all anticipated transients included in the design specification) and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads. | |||
* Accident-Induced Leakage Performance Criterion: The primary to secondary accident-induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed 0.5 gpm per SG and 1 gpm through both SGs. | |||
* OperationalLeakage Performance Criterion: "RCS operational leakage shall be limited to 150 gallons per day primary to secondary leakage through any one steam generator." | |||
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 6.0 MID-CYCLE 16 OPERATIONAL LEAKAGE On January 31, 2012 while operating under nominal conditions and at full power, a high radiation alarm from the condenser air ejector monitor indicated a tube leak in one of the two SGs. Following is a verbatim excerpt from the abstract section of the Licensee Event Report [15] describing the leakage and subsequent shutdown. | |||
"On 01/31/2012 at 1505 PST, SONGS Unit 3 was in Mode I operatingat 100 percent power, when a high radiationalarm from the condenserair ejector monitorindicated a tube leak in one of the two steam generators(SGs). A rapidpower reduction was commenced in accordance with plant procedures when the primaryto secondaryleak rate was determined to be greater than 75 gallons per day (gpd) with an increasingrate of leakage exceeding 30 gpd per hour. At 1731 PST, the operatorsmanually tripped the reactorat 35 percentpower as directed by procedure, resulting in actuationof the Reactor Protection System which is reportable." | |||
After cooling to Mode 5 and draining the primary coolant system to midloop, the leaking SG tube (SG 3E-088 R106 C78) was located by filling the secondary side of the SG and pressurizing to 80 psig with nitrogen. The leak location was confirmed by eddy current testing to be within the U-bend portion of the tube bundle, in the tube freespan. The tube degradation which resulted in the leak was tube-to-tube wear (TTW) caused by tube movement caused by fluid-elastic instability (FEI). | |||
Prior to the forced shutdown, the replaced Unit 3 SGs had been operated for approximately 338 EFPD (Effective Full Power Days) in fuel Cycle 16. The tube leak occurred in Unit 3 while Unit 2 was in the midst of a refueling outage. The utility designated the shutdown as U3F16B. | |||
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 7.0 INSPECTION | |||
==SUMMARY== | ==SUMMARY== | ||
The SONGS Unit 3 leaker outage work scope included the following inspection and testing activities in each of the two replacement SGs (SG 3E-088 and SG 3E-089): " Bobbin probe and rotating probe examinations using site validated ECT techniques | |||
[7] [13]" Secondary side visual examinations | The SONGS Unit 3 leaker outage work scope included the following inspection and testing activities in each of the two replacement SGs (SG 3E-088 and SG 3E-089): | ||
[22]* In-situ pressure testing [11]The initial examination following shutdown was a visual examination of the tubesheets of both SG 3E-088 and SG 3E-089 with the goal of identifying the tube(s) exhibiting signs of leakage. The leaking tube was visually identified as SG 3E-088 R-106 C-78. This tube and a two tube bounding pattern surrounding this tube (19 tubes total) were examined full length with the bobbin coil probe to determine the location of the leak and to define the type of degradation associated with the leak. Once this was determined, SCE decided on the initial inspection scope which included the following: | " Bobbin probe and rotating probe examinations using site validated ECT techniques [7] [13] | ||
" Secondary side visual examinations [22] | |||
* In-situ pressure testing [11] | |||
The initial examination following shutdown was a visual examination of the tubesheets of both SG 3E-088 and SG 3E-089 with the goal of identifying the tube(s) exhibiting signs of leakage. The leaking tube was visually identified as SG 3E-088 R-106 C-78. This tube and a two tube bounding pattern surrounding this tube (19 tubes total) were examined full length with the bobbin coil probe to determine the location of the leak and to define the type of degradation associated with the leak. Once this was determined, SCE decided on the initial inspection scope which included the following: | |||
* 100% bobbin coil probe (610 mil diameter) examination of the complete tube length in both Steam Generators. | * 100% bobbin coil probe (610 mil diameter) examination of the complete tube length in both Steam Generators. | ||
* 100% of all newly reported bobbin "I" codes, PLP, MBM, NQI, SSA, PRX and PVN locations with a rotating +PointTm/pancake coil probe.* 100% of all reported bobbin coil ding (DNG) and dent (DNT) locations measuring | * 100% of all newly reported bobbin "I" codes, PLP, MBM, NQI, SSA, PRX and PVN locations with a rotating +PointTm/pancake coil probe. | ||
>/= 2.0 volts with a rotating +PointTm/pancake coil probe.* All reported bobbin AVB %TW wear measuring | * 100% of all reported bobbin coil ding (DNG) and dent (DNT) locations measuring >/= 2.0 volts with a rotating +PointTm/pancake coil probe. | ||
>/= 25 %TW and all TSP %TW measuring | * All reported bobbin AVB %TW wear measuring >/= 25 %TW and all TSP %TW measuring >/= | ||
>/=30 %TW.Based on the examination results, a series of seven (7) examination expansions were performed to better characterize and bound the tube-to-tube wear damage.The subsections below describe findings that are relevant to the condition monitoring assessment. | 30 %TW. | ||
1814-AU651 - | Based on the examination results, a series of seven (7) examination expansions were performed to better characterize and bound the tube-to-tube wear damage. | ||
+PointTM probe.7.2 Tube-to-Tube Wear Detection At the start of the U3F16B inspection, the suspected leaking tube (SG 3E-088 R-106 C-78) along with 18 surrounding tubes were inspected with the bobbin coil probe to determine the axial location of the flaw responsible for the leak and to get an understanding as to what type of degradation was associated with the area of the tube with the through wall indication. | The subsections below describe findings that are relevant to the condition monitoring assessment. | ||
The degradation observed in the first nineteen tubes examined included AVB wear, deep wear at the TSP's (both hot and cold leg) and long wear type indications in the U-bend region which were eventually classified as Tube-to-Tube Wear (TTW). It was ultimately determined that the Tube-to-Tube Wear was the type of degradation responsible for the tube leak.The SONGS eddy current inspection procedure was updated to include enhanced screening of the U-bend area of the tube using the 100 kHz absolute channel with no voltage criteria for the reporting of small amplitude signals in the U-bend area of the tube. All analysts assigned to the SONGS inspection were made aware of the revised procedure and screening process and bobbin coil data was screened according to the new requirements set forth in the bobbin coil technique Examination Technique Specification Sheet (ETSS).The TTW indications were initially identified as NQI during the bobbin coil analysis with the "from-to" fields of the report line entry defining the overall length. No depth was assigned to the NQI bobbin coil entries. Over 300 NQI's were reported in the U-bend area of each SG. All of the tubes with reported U-bend NQI's were examined with the rotating 1-coil +PointTM probe through the complete region of the U-bend (07H to 07C). Most of the NQI's were confirmed to be degradation categorized as TTW and were reported as Single Volumetric Indications (SVI's).The TTW indications were very long and ranged in length from approximately 1.0" to 41.0" and in depth from 4% to 100% through wall. In many cases, the region of the tube with the TTW present would have two separate indications, one on the intrados of the tube and one on the extrados of the tube. In this case, two separate SVI's would be reported with measured depth and length. In addition to the tubes with reported bobbin coil NQI's, additional tubes surrounding the TTW region were also examined with the 1-coil rotating +PointTM probe. With these supplemental inspections, a total of 1375 contiguous tubes in each SG were examined the full length of the U-bend (07H-07C) specific to the detection of TTW. As a result of these inspections, 407 TTW SVI indications (161 tubes) were reported in SG 3E-088 and 416 TTW SVI indications (165 tubes) were reported in SG 3E-089.1814-AU651-M0158, REV. 0 Page 23 of 98 Page 23 A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage -Steam Generator Condition Monitoring Report The TTW indications were depth sized using EPRI ETSS 27902.2 even though it was known to be very conservative. | of 98 Page 22 1814-AU651-MO158, REV. 0 1814-AU651 -MOl 58, REV. 0 Page 22 Page 22 of 98 Page 22 | ||
Selected TTW SVI indications based on depth were line by line sized using the ETSS 27902.2 technique. | |||
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 7.1 Eddy Current Inspections Performed A summary of the total number of bobbin probe and rotating probe examinations performed during the current outage is provided in Table 7-1. As indicated in Table 7-1, the examination scope was expanded subsequent to completion of the initial plan. These expansions were implemented in some cases to further characterize identified degradation, and in other cases to further bound regions of potential degradation with the more sensitive +PointTM probe. | |||
7.2 Tube-to-Tube Wear Detection At the start of the U3F16B inspection, the suspected leaking tube (SG 3E-088 R-106 C-78) along with 18 surrounding tubes were inspected with the bobbin coil probe to determine the axial location of the flaw responsible for the leak and to get an understanding as to what type of degradation was associated with the area of the tube with the through wall indication. The degradation observed in the first nineteen tubes examined included AVB wear, deep wear at the TSP's (both hot and cold leg) and long wear type indications in the U-bend region which were eventually classified as Tube-to-Tube Wear (TTW). It was ultimately determined that the Tube-to-Tube Wear was the type of degradation responsible for the tube leak. | |||
The SONGS eddy current inspection procedure was updated to include enhanced screening of the U-bend area of the tube using the 100 kHz absolute channel with no voltage criteria for the reporting of small amplitude signals in the U-bend area of the tube. All analysts assigned to the SONGS inspection were made aware of the revised procedure and screening process and bobbin coil data was screened according to the new requirements set forth in the bobbin coil technique Examination Technique Specification Sheet (ETSS). | |||
The TTW indications were initially identified as NQI during the bobbin coil analysis with the "from-to" fields of the report line entry defining the overall length. No depth was assigned to the NQI bobbin coil entries. Over 300 NQI's were reported in the U-bend area of each SG. All of the tubes with reported U-bend NQI's were examined with the rotating 1-coil +PointTM probe through the complete region of the U-bend (07H to 07C). Most of the NQI's were confirmed to be degradation categorized as TTW and were reported as Single Volumetric Indications (SVI's). | |||
The TTW indications were very long and ranged in length from approximately 1.0" to 41.0" and in depth from 4% to 100% through wall. In many cases, the region of the tube with the TTW present would have two separate indications, one on the intrados of the tube and one on the extrados of the tube. In this case, two separate SVI's would be reported with measured depth and length. In addition to the tubes with reported bobbin coil NQI's, additional tubes surrounding the TTW region were also examined with the 1-coil rotating +PointTM probe. With these supplemental inspections, a total of 1375 contiguous tubes in each SG were examined the full length of the U-bend (07H-07C) specific to the detection of TTW. As a result of these inspections, 407 TTW SVI indications (161 tubes) were reported in SG 3E-088 and 416 TTW SVI indications (165 tubes) were reported in SG 3E-089. | |||
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report The TTW indications were depth sized using EPRI ETSS 27902.2 even though it was known to be very conservative. Selected TTW SVI indications based on depth were line by line sized using the ETSS 27902.2 technique. | |||
The Unit 3 experience in the detection and sizing of the TTW damage mechanism was reflected back into the Unit 2 examination which had just been completed. | The Unit 3 experience in the detection and sizing of the TTW damage mechanism was reflected back into the Unit 2 examination which had just been completed. | ||
7.3 Tube-to-Tube Wear Sizing Upon detection of tube-to-tube wear in the Unit 3 SG's, a determination was made that the most appropriate technique for sizing the wear was EPRI ETSS 27902.2 or 27902.5. However, with some initial review, it was apparent that the techniques produced very conservative depth estimates. | 7.3 Tube-to-Tube Wear Sizing Upon detection of tube-to-tube wear in the Unit 3 SG's, a determination was made that the most appropriate technique for sizing the wear was EPRI ETSS 27902.2 or 27902.5. However, with some initial review, it was apparent that the techniques produced very conservative depth estimates. The depth estimates reported for the deepest indications were near throughwall, however the tubes had maintained structural integrity at normal operating differential pressure (NODP). Using the actual tube operational performance, the throughwall depth values should have been around 80 %TW or smaller. | ||
The depth estimates reported for the deepest indications were near throughwall, however the tubes had maintained structural integrity at normal operating differential pressure (NODP). Using the actual tube operational performance, the throughwall depth values should have been around 80 %TW or smaller.Based on the best understanding of the tube-to-tube wear degradation morphology, a wear standard was designed with two machined wear flaws. Although the sample had only two separate flaws, the flaws were fabricated to a maximum depth of 81 % TWD. The length of the flaws made it possible to measure multiple discrete depth sizing grading units. On the basis of these multiple points, a polynomial function was developed to adjust the depth estimates. | Based on the best understanding of the tube-to-tube wear degradation morphology, a wear standard was designed with two machined wear flaws. Although the sample had only two separate flaws, the flaws were fabricated to a maximum depth of 81 % TWD. The length of the flaws made it possible to measure multiple discrete depth sizing grading units. On the basis of these multiple points, a polynomial function was developed to adjust the depth estimates. The revised technique was documented in Reference 13. | ||
The revised technique was documented in Reference 13.The actual flaw sizing was performed using the 27902.2 technique. | The actual flaw sizing was performed using the 27902.2 technique. Screening for selection of In-Situ pressure test candidates was based on the 27902.2 sizing data without the polynomial correction in Reference 13. This produced a conservative population for the In-Situ pressure testing. | ||
Screening for selection of In-Situ pressure test candidates was based on the 27902.2 sizing data without the polynomial correction in Reference | 1814-AU651-M01 58, REV. 0 Page 24 of 98 Page 24 | ||
* Anti-vibration bar (AVB) wear" Tube support plate (TSP) wear* Retainer bar (RB) wear* Tube-to-tube wear (TTW)Table 7-2 summarizes the number of identified degradation indications for each of the wear categories identified (AVB wear, TSP wear, RB wear, and TTW). A complete accounting of the number of tubes plugged and stabilized is provided in Table 7-3, and the plugging/stabilization lists for both SGs are provided in Appendices A and B. The plugging and stabilization information provided in this table and the appendices is current as of June 2012. Due to the ongoing SG recovery efforts, the plugging strategy and, hence, the plugging and stabilization information shown in this report may change prior to startup.Table 7-4 through Table 7-7 summarize the reported throughwall depths for each category. | A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 7.4 Degradation Identified The following tube wear categories (types) were identified during the current outage inspections: | ||
Because only four RB wear indications were identified, Table 7-6 lists these indications by tube number and provides the structurally equivalent length and depth, as well as the overall length and maximum depth of the wear. The structurally equivalent dimensions correspond to a rectangular flaw which would burst at the same pressure as the measured flaw; determined using the methods described in Section 5.1.5 of Reference 4.While AVB wear accounts for the largest number of indications and affected tubes, it is the least structurally challenging damage mechanism among those identified. | * Anti-vibration bar (AVB) wear | ||
Figure 7-1 provides histograms of reported AVB wear depths for both SGs which demonstrate that the vast majority of AVB wear was less than 25 %TW. Approximately 50% more AVB wear indications were identified in Unit 3 than in Unit 2; however, the depth distributions at both units were very similar (Figure 7-2). However, since Unit 3 operated for only part of a cycle, it must be concluded that AVB wear is progressing more aggressively at Unit 3 than at Unit 2.Figure 7-3 provides histograms of reported TSP wear depths for both SGs. This data illustrates that a significant number of tubes experienced TSP wear with throughwall depths in excess of the criteria for plugging. | " Tube support plate (TSP) wear | ||
This contrasts sharply with the relatively minor TSP wear identified at Unit 2 after a full cycle of operation (Figure 7-4).Only four tubes experienced RB wear but three of the four indications exceeded the 35 %TW plugging criteria.Figure 7-6 through Figure 7-17 provide tubesheet maps illustrating the locations of degradation reported in each SG. The AVB wear is most prevalent in the central region of the tubesheet matrix, in longer tube rows. The most severe TSP wear occurred in the same region as the TTW: a discrete centralized region of the bundle in higher row tubes (Figure 7-14 through Figure 7-17).1814-AU651-MO158, REV. 0 Page 25 of 98 Page 25 A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage -Steam Generator Condition Monitoring Report 7.5 Secondary Side Visual Examination Results Due to the wear degradation detected, significant secondary side inspections (SSI) were performed. | * Retainer bar (RB) wear | ||
The main purposes of these inspections were to provide confirmation of the eddy current results and obtain additional information to help with the root cause evaluation. | * Tube-to-tube wear (TTW) | ||
These visual inspections included the following: | Table 7-2 summarizes the number of identified degradation indications for each of the wear categories identified (AVB wear, TSP wear, RB wear, and TTW). A complete accounting of the number of tubes plugged and stabilized is provided in Table 7-3, and the plugging/stabilization lists for both SGs are provided in Appendices A and B. The plugging and stabilization information provided in this table and the appendices is current as of June 2012. Due to the ongoing SG recovery efforts, the plugging strategy and, hence, the plugging and stabilization information shown in this report may change prior to startup. | ||
: 1. All small diameter retainer bars.2. Retaining bars and AVB end caps associated with B04 and B09.3. 7 th tube support plate 4. Inner bundle passes at B01, B04, and B09.The retainer bars, retaining bars, and AVB end caps appeared to be structurally sound with no evidence of corrosion, broken welds, etc. The 7th TSP inspection revealed no unexpected or unusual conditions. | Table 7-4 through Table 7-7 summarize the reported throughwall depths for each category. Because only four RB wear indications were identified, Table 7-6 lists these indications by tube number and provides the structurally equivalent length and depth, as well as the overall length and maximum depth of the wear. The structurally equivalent dimensions correspond to a rectangular flaw which would burst at the same pressure as the measured flaw; determined using the methods described in Section 5.1.5 of Reference 4. | ||
The inner bundle passes in the U-bend were performed by going through the transition cone handhole above the 7 th TSP and entering the tube bundle at either 90 degree or 30 degree angles. The 90-degree inspections included many passes between Columns 73 and 87. These inspections showed some wear indications that extended slightly outside of the AVB intersection. | While AVB wear accounts for the largest number of indications and affected tubes, it is the least structurally challenging damage mechanism among those identified. | ||
This phenomenon was confirmed with eddy current. Additional passes were made between Columns 50 and 60. These inspections did not show any AVB wear outside the AVB intersections. | Figure 7-1 provides histograms of reported AVB wear depths for both SGs which demonstrate that the vast majority of AVB wear was less than 25 %TW. Approximately 50% more AVB wear indications were identified in Unit 3 than in Unit 2; however, the depth distributions at both units were very similar (Figure 7-2). However, since Unit 3 operated for only part of a cycle, it must be concluded that AVB wear is progressing more aggressively at Unit 3 than at Unit 2. | ||
Figure 7-3 provides histograms of reported TSP wear depths for both SGs. This data illustrates that a significant number of tubes experienced TSP wear with throughwall depths in excess of the criteria for plugging. This contrasts sharply with the relatively minor TSP wear identified at Unit 2 after a full cycle of operation (Figure 7-4). | |||
Only four tubes experienced RB wear but three of the four indications exceeded the 35 %TW plugging criteria. | |||
Figure 7-6 through Figure 7-17 provide tubesheet maps illustrating the locations of degradation reported in each SG. The AVB wear is most prevalent in the central region of the tubesheet matrix, in longer tube rows. The most severe TSP wear occurred in the same region as the TTW: a discrete centralized region of the bundle in higher row tubes (Figure 7-14 through Figure 7-17). | |||
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 7.5 Secondary Side Visual Examination Results Due to the wear degradation detected, significant secondary side inspections (SSI) were performed. | |||
The main purposes of these inspections were to provide confirmation of the eddy current results and obtain additional information to help with the root cause evaluation. These visual inspections included the following: | |||
: 1. All small diameter retainer bars. | |||
: 2. Retaining bars and AVB end caps associated with B04 and B09. | |||
: 3. 7 th tube support plate | |||
: 4. Inner bundle passes at B01, B04, and B09. | |||
The retainer bars, retaining bars, and AVB end caps appeared to be structurally sound with no evidence of corrosion, broken welds, etc. The 7th TSP inspection revealed no unexpected or unusual conditions. | |||
The inner bundle passes in the U-bend were performed by going through the transition cone handhole above the 7 th TSP and entering the tube bundle at either 90 degree or 30 degree angles. The 90-degree inspections included many passes between Columns 73 and 87. These inspections showed some wear indications that extended slightly outside of the AVB intersection. This phenomenon was confirmed with eddy current. Additional passes were made between Columns 50 and 60. These inspections did not show any AVB wear outside the AVB intersections. | |||
During the secondary side examination activities described above, no foreign objects were identified. | During the secondary side examination activities described above, no foreign objects were identified. | ||
In addition, during the eddy current inspection, no potential loose parts were identified. Therefore, no unscheduled secondary side FOSAR (Foreign Object Search and Retrieval) activities were required. | |||
1814-AU651-MO158, REV. 0 Page 26 of 98 Page 26 | |||
A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 7-1: Steam Generator Tube Inspection Scope Summary SCOPE DESCRIPTION SIG 3E-088 S/G 3E-089 Leg Exam Description Extents Analyzed Scope %Completed Analyzed Scope %Completed Hot I Cold 100 % Bobbin F/L TEH-TEC 9,727 9,727 100.00% 9,727 9,727 100.00% | |||
Hot HL Special Interest Various 283 283 100.00% 309 309 100.00% | |||
Cold CL Special Interest Vanous 218 218 100.00% 242 242 100.00% | |||
Hot UB Special Interest Various 16 16 100.00% 3 3 100.00% | |||
Cold UB Special Interest Various 5 5 100.00% 0 0 N/A Hot/Cold UB NQI Rows<70 07H-07C 19 19 100.00% 1 1 100.00% | |||
Hot HL UB NQI Rows>=70 07H-B07 150 150 100.00% 168 168 100.00% | |||
Cold CL UB NQI Rows>= | |||
Consequently, all of the TTW that exceeded the CM limit was subjected to in-situ pressure testing in an attempt to demonstrate CM criteria compliance. | Consequently, all of the TTW that exceeded the CM limit was subjected to in-situ pressure testing in an attempt to demonstrate CM criteria compliance. | ||
8.2.4.1 In-Situ Test Results Figure 8-12 and Figure 8-13 summarize the results of in-situ testing of TTW indications in each SG. All tested TTW wear in SG 3E-089 satisfied the structural integrity and accident leakage performance criteria. | 8.2.4.1 In-Situ Test Results Figure 8-12 and Figure 8-13 summarize the results of in-situ testing of TTW indications in each SG. All tested TTW wear in SG 3E-089 satisfied the structural integrity and accident leakage performance criteria. In SG 3E-088 three TTW indications failed both the AILPC and SIPC, and five flaws passed the AILPC but failed the SIPC. These results are summarized in Table 8-4. | ||
In SG 3E-088 three TTW indications failed both the AILPC and SIPC, and five flaws passed the AILPC but failed the SIPC. These results are summarized in Table 8-4.In addition, four TTW indications predicted analytically to fail the SIPC, could not be tested to the required pressure levels because more limiting TTW in the same tube failed below the target pressure, terminating the test. These indications are depicted in Figure 8-12 as "Incomplete" (above the CM curve). In the absence of a successful in-situ pressure test, these must be considered to be SIPC failures (see Table 8-4).1814-AU651-MO158, REV. 0 Page 68 of 98 Page 68 A | In addition, four TTW indications predicted analytically to fail the SIPC, could not be tested to the required pressure levels because more limiting TTW in the same tube failed below the target pressure, terminating the test. These indications are depicted in Figure 8-12 as "Incomplete" (above the CM curve). In the absence of a successful in-situ pressure test, these must be considered to be SIPC failures (see Table 8-4). | ||
This flaw is labeled in Table 8-4 as "In Situ Test Indeterminate" due to the failure of a TTW flaw in the same tube at a pressure below the target AILPC pressure. | 1814-AU651-MO158, REV. 0 Page 68 of 98 Page 68 | ||
The maximum measured throughwall depth of this flaw was 99%TW and the structural length exceeded 2 inches.From Figure 8-8 it must be concluded that this flaw does not satisfy the AILPC.In summary, 12 TTW flaws in eight tubes failed to satisfy the structural integrity performance criteria, and four of the flaws (in three tubes) failed to satisfy the accident-induced leakage performance criteria.8.2.4.2 Eddy Current Sizing Following the detection of TTW, application of ETSS 27902.2 was site validated | |||
[13]. This was done by building a test specimen with flaws similar to the TTW flaws observed at SONGS. Many depth estimates were made with +PointTM using ETSS 27902.2. These results were compared with the actual depths of the wear flaws. This comparison showed that ETSS 27902.2 conservatively overestimated the depths across the entire range of depths tested (from 5%TW to 81 %TW). The flaws in the test specimen that measured >70%TW were overestimated by an average of 17%TW.The conservatism in the sizing technique as discussed above is supported by the in-situ test results. A cursory review of the best estimate burst pressures for the tubes that were in-situ pressure tested shows that approximately 45 failures would have been expected if the NDE sizing was accurate.Because there were only eight tubes that failed in-situ pressure testing, the measured depths are assumed to be overestimated using ETSS 27902.2. Again, this is consistent with the site validation work which showed that ETSS 27902.2 consistently overestimated the depths.1814-AU651-MO158, REV. 0 Page 69 of 98 Page 69 A | A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report For one TTW flaw a determination could not be made based upon in-situ test result as to whether the AILPC was satisfied. This flaw is labeled in Table 8-4 as "In Situ Test Indeterminate" due to the failure of a TTW flaw in the same tube at a pressure below the target AILPC pressure. The maximum measured throughwall depth of this flaw was 99%TW and the structural length exceeded 2 inches. | ||
From Figure 8-8 it must be concluded that this flaw does not satisfy the AILPC. | |||
SG 3E-088 98 80 74.4 3.28 B02 4886 No Yes NA NA SG 3E-088 99 81 71.8 4.17 B02 5026 No Yes NA NA 79.7 2.8 B02-1 No Yes NA NA SG 3E-088 100 80 4732 52.6 3.33 B02-2 Not Yes NA NA 74.3 3.86 B02-1 No Yes NA NA SG 3E-088 101 81 4889 50.7 5.02 B02-2 Not Yes NA NA SG 3E-088 102 78 98.7 2.63 B02 3268 No No NA NA 91.7 1.06 B03 No No NA NA SG 3E-088 104 78 3180 In-Situ Test 92.6 2.12 802 Not Indeterminatef 99 No SG 3E-088 106 78 91.7 3.05 B03 2874 No No NA NA 78.8 3.84 B02 No Yes NA NA SG 3E-088 107 77 5160 47.5 3.22 B08 No* Yes NA NA t Failure of SIPC predicted analytically, not proven otherwise by in-situ test.* AILPC failed at the B03 TTW flaw. Test inconclusive for this flaw. | In summary, 12 TTW flaws in eight tubes failed to satisfy the structural integrity performance criteria, and four of the flaws (in three tubes) failed to satisfy the accident-induced leakage performance criteria. | ||
8.2.4.2 Eddy Current Sizing Following the detection of TTW, application of ETSS 27902.2 was site validated [13]. This was done by building a test specimen with flaws similar to the TTW flaws observed at SONGS. Many depth estimates were made with +PointTM using ETSS 27902.2. These results were compared with the actual depths of the wear flaws. This comparison showed that ETSS 27902.2 conservatively overestimated the depths across the entire range of depths tested (from 5%TW to 81 %TW). The flaws in the test specimen that measured >70%TW were overestimated by an average of 17%TW. | |||
The conservatism in the sizing technique as discussed above is supported by the in-situ test results. A cursory review of the best estimate burst pressures for the tubes that were in-situ pressure tested shows that approximately 45 failures would have been expected if the NDE sizing was accurate. | |||
Because there were only eight tubes that failed in-situ pressure testing, the measured depths are assumed to be overestimated using ETSS 27902.2. Again, this is consistent with the site validation work which showed that ETSS 27902.2 consistently overestimated the depths. | |||
1814-AU651-MO158, REV. 0 Page 69 of 98 Page 69 | |||
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 8-4: In-Situ Test Result Summary for TTW Flaws Test SIPC AILPC Maximum Structural StructuralStucualStutual . | |||
Ts at Pressure ICAL Success Success Mxmm Measured AILPC ALP SG Row Col GDepth Ro Co Length DeTh) Length Location Loca Prsuea Termination ucsIn-During ucs During In-Situ esrd Depth Success Succss | |||
(%Tt (in.) (psi) Situ Test? Test? (%TW) Analytically? | |||
SG 3E-088 98 80 74.4 3.28 B02 4886 No Yes NA NA SG 3E-088 99 81 71.8 4.17 B02 5026 No Yes NA NA 79.7 2.8 B02-1 No Yes NA NA SG 3E-088 100 80 4732 52.6 3.33 B02-2 Not Yes NA NA 74.3 3.86 B02-1 No Yes NA NA SG 3E-088 101 81 4889 50.7 5.02 B02-2 Not Yes NA NA SG 3E-088 102 78 98.7 2.63 B02 3268 No No NA NA 91.7 1.06 B03 No No NA NA SG 3E-088 104 78 3180 In-Situ Test 92.6 2.12 802 Not Indeterminatef 99 No SG 3E-088 106 78 91.7 3.05 B03 2874 No No NA NA 78.8 3.84 B02 No Yes NA NA SG 3E-088 107 77 5160 47.5 3.22 B08 No* Yes NA NA t Failure of SIPC predicted analytically, not proven otherwise by in-situ test. Failure assumed. | |||
* AILPC failed at the B03 TTW flaw. Test inconclusive for this flaw. | |||
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-10: CM Limit for SG 3E-088 TTW, ETSS 27902.2, Structural Dimensions 1nn I | |||
90 80 | |||
* 70o CL 60 ty 50 -~~ ~ -~* - *.** | |||
0j AAA AALA AAA AA 40 4 A | |||
A &A A A A A AA A A A A | |||
A 30 20 A - - - CM Limit | |||
* Analytical CM Failure | |||
* Analytical CM Success 10 0 | |||
0 1 2 3 4 5 6 7 8 9 Structurally Equivalent Length (Inches) | |||
Page 71 1814-AU651-MO1 58, REV. | |||
1814-AU651-MO158, REV. 00 Page 71 Page of 98 71 of 98 Page 71 | |||
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-11: CM Limit for SG 3E-089 TTW, ETSS 27902.2, Structural Dimensions 100 90 80 70 II L | |||
0 C 60 ICr 50* | |||
: a. A,,, | |||
40 AA.h A A A W-AA A A4 A-A A Ak 4 30 | |||
- - - CM Limit 20 41 | |||
* Analytical CM Failure A Analytical CM Success I | |||
10 0 +/-- | |||
0 1 2 3 4 5 6 7 8 9 Structurally Equivalent Length (inches) | |||
Page 72 1814-AU651-MO158, REV. 0 1814-AU651-MO1 58, REV. 0 Page 72 Page of 98 72 of 98 Page 72 | |||
==10.0 REFERENCES== | A Document No.: 51-9180143-001 ARE VA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-12: In-Situ Test Results for SG 3E-088 TTW, ETSS 27902.2, Structural Dimensions 100 | ||
: 1. NEI 97-06, "SG Program Guidelines," Rev. 3, January 2011.2. EPRI Report 1019038, "SG Integrity Assessment Guidelines: | * 102-78 | ||
Revision 3", November 2009.3. EPRI Report 1014983, "Steam Generator In Situ Pressure Test Guidelines, Revision 3", August 2007.4. EPRI Report 1019037 "Steam Generator Degradation Specific Management Flaw Handbook", Revision 1, with error correction in J. Benson email dated 3/30/2012, December 2009.5. EPRI, SG Management Project, "sgmp.epriq.com." 6. AREVA Document 51-9176667-001, "SONGS 2C17 & 3C17 Steam Generator Degradation Assessment." 7. AREVA Document 51-9104383-002, "SONGS Units 2 & 3 Replacement Steam Generator Eddy Current Technique Validation." 8. AREVA Document 32-5033045-002, "Mathcad Implementation of SG Flaw Handbook Equations for Integrity Assessment". | -- - CM Limit 90 + 104-78 | ||
: 9. *Matheny, Southern California Edison, "Numerical Values for the SG OAs, SONGS Units 2 and 3", February 8, 2012 10. *SONGS Unit 3 Replacement Steam Generator Receipt Inspection QA Document Review Package 11. AREVA Document 51-9179808-000, "In-Situ Pressure Test Results for SONGS U3F16B Outage." 12. *MHI, "SONGS Unit 2 & 3 RSGs, Regulatory Guide 1.121 Analysis," S023-617-1-C1262, Rev. 4 13. AREVA Document 51-9177744-000 "Site Validation of EPRI Sizing ETSS for Tube-Tube Wear in SONGS Steam Generators". | * 104-78 + 106-78 | ||
* Pass | |||
* Failed 80 IIncomplete | |||
+ 100-80 | |||
* 107-77 | |||
+98-8r101-81**99-81 70 CL | |||
+ | |||
60 C. | |||
0 Ca t0 50 | |||
+ | |||
0* | |||
40 30 20 "Incomplete" = Flaw is in a tube that has been tested and a largerflaw failed 10 before full test pressurecould be reached 0 | |||
0 1 2 3 4 5 6 7 8 9 Structurally Equivalent Length (inches) | |||
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-13: In-Situ Test Results for SG 3E-089 TTW, ETSS 27902.2, Structural Dimensions 100 90 - CM Limit | |||
* Pass 80 Failed 0 Incomplete 70 l CL 60 Cr 50 | |||
. . . . .. . .. . . * - - -e - | |||
w ~4 4, 4 40 30 U) | |||
LU -i 10 0 | |||
0 1 2 3 4 5 6 7 8 9 Structurally Equivalent Length (inches) 1814-AU651-M10158, REV. 0 Page 74 of 98 Page 74 | |||
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 9.0 CONDITION MONITORING CONCLUSION This condition monitoring assessment has evaluated all SG tube degradation detected during the Unit 3 2012 leaker outage against the three SONGS Technical Specification performance criteria. Through a combination of eddy current inspection, analytical evaluation, in-situ pressure testing, and operational leakage monitoring, the following conclusions are drawn: | |||
: 1) Despite the fact that operational SG tube leakage resulted in a forced outage, the leak rate remained below the Technical Specification limit (150 GPD); therefore the operational leakage integrity performance criterion was met. | |||
: 2) A total of eight tubes failed to meet the structural integrity performance criterion due to tube-to-tube wear and tube support plate wear. | |||
: 3) A total of three tubes failed to meet the accident-induced leakage performance criterion due to tube-to-tube wear and tube support plate wear. | |||
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A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report | |||
==10.0 REFERENCES== | |||
: 1. NEI 97-06, "SG Program Guidelines," Rev. 3, January 2011. | |||
: 2. EPRI Report 1019038, "SG Integrity Assessment Guidelines: Revision 3", November 2009. | |||
: 3. EPRI Report 1014983, "Steam Generator In Situ Pressure Test Guidelines, Revision 3", August 2007. | |||
: 4. EPRI Report 1019037 "Steam Generator Degradation Specific Management Flaw Handbook", | |||
Revision 1, with error correction in J. Benson email dated 3/30/2012, December 2009. | |||
: 5. EPRI, SG Management Project, "sgmp.epriq.com." | |||
: 6. AREVA Document 51-9176667-001, "SONGS 2C17 & 3C17 Steam Generator Degradation Assessment." | |||
: 7. AREVA Document 51-9104383-002, "SONGS Units 2 & 3 Replacement Steam Generator Eddy Current Technique Validation." | |||
: 8. AREVA Document 32-5033045-002, "Mathcad Implementation of SG Flaw Handbook Equations for Integrity Assessment". | |||
: 9. *Matheny, Southern California Edison, "Numerical Values for the SG OAs, SONGS Units 2 and 3", February 8, 2012 | |||
: 10. *SONGS Unit 3 Replacement Steam Generator Receipt Inspection QA Document Review Package | |||
: 11. AREVA Document 51-9179808-000, "In-Situ Pressure Test Results for SONGS U3F16B Outage." | |||
: 12. *MHI, "SONGS Unit 2 & 3 RSGs, Regulatory Guide 1.121 Analysis," S023-617-1-C1262, Rev. 4 | |||
: 13. AREVA Document 51-9177744-000 "Site Validation of EPRI Sizing ETSS for Tube-Tube Wear in SONGS Steam Generators". | |||
: 14. AREVA Document 51-9179946-001, "Comparison of Bobbin and +Point POD for Tube-Tube Wear in SONGS Steam Generators". | : 14. AREVA Document 51-9179946-001, "Comparison of Bobbin and +Point POD for Tube-Tube Wear in SONGS Steam Generators". | ||
: 15. SCE Licensee Event Report 2012-001-00, "Unit 3 Manual Reactor Trip due to Steam Generator Tube Leak", March 29 2012. | |||
: 16. SONGS Technical Specifications Section 5.5.2.11, "Steam Generator (SG) Program". | |||
Latest revision as of 12:58, 20 March 2020
ML12285A264 | |
Person / Time | |
---|---|
Site: | San Onofre ![]() |
Issue date: | 10/01/2012 |
From: | AREVA NP, Southern California Edison Co |
To: | Office of Nuclear Reactor Regulation, NRC Region 4 |
References | |
51-9180143-001 | |
Download: ML12285A264 (100) | |
Text
SOUTHERN CALIFORNIA EDISON0 An L:IS),O~N I V7TtR,*' g I'lI)\"'L Cotnpam*
SONGS Unit 2 Return to Service Report ATTACHMENT 3 AREVA Document 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage Steam Generator Condition Monitoring Report
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A 20004-018 (10/18/2010)
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Engineering Information Record Document No.: 51 - 9180143 - 001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Supplier Status Stamp VPL 1814-AU651-MO 158 1M- 0-N/Al
[DESIGN DOCUMENT XREFERENCE DOCUMENT-INFORMATION ONLY ORDER NO. 800918458A
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Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Safety Related? [K YES r] NO Does this document contain assumptions requiring verification? L] YES NO Does this document contain Customer Required Format? L YES g NO Signature Block PILP, R/LR, PageslSections Name and A/A-CRF, PreparedlReviewed/
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Document No,: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Safety Related? K] YES r-D NO Does this document contain assumptions requiring verification? E-, YES [ NO Does this document contain Customer Required Format? D YES M NO Signature Block PILP, R/LR, PageslSections Name and AIA.CRF, Prepared/Reviewed/
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-. ~ - *1 1- I.
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Note: P/LP designates Preparer (P), Lead Preparer (LP)
I I _ _______
R/LR designates Reviewer (R), Lead Reviewer (LR)
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Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Record of Revision Revision Pages/Sections/
No. Paragraphs Changed Brief Description / Change Authorization 000 All Original Release 001 All Added Sections 2.0, 4.1, 4.2, 4.3, 7.2 and 7.3. Incorporated a significant number of editorial corrections and modifications throughout the document.
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A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table of Contents Page SIG NATURE BLOCK ................................................................................................................................ 2 RECO RD O F REVISIO N .......................................................................................................................... 3 LIST O F TABLES ..................................................................................................................................... 6 LIST O F FIG URES ................................................................................................................................... 7 1.0 PURPO SE ..................................................................................................................................... 9 2.0 ABBREVIATIO NS AND ACRO NYM S ..................................................................................... 10 3.0 SCO PE ........................................................................................................................................ 13 4.0 BACKG RO UND .......................................................................................................................... 13 4.1 Previous Operating Experience (OE) Related to Tube-to-Tube Wear ....................... 17 4.2 Previous Operating Experience Related to Tube-to-AVB Wear ..................... 18 4.3 Pre-Service Exam ination Results .............................................................................. 19 5.0 PERFO RMANCE CRITERIA ................................................................................................ 20 6.0 MID-CYCLE 16 O PERATIONAL LEAKAG E ......................................................................... 21 7.0 INSPECTIO N SUM MARY ...................................................................................................... 22 7.1 Eddy Current Inspections Perform ed ......................................................................... 23 7.2 Tube-to-Tube Wear Detection ................................................................................... 23 7.3 Tube-to-Tube Wear Sizing ......................................................................................... 24 7.4 Degradation Identified ................................................................................................ 25 7.5 Secondary Side Visual Exam ination Results .............................................................. 26 8.0 CONDITIO N MO NITO RING ASSESSM ENT .......................................................................... 50 8.1 Input Param eters ........................................................................................................ 51 8.2 Evaluation of Structural and Leakage Integrity ............................................................ 52 8.2.1 AVB Wear ................................................................................................. 52 8.2.2 TSP wear ................................................................................................... 55 8.2.3 Retainer Bar Wear ..................................................................................... 65 8.2.4 Tube-To-Tube Wear ................................................................................ 68 9.0 CO NDITIO N MO NITO RING CO NCLUSIO N.......................................................................... 75
10.0 REFERENCES
............................................................................................................................ 76 1814-AU651-M0158, REV. 0 Page 4 of 98 Page 4
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table of Contents (continued)
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report List of Tables Page TABLE 2-1: ABBREVIATIONS AND ACRONYMS ........................................................................... 10 TABLE 4-1:
SUMMARY
OF PRE-SERVICE INSPECTION RESULTS ............................................ 19 TABLE 7-1: STEAM GENERATOR TUBE INSPECTION SCOPE
SUMMARY
................................. 27 TABLE 7-2: WEAR INDICATION SUM MARY ................................................................................. 30 TABLE 7-3: PLU G G ING S UMMARY ................................................................................................. 31 TABLE 7-4: AVB WEAR DEPTHS (%TWV) (BOBBIN ETSS 96004.1) .............................................. 31 TABLE 7-5: TSP WEAR DEPTHS (%TW) (BOBBIN ETSS 96004.1) ............................................. 31 TABLE 7-6: RETAINER BAR WEAR (+POINT MT ETSS 27903.1) .................................................... 32 TABLE 7-7: TUBE-TO-TUBE WEAR (%TW) (+POINT M T
ETSS 27902.2) ....................................... 32 TABLE 8-1: SONGS UNIT-3 STEAM GENERATOR INPUT VALUES .............................................. 51 TABLE 8-2: EDDY CURRENT ETSS INPUT VALUES [51 .............................................................. 52 TABLE 8-3: INCOMPLETE PROOF TESTS OF TSP WEAR EXCEEDING CM LIMIT CURVE ..... 57 TABLE 8-4: IN-SITU TEST RESULT
SUMMARY
FOR TTW FLAWS .............................................. 70 Page 6 of 98 Page 6 1814-AU651-MO158, REV. 00 1814-AU651-MO1 58, REV. Page 6 of 98 Page 6
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report List of Figures Page FIGURE 4-1: SONGS STEAM GENERATOR SUPPORT STRUCTURE LAYOUT .......................... 14 FIGURE 4-2: VIEW FROM ABOVE BUNDLE SHOWING RETAINER BAR LOCATIONS ............... 15 FIGURE 4-3: SKETCH SHOWING RETAINER/RETAINING BAR CONFIGURATION ..................... 16 FIGURE 7-1: UNIT 3 AVB WEAR DEPTH DISTRIBUTION (INDICATION COUNT) ....................... 33 FIGURE 7-2: COMPARISON OF UNIT 2 AND UNIT 3 AVB WEAR DEPTH DISTRIBUTION (IND ICA T IO N C O UNT) ......................................................................................................... 34 FIGURE 7-3: UNIT 3 TSP WEAR DEPTH DISTRIBUTION (INDICATION COUNT) ....................... 35 FIGURE 7-4: COMPARISON OF UNIT 2 AND UNIT 3 TSP WEAR DEPTH DISTRIBUTION (IND ICA T IO N C O UNT) ......................................................................................................... 36 FIGURE 7-5: UNIT 3 TTW DEPTH DISTRIBUTION (INDICATION COUNT) ................................... 37 FIG URE 7-6: SG 3E-088 AVB WEAR ............................................................................................... 38 FIG URE 7-7: SG 3E-089 AVB WEAR ............................................................................................... 39 FIGURE 7-8: SG 3E-088 TSP WEAR - HOT LEG ............................................................................ 40 FIGURE 7-9: SG 3E-088 TSP WEAR - COLD LEG ....................................................................... 41 FIGURE 7-10: SG 3E-089 TSP WEAR - HOT LEG .......................................................................... 42 FIGURE 7-11: SG 3E-089 TSP WEAR - COLD LEG ..................................................................... 43 FIGURE 7-12: SG 3E-088 RETAINER BAR W EAR .......................................................................... 44 FIGURE 7-13: SG 3E-089 RETAINER BAR W EAR .......................................................................... 45 FIGURE 7-14: SG 3E-088 TUBE-TO-TUBE WEAR .......................................................................... 46 FIGURE 7-15: SG 3E-089 TUBE-TO-TUBE WEAR .......................................................................... 47 FIGURE 7-16: SG 3E-088 TTW INDICATIONS WITH IN-SITU RESULTS ...................................... 48 FIGURE 7-17: SG 3E-089 TTW INDICATIONS WITH IN-SITU RESULTS ...................................... 49 FIGURE 8-1: CM LIMIT FOR AVB WEAR, BOTH SGS, ETSS 96004.1 .......................................... 54 FIGURE 8-2: CM LIMIT FOR TSP WEAR, BOTH SGS, ETSS 96004.1 ......................................... 58 FIGURE 8-3: CM LIMIT FOR SG 3E-088 TSP WEAR, ETSS 96910.1, STRUCTURAL DIMENSIONS59 FIGURE 8-4: CM LIMIT FOR SG 3E-089 TSP WEAR, ETSS 96910.1, STRUCTURAL DIMENSIONS60 FIGURE 8-5: IN-SITU TEST RESULTS FOR SG 3E-088 TSP WEAR, ETSS 96910.1, STRUCTURAL DIME NS IONS ....................................................................................................................... 61 FIGURE 8-6: IN-SITU TEST RESULTS FOR SG 3E-089 TSP WEAR, ETSS 96910.1, STRUCTURAL DIMENS IONS ....................................................................................................................... 62 FIGURE 8-7: AXIAL DEPTH PROFILE - SG 3E-088 R106 C78 07H-1 ............................................ 63 FIGURE 8-8: AXIAL POP-THROUGH LIMIT FOR TSP WEAR ...................................................... 64 1814-AU651-MO158, REV. 0 Page 7 of 98 Page 7
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report List of Figures (continued)
Page FIGURE 8-9: CM LIMIT FOR RB W EAR, ETSS 27903.1 ................................................................ 67 FIGURE 8-10: CM LIMIT FOR SG 3E-088 TTW, ETSS 27902.2, STRUCTURAL DIMENSIONS ........ 71 FIGURE 8-11: CM LIMIT FOR SG 3E-089 TTW, ETSS 27902.2, STRUCTURAL DIMENSIONS ........ 72 FIGURE 8-12: IN-SITU TEST RESULTS FOR SG 3E-088 TTW, ETSS 27902.2, STRUCTURAL DIMENS IONS ....................................................................................................................... 73 FIGURE 8-13: IN-SITU TEST RESULTS FOR SG 3E-089 TTW, ETSS 27902.2, STRUCTURAL D IME NS IONS ....................................................................................................................... 74 1814-AU651-M01 58, REV. 0 Page 8 of 98 Page 8
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 1.0 PURPOSE In accordance with the EPRI Steam Generator Integrity Assessment Guidelines [2], a Condition Monitoring (CM) assessment must be performed at the conclusion of each steam generator eddy current examination. This process is described as "backward-looking," since its purpose is to determine whether Steam Generator (SG) integrity was maintained during the most recent operating period. It involves an evaluation of the as-found conditions of the SGs relative to established performance criteria for structural and leakage integrity. The performance criteria are defined in plant Technical Specifications [16] [17] and are based on NEI (Nuclear Energy Institute) 97-06 [1] (see Section 5.0 below).
In late January 2012 during Cycle 16, SONGS (San Onofre Nuclear Generating Station) Unit 3 entered a forced outage due to a SG tube leak, prompting a comprehensive examination of the SGs. This report documents the required SG CM assessment following that examination, and concludes that the tube structural and leakage integrity performance criteria were not satisfied by Unit 3 during Cycle 16 operation.
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 2.0 ABBREVIATIONS AND ACRONYMS The following table provides a listing of abbreviations and acronyms used throughout this report.
Table 2-1: Abbreviations and Acronyms Abbreviation or Definition Acronym 01C to 07C Tube Support Plate Designations for Cold Leg (7 Locations) 01 H to 07H Tube Support Plate Designations for Hot Leg (7 Locations) 2E-088 Unit 2 Steam Generator 88 2E-089 Unit 2 Steam Generator 89 3E-088 Unit 3 Steam Generator 88 3E-089 Unit 3 Steam Generator 89 3 NOPD 3 Times Normal Operating Pressure Differential 3AP 3 Times Normal Operating Pressure Differential ADI Absolute Drift Indication AILPC Accident Induced Leakage Performance Criterion ANO Arkansas Nuclear One ASME American Society of Mechanical Engineers AVB Anti-Vibration Bar B01 to B12 AVB Designations (12 Locations)
BLG Bulge C Column CE Combustion Engineering CL or C/L Cold Leg CM Condition Monitoring DA Degradation Assessment DBE Design Basis Earthquake DNG Ding DNT Dent ECT Eddy Current Testing EFPD Effective Full Power Days EOC End of Operating Cycle EPRI Electric Power Research Institute ETSS Examination Technique Specification Sheet FOSAR Foreign Object Search and Retrieval GMD Geometric Distortion GPD Gallons per Day GPM Gallons per Minute 1814-AU651-M01 58, REV. 0 Page 10 of 98 Page 10
A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 2-1: Abbreviations and Acronyms Abbreviation or Definition Acronym HL or H/L Hot Leg INPO Institute of Nuclear Power Operators kHz Kilohertz KSI Thousand Pounds per Square Inch LER Licensee Event Report MBM Manufacturing Burnish Mark MHI Mitsubishi Heavy Industries MSLB Main Steam Line Break NDE Non Destructive Examination NEI Nuclear Energy Institute NN Nuclear Notification NOPD Normal Operating Pressure Differential NQI Non-Quantifiable Indication NRC Nuclear Regulatory Commission NSAL Nuclear Safety Advisory Letter OA Operational Assessment OE Operating Experience OTSG Once Through Steam Generator PDA Percent Degraded Area PLP Possible Loose Part POD Probability of Detection PRX Proximity Indication PSI Pounds per Square Inch PSIG Pounds per Square Inch Gage PST Pacific Standard Time PVN Permeability Variation PWR Pressurized Water Reactor QA Quality Assurance R Row RB Retainer Bar RCS Reactor Coolant System REPL Replacement ROLLED Rolled Plug Designation ROLLSTAB Rolled Plug with a Stabilizer RPC Rotating Probe Coil RSG Recirculating Steam Generator 1814-AU651-MO158, REV. 0 Page 11 of 98 Page 11
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 2-1: Abbreviations and Acronyms Abbreviation or Definition Acronym SCE Southern California Edison SG Steam Generator SIPC Structural Integrity Performance Criteria SL2 St. Lucie Unit 2 SLB Steam Line Break SONGS San Onofre Nuclear Generating Station SSA Secondary Side Anomaly SSI Secondary Side Inspection SVI Single Volumetric Indication TMI Three Mile Island TSP Tube Support Plate TTW Tube to Tube Wear TW Through Wall U3F16B Unit 3 Outage Designation UB U-bend Page 12 of 98 Page 12 1814-AU651-MO158, REV. 00 1814-AU651-MOI 58, REV. Page 12 of 98 Page 12
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 3.0 SCOPE This evaluation pertains to the SONGS Unit 3 replacement SGs, which are reactor coolant system components. The CM assessment is required to be completed prior to plant entry into Mode 4 during start up after a SG inspection. The operational assessment (OA) will be documented separately.
4.0 BACKGROUND
SONGS Unit 3 is a two loop Combustion Engineering (CE) PWR (Pressurized Water Reactor) plant which began commercial operation in 1984. The original CE steam generators were replaced in 2010-2011 with new SGs designed and manufactured by Mitsubishi Heavy Industries (MHI) [21]. The replacements, referred to by MHI as model 11 6TT-1, incorporate thermally treated Inconel Alloy 690 (I-690TT) tubing which has demonstrated, through laboratory testing and industry experience, superior resistance to stress corrosion cracking as compared with the 1-600 tubing used in the original SGs.
Other design features include full tubesheet depth hydraulic tube expansion and seven stainless steel trefoil broach Tube Support Plates (TSPs); features chosen primarily to minimize the potential for tube corrosion.
There are 9727 tubes in each SG, in 142 rows and 177 columns, in a triangular pitch arrangement.
The tubes in rows 1-13 are thermally stress-relieved to further minimize the potential for in-service stress corrosion cracking in the U-bends.
The tube bundle U-bend region is supported by a floating Anti-Vibration Bar (AVB) structure consisting of six V-shaped AVBs between each tube column. The AVBs were fabricated from ASME (American Society of Mechanical Engineers) SA-479, Type 405 ferritic stainless steel and are equipped with two Alloy 690 (ASME SB-168 UNS N06690) end caps. Each AVB end cap is welded to an Alloy 690 retaining bar. The retaining bars with AVBs attached are supported by twenty four chrome-plated Alloy 690 retainer bars that anchor the assembly to the tubes. Thirteen Alloy 690 bridges run perpendicular to the retaining bars, and hold the entire assembly together. The AVB structure is not attached to any steam generator component. Figure 4-1 illustrates the general layout of the tube support structures.
Figure 4-2 and Figure 4-3 illustrate the arrangements of the retainer bars and retaining bars.
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A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 4-1: SONGS Steam Generator Support Structure Layout 98 of 98 Page 14 1814-AU651-MO158, REV. 0 1814-AU651-MQ1 58, REV. 0 Page 14 Page 14 of Page 14
A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 4-2: View From Above Bundle Showing Retainer Bar Locations
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A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 3: Sketch Showing Retainer/Retaining Bar Configuration 1814-AU651 -M01 58, REV. 0 Page 16 of 98 Page 16
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 4.1 Previous Operating Experience (OE) Related to Tube-to-Tube Wear Prior to the SONGS Unit 3 shutdown in January of 2012, the recent operating experience related to tub-to-tube wear was limited to once-through steam generators (OTSGs). In December 2011, INPO (Institute of Nuclear Power Operators) OE 34946 [18] was released. This Operating Experience Report discusses experience at Three Mile Island Unit 1 (TMI-1). In July 2012, the NRC (Nuclear Regulatory Commission) released Information Notice 2012-07 [19]. This Information Notice contains information on the experience at TMI-1 as well as Oconee as well as ANO-1 (Arkansas Nuclear One - Unit 1).
This section summarizes the experiences at these plants with OTSGs.
TMI-1 completed replacement of its original OTSGs in 2010. The design of the OTSG differs from the recirculating SG design in that the tubes are straight. The tubes are supported by 15 tube support plates. The first inspection of the TMI-1 replacement SGs took place in the fall of 2011. During this examination, indications were detected on the absolute channel with no discernible response on the differential channel. The indications were designated as Absolute Drift Indications (ADIs). A comprehensive review of all of the ADIs identified tubes with long shallow wear signals between the eighth and ninth tube support plates. The indications were in adjacent tube combinations of either 2 or 3 tubes (the tube pattern is a triangular pitch). A more detailed investigation led to the conclusion that these wear indications were the result of tube-to-tube contact wear. The lengths ranged from 2 to 8 inches and from 1 to 21 percent through-wall.
As a result of the TMI-1 findings, and because TMI and ANO both have AREVA replacement steam generators, the licensee for Arkansas Nuclear One, Unit 1 (ANO-1) was notified. Upon a review of previously recorded eddy current examination data, it was determined that ANO-1 also had similar indications of tube-to-tube wear. The depth and length of the ANO-1 indications were similar to those recorded at TM I-1 In the spring of 2012, the licensee for Oconee, also detected wear attributed to tube-to-tube contact in their Unit 3 replacement SGs. Because the design of the Oconee OTSG are built by BWI and are not the same as the TMI or ANO generators, the location of the tube-to-tube wear was different, but the characteristics were similar. The lengths ranged from 1 to 9 inches and the depths ranged up to 20 percent through-wall.
The severity of the replacement OTSG tube-to-tube wear was evaluated and was not found to compromise tube integrity.
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report The combined experience from the above discussion demonstrated several significant points:
" New or unexpected forms of degradation may be difficult to identify. Robust inspection planning is an important part of identifying new degradation as well as properly characterizing known degradation.
" A comprehensive review of examination data from different perspectives is valuable. By considering the change in indications over time, responses to different channels or techniques, or the spatial distribution of the indications, important information may be found.
- The reporting criteria are critical to proper identification of new or existing damage mechanisms.
" Comprehensive examination of new or replacement steam generators is necessary to ensure that performance is as expected.
4.2 Previous Operating Experience Related to Tube-to-AVB Wear INPO OE 35359 [20] discusses the results of the first two inspections at St. Lucie Unit 2. The recirculating SGs at St. Lucie Unit 2 were replaced during 2007. During the Cycle 18 Refueling Outage (SL2-18, April 2009), eddy current testing of the replacement SGs reported over 5800 AVB wear indications in more than 2000 tubes. Fourteen tubes were plugged as a result of the wear indications.
None of the indications challenged the condition monitoring limits.
Based on the high number of wear indications reported during the SL2-18 inspection, and to further establish growth rates, the St. Lucie Unit 2 SGs were examined again during the next refueling outage at SL2-19 in January 2011. Approximately 3000 new AVB wear indications were reported during the SL2-19 examination. As a result of the SL2-19 inspection, an additional twenty-one (21) tubes were plugged, only one of which exceeded the Plant Technical Specification limit of > 40 %TW (throughwall).
None of the indications detected in SL2-19 challenged the condition monitoring limits.
The OE reinforces the importance of inspecting replacement SGs with the bobbin coil at the end of the first cycle of operation, post-replacement. The diagnostic examinations performed with the +PointTM rotating coil concluded that the AVB wear indications could be flat or tapered, single or double sided.
These wear characteristics are important to consider when selecting the proper depth-sizing technique(s).
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A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 4.3 Pre-Service Examination Results The pre-service inspection of the Unit 3 replacement SGs was performed during June of 2010 at the MHI manufacturing facility in Kobe Japan. The examination consisted of 100 % bobbin coil inspection of all tubes (9727 tubes), 100 % inspection of the Hot Leg (HL) and Cold Leg (CL) Tubesheet region with the +PointTM probe (9727 tubes), and a 100 % inspection of the row 1-15 U-bend regions with the
+PointTM probe (1314 tubes).
No significant degradation was detected during this examination. There were a number of geometric type indications reported in each SG (dings, geometric distortions, proximity, bulge). The following table provides a count of the number of tubes and total number of indications for each Unit 3 SG.
Table 4-1: Summary of Pre-Service Inspection Results SG 3E-088 SG 3E-089 Indication Code Tube Count Indication Count Tube Count Indication Count BLG (Bulge) 10 11 3 3 DNG (Ding) 364 395 706 831 GMD (Geometric 3 3 5 5 Distortion)
MBM (Manufacturing 0 0 0 0 Burnish Mark)
NQI (Non-Quantifiable 0 0 0 0 Indication)
PLP (Possible 6 6 3 3 Loose Part)
PRX (Proximity) 106 106 128 128 PVN (Permeability 0 0 0 0 Variation)
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 5.0 PERFORMANCE CRITERIA The SONGS Unit-3 performance criteria, based on NEI 97-06 [1], are shown below. The structural integrity and accident-induced leakage criteria were taken from Section 5.5.2.11 [16] from the SONGS Unit-3 Technical Specifications. The operational leakage criterion was taken from Section 3.4.13 [17]
of the SONGS Technical Specifications.
StructuralInte-grity Performance Criterion: All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cooldown, and all anticipated transients included in the design specification) and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.
- Accident-Induced Leakage Performance Criterion: The primary to secondary accident-induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed 0.5 gpm per SG and 1 gpm through both SGs.
- OperationalLeakage Performance Criterion: "RCS operational leakage shall be limited to 150 gallons per day primary to secondary leakage through any one steam generator."
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 6.0 MID-CYCLE 16 OPERATIONAL LEAKAGE On January 31, 2012 while operating under nominal conditions and at full power, a high radiation alarm from the condenser air ejector monitor indicated a tube leak in one of the two SGs. Following is a verbatim excerpt from the abstract section of the Licensee Event Report [15] describing the leakage and subsequent shutdown.
"On 01/31/2012 at 1505 PST, SONGS Unit 3 was in Mode I operatingat 100 percent power, when a high radiationalarm from the condenserair ejector monitorindicated a tube leak in one of the two steam generators(SGs). A rapidpower reduction was commenced in accordance with plant procedures when the primaryto secondaryleak rate was determined to be greater than 75 gallons per day (gpd) with an increasingrate of leakage exceeding 30 gpd per hour. At 1731 PST, the operatorsmanually tripped the reactorat 35 percentpower as directed by procedure, resulting in actuationof the Reactor Protection System which is reportable."
After cooling to Mode 5 and draining the primary coolant system to midloop, the leaking SG tube (SG 3E-088 R106 C78) was located by filling the secondary side of the SG and pressurizing to 80 psig with nitrogen. The leak location was confirmed by eddy current testing to be within the U-bend portion of the tube bundle, in the tube freespan. The tube degradation which resulted in the leak was tube-to-tube wear (TTW) caused by tube movement caused by fluid-elastic instability (FEI).
Prior to the forced shutdown, the replaced Unit 3 SGs had been operated for approximately 338 EFPD (Effective Full Power Days) in fuel Cycle 16. The tube leak occurred in Unit 3 while Unit 2 was in the midst of a refueling outage. The utility designated the shutdown as U3F16B.
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 7.0 INSPECTION
SUMMARY
The SONGS Unit 3 leaker outage work scope included the following inspection and testing activities in each of the two replacement SGs (SG 3E-088 and SG 3E-089):
" Bobbin probe and rotating probe examinations using site validated ECT techniques [7] [13]
" Secondary side visual examinations [22]
- In-situ pressure testing [11]
The initial examination following shutdown was a visual examination of the tubesheets of both SG 3E-088 and SG 3E-089 with the goal of identifying the tube(s) exhibiting signs of leakage. The leaking tube was visually identified as SG 3E-088 R-106 C-78. This tube and a two tube bounding pattern surrounding this tube (19 tubes total) were examined full length with the bobbin coil probe to determine the location of the leak and to define the type of degradation associated with the leak. Once this was determined, SCE decided on the initial inspection scope which included the following:
- 100% bobbin coil probe (610 mil diameter) examination of the complete tube length in both Steam Generators.
- 100% of all newly reported bobbin "I" codes, PLP, MBM, NQI, SSA, PRX and PVN locations with a rotating +PointTm/pancake coil probe.
- 100% of all reported bobbin coil ding (DNG) and dent (DNT) locations measuring >/= 2.0 volts with a rotating +PointTm/pancake coil probe.
- All reported bobbin AVB %TW wear measuring >/= 25 %TW and all TSP %TW measuring >/=
30 %TW.
Based on the examination results, a series of seven (7) examination expansions were performed to better characterize and bound the tube-to-tube wear damage.
The subsections below describe findings that are relevant to the condition monitoring assessment.
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 7.1 Eddy Current Inspections Performed A summary of the total number of bobbin probe and rotating probe examinations performed during the current outage is provided in Table 7-1. As indicated in Table 7-1, the examination scope was expanded subsequent to completion of the initial plan. These expansions were implemented in some cases to further characterize identified degradation, and in other cases to further bound regions of potential degradation with the more sensitive +PointTM probe.
7.2 Tube-to-Tube Wear Detection At the start of the U3F16B inspection, the suspected leaking tube (SG 3E-088 R-106 C-78) along with 18 surrounding tubes were inspected with the bobbin coil probe to determine the axial location of the flaw responsible for the leak and to get an understanding as to what type of degradation was associated with the area of the tube with the through wall indication. The degradation observed in the first nineteen tubes examined included AVB wear, deep wear at the TSP's (both hot and cold leg) and long wear type indications in the U-bend region which were eventually classified as Tube-to-Tube Wear (TTW). It was ultimately determined that the Tube-to-Tube Wear was the type of degradation responsible for the tube leak.
The SONGS eddy current inspection procedure was updated to include enhanced screening of the U-bend area of the tube using the 100 kHz absolute channel with no voltage criteria for the reporting of small amplitude signals in the U-bend area of the tube. All analysts assigned to the SONGS inspection were made aware of the revised procedure and screening process and bobbin coil data was screened according to the new requirements set forth in the bobbin coil technique Examination Technique Specification Sheet (ETSS).
The TTW indications were initially identified as NQI during the bobbin coil analysis with the "from-to" fields of the report line entry defining the overall length. No depth was assigned to the NQI bobbin coil entries. Over 300 NQI's were reported in the U-bend area of each SG. All of the tubes with reported U-bend NQI's were examined with the rotating 1-coil +PointTM probe through the complete region of the U-bend (07H to 07C). Most of the NQI's were confirmed to be degradation categorized as TTW and were reported as Single Volumetric Indications (SVI's).
The TTW indications were very long and ranged in length from approximately 1.0" to 41.0" and in depth from 4% to 100% through wall. In many cases, the region of the tube with the TTW present would have two separate indications, one on the intrados of the tube and one on the extrados of the tube. In this case, two separate SVI's would be reported with measured depth and length. In addition to the tubes with reported bobbin coil NQI's, additional tubes surrounding the TTW region were also examined with the 1-coil rotating +PointTM probe. With these supplemental inspections, a total of 1375 contiguous tubes in each SG were examined the full length of the U-bend (07H-07C) specific to the detection of TTW. As a result of these inspections, 407 TTW SVI indications (161 tubes) were reported in SG 3E-088 and 416 TTW SVI indications (165 tubes) were reported in SG 3E-089.
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report The TTW indications were depth sized using EPRI ETSS 27902.2 even though it was known to be very conservative. Selected TTW SVI indications based on depth were line by line sized using the ETSS 27902.2 technique.
The Unit 3 experience in the detection and sizing of the TTW damage mechanism was reflected back into the Unit 2 examination which had just been completed.
7.3 Tube-to-Tube Wear Sizing Upon detection of tube-to-tube wear in the Unit 3 SG's, a determination was made that the most appropriate technique for sizing the wear was EPRI ETSS 27902.2 or 27902.5. However, with some initial review, it was apparent that the techniques produced very conservative depth estimates. The depth estimates reported for the deepest indications were near throughwall, however the tubes had maintained structural integrity at normal operating differential pressure (NODP). Using the actual tube operational performance, the throughwall depth values should have been around 80 %TW or smaller.
Based on the best understanding of the tube-to-tube wear degradation morphology, a wear standard was designed with two machined wear flaws. Although the sample had only two separate flaws, the flaws were fabricated to a maximum depth of 81 % TWD. The length of the flaws made it possible to measure multiple discrete depth sizing grading units. On the basis of these multiple points, a polynomial function was developed to adjust the depth estimates. The revised technique was documented in Reference 13.
The actual flaw sizing was performed using the 27902.2 technique. Screening for selection of In-Situ pressure test candidates was based on the 27902.2 sizing data without the polynomial correction in Reference 13. This produced a conservative population for the In-Situ pressure testing.
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 7.4 Degradation Identified The following tube wear categories (types) were identified during the current outage inspections:
- Anti-vibration bar (AVB) wear
" Tube support plate (TSP) wear
- Retainer bar (RB) wear
- Tube-to-tube wear (TTW)
Table 7-2 summarizes the number of identified degradation indications for each of the wear categories identified (AVB wear, TSP wear, RB wear, and TTW). A complete accounting of the number of tubes plugged and stabilized is provided in Table 7-3, and the plugging/stabilization lists for both SGs are provided in Appendices A and B. The plugging and stabilization information provided in this table and the appendices is current as of June 2012. Due to the ongoing SG recovery efforts, the plugging strategy and, hence, the plugging and stabilization information shown in this report may change prior to startup.
Table 7-4 through Table 7-7 summarize the reported throughwall depths for each category. Because only four RB wear indications were identified, Table 7-6 lists these indications by tube number and provides the structurally equivalent length and depth, as well as the overall length and maximum depth of the wear. The structurally equivalent dimensions correspond to a rectangular flaw which would burst at the same pressure as the measured flaw; determined using the methods described in Section 5.1.5 of Reference 4.
While AVB wear accounts for the largest number of indications and affected tubes, it is the least structurally challenging damage mechanism among those identified.
Figure 7-1 provides histograms of reported AVB wear depths for both SGs which demonstrate that the vast majority of AVB wear was less than 25 %TW. Approximately 50% more AVB wear indications were identified in Unit 3 than in Unit 2; however, the depth distributions at both units were very similar (Figure 7-2). However, since Unit 3 operated for only part of a cycle, it must be concluded that AVB wear is progressing more aggressively at Unit 3 than at Unit 2.
Figure 7-3 provides histograms of reported TSP wear depths for both SGs. This data illustrates that a significant number of tubes experienced TSP wear with throughwall depths in excess of the criteria for plugging. This contrasts sharply with the relatively minor TSP wear identified at Unit 2 after a full cycle of operation (Figure 7-4).
Only four tubes experienced RB wear but three of the four indications exceeded the 35 %TW plugging criteria.
Figure 7-6 through Figure 7-17 provide tubesheet maps illustrating the locations of degradation reported in each SG. The AVB wear is most prevalent in the central region of the tubesheet matrix, in longer tube rows. The most severe TSP wear occurred in the same region as the TTW: a discrete centralized region of the bundle in higher row tubes (Figure 7-14 through Figure 7-17).
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 7.5 Secondary Side Visual Examination Results Due to the wear degradation detected, significant secondary side inspections (SSI) were performed.
The main purposes of these inspections were to provide confirmation of the eddy current results and obtain additional information to help with the root cause evaluation. These visual inspections included the following:
- 1. All small diameter retainer bars.
- 2. Retaining bars and AVB end caps associated with B04 and B09.
- 3. 7 th tube support plate
- 4. Inner bundle passes at B01, B04, and B09.
The retainer bars, retaining bars, and AVB end caps appeared to be structurally sound with no evidence of corrosion, broken welds, etc. The 7th TSP inspection revealed no unexpected or unusual conditions.
The inner bundle passes in the U-bend were performed by going through the transition cone handhole above the 7 th TSP and entering the tube bundle at either 90 degree or 30 degree angles. The 90-degree inspections included many passes between Columns 73 and 87. These inspections showed some wear indications that extended slightly outside of the AVB intersection. This phenomenon was confirmed with eddy current. Additional passes were made between Columns 50 and 60. These inspections did not show any AVB wear outside the AVB intersections.
During the secondary side examination activities described above, no foreign objects were identified.
In addition, during the eddy current inspection, no potential loose parts were identified. Therefore, no unscheduled secondary side FOSAR (Foreign Object Search and Retrieval) activities were required.
1814-AU651-MO158, REV. 0 Page 26 of 98 Page 26
A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 7-1: Steam Generator Tube Inspection Scope Summary SCOPE DESCRIPTION SIG 3E-088 S/G 3E-089 Leg Exam Description Extents Analyzed Scope %Completed Analyzed Scope %Completed Hot I Cold 100 % Bobbin F/L TEH-TEC 9,727 9,727 100.00% 9,727 9,727 100.00%
Hot HL Special Interest Various 283 283 100.00% 309 309 100.00%
Cold CL Special Interest Vanous 218 218 100.00% 242 242 100.00%
Hot UB Special Interest Various 16 16 100.00% 3 3 100.00%
Cold UB Special Interest Various 5 5 100.00% 0 0 N/A Hot/Cold UB NQI Rows<70 07H-07C 19 19 100.00% 1 1 100.00%
Hot HL UB NQI Rows>=70 07H-B07 150 150 100.00% 168 168 100.00%
Cold CL UB NQI Rows>=70 07C-B07 150 150 100.00% 168 168 100.00%
Expansion 1 - Retainer Bar Region SCOPE DESCRIPTION S/G 3E-088 S/G 3E-089 Hot HL U-Bend Retainer Bar 07H-B07 90 90 100.00% 93 93 100.00%
Tubes Cold CIL U-Bend Retainer Bar 07C-B07 90 90 100.00% 93 93 100.00%
Tubes Expansion 2 - Bound Tube-to-Tube Wear (TTW) Region SCOPE DESCRIPTION SlG 3E-088 SlG 3E-089 Hot H/IL U-Bend Bounding 07H-B07 72 72 100.00% 63 63 100.00%
Region #1 Cold C/IL U-Bend Bounding 07C-B07 72 72 100.00% 63 63 100.00%
Region #1 of 98 Page 27 1814-AU651-M0158, REV.
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A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Expansion 3 - Additional Characterization of Wear Expansion 4 - Additional Boundinq of TTW Region SCOPE DESCRIPTION SIG 3E-088 SIG 3E-089 Hot HL U-Bend Freespan Wear 07H-B07 146 146 100.00% 183 183 100.00%
Zone Bounding #1 Cold CIL U-Bend Freespan Wear 07C-B07 146 146 100.00% 183 183 100.00%
Zone Bounding #1 Expansion 5 - Additional Characterization of Wear SCOPE DESCRIPTION SIG 3E-088 SIG 3E-089 Hot HIL TSP +Point TSP +1-3 133 133 100.00% NIA NIA NIA Cold CIL TSP +Point TSP +1-3 133 133 100.00% NIA N/A NIA Hot HIL U-Bend +Point 07H-B07 19 19 100.00% NIA N/A NIA Cold CIL U-Bend +Point 07C-B07 19 19 100.00% NIA NIA N/A Total Plan 11,513 11,513 100.00% r 11,310 r 11,310 100.00%
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A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Expansion 6 - Post In-Situ Pressure Testing SCOPEDESCRIPTION SIG 3E-088 SIG 3E-089 Hot/Cold Bobbin F/L TEH-TEC 73 73 100.00% 56 56 100.00%
Hot HIL U-Bend RPC 07H-B07 73 73 100.00% 56 56 100.00%
Cold CIL U-Bend RPC 07C-B07 73 73 100.00% 56 56 100.00%
Hot HA. Straight TSP Wear Various 232 232 100.00% 179 179 100.00%
Cold CIL Straight TSP Wear Various 180 180 100.00% 172 172 100.00%
Total Plan 631 631 100.00% 519 519 100.00%
Expansion 7 - U-Bend RPC SCOPE DESCRIPTION SIG 3E-088 S/G 3E-089 Hot HIL U-Bend RPC 07H-B07 993 993 100.00% 964 964 100.00%
Cold CIL U-Bend RPC 07C-B07 993 993 100.00% 964 964 100.00%
Total Plan 1 1,986 11,986 1100.00% 1,928 1,928 100.00%
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A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 7-2: Wear Indication Summary Steam Generator Tubes with Steam (enraor Anti-Vibration Tube Support Tube-to-Tube Retainer Foreign Total Indicatons Bar Plate Wear Bar Object Indications (out of 9727 Wall Wear) __tal_________
>50% 0 117 48 0 0 165 74 35 - 49% 3 217 116 2 0 338 119 20-34% 156 506 134 1 0 797 197 10-19% 1380 542 98 0 0 2020 554
< 10% 1818 55 11 0 0 1884 817 TOTAL 3357 1437 407 3 0 5204 919*
- This value is the number of tubes with wear indications at any depth and at any location. Since many tubes have indications in more than one depth and locations, the total number of tubes is less than the total number of indications.
Steam Generator Tubes with Steam Genhraou- Anti-Vibration Tube Support Tube-to-Tube Retainer Foreign Total Indcatlons Wall (Thro Bar Plate Wear Bar Object Indications (out of 9727 Wall Wear) ___ _-*
a 50% 0 91 26 0 0 117 60 35-49% 0 252 102 1 0 355 128 20-34% 45 487 215 0 0 747 175 10-19% 940 590 72 0 0 1602 450
< 10% 2164 94 1 0 0 2259 838 TOTAL 3149 1514 416, 1 0 5080 887*
- This value is the number of tubes with wear indications at any depth and at any location. Since many tubes have indications in more than one depth and locations, the total number of tubes is less than the total number of Indications.
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A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 7-3: Plugging Summary Steam Generator Reason for Plugging 3E-088 3E-089 Total*
U-bend TTW** 161 165 326 Retainer Bar Wear 3 1 4 AVB Wear >=35% 1 1 Preventative (TTW - MHI Screening) 151 112 263 Preventative (TTW Fence)*** 11 14 25 Preventative (Six Consecutive AVB Wear Inds) 2 2 4 Preventative - Retainer Bar 91 93 184 Total 420 387 807
- The plugging status shown in this table is current as of June 2012. Due to the ongoing SG recovery efforts, the plugging strategy and, hence, the numbers shown in this table may change prior to startup.
- Many tubes with TTW also have support wear >=35%. These tubes are only included in the TTW category.
"TTW Fence" refers to the plugging and stabilization of tubes to bound tubes with TTW.
Table 7-4: AVB Wear Depths (%TW) (Bobbin ETSS 96004.1)
SG Average Upper 9 5 th Maximum 3E-088 10.2 19 37 3E-089 8.8 16 30 Both SGs 9.5 18 37 Table 7-5: TSP Wear Depths (%TW) (Bobbin ETSS 96004.1)
SG Average Upper 95th Maximum 3E-088 25.8 55 72 3E-089 24.7 52 79 Both SGs 25.2 53 79 Page 31 of 98 Page 31 1814-AU651-MO158, REV. 0 1814-AU651-MO1 58, REV. 0 Page 31 of 98 Page 31
A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 7-6: Retainer Bar Wear (+PointTM ETSS 27903.1)
Circ Axial Structural Structural Extent Extent Depth Length SG Row Col Location (in) (in) (%TW) (in) 3E-088 117 137 B10-0.42" 0.36 0.32 44 0.26 3E-088 125 49 B11-0.50" 0.26 0.31 29 0.27 3E-088 128 126 B10-0.44" 0.26 0.29 39 0.24 3E-089 124 130 Bl1-0.47" 0.31 0.32 45 0.27 Table 7-7: Tube-to-Tube Wear (%TW) (+PointTM ETSS 27902.2)
SG Average Upper 95th Maximum 3E-088 32.5 60 99 3E-089 30.4 51 66 Both SGs 31.4 57 99 1814-AU651-MO158, REV. 0 Page 32 of 98 Page 32
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-1: Unit 3 AVB Wear Depth Distribution (Indication Count) 2200 2000 1800 1600 (0 1400 0 1200 E.
(U 1000 800 600 400 200 0
0-5 6-10 11-15 16-20 21-25 26-30 31-35 36-40 41-45 46-50 51-55 56-60 61-65 66-70 71-75 76-80 81-85 86-90 91-95 96-100 Depth Bin j%TW)
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-M01 58, Page 33 Page of 98 33 of 98 Page 33
A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-2: Comparison of Unit 2 and Unit 3 AVB Wear Depth Distribution (Indication Count) 2200 2000 I
1800 1600 1400
- Unit 2 SG88 AVB Wear 0
- Unit 2 SG89 AVB Wear M 1200 -]
- Unit 3 SG88 AVB Wear
- Unit 3 SG89 AVB Wear i000 1.
.0 E SooA z 600 j I
0 I-r--r -_____
0-5 6-10 11-15 16-20 21-25 26-30 31-35 36-40 41-45 46-50 51-55 56-60 61-65 66-70 71-75 76-80 81-85 86-90 91-95 96-100 Depth Bin (%TW) 1814-AU651-M0158, REV. 0 Page 34 of 98 Page 34
A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-3: Unit 3 TSP Wear Depth Distribution (Indication Count) 350 300 250
" Unit 3 SG88 TSP Wear
" Unit 3 SG89 TSP Wear 200
.2 0
I.-
150 0
E z 100 50 0
0-5 6-10 11-15 16-20 21-25 26-30 31-35 36-40 41-45 46-50 51-55 56-60 61-65 66-70 71-75 76-80 81-85 86-90 91-95 96-100 Depth Bin (%TIW) 98 Page 35 REV. 00 1814-AU651-MOI 58, REV.
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A AREVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-4: Comparison of Unit 2 and Unit 3 TSP Wear Depth Distribution (Indication Count) 350 300 250
" Unit 2 SG88 TSP Wear
- Unit 2SG89 TSP Wear 200
" Unit 3 SG88 TSP Wear 0
" Unit 3 SG89 TSP Wear 150 0
E 100 z
0 0-5 6-10 11-15 16-20 21-25 26-3D 31-35 36-40 41-45 46-50 51-55 56-60 61-65 66-70 71-75 76-80 81-85 86-90 91-95 96-100 Depth Bin (%TW) 1814-AU651-MO158, REV. 0 Page 36 of 98 Page 36
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-5: Unit 3 TTW Depth Distribution (Indication Count) 100 80 80
-~---- SG3E-088 -
~40 -
20 Depth Bin (%TWD) 1814-AU651-M01 58, REV. 0 Page 37 of 98 Page 37
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-6: SG 3E-088 AVB Wear 2
SCE-SONGS Unit 3 - REPL 20-39%TWC 108 3F16B AVB Wear SfG 88 Rao1 TOTAL TUBES 9727 HOT and COLD Leg Indications SELECTED TUBES 896 OUT OF SERVICE (Il- NA SCALE 0088571 X PRIMARY FACE MANWAY 50 40 20
~30
'a 20 170 10 150 100 130 120 Ila 100 90 00 70 60 5 0 30 20 to COLUMNS NOZZLE NOZZLE 1814-AU651-M0158, REV. 0 Page 38 of 98 Page 38
A A REVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-7: SG 3E-089 AVB Wear GROUPTUBES
=10 0 SCE-SONGS Unit 3 - REPL 20-3%^TWO 38~
3F16B AVB Wear FriTM 10% 1352 12 S/G 89 Reps TUBES 9727 TOTAL TUBES:
SELECTED 871 HOT and COLD Leg Indications PRIMARY FACE OUT OF SERVICE (*)' NA MANWAY 30 20 20 t0 to 170 ISO IS0 100 in 120 110 to0 so so it so go 40 30 20 1*
NOZZLE COLUMNS NOMZE of 98 Page 39 1814-AU651-M0158, 1814-AU651 REV. 0
-M01 58, REV. 0 Page 39 Page 39 of 98 Page 39
A A REVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-8: SG 3E-088 TSP Wear - Hot Leg
-T-i3Bgs 53 SCE-SONGS Unit 3 - REPL 0'19 IV.- 130 3F16B Hot Leg TSP Wear SrG 88 Repl TOTAL TUBES 9727; HOT SELECTED TUBES 223 PRIMARY FACE OUT OF SERVICE (X) NA ISCALE 0068571 X FriAug1017 00.46 2012, NOZZLE 20 20 10 4IO 10 20 30 50 60 "0 0 0 M 110 130 IN0 140 ISO Me0 17M COLUMNS MA,,AY 1814-AU651-MO158, REV. 0 Page 40 of 98 Page 40
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-9: SG 3E-088 TSP Wear - Cold Leg
,W% TvM -Tu SCE-SONGS Unit 3 - REPL 20-44% TWO li 3F16B Cold Leg TSP Wear Gmlv% tm SWO 88 RoV TOTAL TUES: 9727 COLD SELECTED TUESM 171 --j PRIMARY FACE OUT OF SERViCE (N) NA
__EAuaj01665:14 212 MANWMY 20 so 20-t0 t t60 ISO No in 120 1t0 "a so I so 0 30 20 111 NOZZLE COLUMNS NOZZLE 1814-AU651-M01 58, REV. 0 Page 41 of 98 Page 41
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-10: SG 3E-089 TSP Wear - Hot Leg SCE-SONGS Unit 3 - REPL 147 20-34%TWD 3F16B Hot Leg TSP Wear Sw0 8 Reo, TOTAL TUBES 9727 HOT SELECTED TUBES 20 PRIMARY FACE OUT OF SERVICE (0) NA SCALE O*06*71 X
- , _ Fr'-gO4 41 2012 NOZZLE 34 20- 20 10 10 to 20 30 s 00 0 70 0o 9D 100 110 1"0 120 140 000 IN 100 COLUMNS MANWAY 1814-AU651 -M01 58, REV. 0 Page 42 of 98 Page 42
A A REVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-11: SG 3E-089 TSP Wear - Cold Leg SCE-SONGS Unit 3 - REPL 21-34 TWO127 3F16B Cold Leg TSP Wear 0.20% rv lw SK3 89 ROO TOTAL TUBES: 9727 COLD SELECTED TUBES: 166 PRIMARY FACE OUT OF SER.ICE (*)ý NA
_n F _tj17 56*2 2012 MMANWAY 20 n 20 -
20 t0 ie 0 tIo IS0 140 i30 120 1la No to s0 70 60 60 30 20 to NOZZLE COLUMNS NOZZLE Page 43 1814-AU651-MO158, REV. 00 1814-AU651-M0158, REV. 43 of Page 43 Page of 98 98 Page 43
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-12: SG 3E-088 Retainer Bar Wear Retainer Bat V'Met 3 SCE-SONGS Unit 3 - REPL 3F16B Retainer Bar Wear Indications SIG 88 RepV TOTAL TUBES: 9727 COLD SELECTED TUBES 3 PRIMARY FACE OUT OF SERVICE (*) NA CALE 6668511 X MANWAY
- ---- -o -
- -o - -
-o- -
ROWS too -Z -- - -
-~. - -- 10 90 - - - -.- -
-* W
-o- - - - - -
-- -- - - - - - - ~ --E?~-- - -
20 10
- ~~ 40
-~.yt
-j~
t7o NoO tso 140 INO 120 1to too go so to , 50 00 20 to NOZZLE NOZZLE COLUMNS 98 Page~
REV. 00 1814-AU651-M0158, REV.
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A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-13: SG 3E-089 Retainer Bar Wear Rtoawr Bar WSW SCE-SONGS Unit 3 - REPL 3F16B Retainer Bar Wear Indications SG R89R4 TOTALTUES: 9727 COLD SELECTED TUBES I PRIMARY FACE OUT OF SERVICE (1: NA Fn Au 101808.35 2012 MANWMY RO' 40 so
-V lye 3 ISO 510 $4 04 1t1 Il4 "a 10 so Or 50 40 30 30 10 NOZZLE COLUMNS NOZZLE of 98 Page 45 1814-AU651-MO1 1814-AU651 -M01 58, REV. 00 583 REV. Page 45 Page 45 of 98 Page 45
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-14: SG 3E-088 Tube-To-Tube Wear GIROUP- TUBES]-
42 SCE-SONGS Unit 3 - REPL 20-34% 38 Tube-to-Tube Wear S/G 88 Repl TOTAL TUBES. 9727 HOT and COLD Leg Indications SELECTED TUBES: 181 PRIMARY FACE OUTOF SERNACE (#). NA SCALE: 0086571 X Fr!May_2S120907 2012, MAJONAY 20 20 to 170 I 12070 0 0 s 40 20 1 NOZZLE COLUMNS NOZZLE of 98 Page 46 1814-AU651-MOI 1814-AU651 -M01 58, REV. 00 58, REV. Page 46 Page 46 of 98 Page 46
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-15: SG 3E-089 Tube-To-Tube Wear 25 SCE-SONGS Unit 3 - REPL 2"%O~ 14 I--*,----,-- Tube-to-Tube Wear <M4% 52 14 SIG 89 RepV TOTAL TUBES: 9727 HOT and COLD Leg Indications SELECTED TUBES: 165 PRIMARY FACE OUT OF SERVICE (M: NA SCALE: 0 X -571
_fri Ma4 12:1Z31 2012 MANWAY 20 - 20 tO to1 170 160 ISO t40o 13 120 ISO 10 too so io 40 3 30 0 10 NOZZLE COLUMNS NOZZLE Page 47 1814-AU651-MO1 58, REV.
1814-AU651-MO158, REV. 0 0 Page 47 Page of 98 47 of 98 Page 47
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-16: SG 3E-088 TTW Indications with In-Situ Results GROUP_
In-Situ Too Fattures SCE-SONGS Unit 3 - REPL Tubes In-Situ Tested 73 TTW Indications with In-Situ Test Results S£G88 Rept TOTAL TUBES 9727 HOT and COLD Leg Indications SELECTED TUBES 1375 __
OUT OF SERVICE (0) NA . S(*LE 0+e71 .
PRIMARY FACE .. ... _
. ... Mon*.A !1313W0 12 MANWAY ROWS 100 go 40 30 20 20
--- - -- - - t0 170 IN0 M i4 100 1" 110 10 0 00 00 it 50 NOZLE0 NOZZLE COLUMNS NOZZLE Page 48 REV. 0 58, REV. Page 48 of 98 Page 48 1814-AU651-MO1 1814-AU651 -M01 58, 0 Page 48 of 98
A AR EVA Document No.: 51-9180143-001 SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 7-17: SG 3E-089 TTW Indications with In-Situ Results 0
SCE-SONGS Unit 3- REPL Tub" In.hF
-SW 50 1 ,T , T d TTW Indications with In-Situ Test Results
_.1;.
Sf 89 RePl TOTAL TUBS 972 HOT and COLD Leg Indications SELECTED TUMES: 1375 PRIMARY FACE OUT OF SERVICE (0). NA . .. 6LO06
_Moer AMQ1u 1 MANVIkY 30 30 20 -
10 10 170 tU 150 we4 13 14 Ila Wo 90 so to 48 so 4 30 30 to NOZZLE COLUMNS NOZZLE 1814-AU651-MO158, REV. 0 Page 49 of 98 Page 49
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 8.0 CONDITION MONITORING ASSESSMENT In order to satisfy condition monitoring requirements, all degradation mechanisms detected during the Unit 3 leaker outage must meet the structural and leakage performance criteria described in Section 5.0. Assessment of operational leak integrity is based entirely on whether the operating leakage performance criterion (150 GPD) was exceeded during operation. Because the operating leak rate prior to the forced outage remained below the performance criteria, the operational leakage integrity criterion was met.
Assessment of the structural and accident-induced leakage integrity CM criteria can be performed either analytically or through in-situ pressure testing [3]. An analytical assessment is based upon the degradation mechanism's characteristics, including circumferential extent, axial length, and through-wall depth. In-situ pressure testing provides a means of physically determining whether a tube has met the structural integrity and accident-induced leakage performance criteria. It involves pressurizing a tube, or a locally degraded region within a tube, such that the applied loads are prototypical of the required performance criteria loads. The response of the tube during the test is a direct indicator of whether the tube satisfied the performance criteria. Because the required loading is imposed directly onto the tube under test, some of the uncertainties which must be conservatively represented in an analytical evaluation may be eliminated (in particular, NDE sizing, material strength, and burst equation uncertainties). This improves the likelihood of demonstrating compliance with the CM criteria.
Consistent with the structural integrity criteria described in Section 5.0, the limiting pressure loading occurs at a value of three times the normal operating differential pressure. For Unit 3 this value is 4260 psi [9]. In addition to pressure loads, the CM must also consider the impact of non-pressure accident loads if they could have a significant effect on the burst pressure of the degraded tubes. A review of the screening guidance of Section 3.7.2 of Reference 2 provides the basis for concluding that design-basis, non-pressure accident loads are not limiting for the identified tube wear in the Unit 3 SG tubes.
Reference 2 indicates that the burst pressure of degradation less than 2700 in circumferential extent at supports below the top TSP, and degradation with circumferential involvement less than 25 PDA (Percent Degraded Area) anywhere in the tube bundle; will not be significantly affected by non-pressure loads. Although significant tube degradation was identified during the forced outage, the circumferential involvement of all degradation was less than 25 PDA. Consequently, the limiting loading scenario for the evaluation of structural integrity is that involving pressure loads only (i.e., three times the normal operating differential pressure). The accident-induced leakage performance criteria must also be assessed, and in addition to the Steam Line Break (SLB) pressure (2560 psi), must also consider non-pressure loads where appropriate. This is discussed in more detail within this section.
In order for a degraded tube to be returned to service, the degradation must be measured using a qualified ECT sizing technique, and the degradation must be evaluated as acceptable for continued operation. The sizing techniques qualified for use at SONGS Unit-3 are identified in the degradation assessment [6] and are detailed in the ECT technique site validation documents [7][13]. If a degradation mechanism cannot be sized with appropriate sizing confidence, it is plugged upon detection. All degradation identified during the current outage was measured with a qualified ECT technique.
This was the first in-service inspection of the SONGS Unit 3 SG tubes; performed after 338 EFPD of operation following SG replacement. The potential for AVB, TSP, and retainer bar wear to develop was recognized prior to the examination. However, the occurrence and severity of tube-to-tube wear was 1814-AU651-MO158, REV. 0 Page 50 of 98 Page 50
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report not expected. Although the examination program as planned was fully capable of detecting this mechanism, the Degradation Assessment [6] was revised during the outage to include this new mechanism.
8.1 Input Parameters Table 8-1 and Table 8-2 identify the input parameters used to perform the condition monitoring assessment. In particular, these inputs were used within the AREVA Mathcad tool which implements the SG Flaw Handbook equations [8], in order to generate the limit curves discussed in the following sections. The 4260 psid 3 NOPD value is based on a conservative assessment of Unit 3 secondary side steam pressure as measured during cycle 16.
Table 8-1: SONGS Unit-3 Steam Generator Input Values Parameter Value Desired probability of meeting burst pressure limit 0.95 Tubing wall thickness 0.043 inch, [7]
Tubing outer diameter 0.750 inch, [7]
Mean of the sum of yield and ultimate strengths at temperature 116440 psi, [10]
Standard deviation of the sum of yield and ultimate strengths 2460 psi, [10]
3 X Normal Operating Pressure Differential (3 NOPD) 4260 psid, [9]
MSLB Pressure Differential 2560 psid, [18]
EFPD from SG Replacement through U3 2/12 Leaker Outage 338 EFPD, [9]
Expected EFPD from U3 2/12 Leaker Outage to EOC16 252 EFPD, [9))
98 Page 51 REV. 00 1814-AU651-MO1 58, REV.
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 8-2: Eddy Current ETSS Input Values [5]
Parameter ETSS 96004.1 ETSS 27903.1 ETSS 27902.2 ETSS 96910.1 Probe Type Bobbin Coil +Point TM +PointTM +Point TM NDE depth sizing Slope = 0.98 Slope = 0.97 Slope = 1.02 Slope = 1.01 regression Intercept = 2.89 Intercept = 2.80 Intercept = Intercept =
parameters %TW %TW 0.94 %TW 4.30 %TW NDE depth sizing technique uncertainty 4.19 %TW 2.11 %TW 2.87 %TW 6.68 %TW (standard deviation)
NDE depth sizing analysis uncertainty 2.10 %TW 1.06 %TW 1.44 %TW 3.34 %TW (standard deviation)
Total NDE (Sizing and Technique) 4.69 %TW 2.36 %TW 3.22 %TW 7.48 %TW (standard deviation)* III
- Total uncertainty is the technique and analysis uncertainties combined via the square root of the sum of the squares.
8.2 Evaluation of Structural and Leakage Integrity 8.2.1 AVB Wear AVB wear was evaluated with the flaw model described in Reference 4 as "axial part-throughwall degradation < 1350 in circumferential extent." The maximum circumferential extent of a single 100%TW wear scar formed by a long flat bar positioned tangentially to the tube surface (e.g., an AVB) is 55.40. For double-sided AVB wear the total circumferential extent for this limiting case would be well below the 1350 limit established by this model; hence, this flaw model is appropriate for AVB wear. In addition, the AVB geometries provide sufficient circumferential separation between the wear scars to permit each indication to be treated separately. The separation between centerline contact points for AVB wear is 1800 and results in negligible circumferential interaction between separate wear locations in the same axial plane of the tube.
The topic of external loads must be addressed. As discussed earlier it has been established that due to the limited circumferential involvement of the AVB wear (i.e., <25 PDA), external loads present during design basis accidents, with required margins of safety, are less limiting than normal operating pressure loads evaluated with a safety factor of three. Hence external loads need not be included in the evaluation of AVB wear burst integrity.
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A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report The bobbin probe was used to measure the depth of AVB wear through the application of ETSS 96004.1. A CM limit curve for AVB wear based upon ETSS 96004.1 and the parameters provided in Table 8-1 and Table 8-2 is provided in Figure 8-1. This figure also includes the throughwall depth of each indication reported. The five largest indications are plotted at their measured axial length, while the rest are plotted at the assumed axial length of 1.8 inches. The assumed flaw length for AVB wear indications was derived from measurements taken on over 350 AVB wear indications in the Unit 3 SGs, wherein the maximum indicated length was 1.59 inches. The field of the eddy current probe extends beyond the dimensions of the coil and thus the probe will sense a flaw before the coil is physically over the flaw. This effect occurs on both ends of the flaw, and the effect becomes more significant as the flaw depth increases. This phenomenon is known as "probe look-ahead" and the net effect is that the axial length reported for a wear flaw will normally be longer than the actual flaw length. Because the above AVB wear measurements were not adjusted downward to reflect the impact of ECT probe look-ahead, these measurements are considered to be appropriately conservative.
Because all AVB wear lies below the CM limit curve, it is concluded that the structural integrity performance criterion was satisfied with respect to AVB wear during the operating period preceding the forced outage.
AVB wear must also be evaluated against the accident-induced leakage performance criterion (AILPC).
Under accident conditions, pressure and/or mechanical loading can lead to mechanical tearing of partial depth degradation to create a 100% throughwall leak path. This mechanical tearing is referred to as "pop-through". Pop-through does not constitute a tube burst in regards to tube integrity but is important when determining leakage integrity.
AVB wear resides on the tube flanks (sides facing adjacent columns - not intrados or extrados) where bending stresses resulting from in-plane motion during analyzed events are negligible. In a typical RSG design, limited out-of-plane motion also produces negligible bending stress at the flanks. For the SONGS U-bend support design, moderate out-of-plane bending moments are anticipated during a design basis earthquake (DBE) [12], which would produce bending stress in the limiting tube flanks of approximately 8,500 psi.
The pressure at which circumferential pop-through and leakage will occur in the presence of pressure and external loads may be evaluated using the methods described in Section 9.6.1 of Reference 2.
The maximum depth of identified AVB wear was 37%TW. Adjusting upwards to conservatively account for ETSS 96004.1 sizing uncertainty yields an upper bound estimate of 47%TW. Assuming that this limiting AVB wear flaw has a circumferential extent of 55.40 (see earlier discussion), and is subjected to a 20 ksi bending stress, circumferential pop-through would not occur at or below MSLB pressure.
Consequently, it is concluded that external loads do not lead to failure to satisfy the AILPC in the circumferential orientation.
Volumetric degradation that is predominantly axial in orientation and is greater than 0.25 inch long will leak and burst at essentially the same pressure per section 9.6.3 of Reference 2. The Unit 3 AVB wear indications meet this description. Since the earlier evaluation demonstrated that the AVB wear identified during the current outage satisfied the burst integrity criteria at a pressure of 4260 psid, the leakage integrity of AVB wear at the much lower MSLB pressure differential of 2560 psid is also demonstrated by that evaluation. Hence, all of the AVB wear indications satisfied the SONGS AILPC during the operating period prior to the leaker outage.
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A r ý,nfNo: 51-9180143-001 AREVA L.IU*CUIii lv ...
SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report
....... ,A,~I -A, Rnth SGs, ETSS 96004.1 Figure 8-1: CM LiMIT Tor Avu w 50 6
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A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 8.2.2 TSP wear TSP wear was evaluated with the flaw model described in Reference 4 as "axial part-throughwall degradation < 1350 in circumferential extent." The maximum circumferential extent of a single 1 00%TW wear scar formed by a long flat bar positioned tangentially to the tube surface (e.g., a TSP land contact) is 55.40. For double- or triple-sided TSP wear this model is bounding because the TSP geometry provides sufficient circumferential separation between the wear scars to permit each indication to be treated separately. The separation between centerline contact points for TSP wear is 1200, and results in negligible circumferential interaction between separate wear locations in the same axial plane of the tube. With respect to external loads, each wear flaw at the same support elevation may be treated individually. An individual TSP wear flaw with a depth of 100%TW and a circumferential extent of 55.40 would be less than 16 PDA. Because the circumferential involvement of this limiting flaw is less than 25 PDA, external loads need not be considered in the evaluation of burst integrity for TSP wear.
The bobbin probe was used to estimate the depth of TSP wear through the application of ETSS 96004.1. A CM limit curve for TSP wear based upon ETSS 96004.1 and the parameters provided in Table 8-1 and Table 8-2, is provided in Figure 8-2. This figure also includes the throughwall depth of each indication reported. Indications for which axial length measurements were available are plotted using the bobbin-measured lengths. The rest of the indications are plotted at an assumed axial length of 1.8 inches. This value was derived from measurements taken on over 400 TSP wear indications in the Unit 3 SGs, wherein the maximum indicated length was 1.6 inches. Because these measurements were not adjusted downward to reflect the impact of ECT probe look-ahead, and because the actual flaw length is expected to be limited to the TSP thickness (1.38"), this assumption is considered to be appropriately conservative.
Figure 8-2 illustrates that a substantial number of TSP wear indications exceeded the CM limit.
However, this result is based upon bobbin probe estimates of maximum indication depth, assumed to occur over the entire bounding indication length. This is a very conservative approach.
All TSP wear indications with bobbin depths >20%TW were inspected with +PointTM. All +PointTM indications measuring >38%TW had axial depth profiles performed. The depth profiles were used to calculate each indication's structurally equivalent depth and length. The structural depth and length correspond to a rectangular flaw which would burst at the same pressure as would a flaw having the measured depth profile. The measurements were performed using +PointTM probe ETSS 96910.1, and the structurally equivalent dimensions were determined using the methods described in Section 5.1.5 of Reference 4.
CM limit curves for TSP wear based upon ETSS 96910.1 are provided for SG 3E-088 and SG 3E-089 in Figure 8-3 and Figure 8-4, respectively. This figure also depicts the structural dimensions of all indications for which axial depth profiling was performed, including those that exceeded the CM curve in Figure 8-2. Note that any given TSP elevation may have multiple wear flaws (i.e., at more than one land contact) and one of the flaws is typically deeper than the others. Since, in some cases, depth profiling was performed on all of the flaws at a given TSP elevation, the figures include many TSP wear indications of lesser significance than those that exceeded the CM curve in Figure 8-2.
The use of structurally equivalent dimensions provides the highest likelihood of analytically demonstrating compliance with the CM structural performance criteria. However, as illustrated in 1814-AU651-MO158, REV. 0 Page 55 of 98 Page 55
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-3 and Figure 8-4, many TSP wear indications exceeded the CM curve thus; satisfaction of the CM criteria could not be analytically demonstrated. Consequently, all of the TSP wear flaws that exceeded the CM limit were subjected to in-situ pressure testing in an attempt to demonstrate CM criteria compliance.
Figure 8-5 and Figure 8-6 summarize the results of in-situ testing of TSP wear flaws in each SG. All tested TSP wear in SG 3E-089 satisfied the structural integrity and accident leakage performance criteria. In SG 3E-088 a number of indications could not be tested to the required pressure levels because more limiting TTW in the same tube failed below the target pressure thus terminating the test.
These indications are depicted in Figure 8-5 as "Incomplete." In the absence of a successful in-situ pressure test, those indications identified as incomplete which lie above the CM curve must be considered to be CM structural integrity performance criteria (SIPC) failures. These indications are listed in Table 8-3.
All but four of the TSP wear indications listed in Table 8-3 were successfully tested at the MSLB hold point without leakage, thereby satisfying the AILPC. Compliance with the AILPC could not be demonstrated through in-situ testing for the four indications identified as "In Situ Test Indeterminate" due to the failure of a TTW flaw in the same tube.
Of the four, the indication at location SG 3E-088 R106 C78 07H-1 is the most limiting from a pop-through and leakage perspective. Figure 8-7 provides the axial depth profile for this indication which is predominantly axial in orientation with an overall measured length of 1.79 inches (based on line-by-line sizing), a measured maximum depth of 75%TW (ETSS 96910.1), and a conservatively assumed circumferential extent of 55.40. Adjusting upwards to account for ETSS 96910.1 depth sizing uncertainty yields an upper bound depth estimate of 92.4%TW.
The pressure at which circumferential pop-through and leakage will occur in the presence of pressure and external loads may be evaluated using the methods described in Section 9.6.1 of Reference 2. For the top TSP, the limiting in-plane and out-of plane bending moment anticipated to occur during a DBE is approximately 209 in-lb [12], which would produce bending stress of approximately 13,100 psi.
Under this loading condition and using the above methodology, a 55.40 circumferential flaw with maximum depth 88.9%TW would pop-through at slightly above 2560 psi. For the TSP wear indication in SG 3E-088 R106 C78 07H-1, circumferential pop-through and leakage is projected to occur at 1120 psi, well below the MSLB pressure. Axial pop-through is calculated to occur at less than 1000 psi using the methodology described in Section 9.6.2 of Reference 2. This tube was pressurized to 2874 psi at room temperature without pop-through of the subject wear location, which for comparison with the analytical results, equates to approximately 2400 psi at operating temperature. Clearly the analytical estimation of pop-through pressure is conservative; however, in the absence of a successful in-situ test result, it must be concluded that the TSP wear at location SG 3E-088 R106 C78 07H-1 did not satisfy the AILPC. The upper bound depths of the three remaining indications are below the depth required to pop-through at MSLB pressure; however, all three are projected to pop-through axially (see Figure 8-8).
In summary, 13 TSP wear flaws in seven tubes failed to satisfy the structural integrity performance criteria, and four of the flaws (in two tubes) failed to satisfy the accident-induced leakage performance criteria.
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 8-3: Incomplete Proof Tests of TSP Wear Exceeding CM Limit Curve Analytical Pop-Through Evaluation Structural Structural Test SIPC Success AILPC Success Maximum Upper Project Circ Project Axial AILPC SG Row Col Depth Length Location Tesrination During In-Situ During In-Situ Measured Overall Bound Pop-Thru Pop-Thru Success
(%TW) (in.) (psmi)aio Test? Test? Depth Length (in.) Depth Below Beow-hr SuBAaltccss?
(psi) (%TW) (%Tw) MSLB? Below MSLB? Analytically?
88 98 80 53.3 0.52 07H 4886 No Yes NA NA NA NA NA NA 88 98 80 46.0 1.00 07C 4886 No Yes NA NA NA NA NA NA 88 99 81 49.1 1.18 07C 5026 No Yes NA NA NA NA NA NA 88 99 81 50.8 0.94 07H 5026 No Yes NA NA NA NA NA NA 88 100 80 44.3 0.61 07H 4732 No Yes NA NA NA NA NA NA 88 100 80 42.8 1.10 07C 4732 No Yes NA NA NA NA NA NA 88 101 81 53.1 1.20 07C 4889 No Yes NA NA NA NA NA NA 88 101 81 50.1 0.88 07H 4889 No Yes NA NA NA NA NA NA 88 104 78 49.7 0.84 07C 3180 No In-Situ Test Indeterminate* 57 1.57 74.2 No Yes No In-SturmTestel 88 104 78 48.6 0.73 07H 3180 No In-Situ Test 58 1.59 75.2 No Yes No Indeterminates 88 106 78 64.6 0.96 07H 2874 No In-Situ Test 75 1.79 92.4 Yes Yes No Indeterminates 88 106 78 55.3 0.69 07C 2874 No In-Situer t 65 1.02 82.3 No Yes No 8 Indeterminate1 NA NA NA NA NA NA 88 107 77 47.2 1.56 07C 1 5160 No Yes NA NA NA NA NA NA
- AILPC failed at a TTW flaw. Test inconclusive for this TSP wear flaw.
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-2: CM Limit for TSP Wear, Both SGs, ETSS 96004.1 100.
As discussed in Section 7.3, measured lengths were used where available; otherwise, a bounding length of 1.8" was used.
40
-I I CD a
- - Condition Monitoring Limit aTSP M'ar FRaws I 19 -
U 0.0 II 1"Q 1".8 2.0 Degradatklon Length (in.)
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-3: CM Limit for SG 3E-088 TSP Wear, ETSS 96910.1, Structural Dimensions 100 r 90 80 70
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- Analytical CM Success A A 10 kAA 0 -2 0o0 012 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 2.0 Structurally Equivalent Length (inches) 98 Page 59 REV. 0 1814-AU651-MO1 58, REV.
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-4: CM Limit for SG 3E-089 TSP Wear, ETSS 96910.1, Structural Dimensions 100 90 80 t 70 60 I+
50 A~ AA*A,1*
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0.0 0.2 0.4 0.6 08 1.0 1-2 1.4 1.6 1.8 2.0 Structurally Equivalent Length (inche of 98 Page 60 1814-AU651-MO158, REV. 00 1814-AU651-MOI 58, REV. Page 60 Page 60 of 98 Page 60
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-5: In-Situ Test Results for SG 3E-088 TSP Wear, ETSS 96910.1, Structural Dimensions 100
- - -CM Limit 90
- Pass
- Failed 80 d
- Incomplete S70O
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- '"Incomplete" =Flaw is in a tube
+ that has been tested and a larger 10 flaw failed before fulltest pressure 4could be reached 0 0 - 4 T i i II 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 2.0 Structurally Equivalent Length (inches) 98 Page 61 1814-AU651 REV. 00
-M01 58, REV.
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A Document No.: 51-9180143-001 ARE VA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-6: In-Situ Test Results for SG 3E-089 TSP Wear, ETSS 96910.1, Structural Dimensions 100
--- CM Limit 90
- Pass Failed
< Incomplete 80 IF 70 60
+ , -;** - .+
50 4-40 30 -
20 10 n
u 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 20 Structurally Equivalent Length (inches) 98 Page 62 1814-AU651 -M01 1814-AU651 REV. 00 58, REV.
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-7: Axial Depth Profile - SG 3E-088 R106 C78 07H-1 100 90 80 70 60 0.
0 CM 50 a
0 40 0
30 20 10 0 ....... ............... .... ..... ....
0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 120 1.30 1.40 1.50 1.60 1.70 Axial Position (in.)
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-8: Axial Pop-Through Limit for TSP Wear 100 95 90
-e 0 85 a.
S80 a.
a o 75 o 70 65 faU 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 2.0 Degradation Length (in.)
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 8.2.3 Retainer Bar Wear Retainer bar wear was also evaluated with the "axial part-throughwall degradation < 1350 in circumferential extent" degradation model as described in Reference 4. The maximum measured circumferential extent of RB wear was 0.36 inches (Table 7-6) which corresponds with an angular extent at the mid tube wall of 580; well within the 1350 requirement for this flaw model. Because of the rather short axial extent of the RB wear indications, it is prudent to also consider the potential for rupture in the circumferential direction. For the indication with the largest circumferential extent (0.36 inch, SG 3E-088 R1 17 C137 B10), and a limiting assumption that the wear is 100%TW over the entire circumferential extent, the percent degraded area (PDA) is found to be 16 PDA (i.e., (0.36)/(Tr(mid-wall diameter)) ). This limiting flaw was evaluated with the degradation model for circumferential cracking under pressure loading as described in Reference 2. Based on this model the lower bound burst pressure in the circumferential direction was determined to be 7000 psi; much less limiting than the results from the axial part-throughwall model (discussed below). This provides the basis for concluding that the axial part-throughwall degradation model is appropriate for the evaluation of RB wear.
External loads which are assumed to exist concurrently with the SLB accident do not significantly affect burst pressure in tubes with flaws located in the U-bend region on the tube flanks (+/-450) [2]. On Unit 2,
+PointTM probe examinations were performed with another eddy current probe placed in an adjacent tube in order to estimate the position of the limiting flaw (Unit 2 SG 2E-089 R119 C133 B02) relative to the tube flank. This testing showed that the indication lies approximately 40 to 50 degrees from the flank position; consequently, the RB wear may not lie entirely within the flank region. However, it is also known that external loads do not significantly affect burst pressure in tubes with flaws whose circumferential involvement is less than 25 PDA [2]. The upper bound circumferential involvement of the limiting Unit 3 RB wear indication is only 16 PDA. It is therefore concluded that the limiting condition monitoring structural criteria is 3x normal operating pressure differential, rather than 1.2x the combined loading of SLB pressure and external loads. In short, it is appropriate to consider pressure loading-only for the structural integrity evaluation of RB wear indications.
The axial depth profile of each RB wear indication was measured using ETSS 27903.1, and this data was used to determine the structurally significant dimensions of the indications using the methods described in Section 5.1.5 of Reference 4. The results are provided in Table 7-6 and are plotted on the CM curve provided in Figure 8-9. Since all four RB wear indications lie well below CM curve it is concluded that all Unit 3 RB wear satisfied the structural integrity performance criteria.
RB wear must also be evaluated against the AILPC. For the purpose of this evaluation it is assumed that RB wear resides on the tube intrados or extrados where in-plane motion produces consequential bending stress during analyzed events. For the SONGS SGs, bending moments anticipated in the vicinity of B10 and B131 during a DBE [12], would produce in-plane bending stress of approximately 8,800 psi.
The pressure at which circumferential pop-through and leakage will occur in the presence of pressure and external loads may be evaluated using the methods described in Section 9.6.1 of Reference 2.
The maximum depth of identified RB wear was 51 %TW. Adjusting upwards to conservatively account for ETSS 27903.1 sizing uncertainty yields an upper bound estimate of 56%TW. Assuming that this limiting RB wear flaw has a circumferential extent of 580 (see earlier discussion), and is subjected to a 20 ksi bending stress, circumferential pop-through would not occur at or below MSLB pressure.
Consequently, it is concluded that external loads do not lead to failure to satisfy the AILPC in the 1814-AU651-MO158, REV. 0 Page 65 of 98 Page 65
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report circumferential orientation. The axial pop-through evaluation performed for TSP wear and summarized in Figure 8-8 is applicable for RB wear and provides the basis for concluding that the limiting RB wear satisfied the AILPC in the axial direction. Hence, all four of the RB wear indications satisfied the SONGS AILPC during the operating period prior to the leaker outage.
It should be noted that multiple eddy current examination techniques and multiple phases of eddy current analysis are applied when characterizing tube degradation to provide as much information and accuracy as practical. Certain indications, such as retainer bar wear, which are detected by the bobbin coil examination are subsequently tested by a rotating coil probe to provide a better and more detailed characterization of the degradation. An initial single-point evaluation of the depth of an indication is performed from the rotating +PointTM data by a resolution analyst. Subsequent analysis of any significant indications is performed to assign a depth evaluation to each scan line of the rotating coil data. This process is called line-by-line sizing and produces a detailed profile of the subject indication.
It is not unusual to have some variation between the single-point analysis result and the subsequent line-by-line sizing evaluation. In the case of the SG 3E-089 retainer bar wear, the initial depth report was 46% TW based on EPRI ETSS sizing technique 27903.1 for the Single Volumetric Indication (SVI) report. The line-by-line sizing produced a maximum depth of 51% TW at one position within the indication. As a conservative approach, this maximum depth value of 51% TW was used in the CM analysis of the retainer bar wear degradation.
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-9: CM Limit for RB Wear, ETSS 27903.1 100 80.
- Condition Monbring Limit 149- i 369 R124 C13Q0 Bll U 6068 R12 012 D19 U 988 R126 .49 W11 zo 010 10 0.0 0.2 QA 9.0 0. 1.0 1:2 D.gIdahion LangMi on.)
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A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 8.2.4 Tube-To-Tube Wear Tube-to-Tube wear was evaluated with the flaw model described in Reference 4 as "axial part-throughwall degradation < 1350 in circumferential extent." The circumferential extent of a TTW flaw is limited by the geometry of the interacting tubes such that it can be modeled as a single 100%TW wear scar formed by a flat bar positioned tangentially to the tube surface. In this configuration the maximum circumferential extent of the degradation will be 55.40. For double-sided TTW, this model is bounding because the wear geometry provides sufficient circumferential separation between the wear scars to permit each indication to be treated separately. The separation between centerline contact points for double-side TTW is 1800, and results in negligible circumferential interaction between separate wear locations in the same axial plane of the tube. With respect to external loads, each wear indication at the same axial location may be treated individually. An individual TTW indication with a depth of 100%TW and a circumferential extent of 55.40 would be less than 16 PDA. Because the circumferential involvement of this limiting indication is less than 25 PDA, external loads need not be considered in the evaluation of burst integrity for TTW.
The +PointTM probe was used to measure the depth and the overall length of TTW through the application of ETSS 27902.2. The maximum measured length of any TTW indication was 41 inches.
Using the flaw model discussed above it was determined that a rectangular flaw 41 inches long and 45%TW would meet the SIPC. Hence, it was concluded that all TTW sized less than 45%TW satisfied the SIPC. Although only TTW exceeding 45%TW required the more detailed flaw profiling analysis, all TTW indications with maximum depth >40%TW were profiled and analyzed to determine the structurally equivalent dimensions.
CM limit curves for TTW based upon ETSS 27902.2 are provided for SG 3E-088 and SG 3E-089 in Figure 8-10 and Figure 8-11, respectively. The figures also depict the structural dimensions of all indications for which axial depth profiling was performed. The use of structurally equivalent dimensions provides the highest likelihood of analytically demonstrating compliance with the CM structural performance criteria. However, as illustrated in Figure 8-10 and Figure 8-11, many TTW flaws exceeded the CM curve thus; satisfaction of the CM criteria could not be analytically demonstrated.
Consequently, all of the TTW that exceeded the CM limit was subjected to in-situ pressure testing in an attempt to demonstrate CM criteria compliance.
8.2.4.1 In-Situ Test Results Figure 8-12 and Figure 8-13 summarize the results of in-situ testing of TTW indications in each SG. All tested TTW wear in SG 3E-089 satisfied the structural integrity and accident leakage performance criteria. In SG 3E-088 three TTW indications failed both the AILPC and SIPC, and five flaws passed the AILPC but failed the SIPC. These results are summarized in Table 8-4.
In addition, four TTW indications predicted analytically to fail the SIPC, could not be tested to the required pressure levels because more limiting TTW in the same tube failed below the target pressure, terminating the test. These indications are depicted in Figure 8-12 as "Incomplete" (above the CM curve). In the absence of a successful in-situ pressure test, these must be considered to be SIPC failures (see Table 8-4).
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A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report For one TTW flaw a determination could not be made based upon in-situ test result as to whether the AILPC was satisfied. This flaw is labeled in Table 8-4 as "In Situ Test Indeterminate" due to the failure of a TTW flaw in the same tube at a pressure below the target AILPC pressure. The maximum measured throughwall depth of this flaw was 99%TW and the structural length exceeded 2 inches.
From Figure 8-8 it must be concluded that this flaw does not satisfy the AILPC.
In summary, 12 TTW flaws in eight tubes failed to satisfy the structural integrity performance criteria, and four of the flaws (in three tubes) failed to satisfy the accident-induced leakage performance criteria.
8.2.4.2 Eddy Current Sizing Following the detection of TTW, application of ETSS 27902.2 was site validated [13]. This was done by building a test specimen with flaws similar to the TTW flaws observed at SONGS. Many depth estimates were made with +PointTM using ETSS 27902.2. These results were compared with the actual depths of the wear flaws. This comparison showed that ETSS 27902.2 conservatively overestimated the depths across the entire range of depths tested (from 5%TW to 81 %TW). The flaws in the test specimen that measured >70%TW were overestimated by an average of 17%TW.
The conservatism in the sizing technique as discussed above is supported by the in-situ test results. A cursory review of the best estimate burst pressures for the tubes that were in-situ pressure tested shows that approximately 45 failures would have been expected if the NDE sizing was accurate.
Because there were only eight tubes that failed in-situ pressure testing, the measured depths are assumed to be overestimated using ETSS 27902.2. Again, this is consistent with the site validation work which showed that ETSS 27902.2 consistently overestimated the depths.
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Table 8-4: In-Situ Test Result Summary for TTW Flaws Test SIPC AILPC Maximum Structural StructuralStucualStutual .
Ts at Pressure ICAL Success Success Mxmm Measured AILPC ALP SG Row Col GDepth Ro Co Length DeTh) Length Location Loca Prsuea Termination ucsIn-During ucs During In-Situ esrd Depth Success Succss
(%Tt (in.) (psi) Situ Test? Test? (%TW) Analytically?
SG 3E-088 98 80 74.4 3.28 B02 4886 No Yes NA NA SG 3E-088 99 81 71.8 4.17 B02 5026 No Yes NA NA 79.7 2.8 B02-1 No Yes NA NA SG 3E-088 100 80 4732 52.6 3.33 B02-2 Not Yes NA NA 74.3 3.86 B02-1 No Yes NA NA SG 3E-088 101 81 4889 50.7 5.02 B02-2 Not Yes NA NA SG 3E-088 102 78 98.7 2.63 B02 3268 No No NA NA 91.7 1.06 B03 No No NA NA SG 3E-088 104 78 3180 In-Situ Test 92.6 2.12 802 Not Indeterminatef 99 No SG 3E-088 106 78 91.7 3.05 B03 2874 No No NA NA 78.8 3.84 B02 No Yes NA NA SG 3E-088 107 77 5160 47.5 3.22 B08 No* Yes NA NA t Failure of SIPC predicted analytically, not proven otherwise by in-situ test. Failure assumed.
- AILPC failed at the B03 TTW flaw. Test inconclusive for this flaw.
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A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-10: CM Limit for SG 3E-088 TTW, ETSS 27902.2, Structural Dimensions 1nn I
90 80
- 70o CL 60 ty 50 -~~ ~ -~* - *.**
0j AAA AALA AAA AA 40 4 A
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- Analytical CM Failure
- Analytical CM Success 10 0
0 1 2 3 4 5 6 7 8 9 Structurally Equivalent Length (Inches)
Page 71 1814-AU651-MO1 58, REV.
1814-AU651-MO158, REV. 00 Page 71 Page of 98 71 of 98 Page 71
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-11: CM Limit for SG 3E-089 TTW, ETSS 27902.2, Structural Dimensions 100 90 80 70 II L
0 C 60 ICr 50*
- a. A,,,
40 AA.h A A A W-AA A A4 A-A A Ak 4 30
- - - CM Limit 20 41
10 0 +/--
0 1 2 3 4 5 6 7 8 9 Structurally Equivalent Length (inches)
Page 72 1814-AU651-MO158, REV. 0 1814-AU651-MO1 58, REV. 0 Page 72 Page of 98 72 of 98 Page 72
A Document No.: 51-9180143-001 ARE VA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-12: In-Situ Test Results for SG 3E-088 TTW, ETSS 27902.2, Structural Dimensions 100
- 102-78
-- - CM Limit 90 + 104-78
- 104-78 + 106-78
- Pass
- Failed 80 IIncomplete
+ 100-80
- 107-77
+98-8r101-81**99-81 70 CL
+
60 C.
0 Ca t0 50
+
0*
40 30 20 "Incomplete" = Flaw is in a tube that has been tested and a largerflaw failed 10 before full test pressurecould be reached 0
0 1 2 3 4 5 6 7 8 9 Structurally Equivalent Length (inches)
Page 73 1814-AU651-MO158, REV. 00 1814-AU651-MQ1 58, REV. Page 73 Page 73 ofof 98 98 Page 73
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Figure 8-13: In-Situ Test Results for SG 3E-089 TTW, ETSS 27902.2, Structural Dimensions 100 90 - CM Limit
- Pass 80 Failed 0 Incomplete 70 l CL 60 Cr 50
. . . . .. . .. . . * - - -e -
w ~4 4, 4 40 30 U)
LU -i 10 0
0 1 2 3 4 5 6 7 8 9 Structurally Equivalent Length (inches) 1814-AU651-M10158, REV. 0 Page 74 of 98 Page 74
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report 9.0 CONDITION MONITORING CONCLUSION This condition monitoring assessment has evaluated all SG tube degradation detected during the Unit 3 2012 leaker outage against the three SONGS Technical Specification performance criteria. Through a combination of eddy current inspection, analytical evaluation, in-situ pressure testing, and operational leakage monitoring, the following conclusions are drawn:
- 1) Despite the fact that operational SG tube leakage resulted in a forced outage, the leak rate remained below the Technical Specification limit (150 GPD); therefore the operational leakage integrity performance criterion was met.
- 2) A total of eight tubes failed to meet the structural integrity performance criterion due to tube-to-tube wear and tube support plate wear.
- 3) A total of three tubes failed to meet the accident-induced leakage performance criterion due to tube-to-tube wear and tube support plate wear.
Page 75 1814-AU651-MO158, REV. 0 1814-AU651-MOI 58, REV. Page Page 75 of 0 75 of 98 98 Page 75
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report
10.0 REFERENCES
- 3. EPRI Report 1014983, "Steam Generator In Situ Pressure Test Guidelines, Revision 3", August 2007.
- 4. EPRI Report 1019037 "Steam Generator Degradation Specific Management Flaw Handbook",
Revision 1, with error correction in J. Benson email dated 3/30/2012, December 2009.
- 6. AREVA Document 51-9176667-001, "SONGS 2C17 & 3C17 Steam Generator Degradation Assessment."
- 7. AREVA Document 51-9104383-002, "SONGS Units 2 & 3 Replacement Steam Generator Eddy Current Technique Validation."
- 8. AREVA Document 32-5033045-002, "Mathcad Implementation of SG Flaw Handbook Equations for Integrity Assessment".
- 9. *Matheny, Southern California Edison, "Numerical Values for the SG OAs, SONGS Units 2 and 3", February 8, 2012
- 10. *SONGS Unit 3 Replacement Steam Generator Receipt Inspection QA Document Review Package
- 11. AREVA Document 51-9179808-000, "In-Situ Pressure Test Results for SONGS U3F16B Outage."
- 12. *MHI, "SONGS Unit 2 & 3 RSGs, Regulatory Guide 1.121 Analysis," S023-617-1-C1262, Rev. 4
- 13. AREVA Document 51-9177744-000 "Site Validation of EPRI Sizing ETSS for Tube-Tube Wear in SONGS Steam Generators".
- 14. AREVA Document 51-9179946-001, "Comparison of Bobbin and +Point POD for Tube-Tube Wear in SONGS Steam Generators".
- 15. SCE Licensee Event Report 2012-001-00, "Unit 3 Manual Reactor Trip due to Steam Generator Tube Leak", March 29 2012.
- 16. SONGS Technical Specifications Section 5.5.2.11, "Steam Generator (SG) Program".
1814-AU651 -M01 58, REV. 0 Page 76 of 98 Page 76
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report
- 18. INPO Operating Experience Report OE 34946, "Tube -to-Tube Contact Wear Identified in TMI-1 Steam Generators (TMI-1)".
- 19. NRC Information Notice 2012-7, "Tube-to-Tube Contact Resulting in Wear in Once Through Steam Generators".
- 20. INPO Operating Experience Report OE 35359, "Large Number of Anti-Vibration Bar Wear Indications Reported in the Unit 2 Replacement Steam Generators (St. Lucie)."
- 21. *MHI Document L5-04GA1 11, "San Onofre Generating Station, Units 2 & 3 Replacement Steam Generators Vendor Manual", Rev 6 (SONGS Document S023-617-1-M1273, Rev 6).
- These references are not available from the AREVA NP records center. However, they are available from the SCE document control system. Therefore, this is an acceptable reference for use on this contract per AREVA NP Procedure 0402-01, Attachment 8 as authorized by the PM signature on page 2 1814-AU651-MO158, REV. 0 Page 77 of 98 Page 77
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Appendix A SG 3E-088 Plugging List Page 78 1814-AU651-MO158, REV. 0 Page 78 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold L Reason for Tube Repair Rev 3E088 117 81 ROLLSTAB (750") ROLLED AVB Wear >-35% Rev3 3E088 108 34 ROLLED ROLLED Preventative - Retainer Bar Reva 3E088 110 34 ROLLSTAB (688") ROLLED Preventative - Retainer Bar Revi 3E088 109 35 ROLLSTAB (668") ROLLED Preventative - Retainer Bar Revl 3E088 111 35 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 110 36 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 112 3I ROLLED ROLLED Preventative - Retainer Bar Revl Revi 3E088 111 37 ROLLED ROLLED Preventative - Retainer Bar 37 ROLLED ROLLED Preventative - Retainer Bar Reva 3E088 13 38 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 112 38 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 114 39 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 113 39 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 115 40 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 114 40 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 116 41 ROLLED ROLLED Preventative -Retainer Bar Revl 3E088 115 41 ROLLED ROLLED Preventative -Retainer Bar Revi 3E088 117 42 ROLLED ROLLED Preventative -Retainer Bar Revl 3E088 116 42 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 118 43 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 117 43 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 119 44 ROLLED ROLLED Preventative - Retainer Bar RevIl 3E088 118 44 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 120 45 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 119 45 ROLLSTAB (668E) ROLLED Preventative - Retainer Bar Revl 3E088 121 46 ROLLSTAB (668") ROLLED Preventative - Retainer Bar Revl 3E088 120 46 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 122 47 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 121 47 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 123 40 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 122 48 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 124 49 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 123 50 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 124 50 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 126 51 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 125 51 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 127 52 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 126 52 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 128 53 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 127 53 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 129 54 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 128 54 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 130 55 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 129 55 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 131 Page 79 1814-AU651 -M01 58, REV. 0 Page 79 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E088 130 56 ROLLSTAB (668") ROLLED Preventative - Retainer Bar Revl 3E088 132 56 ROLLSTAB (668") ROLLED Preventative - Retainer Bar Revl 3E088 131 57 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 131 121 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 130 122 ROLLSTAB (668") ROLLED Preventative - Retainer Bar Revl 3E088 132 122 ROLLSTAB (668") ROLLED Preventative - Retainer Bar Revl 3E088 129 123 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 131 123 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 128 124 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 130 124 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 127 125 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 129 125 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 126 126 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 125 127 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 127 127 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 124 128 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 126 128 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 123 129 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 125 129 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 122 130 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 124 130 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 121 131 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 123 131 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 120 132 ROLLSTAB (668') ROLLED Preventative - Retainer Bar Revl 3E088 122 132 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 119 133 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 121 133 ROLLSTAB (668") ROLLED Preventative - Retainer Bar Revl 3E088 118 134 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 120 134 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 117 135 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 119 135 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 116 136 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 118 136 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 115 137 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 114 138 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 116 138 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 113 139 ROLLED ROLLED Preventative - Retainer Bar Revi 3E088 115 139 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 112 140 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 114 140 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 111 141 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 113 141 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 110 142 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 112 142 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 109 143 ROLLSTAB (668") ROLLED Preventative - Retainer Bar Revl Page 80 1814-AU651-M01 58, REV. 0 Page 80 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E088 111 143 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 108 144 ROLLED ROLLED Preventative - Retainer Bar Revl 3E088 110 144 ROLLSTAB (668") ROLLED Preventative - Retainer Bar Revi 3E088 92 74 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 94 74 ROLLSTAB (750') ROLLED Preventative (MHI for TTVW Rev4 3E088 102 74 ROLLSTAB (750") ROLLED Preventative (MHI for TTVW Rev4 3E088 106 74 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 108 74 ROLLSTAB (780") ROLLED Preventative (MHi for TTW.) Rev4 3E088 93 75 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 95 75 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 121 75 ROLLSTAB (780") ROLLED Preventative (MHIfor TTW) Rev4 3E088 92 76 ROLLSTAB (750") ROLLED Preventative (MHi for TrW) Rev4 3E088 94 76 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 96 78 ROLLSTAB (750") ROLLED Preventative (MHi for TTW) Rev4 3E088 116 76 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 122 76 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 124 76 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 81 77 ROLLSTAB (668') ROLLED Preventative (MHI for TTW) Rev4 3E088 87 77 ROLLSTAB (750") ROLLED Preventative (MHIfor TTW) Rev4 3E088 89 77 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 93 77 ROLLSTAB (750") ROLLED Preventative (MHI for TTVW Rev4 3E088 95 77 ROLLSTAB (750") ROLLED Preventative (MHi for TTW) Rev4 3E088 97 77 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 123 77 ROLLSTAB (780") ROLLED Preventative (MHI for TfW) Rev4 3E088 125 77 ROLLSTAB (780") ROLLED Preventative (MHi for TTW) Rev4 3E088 80 78 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev4 3E088 82 78 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev4 3E088 84 78 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev4 3E088 86 78 ROLLSTAB (668") ROLLED Preventative (MHIfor TTW) Rev4 3E088 88 78 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 90 78 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 92 78 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 94 78 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 124 78 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 130 78 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 81 79 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev4 3E088 83 79 ROLLSTAB (668") ROLLED Preventative (MHI for TrW) Rev4 3E088 85 79 ROLLSTAB (668") ROLLED Preventative (MHI for TTV) Rev4 3E088 87 79 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 89 79 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 91 79 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 93 79 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 123 79 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 80 80 ROLLSTAB (668") ROLLED Preventative (MHI for TTV Rev4 3E088 82 80 ROLLSTAB (668") ROLLED Preventative (MHI for TT" Rev4 Page 81 1814-AU651-MO158, REV. 0 Page 81 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E088 84 80 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev4 3E088 88 80 ROLLSTAB (750-) ROLLED Preventative (MHI for TTW) Rev4 3E088 90 80 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 92 80 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 120 80 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 122 80 ROLLSTAB (780") ROLLED Preventative (MHI for T1W) Rev4 3E088 124 80 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 79 81 ROLLSTAB (868') ROLLED Preventative (MHI for TTV) Rev4 3E088 81 81 ROLLSTAB (668') ROLLED Preventative (MHI for TW) Rev4 3E088 83 81 ROLLSTAB (68") ROLLED Preventative (MHI for TTW) Rev4 3E088 85 81 ROLLSTAB (688") ROLLED Preventative (MHI for TTV) Rev4 3E088 87 81 ROLLSTAB (750") ROLLED Preventative (MHI for TT'V) Rev4 3E088 89 81 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 91 81 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 119 81 ROLLSTAB (780") ROLLED Preventative (MHI for TTV) Rev4 3E088 121 81 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 80 82 ROLLSTAB (788") ROLLED Preventative (MHI for TTV) Rev4 3E088 82 82 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev4 3E088 84 82 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev4 3E088 88 82 ROLLSTAB (668') ROLLED Preventative (MHI for TTW) Rev4 3E088 88 82 ROLLSTAB (750") ROLLED Preventative (MHI for -1W) Rev4 3E088 90 82 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 92 82 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 116 82 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 118 82 ROLLSTAB (780") ROLLED Preventative (MHI for TTV) Rev4 3E088 124 82 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 85 83 ROLLSTAB (668") ROLLED Preventative (MHI for TTV) Rev4 3E088 87 83 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 89 83 ROLLSTAB (750') ROLLED Preventative (MHI for TTW) Rev4 3E088 115 83 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 117 83 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 125 83 ROLLSTAB (780") ROLLED Preventative (MHI for TTV) Rev4 3E088 84 84 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev4 3E088 88 84 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 114 84 ROLLSTAB (780") ROLLED Preventative (MHI for TT" Rev4 3E088 118 84 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 83 85 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev4 3E088 85 85 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev4 3E088 87 85 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 89 85 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 1 13 85 ROLLSTAB (780") ROLLED Preventative (MHI for -rw) Rev4 3E088 117 85 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 119 85 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 121 85 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 84 88 ROLLSTAB (688") ROLLED Preventative (MHI for TTW) Rev4 Page 82 1814-AU651-M01 58, REV. 0 Page 82 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E088 86 86 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev4 3E088 88 86 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 90 86 ROLLSTAB (750") ROLLED Preventative (MHI for TTV) Rev4 3E088 92 86 ROLLSTAB (750") ROLLED Preventative (MHI for "TVT Rev4 3E088 108 86 ROLLSTAB (780") ROLLED Preventative (MHI for 1TVW Rev4 3E088 110 86 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 112 86 ROLLSTAB (780-) ROLLED Preventative (MHI for Trw) Rev4 3E088 85 87 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev4 3E088 89 87 ROLLSTAB (750") ROLLED Preventative (MHI for Trw) Rev4 3E088 91 87 ROLLSTAB (750") ROLLED Preventative (MHI for T 'W) Rev4 3E088 93 109 87 87 ROLLSTAB (750") ROLLED Preventative (MHI for TTVV) Rev4 ROLLSTAB (780") ROLLED Preventative (MHI for TTV 3E088 111 87 ROLLSTAB (780") Rev4 ROLLED Preventative (MHI for TTW) Rev4 3E088 113 87 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 92 88 ROLLSTAB (750") ROLLED Preventative (MHI for T7r) Rev4 3E088 108 88 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 110 88 ROLLSTAB (780") ROLLED Preventative (MHI for lTW) Rev4 3E088 112 88 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 116 88 ROLLSTAB (780") ROLLED Preventative (MHI for 11W Rev4 3E088 118 88 ROLLSTAB (780") ROLLED Preventative (MHI for l-Vv) Rev4 3E088 93 89 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 95 89 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 97 89 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 109 89 ROLLSTAB (780") ROLLED Preventative (MHI for TT'V Rev4 3E088 111 89 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 94 90 ROLLSTAB (750") ROLLED Preventative (MHI for TTV" Rev4 3E088 96 90 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 98 90 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 100 90 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 102 90 ROLLSTAB (750") ROLLED Preventative (MHI for TTV) Rev4 3E088 108 90 ROLLSTAB (780") ROLLED Preventative (MHI for 11W Rev4 3E088 112 90 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 89 91 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 95 91 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 97 91 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 99 91 ROLLSTAB (750") ROLLED Preventative (MHI for TTVV) Rev4 3E088 101 91 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 103 91 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 105 91 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 107 91 ROLLSTAB (750") ROLLED Preventative (MHI for TTw) Rev4 3E088 94 92 ROLLSTAB (750") ROLLED Preventative (MHI for Trw) Rev4 3E088 98 92 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 98 92 ROLLSTAB (750") ROLLED Preventative (MHI for 1-lW) Rev4 3E088 100 92 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 102 92 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 Page 83 1814-AU651-M0158, REV. 0 Page 83 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E088 104 92 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 106 92 ROLLSTAB (750') ROLLED Preventative (MHI for TTW) Rev4 3E088 108 92 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev4 3E088 89 93 ROLLSTAB (750") ROLLED Preventative (MHI for Tl-w) Rev4 3E088 93 93 ROLLSTAB (750") ROLLED Preventative (MHI for TTw) Rev4 3E088 95 93 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 97 93 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 99 93 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 101 93 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 105 93 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 107 93 ROLLSTAB (750") ROLLED Preventative (MHI for TT) Rev4 3E088 88 94 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 94 94 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 89 95 ROLLSTAB (750") ROLLED Preventative (MHI for "IW) Rev4 3E088 88 96 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 90 96 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 92 96 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 89 97 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 91 97 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev4 3E088 87 75 ROLLSTAB (750") ROLLED Preventative (Six Consecutive AVB Wear) Rev5 3E088 78 80 ROLLSTAB (750") ROLLED Preventative (Six Consecutive AVB Wear) Rev5 3E088 109 73 ROLLSTAB (780") ROLLED Preventative (TTW Fence) Rev4 3E088 111 73 ROLLSTAB (780") ROLLED Preventative (TTW Fence) Rev4 3E088 113 73 ROLLSTAB (780") ROLLED Preventative (TTW Fence) Rev4 3E088 115 73 ROLLSTAB (780") ROLLED Preventative (TTW Fence) Rev4 3E088 100 74 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev4 3E088 104 74 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev4 3E088 116 74 ROLLSTAB (780") ROLLED Preventative (TTW Fence) Rev4 3E088 97 75 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev4 3E088 99 75 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev4 3E088 117 75 ROLLSTAB (780") ROLLED Preventative (TTW Fence) Rev4 3E088 119 75 ROLLSTAB (780") ROLLED Preventative (TTW Fence) Rev4 3E088 125 49 ROLLSTAB (668") ROLLED Retainer Bar Wear Revi 3E088 128 126 ROLLSTAB (668") ROLLED Retainer Bar Wear Revl 3E088 117 137 ROLLSTAB (668") ROLLED Retainer Bar Wear Revl 3E088 110 74 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 112 74 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 114 74 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 101 75 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 103 75 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 105 75 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 107 75 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 109 75 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 111 75 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 113 75 ROLLSTAB (750") ROLLED U-bend TTW Rev3 Page 84 1814-AU651-M0158, REV. 0 Page 84 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E088 115 75 ROLLSTAB (750') ROLLED U-bend TTW Rev3 3E088 98 76 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 100 76 ROLLSTAB (750-) ROLLED U-bend TTW Rev3 3E088 102 76 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 104 76 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 106 76 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 108 76 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 110 76 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 112 76 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 114 76 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 118 76 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 120 76 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 99 77 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 101 77 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 103 77 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 105 77 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 107 77 ROLLSTAB (780") ROLLED U-bend TTW RevO 3E088 109 77 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 111 77 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 113 77 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 115 77 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 117 77 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 119 77 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 121 77 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 96 78 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 98 78 ROLLSTAB (750") ROLLED U-bend TTWl Rev3 3E088 100 78 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 102 78 ROLLSTAB (780") ROLLED U-bend TTW RevO 3E088 104 78 ROLLSTAB (780") ROLLED U-bend TTW RevO 3E088 106 78 ROLLSTAB (780") ROLLED U-bend TTW RevO 3E088 108 78 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 110 78 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 112 78 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 114 78 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 116 78 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 118 78 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 120 78 ROLLSTAB (750") ROLLED U-bend T'11W Rev2 3E088 122 78 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 95 79 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 97 79 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 99 79 ROLLSTAB (750") ROLLED U-bend 11W Rev3 3E088 101 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 103 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 103 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 107 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 Page 85 1814-AU651-MO158, REV. 0 Page 85 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E088 109 79 ROLLSTAB (750') ROLLED U-bend TTW Rev2 3E088 111 79 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 113 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 115 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 117 79 ROLLSTAB (750') ROLLED U-bend TTW Rev2 3E088 119 79 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 121 79 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 94 80 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 96 80 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 98 80 ROLLSTAB (780") ROLLED U-bend TTW RevO 3E088 100 80 ROLLSTAB (780") ROLLED U-bend TTW RevO 3E088 102 80 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 104 80 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 106 80 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 108 80 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 110 80 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 112 80 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 114 80 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 116 80 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 118 80 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 93 81 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 95 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 97 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 99 81 ROLLSTAB (780") ROLLED U-bend TTW RevO 3E088 101 81 ROLLSTAB (780") ROLLED U-bend TTW RevO 3E088 103 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 105 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 107 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 109 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 111 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 113 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 115 81 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 94 82 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 96 82 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 98 82 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 100 82 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 102 82 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 104 82 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 106 82 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 108 82 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 110 82 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 112 82 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 114 82 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 91 83 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 93 83 ROLLSTAB (750") ROLLED U-bend TTW Rev2 Page 86 1814-AU651-M0158, REV. 0 Page 86 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report S/G Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E088 95 83 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 97 83 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 99 83 ROLLSTAB (750-) ROLLED U-bend TTW Rev2 3E088 101 83 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 103 83 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 105 83 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 107 83 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 109 83 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 111 83 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 113 83 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 90 84 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 92 84 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 94 84 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 96 84 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 98 84 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 100 84 ROLLSTAB (75(0) ROLLED U-bend TTW Rev2 3E088 102 84 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 104 84 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 108 84 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 108 84 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 110 84 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 112 84 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 91 85 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 93 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 95 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 97 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 99 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 101 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 103 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 105 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 107 85 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 109 85 ROLLSTAB (75(0) ROLLED U-bend TTW Rev3 3E088 111 85 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 94 88 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3EO88 98 86 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 98 86 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 100 86 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 102 86 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 104 86 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 108 86 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 95 87 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 97 87 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 99 87 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 101 87 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 103 87 ROLLSTAB (750") ROLLED U-bend TTW Rev2 Page 87 1814-AU651-M0158, REV. 0 Page 87 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E088 105 87 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 107 87 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 94 88 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 96 88 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 98 88 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 100 88 ROLLSTAB (750') ROLLED U-bend TTW Rev2 3E088 102 88 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 104 88 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E088 106 88 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 99 89 ROLLSTAB (750') ROLLED U-bend TTW Rev3 3E088 101 89 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 103 89 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 105 89 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 107 89 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 104 90 ROLLSTAB (750") ROLLED U-bend TTW Rev3 3E088 106 90 ROLLSTAB (750") ROLLED U-bend TTW Rev3 Page 88 1814-AU651-MO158, REV. 0 Page 88 of 98
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report Appendix B SG 3E-089 Plugging List Page 89 1814-AU651-MO158, REV. 0 Page 89 of 98
A Document No.: 51-9180143-001 AR EVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report S/G Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E089 108 34 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 110 34 ROLLSTAB (668") ROLLED Preventative - Retainer Bar RevO 3E089 109 35 ROLLSTAB (668") ROLLED Preventative - Retainer Bar RevO 3E089 111 35 ROLLED ROLLED Preventative - Retainer Bar Rev0 3E089 110 36 ROLLED ROLLED Preventative - Retainer Bar Rev0 3E089 112 36 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 111 37 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 113 37 ROLLED ROLLED Preventative - Retainer Bar Revi 3E089 112 38 ROLLED ROLLED Preventative - Retainer Bar Rev,0 3E089 114 38 ROLLED ROLLED Preventative - Retainer Bar Rev0 3E089 113 39 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 115 39 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 114 40 ROLLED ROLLED Preventative - Retainer Bar Rev0 3E089 116 40 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 115 41 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 117 41 ROLLED ROLLED Preventative - Retainer Bar Rev0 3E089 116 42 ROLLED ROLLED Preventative - Retainer Bar Revi 3E089 118 42 ROLLED ROLLED Preventative - Retainer Bar Rev0 3E089 117 43 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 119 43 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 118 44 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 120 44 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 119 45 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 121 45 ROLLSTAB (668") ROLLED Preventative - Retainer Bar RevO 3E089 120 46 ROLLSTAB (668") ROLLED Preventative - Retainer Bar RevO 3E089 122 46 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 121 47 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 123 47 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 122 48 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 124 48 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 123 49 ROLLED ROLLED Preventative - Retainer Bar Revi 3E089 125 49 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 124 50 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 126 50 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 125 51 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 127 51 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 126 52 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 128 52 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 127 53 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 129 53 ROLLED ROLLED Preventative - Retainer Bar Rev0 3E089 128 54 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 130 54 ROLLED ROLLED Preventative - Retainer Bar Revi 3E089 129 55 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 131 55 ROLLED ROLLED Preventative - Retainer Bar RevO Page 90 1814-AU651-MO158, REV. 0 Page 90 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E089 130 56 ROLLSTAB (668) ROLLED Preventative - Retainer Bar RevO 3E089 132 56 ROLLSTAB (668") ROLLED Preventative - Retainer Bar RevO 3E089 131 57 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 131 121 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 130 122 ROLLSTAB (6W68) ROLLED Preventative - Retainer Bar RevO 3E089 132 122 ROLLSTAB (668-) ROLLED Preventative - Retainer Bar RevO 3E089 129 123 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 131 123 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 128 124 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 130 124 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 127 125 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 129 125 ROLLED ROLLED Preventative - Retainer Bar Rev0 3E089 126 126 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 128 126 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 125 127 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 127 127 ROLLED ROLLED Preventative - Retainer Bar Revi 3E089 124 128 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 126 128 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 123 129 ROLLED ROLLED Preventative - Retainer Bar Revi 3E089 125 129 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 122 130 ROLLED ROLLED Preventative - Retainer Bar Revi 3E089 121 131 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 123 131 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 120 132 ROLLSTAB (661r) ROLLED Preventative - Retainer Bar RevO 3E089 122 132 ROLLED ROLLED Preventative - Retainer Bar Rev0 3E089 119 133 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 121 133 ROLLSTAB (668) ROLLED Preventative - Retainer Bar RevO 3E089 118 134 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 120 134 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 117 135 ROLLED ROLLED Preventative- Retainer Bar RevO 3E089 119 135 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 116 136 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 118 136 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 115 137 ROLLED ROLLED Preventative - Retainer Bar Revi 3E089 117 137 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 114 138 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 116 138 ROLLED ROLLED Preventative - Retainer Bar Rev0 3E089 113 139 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 115 139 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 112 140 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 114 140 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 ill 141 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 113 141 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 110 142 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 112 142 ROLLED ROLLED Preventative - Retainer Bar RayO Page 91 1814-AU651-M01 58, REV. 0 Page 91 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E089 109 143 ROLLSTAB (668") ROLLED Preventative - Retainer Bar RevO 3E089 111 143 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 108 144 ROLLED ROLLED Preventative - Retainer Bar RevO 3E089 110 144 ROLLSTAB (668") ROLLED Preventative - Retainer Bar RevO 3E089 85 75 ROLLSTAB (668") ROLLED Preventative (MHI for TT W) Rev3 3E089 3E089 97 75 ROLLSTAB (750") ROLLED Preventative (MHI for TTV) Rev3 94 76 ROLLSTAB (750")
3E089 86 76 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev3 Preventative (MHI for TVW) 3E089 96 76 Rev3 ROLLSTAB (750") ROLLED Preventative (MHI for TT'W) Rev3 3E089 98 76 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 100 76 ROLLSTAB (750") ROLLED Preventative (MHI for TTV) Rev3 3E089 83 77 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev3 3E089 87 77 ROLLSTAB (760") ROLLED Preventative (MHI for TTW) Rev3 3E089 93 77 ROLLSTAB (750") ROLLED Preventative (MHi for T"W) Rev3 3E089 107 77 ROLLSTAB (750") ROLLED Preventative (MHI for TTV) Rev3 3E089 86 78 ROLLSTAB (868") ROLLED Preventative (MHI for TTW) Rev3 3E089 88 78 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 92 78 ROLLSTAB (750") ROLLED Preventative (MHI for TT"W Rev3 3E089 94 78 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 83 79 ROLLSTAB (668") ROLLED Preventative (MHI for TTVV) Rev3 3E089 85 79 ROLLSTAB (668-) ROLLED Preventative (MHI for TTW) Rev3 3E089 87 79 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 89 79 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 91 79 ROLLSTAB (7560) ROLLED Preventative (MHI for T"W Rev3 3E089 115 79 ROLLSTAB (780") ROLLED Preventative (MHI for TTV) Rev3 3E089 86 80 ROLLSTAB (668") ROLLED Preventative (MHI for TTr) Rev3 3E089 88 80 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 90 80 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 110 80 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 114 80 ROLLSTAB (780") ROLLED Preventative (MHi for TTW) Rev3 3E089 87 81 ROLLSTAB (750") ROLLED Preventative (MHt for TTW) Rev3 3E089 109 81 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 84 82 ROLLSTAB (668") ROLLED Preventative (MHi for TTW) Rev3 3E089 86 82 ROLLSTAB (750") ROLLED Preventative (MHI for TTV) Rev3 3E089 86 82 ROLLSTAB (750") ROLLED Preventative (MHI for T'W) Rev3 3E089 108 82 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 112 82 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 118 82 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 120 82 ROLLSTAB (780T) ROLLED Preventative (MHI for TTW) Rev3 3E089 83 83 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev3 3E089 85 83 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 109 83 ROLLSTAB (750") ROLLED Preventative (MHi for TTW) Rev3 3E089 111 83 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 113 83 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 117 83 ROLLSTAB (780") ROLLED Preventative (MHI for TTV) Rev3 Page 92 1814-AU651-MO158, REV. 0 Page 92 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E089 119 83 ROLLSTAB (780-) ROLLED Preventative (MHI for TTW)
TTW) Rev3 ROLLED Preventative (MHI for 82 84 ROLLSTAB (668")
3E089 Preventative (MHI for TTW) Rev3 3E089 84 84 ROLLSTAB (6507) ROLLED Preventative (MHI for TTW) Rev3 3E089 108 84 ROLLSTAB (750") ROLLED Preventative (MHI for TTVV) Rev3 3E089 110 84 ROLLSTAB (780() ROLLED Preventative (MHI for TTW) Rev3 3E089 112 84 ROLLSTAB (78(0) ROLLED Preventative (MHI for TTVV) Rev3 3E089 114 84 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 81 85 ROLLSTAB (668") ROLLED Preventative (MHI for TTW) Rev3 3E089 83 85 ROLLSTAB (750') ROLLED Preventative (MHI for TFW) Rev3 3E089 109 85 ROLLSTAB (750") ROLLED Preventative (MHI for TrW) Rev3 3E089 101 85 ROLLSTAB (7850) ROLLED Preventative (MHI for TTW) Rev3 3E089 113 85 ROLLSTAB (78(0) ROLLED Preventative (MHI for TTW) Rev3 3E089 115 85 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 117 85 ROLLSTAB (78(0) ROLLED Preventative (MHI for 1-W) Rev3 3E089 84 85 ROLLSTAB (75(7) ROLLED Preventative (MHI for TTW) Rev3 3E089 86 86 ROLLSTAB (750') ROLLED Preventative (MHI for TTW) Rev3 3E089 110 86 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 112 88 ROLLSTAB (78(0) ROLLED Preventative (MHI for TTW) Rev3 3E089 114 86 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 116 86 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 109 87 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 111 87 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 113 87 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 115 87 ROLLSTAB (78(r) ROLLED 3E089 Preventative (MHI for TTW) Rev3 3E089 108 88 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 110 88 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 112 88 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 114 88 ROLLSTAB (780") ROLLED 3E089 Preventative (MHI for TTW) Rev3 3E089 118 88 ROLLSTAB (78(0) ROLLED Preventative (MHI for TTW) Rev3 3E089 83 89 ROLLSTAB (750") ROLLED Preventative (MHI for TrW) Rev3 3E089 109 89 ROLLSTAB (750") ROLLED Preventative (MHt for TTW) Rev3 3E089 111 89 ROLLSTAB (7850) ROLLED Preventative (MHI for TTW) Rev3 3E089 113 89 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 115 89 ROLLSTAB (78(0) ROLLED Preventative (MHI for TTW) Rev3 108 90 ROLLSTAB (7580) ROLLED 3E089 Preventative (MHI for TTW) Rev3 3E089 110 90 ROLLSTAB (7850) ROLLED Preventative (MHI for TTW) Rev3 3E089 114 90 ROLLSTAB (78(0) ROLLED Preventative (MHI for TTW) Rev3 85 91 ROLLSTAB (750") ROLLED 3E089 Preventative (MHI for TTW) Rev3 3E089 105 91 ROLLSTAB (750") ROLLED Preventative (MHI for TTw) Rev3 3E089 107 91 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 109 91 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 111 91 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 113 91 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 102 92 ROLLSTAB (7580) ROLLED Preventative (MHI for TTW) Rev3 3E089 104 92 ROLLSTAB (75(0) ROLLED Page 93 1814-AU651-MO158, REV. 0 Page 93 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E089 106 92 ROLLSTAB (750") ROLLED Preventative (MHI for TTVv) Rev3 3E089 108 92 ROLLSTAB (750") ROLLED Preventative (MHI for TfV) Rev3 3E089 110 92 ROLLSTAB (780") ROLLED Preventative (MHI for TT") Rev3 3E089 112 92 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 97 93 ROLLSTAB (750") ROLLED Preventative (MHI for TrW) Rev3 3E089 99 93 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 101 93 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 105 93 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 107 93 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 109 93 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 111 93 ROLLSTAB (780') ROLLED Preventative (MHI for TrW) Rev3 3E089 88 94 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 92 94 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 94 94 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 96 94 ROLLSTAB (750") ROLLED Preventative (MHt for TTW) Rev3 3E089 98 94 ROLLSTAB (750") ROLLED Preventative (MHt for TTW) Rev3 3E089 100 94 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 102 94 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 106 94 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 108 94 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 110 94 ROLLSTAB (780") ROLLED Preventative (MHI for TTW) Rev3 3E089 91 95 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 93 95 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 99 95 ROLLSTAB (750") ROLLED Preventative (MHI for TTV) Rev3 3E089 101 95 ROLLSTAB (750") ROLLED Preventative (MHI for TTW/) Rev3 3E089 107 95 ROLLSTAB (750") ROLLED Preventative (MHI for TTW) Rev3 3E089 85 81 ROLLSTAB (750") ROLLED Preventative (Six Consecutive AVB Wear) Rev4 3E089 122 88 ROLLSTAB (750") ROLLED Preventative (Six Consecutive AVB Wear) Rev4 3E089 101 75 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev3 3E089 103 75 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev3 3E089 105 75 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev3 3E089 106 76 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev3 3E089 109 77 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev3 3E089 110 78 ROLLSTAB (780) ROLLED Preventative (TTW Fence) Rev3 3E089 111 79 ROLLSTAB (780") ROLLED Preventative (TTW Fence) Rev3 3E089 83 87 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev3 3E089 82 88 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev3 3E089 84 90 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev3 3E089 86 92 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev3 3E089 85 93 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev3 3E089 86 94 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev3 3E089 90 94 ROLLSTAB (750") ROLLED Preventative (TTW Fence) Rev3 3E089 124 130 ROLLSTAB (668") ROLLED Retainer Bar Wear RevO 3E089 102 76 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 104 76 ROLLSTAB (750") ROLLED U-bend TTW Rev2 Page 94 1814-AU651-MO158, REV. 0 Page 94 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report S/G Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E089 95 77 ROLLSTAB (750r) ROLLED U-bend TTW Rev2 3E089 97 77 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 99 77 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 101 77 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 103 77 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 105 77 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 96 78 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 98 78 ROLLSTAB (750') ROLLED U-bend TTW Revi 3E089 100 78 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 102 78 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 104 78 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 106 78 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 108 78 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 93 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 95 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 97 79 ROLLSTAB (750') ROLLED U-bend TTW Rev2 3E089 99 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 101 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 103 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 105 79 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 107 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 109 79 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 92 80 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 94 80 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 96 80 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 98 80 ROLLSTAB (750") ROLLED U-bend TTW Revi 3E089 100 80 ROLLSTAB (750") ROLLED U-bend TTW Revi 3E089 102 80 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 104 80 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 106 80 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 108 80 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 89 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 91 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 93 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 95 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 97 81 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 99 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 101 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 103 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 105 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 107 81 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 90 82 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 92 82 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 94 82 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 96 82 ROLLSTAB (750') ROLLED U-bend TTW Rev2 Page 95 1814-AU651-MO158, REV. 0 Page 95 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SlG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E089 98 82 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 100 82 ROLLSTAB (750-) ROLLED U-bend TTW Rev2 3E089 102 82 ROLLSTAB (750-) ROLLED U-bend TTW Rev2 3E089 104 82 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 106 82 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 87 83 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 89 83 ROLLSTAB (750') ROLLED U-bend TTW Rev2 3E089 91 83 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 93 83 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 95 83 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 97 83 ROLLSTAB (780") ROLLED U-bend TTW Rev2 U-bend TTW Revl 3E089 99 83 ROLLSTAB (750") ROLLED 3E089 101 83 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 103 83 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 105 83 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 107 83 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 86 84 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 88 84 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 90 84 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 92 84 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 94 84 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 96 84 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 98 84 ROLLSTAB (750") ROLLED U-bend TTW Rev1 3E089 100 84 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 102 84 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 104 84 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 106 84 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 85 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 87 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 89 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 91 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 93 85 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 95 85 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 97 85 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 99 85 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 101 85 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 103 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 105 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 107 85 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 88 86 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 90 86 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 92 86 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 94 86 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 96 86 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 98 86 ROLLSTAB (78W") ROLLED U-bend TTW Rev2 Page 96 1814-AU651-MO158, REV. 0 Page 96 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repair Rev 3E089 100 86 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 102 88 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 104 86 ROLLSTAB (750-) ROLLED U-bend TTW Revl 3E089 106 86 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 108 86 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 85 87 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 87 87 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 89 87 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 91 87 ROLLSTAB (780") ROLLED U-bend T1W Rev2 3E089 93 87 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 95 87 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 97 87 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 99 87 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 101 87 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 103 87 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 105 87 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 107 87 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 84 87 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 86 86 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 86 88 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 90 88 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 92 88 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 94 88 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 96 88 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 98 88 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 100 88 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 102 88 ROLLSTAB (750() ROLLED U-bend TTW Revl 3E089 104 88 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 106 88 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 85 89 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 87 89 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 89 89 ROLLSTAB (780() ROLLED U-bend TTW Rev2 3E089 91 89 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 93 89 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 95 89 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 97 89 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 99 89 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 101 89 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 103 89 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 105 89 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 107 89 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 86 90 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 86 90 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 90 90 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 92 90 ROLLSTAB (780") ROLLED U-bend TTW Rev2 Page 97 1814-AU651-MO158, REV. 0 Page 97 of 98
A Document No.: 51-9180143-001 AREVA SONGS Unit 3 February 2012 Leaker Outage - Steam Generator Condition Monitoring Report SIG Row Col Hot Leg Cold Leg Reason for Tube Repalr Rev 3E089 94 90 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 96 90 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 98 90 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 100 90 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 102 90 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 104 90 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 106 90 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 87 91 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 89 91 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 91 91 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 93 91 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 95 91 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 97 91 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 99 91 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 101 91 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 103 91 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 88 92 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 90 92 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 92 92 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 94 92 ROLLSTAB (780") ROLLED U-bend TTW Rev2 3E089 96 92 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 98 92 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 100 92 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 87 93 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 89 93 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 91 93 ROLLSTAB (750") ROLLED U-bend TTW Rev2 3E089 93 93 ROLLSTAB (750") ROLLED U-bend TTW Revl 3E089 95 93 ROLLSTAB (750") ROLLED U-bend TTW Rev2 Page 98 1814-AU651-M01 58, REV. 0 Page 98 of 98