RS-09-067, Response to Request for Additional Information Regarding Relief Request CR-26
| ML091540385 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/26/2009 |
| From: | Simpson P Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-09-067 | |
| Download: ML091540385 (479) | |
Text
{{#Wiki_filter:Exelon Nuclear www.exeloncorp.com Exelkn 4300 Winfield Road Nuclear Warrenville, IL60555 RS-09-067 May 26, 2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF- 11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
Response to Request for Additional Information Regarding Relief Request CR-26
References:
- 1. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U. S. NRC, "Relief Request CR-26, Inservice Inspection Program Relief Regarding Examination Coverage for Second 10-Year Inservice Inspection Interval,"
dated October 1, 2008
- 2. Letter from S. P. Sands (U. S. NRC) to C. G. Pardee, "LaSalle County Station, Units 1 and 2 - Request for Additional Information Related to Request for Relief No. CR-26 (TAC Nos. MD9817 and MD9818)," dated April 24, 2009 In Reference 1, Exelon Generation Company, LLC (EGC) requested relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," for LaSalle County Station (LSCS) Units 1 and 2. Specifically, CR-26 requested relief on the basis that compliance with the specified requirements is impractical due to plant design. This relief applies to the second 10-year interval inservice inspection program, which concluded on October 1, 2007.
In Reference 2, the NRC provided questions to EGC to support NRC review of Reference 1. The attachments of this letter provide the requested responses.
May 26, 2009 U. S. Nuclear Regulatory Commission Page 2 There are no regulatory commitments contained in this submittal. Should you have any questions concerning this letter, please contact Ms. Tricia Mattson at (630) 657-2813. Patrick R. Simpson Manager - Licensing cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector - LaSalle County Station Attachments:
- 1. Response to Request for Additional Information
- 2. Revised Table CR-26.1
- 3. Revised Table CR-26.2
- 4. Reformatted Submittal Information Regarding Relief Requests Associated With the Second Inservice Inspection Interval
- 5. Additional Information Describing the Impracticalities Associated with the Limited Examinations
ATTACHMENT 1 Response to Request for Additional Information. NRC Request 1 Reorganize and label information from the November 18, 2008, supplemented submittal, and clearly indicate how the information from the original and supplemented submittals are connected.
Response
The information in the Attachment to Reference 1 has been reformatted to include page numbers, and is included as Attachment 4 to this letter. Additionally, Table CR-26.1 for Unit 1 and Table CR-26.2 for Unit 2 have been revised to contain cross-reference information. The original versions of these tables, submitted to the NRC in Reference 2, included a column listing the outage in which the examination was performed. This column has been replaced with a column referencing the page number(s) in Attachment 4 (i.e., the supplemental information previously submitted in the Attachment to Reference 1) that provide the details applicable to each component. The updated Table CR-26.1 and Table CR-26.2 are included as Attachments 2 and 3 of this letter. For example, the first component on Table CR-26.1 is GEL-1 009-AG. For this component, Table CR-26.1 notes that supplemental information about GEL-1009-AG can be found on pages 2, 3, 11, 16, and 22 through 25. Starting at Page 16, the drawing is entitled ISI-GEL-1 009, and the AG weld is shown on the drawing as the reactor pressure vessel (RPV) head-to-flange weld. Pages 22 through 25 contain the inspection reports for the weld, and pages 2, 3, and 11 provide details on the construction of the component. Similar cross-referencing is provided for each component. NRC Request 2 Provide additional information to better describe the impracticalities associated with each of the limited examinations.
Response
The requested information is provided in Attachment 5 of this letter. Many of the causes for the impracticality of the examinations are similar for common components. Therefore, the components and their justifications for impracticality have been grouped together where appropriate. NRC Request 3 Several of the cross-sectional drawings seem to indicate a higher percentage of coverage than is stated in the original submittal. Verify that the coverage percentages cited in the original submittal are accurate and consistent with the cross-sectional drawings. Page 1 of 3
ATTACHMENT 1 Response to Request for Additional Information
Response
The cross-sectional drawings provide an approximate depiction of the component and their associated scanned angles. Typically, there are multiple coverage percentages provided on these documents. The coverage achieved by each of the transducers is listed, and their average is listed as a composite coverage. In some cases, such as on weld GEL-1009-AG, the composite coverage was further reduced due to physical interferences, and a reduced total coverage is listed. The total coverage value is the most conservative for purposes of the proposed relief because it is typically the lowest coverage value associated with the component. The coverage values listed on Table CR-26.1 and Table CR-26.2 are the total coverage values from the cross-sectional drawings. Therefore, the coverage percentages cited in Reference 2 are accurate, conservative, and consistent with the cross-sectional drawings. NRC Request 4 Address whether or not additional coverage of the subject welds could have been achieved if advanced inspection technologies (e.g., phased array ultrasonic transducers) had been applied.
Response
The components within the scope of relief request CR-26 were examined during the second Inservice Inspection (ISI) interval, which encompassed the period from October 17, 1994, through September 31, 2007. Accepted inspection technologies for that time period were utilized to complete these examinations. These included updated equipment-based on-computer modeling of the RPV nozzles, and technology resulting from advances in ultrasonic examinations due to the Performance Demonstration Initiative (PDI). At the time, phased array technology was not generally developed by the industry to the point where it could be utilized to perform qualified examinations. Specifically, Exelon Generation Company, LLC's (EGC's) inspection vendor does not yet have a qualified phased array technique for examination of RPV welds. When such advances are available to deliver qualified examinations, they will be assessed to determine whether that they can achieve increased coverage percentages. NRC Request 5 For those subject welds associated with pump casings encased in concrete, identify any actions Exelon intends to take regarding inspection of these welds if access is gained due to pump disassembly in the future.
Response
The requested information, associated with the High Pressure Core Spray pump, Low Pressure Core Spray pump, and Residual Heat Removal pump welded attachments and casing welds, is provided in Attachment 5. Page 2 of 3
ATTACHMENT 1 Response to Request for Additional Information NRC Request 6 Identify if any indications were observed in the subject welds based upon the limited examinations that were performed, and discuss how these indications were dispositioned.
Response
Attachments 4 and 5 identify indications observed during the limited examinations of the subject welds. None of the observed indications failed to meet the applicable acceptance standards of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI. None of the indications required flaw evaluation. References
- 1. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U. S. NRC, "Supplemental Information Concerning Relief Request CR-26 Associated with the Second 10-Year Inservice Inspection (ISI) Interval," dated November 18, 2008
- 2. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U. S. NRC, "Relief Request CR-26, Inservice Inspection Program Relief Regarding Examination Coverage for Second 10-Year Inservice Inspection Interval," dated October 1, 2008 Page 3 of 3
ATTACHMENT 2 Revised Table CR-26.1 Table CR-26.1 LASALLE COUNTY STATION UNIT 1 List of Welds with Limited Examination Coverage Supplem~ental Informnation~ Page Actual Component ID Number(s) .. Coverage , . K= Remarks ., GEL-1009-AG 2, 3, 11, 16, and 71.90% RPV Head to Flange 0-180 Deg. 22 through 25 limited UT scanning from flange side of weld due to flange design. GEL-1009-DM 3, 16, and 26 77.20% RPV Head Meridional limited UT through 28 scanning due to lifting lugs. GEL-1009-DP 3, 16, and 27 77.20% RPV Head Meridional limited UT through 31 scanning due to lifting lugs. LCS-1-AF 4, 15, and 32 55.40% RPV Shell to Flange limited UT through 34 scanning from Flange side of weld. LCS-1-N1A 6,15, and 35 57.94% Reactor Recirculation nozzle to through 37 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N1B 6, 15, and 38 58.60% Reactor Recirculation nozzle to through 40 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N3A 6, 15, and 41 59.95% Main Steam nozzle to RPV through 43 limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N3B 6,15, and 44 59.95% Main Steam nozzle to RPV through 46 limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N3C 6, 15, and 47 59.95% Main Steam nozzle to RPV through 49 limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N3D 6, 15, and 50 59.95% Main Steam nozzle to RPV through 52 limited UT scanning from nozzle side of weld due to nozzle design. Page 1 of 6
ATTACHMENT 2 Revised Table CR-26.1 RH-HX1B-1 21,244, and 53 80.00% Residual Heat Removal Heat through 54 Exchanger nozzle to Head limited UT scanning from nozzle side of weld due to nozzle desiQn. HP-PU1-05 18, and 55 through 72.00% High Pressure Core Spray Pump 56 PT limited due to design of pump base support. LCS-1-N6A 8,15, and 57 69.5% Residual Heat Removal nozzle through 60 to RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N6C 8, 15, and 61 69.5% Residual Heat Removal nozzle through 64 to RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N10 7,15, and 65 72.4% Control Rod Drive nozzle to RPV through 68 limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N2B 6, 15, and 69 70.9% Reactor Recirculation nozzle to through 72 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N2C 6, 15, and 73 70.9% Reactor Recirculation nozzle to through 76 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N2D 6, 15, and 77 70.9% Reactor Recirculation nozzle to through 80 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N2E 6, 15, and 81 70.9% Reactor Recirculation nozzle to through 84 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N2F 6, 15, and 85 70.9% Reactor Recirculation nozzle to through 88 RPV limited UT scanning from nozzle side of weld due to nozzle design. Page 2 of 6
ATTACHMENT 2 Revised Table CR-26.1 through 92 RPV limited UT scanning from nozzle side of weld due to nozzle desiqn. LCS-1-N2K 6, 15, and 93 70.9% Reactor Recirculation nozzle to through 96 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N4A 8, 15, and 97 72.3% Feedwater nozzle to RPV limited through 103 UT scanning from nozzle side of weld due to nozzle design. LCS-1-N4B 8, 15, and 104 72.3% Feedwater nozzle to RPV limited through 110 UT scanning from nozzle side of weld due to nozzle design. LCS-1-N4C 8,15, and 111 72.3% Feedwater nozzle to RPV limited through 117 UT scanning from nozzle side of weld due to nozzle design. LCS-1-N4D 8, 15, and 118 72.3% Feedwater nozzle to RPV limited through 124 UT scanning from nozzle side of weld due to nozzle design. LCS-1-N4E 8,15, and 125 72.3% Feedwater nozzle to RPV limited through 133 UT scanning from nozzle side of weld due to nozzle design. LCS-1-N4F 8, 15, and 134 72.3% Feedwater nozzle to RPV limited through 139 UT scanning from nozzle side of weld due to nozzle design. IRH-HX1B-08A 21, 244, and 140 76% Residual Heat Removal Heat through 142 Exchanger Attachment limited MT/PT due to structural steel. GEL-1009-AG 2, 3, 16, and 143 49% RPV Flange to Head 180-360 through 147 Deg. limited UT scanning from Flange side of weld. GEL-1006-AJ 9, 17, and 148 19% RPV to Bottom Head Weld through 150 limited UT scanning from bottom side due to RPV Skirt. LCS-1-BG 15 and 151 75.3% Reactor Pressure Vessel through 160 Vertical Weld limited UT scanning due to proximity of instrument nozzle to RPV weld. LCS-1-BH 15 and 161 88.8% Reactor Pressure Vessel through 170 Vertical Weld limited UT scanning due to thermocouple attachments to RPV. Page 3 of 6
ATTACHMENT 2 Revised Table CR-26.1
~Sup~emntalI Information Page, Actual Component ID Nufmber(s) Coverage~ Remarks GEL-1009-DR 3 and 171 through 68% RPV Head Meridional limited UT 173 scanning due to lifting lugs.
GEL-1009-DT 3 and 174 through 68% RPV Head Meridional limited UT 177 scanning due to lifting lugs. LCS-1-N2A 6,15, and 178 83.1% Reactor Recirculation nozzle to through 181 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N2G 6, 15, and 182 83.1% Reactor Recirculation nozzle to through 185 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N2H 6, 15, and 186 83.1% Reactor Recirculation nozzle to through 190 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N5 8,15, and 191 85.5% Low Pressure Core Spray nozzle through 194 to RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N6B 8,15, and 195 83.7% Residual Heat Removal nozzle through 198 to RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N7 5, 16, and 199 87% Reactor Core Isolation Cooling through 201 nozzle to RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N8 5, 16, and 202 79% Reactor Head Vent nozzle to through 204 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N16 8,15, and 205 85.5% High Pressure Core Spray through 208 nozzle to RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-1-N18 5, 16, and 209 87% Spare nozzle to RPV limited UT through 211 scanning from nozzle side of weld due to nozzle design. RPV-SS-1 10, 11, 15, and 66% RPV Stabilizer Lug limited 212 through 214 MT/PT due to structural steel. IHP-PU1-04 18, and 215 16% High Pressure Core Spray Pump through 217 Weld MT limited due to design of pump base support. Page 4 of 6
ATTACHMENT 2 Revised Table CR-26.1 ILP-PU-04 19, and 218 24% Low Pressure Core Spray Pump through 220 Weld MT limited due to design of pump base support. IRH-PUlC-04 20, and 221 21% Residual Heat Removal Pump through 223 Weld MT limited due to design of pump base support. IHP-PU1-7A 18 0% High Pressure Core Spray Pump Weld encased in concrete. IHP-PU1-7B 18 0% High Pressure Core Spray Pump Weld encased in concrete. IHP-PU1-7C 18 0% High Pressure Core Spray Pump Weld encased in concrete. IlHP-PU1-8A 18 0% High Pressure Core Spray Pump Weld encased in concrete. IlHP-PU1-8B 18 0% High Pressure Core Spray Pump Weld encased in concrete. IHP-PU1-8C 18 0% High Pressure Core Spray Pump Weld encased in concrete. IHP-PU1-9 18 0% High Pressure Core Spray Pump Weld encased in concrete. ILP-PU1-7 19 0% Low Pressure Core Spray Pump Weld encased in concrete. ILP-PU1-8 19 0% Low Pressure Core Spray Pump Weld encased in concrete. ILP-PU1-9 19 0% Low Pressure Core Spray Pump Weld encased in concrete. IRH-PU1C-7A 20 0% Residual Heat Removal Pump Weld encased in concrete. IRH-PU1C-7B 20 0% Residual Heat Removal Pump Weld encased in concrete. IRP-PUIC-7C 20 0% Residual Heat Removal Pump Weld encased in concrete. IRH-PU1C-8A 20 0% Residual Heat Removal Pump Weld encased in concrete. IRH-PUlC-8B 20 0% Residual Heat Removal Pump Weld encased in concrete. IRH-PU1C-8C 20 0% Residual Heat Removal Pump Weld encased in concrete. Page 5 of 6
ATTACHMENT 2 Revised Table CR-26.1 Supplemental~ C pe ID InformationPage Actual C pnt Number(s)*
.. ; .. ov era Remarks IRH-PU1C-9 20 0% Residual Heat Removal Pump Weld encased in concrete.
Page 6 of 6
ATTACHMENT 3 Revised Table CR-26.2 Table CR-26.2 LASALLE COUNTY STATION UNIT 2 List of Welds with Limited Examination Coverage Supleentafl Information Page Actual Component ID<. Number(s) coverage C I Remarks GEL-1060-AG 224, 230, 231, 65.3% RPV Head to Flange 0-180 Deg. 232, 246, 247 and limited UT scanning from Flange 252 through 256 side of weld due to flange configuration. LCS-2-AE 224, 246 and 257 54.6% RPV Shell to Flange 180 Deg. to through 260 360 Deg. limited UT scanning from Flange side of weld due to flange configuration. LCS-2-N1A 233, 246 and 261 64.7% Reactor Recirculation nozzle to through 264 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N3C 235, 246 and 265 62.1% Main Steam nozzle to RPV through 268 limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N3D 235, 246 and 269 62.1% Main Steam nozzle to RPV through 272 limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N7 230, 239, 247 and 63.2% Reactor Core Isolation Cooling 273 through 276 nozzle to RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N8 230, 247 and 277 64.1% Reactor Head Vent nozzle to through 280 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N10A 241, 246 and 281 68% Capped Control Rod Drive through 284 Return nozzle to RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N18 230, 243, 247 and 63.2% Spare nozzle to RPV limited UT 285 through 288 scanning from nozzle side of weld due to nozzle design. LCS-2-N1B 233, 246 and 289 60.4% RR nozzle to RPV limited UT through 292 scanning from nozzle side of _weld due to nozzle design. Page 1 of 5
ATTACHMENT 3 Revised Table CR-26.2 Residual Heat Removal nozzle through 296 to RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N6C 238, 246 and 297 68.4% Residual Heat Removal nozzle through 300 to RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N4A 236, 246 and 301 78% Feedwater nozzle to RPV limited through 305 UT scanning from nozzle side of weld due to nozzle design. LCS-2-N4B 236, 246 and 306 78% Feedwater nozzle to RPV limited through 310 UT scanning from nozzle side of weld due to nozzle design. LCS-2-N4C 236, 246 and 311 78% Feedwater nozzle to RPV limited through 315 UT scanning from nozzle side of weld due to nozzle design. LCS-2-N4D 236, 246 and 316 78% Feedwater nozzle to RPV limited through 320 UT scanning from nozzle side of weld due to nozzle design. LCS-2-N4E 236, 246 and 321 78% Feedwater nozzle to RPV limited through 325 UT scanning from nozzle side of weld due to nozzle design. LCS-2-N4F 236, 246 and 326 78% Feedwater nozzle to RPV limited through 330 UT scanning from nozzle side of weld due to nozzle design. IRH-HX2B-08D 244, 249 and 331 74% Residual Heat Removal Heat through 336 Exchanger Attachment limited MT/PT due to structural steel. LCS-2-AE 224, 246 and 337 58% RPV Shell to Flange 0 Deg. to through 342 180 Deg. limited UT scanning from Flange side of weld due to configuration. GEL-1061-DA 224, 226, 227, 66% RPV Bottom Head Meridional 228, 229, 248 and Weld limited UT scanning due to 343 through 346 RPV Skirt. GEL-1061-DE 224, 226, 227, 66% RPV Bottom Head Meridional 228, 229, 248 and Weld limited UT scanning due to 347 through 350 RPV Skirt. GEL-1061-DF 224, 226, 227, 66% RPV Bottom Head Meridional 228, 229, 248 and Weld limited UT scanning due to 351 through 354 RPV Skirt. Page 2 of 5
ATTACHMENT 3 Revised Table CR-26.2 Reactor Recirculation nozzle to through 358 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N2C 234, 246 and 359 70% Reactor Recirculation nozzle to through 364 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N2F 234, 246 and 365 70% Reactor Recirculation nozzle to through 368 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N2G 234, 246 and 369 70% Reactor Recirculation nozzle to through 372 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N2H 234, 246 and 373 70% Reactor Recirculation nozzle to through 378 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N2J 234, 246 and 379 70% Reactor Recirculation nozzle to through 384 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N2K 234, 246 and 385 70% Reactor Recirculation nozzle to through 388 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N3A 235, 246 and 389 68% Main Steam nozzle to RPV through 392 limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N3B 235, 246 and 393 68% Main Steam nozzle to RPV through 396 limited UT scanning from nozzle side of weld due to nozzle design. 2RPV-SS-2 225, 246 and 397 52% Reactor Pressure Vessel through 399 Stabilizer Lug limited MT/PT due to structural steel. GEL-1060-AG 224, 231,232, 247 80.6% RPV Top Head to Flange 180 to and 400 through 360 Deg. limited UT scanning 403 from nozzle side of weld due to flange configuration Page 3 of 5
ATTACHMENT 3 Revised Table CR-26.2 Suppilemental Information Page Actual Component 10 Number(s) Coverage / Remarks LCS-2-N16A 242, 246 and 404 70.5% High Pressure Core Spray through 407 nozzle to RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N2A 234, 246 and 408 70.5% Reactor Recirculation nozzle to through 411 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N2D 234, 246 and 412 70.3% Reactor Recirculation nozzle to through 416 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N2E 234, 246 and 417 70.5% Reactor Recirculation nozzle to through 420 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N5A 237, 246 and 421 70.5% Low Pressure Core Spray nozzle through 424 to RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N6B 238, 246 and 425 70.5% Reactor Recirculation nozzle to through 428 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N9A 240, 246 and 429 82.9% Jet Pump Instrument nozzle to through 431 RPV limited UT scanning from nozzle side of weld due to nozzle design. LCS-2-N9B 240, 246 and 432 82.9% Jet Pump Instrument nozzle to through 434 RPV limited UT scanning from nozzle side of weld due to nozzle design. IHP-PU2-7A 250 0% High Pressure Core Spray Pump Weld encased in concrete. IHP-PU2-7B 250 0% High Pressure Core Spray Pump Weld encased in concrete. IHP-PU2-7C 250 0% High Pressure Core Spray Pump Weld encased in concrete. IHP-PU2-8A 250 0% High Pressure Core Spray Pump Weld encased in concrete. IHP-PU2-8B 250 0% High Pressure Core Spray Pump Weld encased in concrete. Page 4 of 5
ATTACHMENT 3 Revised Table CR-26.2 High Pressure Core Spray Pump Weld encased in concrete. IHP-PU2-9 250 0% High Pressure Core Spray Pump Weld encased in concrete. ILP-PU2-7 251 0% Low Pressure Core Spray Pump Weld encased in concrete. ILP-PU2-8 251 0% Low Pressure Core Spray Pump Weld encased in concrete. ILP-PU2-9 251 0% Low Pressure Core Spray Pump Weld encased in concrete. IRH-PU2C-7A 245 0% Residual Heat Removal Pump Weld encased in concrete. IRH-PU2C-7B 245 0% Residual Heat Removal Pump Weld encased in concrete. IRP-PU2C-7C 245 0% Residual Heat Removal Pump Weld encased in concrete. IRH-PU2C-8A 245 0% Residual Heat Removal Pump Weld encased in concrete. IRH-PU2C-8B 245 0% Residual Heat Removal Pump Weld encased in concrete. IRH-PU2C-8C 245 0% Residual Heat Removal Pump Weld encased in concrete. IRH-PU2C-9 245 0% Residual Heat Removal Pump Weld encased in concrete. Page 5 of 5
ATTACHMENT 4 Reformatted Submittal Information Regarding Relief Requests Associated With the Second Inservice Inspection Interval
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"",:,0""°"I . ,la- L6 1Z,..7 1j-06 19"Le447. Deste 14FC. 1-7-7r.0o Pc. NEo.Prefix Pc. No. Prefix D.W.P. and D.W.P. and Dwg. No. Weld No. Suffix Dw Title Jwg. No. weld No. Suffix Dwg. No. I 301 E-232-788 General Arrangement - Elevation 302 E-232-843 General Ar~ngement - Plans A-2ý;5-515 303 E-232- 898 Stainless Steel Safe Ends 3o4 305 E-232-789 Vessel Shells Forming & Fit-up A-245-830 306 E-232-042 Bottom Head Machining & Welding A-245-831 307 E-232-790 Lower Vessel Shell Ass'y. Machining and Welding A-245-832 308 E-232-791 U3pper Vessel Shell Ass'y. Machining and Welding A-245-833 309 E-232-861 Vessel Support Sklrt - Details & Ass'y.
A-245-834 310 E-232-862 Bottom Head-PenetVations 311 E-232-792 Vessel Machining A-245-836 312 -. 232-7931 Vessel Machining A-245-83T 313 E-232-794 Vessel Assembly A-245-838 314 E-232-879 Nozzle Details A-245-839 315 E42324930 Nozzle Details A-200-263 Mls'!ellareous Repairs and oemporar,' A-245-840 316 E-232-863 Nozzle Details Attachments (DWP) A-245-8o4 317 E=232=880 Nozzle Details A-200-081 Standard Notes A-245-842 318 E-232-839 'losure Head Nozzle Details A-200-083 Material Notes A-245-843 319 E-232-911 Closure Head Machining & Welding A-200-085 14&P Specs. 320 E-232-801 Closure Head Final Machining A-245-845 321 E-232-936 Miscellaneous Details 322 F-233-814I Miscellaneous Details A-245-8e4 323 E-232:-795 Vessel Internal Attachments A-245-848 324 E-232-796 Vessel External Attachments A-245-849 325 E-232-797 Vessel External Attachments 326 r-232- 923 Stud, Nut, and Washer Det.slls A-245-851 327 E-232-937 Shroud Support, Details & Aas'y. A-245-852 328 E-232-840 Nozzle Thermal Liners A-245-853 329 E=2-32802 In--Service InspectIen Pat0ht: A-24 5-8 5k 330 E-232-L)4 Mat'l. for Fabricating Test Specimen 331 E-232-799 Mat'l. Identification 332 'E-232-781 As-Built Dimensions 333 E-232-782 As-Built Dimensions - Bot. Hd. Penet. 334 E-232-928 Closure Head Shipping Details & Ass'y. 335 F-232-841 Nozzle Shipping Covers CHATTANOOGA -- - 28(7 A-24 5-8 57 336 F-232-930 Flange Cover Details & Ass'y. 7:'_.AWING FLAN LU:,7 A-245-858 337 C-232ý931 Lifting Beam Details & Ass'y. A-245-859 338 E-232-932 Vessel Upending Device & Lower Cover Details & Ass'y. 251'r . . 12 339 F-232-933 Vessel shipping Rig Details 340 P-232-847 Vessel Shipping Ass'y. C 9-232-814 Shipping Arrangement on Barge [ jJ 341 6 A-245-8 3 -z42 s-232- 939 Miscellaneous Shipping Details a- E-232-800 Modified Vessel Shipping Rig Assembly 3 43 A-2.4S-94-9 .3+4- E-232-244 UT CALIBRKTION BL..CK' DETMt LS I:COMO*5I1,T,,kGN W..,4... CO . IDRAWING NO, B-230-49S-. 7r
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COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 1993 VLTRASONIC TESTING DATA SEE NDT-DS-C2A STATION/UNIT: LA5A**6 / PAGE: / OF PROCEDURE: NDT- L T V.REV. DATA SHEET NO.: 1-34 DATE:g- to CALIBRATION SHEET NO.(S) ST. BEAM: C - C) 3 ANGLE BEAM: axial C -o 3 - circ. COMPONENT INSPECTED SYSTEM: TR?v WELD 1- __EL -10(q- AL( WELDTYPE: T~i PIPE SIZE- hdI, THICKNESS/SCHEDULE: . MATERIAL: C 5 COMPONENT TEMPERATURE:- * '6, 783 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: 04 . ANGLE BEAM AXIAL: _, V 0.8d3 COUPLANT/ BATCH #: L2LrTArfL Z-.10 0'4QOi1 I ANGLE BEAM.CIRC.s 6_98 _t& EXAMINATION SCANS Performed Indicationa 2 NO OYE
- 1) Base Metal Straight Beam
/]\ 2) Angle Beam-Normal-Against Flow > A/
- 3) Angle Beam-Normal-With Flow X
- 4) Angle Beam-Along Weld-CW <>
- 5) Angle Beam-Along Weld-CCW ><
F"' L 6) Straight Beam of Weld 0 >I W 7) Thickness Across Weld & Base Metal A/,//A I J//A UP STRM WELD DN STR ADDITIONAL COMMENTS
-se A" aA' ~rgcUTS -/Q %-30%Y XrcLL PARTiAL CovA&1- 0hP4 -4 5C A14 -h 6 r LAI rapg u A rig Cj. L,) rAt or znc C,,'i o A& we-
.(
***ES't.J ?ErIET~ Sc4 ~At~1.3 PR6 Vi~u_,L), RCOIZbD6Z 0",& Tt~J1>CAT,6N~ o3jS6RV61> *ELd'sw2of X&-agbABLA gypa EXAMINER: ~kZ--LEVEL: ~ DATE: ~--9 REVIEWER: LEVEL: 722DATE: -- 7~
O THE R.- LEVEL: .2FDATE:____________ STATION: e- ~ DATE:______ ANI I: ~ .DATE: Si Page 22
GE Nuclear Energy Top Head to Flange Weld, GEL-1009- AG. (00 to 1800) Due to the Flange configuration the following coverage was achieved. no A-4 G0°
- Exam area Y WV WW 78.5% 97.4% 96.0% Base Material 78.5% 78.5% CW, Circ scans 78.5% 78.5% CCW, Circ scans 100.0% 100.0% Ax Up I
AA 1Yfv RA. IV 9A Ill! A*. II Ax fn [1* Ill 78.5% 80.2% 75.9% Totals Composite coverage = 78.2% due to the Flange. Also, 166" of weld was limited to a "W" of 5.5" due to OD machining. These areas are 32" at weld DM, 97" at weld DQ and 37" at weld DR. This limitation of 166" resulted in CfN an additional 6.3% of the required volume not examined. C14 0) Total coverage achieved = 71.9% cc Scale: Half REPORT NO.: 9My-t130 2 GE REVIEWED BY LEVEL DATE UTILITY REVIEW DATE SK4WREVIW"DATE PAGOL -. o.. -2_-- GE REVIEWED BY LEVEL DATE UTLIIY REVIEW DATE SNAD REVIEW OAT!
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 1993 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: LAS*1t6 /1 *#4 PAGE: / Or / PROCEDURE: NDT- C O REV. a._DATA SHEET NO.: - 731 - /3/ DATE: f CALIBRATION SHEET NO.(S) ST. BEAM: -*
- 1"-4"
/i/ ANGLE BEAM: axial C- 036 circ.
- COMPONENT INSPECTED SYSTEM: _ /_ WELD 0: Crr16O-/- 4 WELD TYPE: 7-H PIPE SIZE: A/*/ THICKNESS/SCHEDULE: Y._ 75 _ MATERIAL: CS COMPONENT TEMPERATURE: 4L
-#j5 '1"83 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: IVA ANGLE BEAMI AXIAL: -r- 304j COUPLANT/
BATCH #: L ANGLE BEAM CIRC.: 6 EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam V /A
/ \ 2) Angle Beam-Normal-Against Flow A/
- 3) Angle Beam-Normal-With Flow -.-
- 4) Angle Beam-Along Weld-CW -.-
- 5) Angle Beam-Along Weld-CCW ,. -
L 6) Straight Beam of Weld A, (A/A _ 0 W 7) Thickness Across Weld & Base Metal A//A /. A UP STRM WELD DN STR ADDITIONAL COMMETS
-PARrtAL CoyJ 6A A(& 0,J *-; fCAIJ -P,4 To rFL.Aa.j&6 C 0r.. _FjCA_(j 0P L... _D,5 rA IJC6 OF 0, ,rFo~~A6~j EAIE:LEVEL: Jr. DATE:.)C9 REVIEWER: LEVEL: _/77 DATE: ~-/.P?
OTHER: ._LEVEL: I27 DATE:_ ________ STATION61ý 6-. DATE: ANI I: DATE: -ý1 Page 24
NDT-B-1 Revision 6 December, 1993 Page 43 of 44 FORM NDT-B-l-Fl MAGNETIC PARTICLE EXAMINATION DATA SHEET DATE 2-/a to - STATION & UNIT LaSalle Unit I DATA SHEET # 13Z ZX.yIjN ER. J 7'" 2!f-/ LEVEL_ _ _ __ SYSTEM RPV COMPONENT GEL-1009-AG SECTION XI EDITION a ADDENDA 1989 Edition, No Addenda CODE CLASS I SECTION xI CATEGORY B-A ACCEPTANCE STD. IWB-3510.3 PROCEDURE # & REVISION NDT-B-1 Rev. 6 SKETCH SHEET USED: YES NO X COMMENTS: Configuraton: THD SXi)H/ AJ -f /D *,DL w - E"L- /O0 7- A q A/R E M MAGNETIC PARTICLE EXAM: ( Manufacturer Model/Type S/N Yoke Parer E30u0 uPA -AC -T- 0 0 g Current AC X DC Particles Magnaflux 13 A3 A 0 q.9 Color A'RE Black Light NIA N/A N/A D.L.M. Readings N/A B.L.M. Time Checks Initial N/A Final N/A EXAM RESULTS ACCEPT X REJECT REVIEWED BY: EXAMINER: LEVEL:_______ DATE: 2-ic'- 7(, REVIEWER: LEVEL: , DATE: OTHER: :) 7; LEVEL: DATE: 3TATZON: DATE: ANII: DATE: 37.0 Page 25
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 1993 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: !# L-t //, PAGE: / OF PROCEDURE: NDT- C-30 REV. Z DATA SHEET NO.: 95-/4(4 DATE: 12-/2- Y CALIBRATION SEEET NO.(U) ST. BEAM, C-04O ANGLE BEAN: axial C- d"l! circ. _ -__/ COMPONENT INSPECTED SYSTEM: I/>P?&/ 'WELD if I -/e20?-D/4 WELD TYPE:_______ PIPE SIZE: 4// THICKNESS/SCHEDULEs x1, " MATERIALt CS COMPONENT TEMPERATURE: 4, -,o # 773 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: s Y7. 0ANGLE DEM AXIAL:* 0 COJPLANT/ 0 . , BATCH #: , ANGLE BEAM CRc,,, EXAMINATION SCANS
-erformed Indications YES no NO YES
- 1) Base Metal Straight Beam
/ \ 2) Angle Beam-Normal-Against Flow W'
- 3) Angle Beam-Normal-With Flow
- 4) Angle Beam-Along Weld-CW S) Angle Beam-Along Weld-CCW -
a, F-L 6) Straight Beam of Weld a' __ 0 W 7) Thickness Across Weld & Base Metal I -"/ / d"/' UP STRM WELD DN STR ADDITIONAL COMMENTS EXAMIEER: LEVEL: a DATE: __-__-____ REVIEWER: LEVEL:_____ DATE:__________ OTHER.*.* LEVEL._____ DATE:_______ STATIO c ý K, DATE:__________ ANII: DATE:_____ Page 26
!GE Nuclear Energy Weld # AL' 1t 10" Typical for welds, GEL-1009-OM, Data Sheet 96-146 & 147 and GEL-1009-DP Data Sheet 96-150 & 151 Due to the welded lifting lugs an area 6.5" x 24" was unavailable for Inspection. This area represents 35% of the required examination volume, however some coverage was obtained with the axial scans from the T clockwise and counter clockwise side of the weld.
Area of Limitation Composite coverage achieved = 77.2% due to Welded Lug a) C,4 r (L 0_ 6.5" 1.5" 3~4 Weld # AG I REPORT NO.: 9&146 II" __ F - GE REVIEWED BY LEVEL DATE e956UMITY REVIEW SMADR"VIW DATE
..-- *- ~ Li.
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rey. 2 December, 1993 ULTRASONIC TESTING DATA MS NDT-DS-C2A ( STATION/UNIT: / 4*:r-'Le // PAGE J OF / PROCEDURE: NDT-<:3 REV. 2 DATA SHEET NO.: ,2W -/1/7 DATE: .?-12/ 2 CAL~zoA snM SHE o. (S) ST. DEAN: ,IV/ ANGLE BEAN: axial _______ciro. C COMPONENT INSPECTED SYSTEM: ,_,,/_P,_ _,,. WELD it: 2>-/'%- WELD TYPE: > PIPE SIZE: ___/_ THICKNESS/SCHEDULEZ: .' MATERIAL= e COMPONENT TEMPERATURE: _ý k'//15-417,?3 SCAN GAIN CONTROL SETTINGS STRAIGHT DEAN:~s/ ANGLE BEAN AXIAL:s" COUPLAIT / ANGLE oI CRC.: 43,o EXAMINATION SCANS
"*e::o~ldIndications YES no NO YES
- 1) Base Metal Straight Beam a-
/ \ 2) Angle Beam-Normal-Against Flow V
- 3) Angle Beam-Normal-With Flow .- V
- 4) Angle Beam-Along Weld-CW V
- 5) Angle Beam-Along Weld-CCW L
W
- 6) Straight Beam of Weld
- 7) Thickness Across Weld & Base Metal V g/-
*)/* I '4 UP STRM WELD DN STR ADDITIONAL COIGEENTS
,i ,,,', ,, , , F , ,1,, 50 EXAMINER: LEVEL: 22? DATE: o-12 4 REVIEWER: LEVEL: 7227?- DATE: 2 STATION DATE:-ZA04 ANI I: DATE: 3jf ;
Page 28
cOMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 1993 ULTRASONIC TESTING DATA SEET NDTDS-C2A STATION/UNIT: / / PAGE: _ .oF 2-PROCEDURE: NDT-C-3 REV. 2- DATA SHEET NO..: - DATE: .2-/ ,94 CALIBRATION SaEpT NO.(U) ST. BEAM: _________ ANGLE BEAMS axial C__0__'/ _ circ. 4P______t COMPONENT INSPECTED SYSTEM: I/*P WELD 0SSCjD / 9 L WELD TYPE: 7WZ") PIPE SIZE. All^-;-_ THICKNESS/SCHEDULE: ____Y __ MATERIAL: dS COMPONENT TEMPERATURE: ?,-'53
/"7-3 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: A/170 ANGLE BEAN AXIALt "S 6 BATCH 0.:/ ____- ____, __ ANGLE BEAM CIRC., s/
- d2. o' 3XAMIN3tTION SCANS S-Perfornmed Indications yEs no no YES
- 1) Base Metal Straight Beam a V
/i \ 2) Angle Beam-Normal-Against Flow . /
- 3) Angle Beam-Normal-With Flow /_ _
- 4) Angle Beam-Along Weld-CW .. 7
- 5) Angle Beam-Along Weld-CCW V F
L 6) Straight Beam of Weld *./ 0 w 7) Thickness Across Weld & Base Metal . .- /* / UP STRN WELD DN STR ADDITIONAL COMOMENTS _Z,e~.47p-e? 41 A ; EXAMINER: LEVEL:S DATE:__________ REVIEWER:LEEL DATE:S 2 / OTHER:...... LEVEL: -ZEE: DATE:_________ STAT 1 . 6.** DATE._____________ ANII: DATE: Page 29
0GE NuclearEnergy Typical for welds, GEL-1009-OM, Data Sheet 96-146 & 147 Weld # ALU0ý I 10" and GEL-1009-DP Data Sheet 96-150 & 151 Due to the welded lifting lugs an area 6.5" x 24" was unavailable for inspection. This area represents 35% of the required examination volume, however some coverage was obtained with the axial scans from the 24 clockwise and counter clockwise side of the weld. Area of Limitation Composite coverage achieved = 77.2% due to Welded Lug 6.5" 34.5" Weld # AG I REPORT NO.: P.96AO-1 PAGE:_Z__OF. --Z--_ GE REVIEWED BY LEVEL DATE UTITY REVIEW DATE 8MAD REVIEW DATE A (~C7\ ~
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. IIDT-C-30 Rev. 2 December, 1993 ULTRASONIC TESTING DATA SKEET NDT-DS-C2A STATION/UNIT: /.4 Y*4L-I PAGE: oFr PROCEDURE: NDT-e-30 REV. 2- DATA SHEET NO.: , - /,5 DATE: .2-fZ-* CALIBRATION SHEET NO. (2) ST. SEAM: ANGLE BEAM: axial C- / _ circ. - COMPONENT INSPECTED SYSTEM: P/-) *ELD ,: A0-/-o - 1) WELD TYPE: _ "-__ PIPE SIZE: 1//4 THICKNESS/SCHEDULE: 4, 76 MATERIAL: C COMPONENT TEMPERATURE: ~ .'/~7'. SCAN GAIN CONTROL SETTINGS STRAIGHT SEAM: ANGLE BEAM AXIAL:
- 3, Z 23 COUPLANT/ j - - I .~--
BATCH P: 7"- *;*G'- I . ANGLE BEAM CIRC.: __ 3 ,o_ EXAMINATION SCANS erformod Indications YES NO NO YES
- 1) Base Metal Straight Beam I
/ \ 2) Angle Beam-Normal-Against Flow , .
- 3) Angle Beam-Normal-With Flow
- 4) Angle Beam-Along Weld-CW . V S) Angle Beam-Along Weld-CCW V o,
F L 6) Straight Beam of Weld W 7) Thickness Across Weld & Base Metal a- ,// #// s'/- UP STRM WELD DN STR ADDITIONAL COMMENTS
-ý2*OW 47.i
. -,7e X ,9;/- Z 4oe 75 Z;ýt /
4"a .5 c EXAMINER: LEVEL: DATE: ,, /2 12 REIEE 1/LEVE: -/77- DATE: ?-f? OTHR:--1-0 WwA').LEVEL: ~ DATE:_____________ STvx-O ZDATE: AN-,I: e) _ DATE: o)ClU Page 31
COMMONWEALTH EDISON COMPANY Page 20 of 2. Procedure No. NDT-C-30 Rev. 2 December, 191 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: !AS/ii* /1 PAGE: / OF PROCEDURE: NDT-C~ REV. 2 DATA SHEET NO.: -o?_____ DATE: 2 - Z/- 9ý cALIBRATION SREET No.(S) ST. BEAM. 2-O73 ANGLE BEAM: axial _ -__ _ circ. _ -___ COMPONENT INSPECTED SYSTEM: A PVy WELD #: LCS-1-kA WELD TYPE: PZAAVJg 7o /'sgE. PIPE SIZE: NIA THICKNESS/SCHEDULE: 7 MATERIAL: C S, COMPONENT TEMPERATURE: 84jA" W /5T007 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM-: *jm 52-,Y ANGLE BEAM AXIAL: A 57.y .dR COUPLANT/ E BATCH #: /47-AP6--l.4 -.. - ,*"32-53 ANGLE BEAM CIRC._ 7___ V EXAMINATION SCANS Performed Indications YES no No YES
- 1) Bass Metal Straight Beam
\ 2) Angle Beam-Normal-Againet Flow v
- 3) Angle Beam-Normal-With Flow - N
- 4) Angle Beam-Along Weld-CW 11r,
- 5) Angle Beam-Along W.ld-CCW ,
L 0
- 6) Straight Beam of Weld V V _
W 7) Thickcness Across Weld & Base Metal 411A N, UP STRM WELD DN STR ADDITIONAL COMMENTS
~SeCA /fj A W C 77FC71*
E~' X.O A04 4 JtYSA5e/A4 d2 krrzczi 801. ~xLAc44A LUGf Le C nno - -' F',fcA &IF LS) 72 EXAMINER: LEVEL: DATE: 7,2/.2 //6 REVIEWER: LEVEL:_____,-__ DATE:__________ OTHER: LEVEL: -Z= DATE:__________94 STATION:6 6. DATE:______ LANII: -' .DATE:______ Page 32
GE Nuclear Energy Vessel to Flange Weld, GEL-1009-AF. Exam performed for 360° Due to the Flange configuration the following coverage was achieved. 0 458 60' Exam area 54.5% 75.0% 65.4% Base Material 54.5% 54.5% CW Circ. scans 54.5% 54.5% CCW Circ. scans 100.0% 100.0% Ax Down
.5% 56.6% 54.9% Total Composite coverage = 55.4%
(D a-(0 Scale: Half REPORT NO.: GE REVIEWED BY LEVEL DATE 64ýý' -.- 0",- UnLITY REVIEW DATE slwm REVIL=W JýA DATE 9&24n PAGL: ' -F UIU~f REVEWSMAD REVIEW DT
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 199. ULTRASONIC TESTING DATA zKE NDT-D8-C21 STATION/UNIT: L A: A$A /I PACE: Or o / PROCEDURE: NDT- LC 3 REV. DATA SHEET NO. z - / DATE: -20L CALIBRATION SHEET NO. ($) ST. BEAM: ANGLE BEAM, axial _-_0_73-_ circ. e_-_0_7._ _ COMPONENT INSPECTED SYSTEM: P~VWELD #3: i-r-S-'I-AF WELD TYPE: _____.Aý ______ PIPE SIZE: A THICKNESS/SCHEDULE: *Q . MATERIAL: C5 COMPONENT TEMPERATURE: 0 15'% 7 PCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: V AANGLE BEAM AXIAL tz ý ,- COUPLAXT/ 9 BATCH 10: _"L&sLkft1AAW4 S,2d.S ANGLE BEAN CIRC. : *7 I'UcJ ZIAMINATION SCANS Performed Indicatioms YES no 30 YES
- 1) Base Metal Straight Beam N/A
/\2) Angle Beam-Normal-Against Flow .-
- 3) Angle Beam-Normal-With Flow VIA//
- 4) Angle Beam-Along Weld-CW p" A
- 5) Angle Beam-Along Weld-CCW IX L 6) Straight Beam of Weld -/A 0
W 7) Thickness Across Weld & Base Metal ________A________ UP STEM WELD D= STE ADDITIONAL COWIOENTS 5CAp4sL6-TS G'I l l6% Akb 6-xAm~ 26-FoRrM-x2> ra i Ar Q* 105*_ ;?0' pt, *1-
, LoCTb "3" RRo\ A.J6Lr T-0e.
EXAMINER: LEVEL: -Z&- DATE: ___-___-____ REVIEWER: LEVEL s DATE: OTHER:-ý 4 ý LEVEL:. DATE:_______ STAION 6.g4' DAITE: jý ANII: ------- ~ DATE: ~If Page 34
COMMONWEALTH EDISON COMPANY Page 20 of , Procedure No. NDT-C-30 Rev. 2 December, 1! ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: L- -ALL /E . PAGE: OF PROCEDURE: NDT- REV. DATA SHEET NO.: 9t,- 15a. DATE: .2.S- 4 CALIBRATION SHEET NO.(S) ST. BEAM.: (2-Oq3 ANGLE BEAM: axial C-OL44 circ. C- aL COMPONENT INSPECTED SYSTEM: R WELD #: LC.&-I- Il . WELD TYPE: __-_ PIPE SIZE: jýq THICKNESS/SCHEDULE: 'd MATERIAL: ( COMPONENT TEMPERATURE: 980 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: 51. L, dA ANGLE BHEM AXIAL: 63.048 COUPLANT/ BATCH #: ULT'A&E.L -- /9-1;LS I ANGLE BEAM CIRC.: 0AB EXAMINATION SCANS Performed Indications YES NO no YES
- 1) Base Metal Straight Beam
- 2) Angle Beam-Normal-Against Flow
- 3) Angle Beam-Normal-With Flow
- 4) Angle Beam-Along Weld-CW
/ "/
- 5) Angle Beam-Along Weld-CCW F
L 6) Straight Beam of Weld 0 W 7) Thickness Across Weld & Base Metal UP STR' WELD DN STR ADDITIONAL COMMENTS
,t/C tXApI PLL*&l, Im*r OI* )L4O2.LLE_ SlO L. o ' LL3L* bi.l* 1*_b M#-
Z?-LE. C~. tA-,- TL-* -O *. o., - /n WIT*-' EXAMINER: _K4 LEVEL:______ DATE:_______ REVIEWER: 7LEVEL: L~- DATE: ______ OTHER:.:f-: LEVEL:. DATE: /716______ STATION: 65*-.DATE: ,/. AINII: ________________ ___DATE: 31 c Page 35
WGE Nuclear Energy Typical for Welds LCS-1-NIA, Data Sheets 96-152 & 153 and LCS-1-NIB, Data Sheets 96-154 & 155. Due to the configuration of the nozzle no exams were performed from the nozzle side. This limits the coverage achieved to: 0° = 56.25% 45° = 60.75% 60* = 58.81% Coverage due to nozzle = 58.6% Weld LCS-1-NIA was also limited at 1800 due to a 3.25" thermocouple located 2.5" from weld toe. This results in an additional .66% coverage not achieved. Co Total composite coverage for LCS-1-NIA = 57.94% a) 0) C. N K I REPORT NO.:
-96J*52_
LOP- 2.. . .. 2 GE UEVEL ---dAif-- UTILITY REVIEW DATE
.SMAD REVIEW navc
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 199 ULTRASONIC TESTING-DATA SHEET NDT-DS-C2A STATION/UNIT: ZA SALLe/ PAGE: / OF I PROCEDURE: NDT- L REV. 2__ DATA SHEET NO.: ? - /,3 DATE: 2-/5'174 CALIBRATION SHEET NO.(S) ST. BEAM: A_ _ _ _ ANGLE BEAMN axial C-e circ. _ -___- COMPONENT INSPECTED SYSTEM: 8 it A WELD if:LCS-/- A1IA WELD TYPE: N-S PIPE SIZE: 2 q THICKNESS/SCHEDULE: F. .q5 MATERIAL: C.S COMPONENT TEMPERATURE: ." " SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: N
)A ANGLE BEAM AXIALs COUPLANT//
BATCH #: (44Ti7T E-* A ANGLE BEAM CIRC.: EXAMINATION SCANS Performed Indications YES NO 3o YES
- 1) Base Metal Straight Beam v
/ I\ 2) Angle Beam-Normal-Against Flow V
- 3) Angle Beam-Normal-With Flow V
- 4) Angle Beam-Along Weld-CW V V
- 5) Angle Beam-Along Weld-CCW " V F
L 6) Straight Beam of Weld V W 7) Thickness Across Weld & Base Metal I./ A/A AJ At UP STRM WELD DN STR ADDITIONAL COMMENTS
'v06X*A-i" OA/ NtZaL.AC Si0 oF-t#-'e(~ OV0 'rV AJOZtI~e CQeudV2krio'%.'
vo/e'w AX60tfFO~1cime SLOL6 rt' I25'pnex DMHE-l'Ao ~.~'co'.4PL&s Zcc~4rtd' 2,5
)r/oH t4N6-e ro& 65 r I/O EXAMINER: LEVEL:- DATE:_._ _____
REVIEWEE.V E _ _____ DATE: 22-/7 - OTHER :-1-.d ~ ~ LEVEL: DATE: 32'4 STATION<ý5 6 24ý DATE:______ ANII:
.,_ llj _/DAE:
,. ... DATE:..
Page 37
COMMONWEALTH EDISON COMPANY Page 20 of 2. Procedure No. NDT-C-30 Rev. 2 December, 19. ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: 4A LL/_1. ! PAGE: __* OF _ PROCEDURE: NDT- C-3__ REV. A DATA SHEE NO: 96NO.". DATE:* i*-? CALIBRATION SHEET NO.(S) ST. BEAM: AGLE BEAM: ax.al A-ON3 cqV circ. e-oV./ COMPONENT INSPECTED SYSTEM: _ __ WELD .: LCS-I--i/6 WELD TYPE: ,A/-s PIPE SIZE:
- THICKNESS/SCHEDULE: ______' MATERIAL: C_
COMPONENT TEMPERATURE, ______qa SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: s).'.d' ANGLE BEAM AXIAL:.. _ ____ COUPLANT/ 9 . BATCH #: 4LTE-AE-L ( / 9-3A5 ANGLE BEAM CIRC.: ,OAG EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam
/ \ 2) Angle Beam-Normal-Against Flow
- 3) Angle Beam-Normal-With Flow - -
- 4) Angle Beam-Along Weld-CW ,,__"_,,_
- 5) Angle Beam-Along Weld-CCW F -
L 6) Straight Beam of Weld _ __ 0 W 7) Thickness Across Weld &Base Metal $NAdiIj A/q UP STP. WELD ODN!ST ADDITI ONAL COMMENTS
?_i4 * ~ 0 "L 4 g4
.,.ATE4 - -
A10 fxAdrn PFeFoCpMc, e)IM A)402Ž_LPe 50_opL- LOOSF I e-L-Tb AJZ L - OF I 4~DTa,~ EXAMINER: ________________ LEVEL: .~. DATE:_______ REVIEWER:_____________ LEVEL: Z4- DATE: -Y . OTHER: 7-a 21A+/-~LEVEL:________ DATE:_______ STATION DATE:_______ AfNII: DATE: -J99L Page 38
GE NuclearEnergy Typical for Welds LCS-1-NIA, Data Sheets 96-152 & 153 and LCS-1-NIB, Data Sheets 96-154 & 155. Due to the configuration of the nozzle no exams were performed from the nozzle side. This limits the coverage achieved to: 0° = 56.25% 450 = 60.75% 600 = 58.81% Total composite coverage = 58.6% C,.) CU, N. REPORT NO.:
-9&~154-GeRW~EY GE REVIEWED BY LEVEL - DATE UTILITY REVIEW DATE SMAD REVIEW -OF.2 DATE PAGE: -
COMMONWEALTH EDISON COMPANY Page 20 of 2 Procedure No. NDT-C-30 Rev. 2 December, 19 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: tP) JI.-Lp /L HT PAGE: ___OF __ PROCEDURE: NDT- REV. REV0 DATA SHEET NO.: .6 "15 DATE: ____' _ CALIBRATION SHEET NO.(S) ST. BEAM: A/ A ANGLE BEAM: aial _"_____ circ. C-(31O-- COMPONENT INSPECTED SYSTEM: // WELD #: LC5- f-il WELD TYPE: _ _ _s PIPE SIZE: 2 THICKNESS/SCHEDULE: 4____5 _ MATERIAL: _, 7: , .5 ,,1;z COMPONENT TEMPERATURE SCAN GAIN CONTROL SETTINGS STRAIGHT BEAR: AVA ANGLE BEAM AXIIAL: G5 BATCH #: L*1*r? 61t 1-5 2 5- ANGLE BEAM CIRC._: EXAMINATION SCANS Perforued Indications YES NO NO YES Base Metal Straight Beam 1)
/ I\ 2) Angle Beam-Normal-Against Flow ,
- 3) Angle Beam-Normal-With Flow LV
- 4) Angle Beam-Along Weld-CW _ _ - /
- 5) Angle Beam-Along Weld-CCW V F - -
L 6) Straight Beam of Weld V 0 W 7) Thickness Across Weld & Base Metal L. UP STRM WELD DN STR ADDITIONAL COMMENTS 10ove-cni-iew2 sxi~N tA'1M 4 3 MAA- C - f4-*H* otd 01J *'V E C (WL--' (F D'JE TO A/CY7ZL6 C64rr EXAMINER: LEVEL: . ,*Z DATE: -,., REVIEWER: LEVEL:_z j.. DATE:___________ STATION LEVEL~~ DATE:_______ OTHER: LVL 4 ANI I: ~DATE: ~; ? Page 40
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 1992 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: LASALLf- I I PAGE: I OF PROCEDURE: NDT- REV. _ DATA SHEET NO.: _ --/_ DATE: -__-__ CALIBRATION SHEET NO.(S) ST. BEAM: C- 5C)0 ANGLE BEAM: axial (- 051 circ. C-051 COMPONENT INSPECTED SYSTEM: nVs WELD #: LCS- I - M3A WELD TYPE: ALS PIPE SIZE: _2(0 THICKNESS/SCHEDULE: " MATERIAL: C. COMPONENT TEMPERATURE: =O Sq-8,;L SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: _ _ __, ANGLE BEAM AXIAL: _ _ _ _ COUPLANT/ BATCH #: ULTO&(4- X! 9S.6a ANGLE BEAM CIRC., .q,( EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam
/ \ 2) Angle Beam-Normal-Against Flow -
- 3) Angle Beam-Normal-With Flow V/
- 4) Angle Beam-Along Weld-CW 1"-V/
- 5) Angle Beam-Along Weld-CCW L 6) Straight Beam of Weld /'
0 W 7) Thickness Across Weld & Base Metal W Ik/A Rd/q M/c UP STRM WELD DN STR ADDITIONAL COMMENTS
?FK-qt ?-KAM L.ITA eL. 4 4 0SS 40AJO1 LE.... S)CIE &)p Wý_Lt6 fJ4M1KtL~ bw To ArLE Czz(.ALTIA-EXAMINER:______________ LEVEL:______ DATE:______
RVIELER:
- LEVEL: .. DATE: -2 OTE:LEVEL: DATE: 3/261 A?6 STATION: 4 _ DATE:______
ANII: **",* :-- DATE:__-_-__ Page 41
GE NuclearEnergy Typical for Welds: LCS-1-N3A, Data Sheets 96-162 & 163 LCS-I-N3B, Data Sheets 96-164 & 165 LCS-1-N3C, Data Sheets 96-166 & 167 LCS-I-N3D, Data Sheets 98-168 & 169 Due to the configuration of the nozzle no exams were performed from the nozzle side. This limits the coverage achieved to: 0° = 57.85% 4530 61.60% 600 = 60.40% Total composite coverage = 59.95%
\
K 1 REPORT NO.:
, ý 7, C, -" 4--) j /. 1--a .31&
LEVEL DATE UTILITY REIE nI PAM- -_A OF: -2 GE REVIEWED BY SMAD REVIEW DATE GE REVIEWED BY ~LflY REVIEW DATE DATE
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 1993 ULTRASONIC TESTING DATA SHE NDT-DS-C2A STATION/UNIT: IR L' LLE// PAGE / or / PROCEDURE: NDTC-)_b REV. Z DATA SHEET NO.: 1_9( _ e. _3 DATE: _ _-/_-__ CALIBRATION SHEET NO.(s) ST. BEAM: Mk ANGLE BEAM: axial C- C 5Z2 ciro. C-C)-L COMPONENT INSPECTED sYSTEM: M5 wELD #, LCS- - I3A WELD TYPE: NS PIPE SIZE: 2 L4 THICKNESS/SCHEDULE: 7.0 MATERIAL: C S COMPONENT TEMPERATURE: ) ft / 5Lf Y2I SCAN GAIN CONTROL SETTINGS STRAIGHT SEAM: N4A ANGLE SEAM AXIAL: COUPLANT/ BATCH 0: z, / ANGLE BEAM CEC. EXAMINATION SCANS Performed Indications TES NO no YES
- 1) Base Metal Straight Beam V
/ \ 2) Angle Beam-Normal-Against Flow
- 3) Angle Beam-Normal-With Flow
- 4) Angle Beam-Along Weld-CW 9
- 5) Angle Beam-Along Weld-CCW F
L 6) Straight 8eam of Weld 0 w 7) Thickness Across Weld-& Base Metal j, J )VA IV UP STRM WELD DN STR ADDITIONAL COMlENTS fl*c¢,)D,90L- 4p\/Lr-L"
/Avc' ), spbs ossf wei. m ~ z pgrior ' arzow2C ~ 4 7 EXAMINER:_ LEVEL: zz DATE: I-7' REVIEWER: LEVEL: 2 DATE: ? -6 OTHER: 40 LEVEL: - DATE-3 STATION: -_ DATEs______
ANII: -. ~ DATE: - Page 43
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 199. ULTRASONIC TESTING DATA SHEET NOT-DS-C2A STATION/UNIT: L_ P* ,LL. ] i PAGE: I- OF PROCEDURE: NDT- C-30 REV. DATA SHEET NO.: A0-/6q DATE: .2-)-94 CALIBRATION SHEET NO.(S) ST. BEAM: C-oso ANGLE BEAM: axial C-L).} circ. C.-C3,I COMPONENT INSPECTED SYSTEM: _ _ _ _ _WELD #: LCS M32G WELD TYPE: MS PIPE SIZE: " THICKNESS/SCHEDULE: %D0" MATERIAL: C S COMPONENT TEMPERATURE:." o *,JS14(it SCAN GAIN CONTROL SETTING$ STRAIGHT BEAM, ANGLE BEAM AXIAL: $".9 COUPLAT/ BATCH #: (JLTLACf.I2,Vq3 = ANGLE BEA CIRC.:0 EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam //_
/ [\ 2) Angle Beam-Normal-Against Flow_-
- 3) Angle Beam-Normal-WLth Flow -
- 4) Angle Beam-Along Weld-CW ,
F 5) Angle Beam-Along Weld-CCW / i L 6) Straight Beam of Weld . / w 7) Thickness Across Weld & Base metal / A/I/ / UP STRX WELD DN STR ADDITIONAL COMMENTS TEEPAOEMC0 EXAMY uLtT4 0%~ 44e.~3 19IC9~h1C1"S 08S .2A3EI 1AA EmiD WA~LL Rf-Gleild tf _L0U_3 R tO.zpF~jLF LfpLS AIDAJO 2 21..9,-- f aF- US 0 FiLhA I"E6bL~e.. To N 0 2 7 L_ Cap ;:%G p-T 4. EXAMINER: LEVEL:_______ DATE: -39 REVIEWER: LEVEL:., DATE: 2-/ " . OTHER: LEVEL:_ _ _ DATE: 3/E- /?- STATION: - , DATE:-4/,4/, ANI I: __________________DATE: 3e Page 44
OGE NuclearEnergy Typical for Welds: LCS-1-N3A, Data Sheets 96-162 & 163 LCS-1-N3B, Data Sheets 96-164 & 165 LCS-I-N3C, Data Sheets 96-166 & 167 LCS-1-N3D, Data Sheets 96-168 & 169 Due to the configuration of the nozzle no exams were performed from the nozzle side. This limits the coverage achieved to: 00 = 57.85% 450 = 61.60% 60° = 60.40% Total composite coverage a 59.95% LO a, (1) a. REPORT NO.: -"Xý- GE REVIEWED BY 1V -2? LEVEL 7-9~4 DATE UnLITY REVIEW UTUIT REVIEW ZZA6_9 DATE DATE SMDREVIEW - DATE PAGEO 2 _- OF: -.Z - GE REVIEWED BY
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 1991 ULTRASONIC TESTING DATA SEE NDT-DS-C2A STATION/UNIT: LZ S*t.t*1. PAGE: - OF I PROCEDURE: NDT- C-0REV. 2.. DATA SHEET NO.: /9_______ DATE: 2/.C CALIBRATION SHEET NO.(S) ST. BEAM: IVA ANGLE SEAM: axial C- ,X-. circ. (-f _-- _ COMPONENT INSPECTED SYSTEM: /MIS WELD P: LC - /- A/3 WELD TYPE: IVS PIPE SIZE: 2 THICKNESS/SCHEDULE: 7.0 MATERIAL: CS COMPONENT TEMPERATURE: T4 /5 Z) SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: A-'.4 ANGLE BEAM AXIAL: cib BATCH I: u
- 7~53Z5- ANGLE ZW3CIJC.
COUPLANT/ AGEBEAM CIRC.: 6 EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam V
/J\ 2) Angle Beam-Normal-Against Flow
- 3) Angle Beam-Normal-With Flow .V
- 4) Angle Beam-Along Weld-CW Vw
- 5) Angle Beam-Along Weld-CCW ' _ _
F L 6) Straight Beam of Weld V 0 W 7) Thickness Across Weld & Base Metal VN /VA N UP STRM WELD DN STR ADDITIONAL COMMENTS
^NDIor*/aTIJS oB*egE40 IN MI.DWALL th A ,..Goivt.
t3LLL*.4 fZ9C0?9Pk~fLr LeN'J6L3 A/v A(OZZLC5 S106' of 1i4Z.e- e5%Aowa1.,jeb buei -ra yozzC Co/CtifSU?Ar10c.y EXAMINER: LEVEL:. DATE: - /- q_ REVIEWER: LEVEL: _ ___ DATE__._-__-___ OTHER:-/ A~c LEVEL: -27DATE: "/In,4' STATION: d -.
- DATE: /96 ANII: , DATE: ,- -,C Page 46
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. N'DT-C-30 Rev. 2 December, 199. Page 20 of 199: December, 22 ULTRASONIC TESTING DATA SHEET NDT-DU-C2A STATION/UNIT: LAS1LU_ 1 1 PAGE: 1 OF -I,- PROCEDURE: NDT- R-E0 RV. ___ DATA SHEET NO.: ?_,/ ___DATE: -- /4-9/ CALIBRATION SHEET NO'(S) ST. BEAM: -- 063 ANGLE BEAM: axial Q circ. C-Osq COMPONENT INSPECTED SYSTEM: ________ WELD 0: L CS - I-Al3hC- WELD TYPE: M PIPE SIZE: I" THICKNESS/SCHEDULE: 70" MATERIAL: Cs COMPONENT TEMPERATURE: e4 0 IS) 5 4S I SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: 60. ANGLE BEAM AXIAL: 54., COUPLAT/.... BATCH I" IL'T~f~ .EL =1 9s3o-
..- ANGLE BEAN CIRC..: QY 0 EXAMINATION SCANS...
Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam
/ \ 2) Angle Beam-Normal-Against Flow -
- 3) Angle Beam-Normal-With Flow
- 4) Angle Beam-Along Weld-CW
- 5) Angle Beam-Along Weld-CCW V-'/
L 6) Straight Beam of Weld _ 0 W 7) Thickness Across Weld & Base Metal / AA/A -1A/ 1A/A UP STRM WELD DN STR ADDITIONAL COMMENTS
*Lornt* Fe P wIT* L5L 4.* ..
lAo z.L>--1E- LIU otF 65EA.fQ ~,ExX~it b~ti TbPo i2ZzLC - EXAMINER:. LEVEL: 71 DATE: _ _-_ REVIEWER: ___LEVEL: DATE: t*- ,
&2-OTHER: 7ý)
- LEVEL: 2 DATE: ________
STATION - , " DATE: -- ,p 2 ANI - '-' - DATE: z- ( Page 47
0GE Nuclear Energy Typical for Welds: LCS-1-N3A, Data Sheets 96-162 & 163 LCS-1-N3B, Data Sheets 96-164 & 165. LCS-1-N3C, Data Sheets 96-166 & 167 LCS-I-N3D, Data Sheets 96-168 & 169 Due to the configuration of the nozzle no exams were performed from the nozzle aide. This limits the coverage achieved to: 0° = 57.85% 450 = 61.60% 600 = 60.40% Total composite coverage a 59.95% 00 a, CU 0-K I. REPORT NO.: GE REVIEWIED BY DATE ADATE OF: 2 LEVEL DATE UILTY REVIEW PAGE: 2 ER IWA7,
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 1993 ULTRASONIC TESTING DATA SKEET NDT-DS-C2A STATION/UNIT: LN 5hl.Lr!/l PAGE: / OF / PROCEDURE: NDT-C____ REV. 2- DATA SHEET NO.: 9- /67 DATE: 2-/'- ,L CALIBRATION SHEET NO.(3) ST. BEAM: A/A ANGLE SEAM: axial C- ,-6 circ. _ -__.._. _ COMPONENT INSPECTED SYSTEM: M5 WELD LCS- I-L, A13 - WELD TYPE: PVS PIPE SIZE: _____, THICKNESS/SCHEDULE: 7.0" MATERIAL: CS COMPONENT TEMPERATURE: ? £ g ?32 SCAN GAIN CONTROL SETTINGS STRAIGHT D3EA: )V$ ANGLE BEAM AXIAL:3d COUPLANT/ BA ICs________ EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Seam I
/ \ 2) Angle Beam-Normal-Against Flow
- 3) Angle Beam-Normal-With Flow
- 4) Angle Beam-Along Weld-CW V
- 5) Angle Beam-Along Weld-CCW F
L 6) Straight Beam of Weld O W 7) Thickness Across Weld & Base Metal J P4 P.. UP STRM WELD INSTR ADDITIONAL COMMENTS lwoic4ryop40s cose-AVEs /AJ m'p iJmL W'f' Lo4 <fCoXAjLg Li/LS Ado A/p~ze.,C jib06 OA' tueCO e-kA4,N/./ euC 70o A/ozze&CC,6- ~er EXAMINER: LEVEL: -= DAT?: 2-1L1- 7L REVIEWER: LEVEL: I DATES .2-?'%-, OTHER:~ LEVEL: 72Z:_ DATE: 3/261/ye STATION
- DATE:_______
ANII: --- 7_* *- DATE:- Page 49
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 199. ULTRASONIC TESTING DATA SKEET NDT-DS-C2A STATION/UNIT: L-S\LkE. 111 PAGE: OF PROCEDURE: NDT- C- REV. ___ DATA SHEET NO.: 9_ --/_ _ __ DATE: _ -__ -__ CALIBRATION SHEET NO.(S) E ST. BEAM: C- ANGLE BEAM: axial -_I _5_ circ. " COMPONENT INSPECTED SYSTEM: /)-S WELD 0: LC.S -I- "-.!O WELD TYPE: AIS PIPE SIZE: a6, THICXESS/SCHEDULE: MATERIAL: C COMPONENT TEMPERATURE: Ago 5 tjIq~j SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: 14 ANGLE BEAM AXIAL: ,5 6. COUPLANT/ BATCH #: ULTVA_&L- .)" S X5 I ANGLE BEAM CIRC.: 59.0 EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam -
/ I\ 2) Angle Beam-Normal-Against Flow . -
- 3) Angle Beam-Normal-With Flow -
- 4) Angle Beam-Along Weld-CW -
- 5) Angle Beam-Along Weld-CCW7 _ ________
F L 6) Straight Beam of Weld 0 W 7) Thickness Across Weld &Base Metal NI I 'A11, A11/A UP STRM WELD DN STR ADDITIONAL COMMENTS WAF-VnrEbt &~Apm 1t:-& 6LA. 4 LlS.s
)IfJOIC~A-TootS Q&VU060L iki mit3L.PL Qc .. CI.'E-tAL it~S AO AJ02.2.LF_ sioLc-or we6 E- O tip -Tb oanzzL~s C gau4ra+/- i .
EXAMINER: _<4 ) LEVEL: f DATE: .,-)'-9., REVIEWER:- LEVEL:.,. . DATE:_ _____ OTHER: 1; " Z)LEVEL: DATE._______ ST IO A T e-,4Zt' DATE: ~ ANII: ._ DATE: _-Z -t Page 50
S GE Nuclear Energy Typical for Welds: LCS-1-N3A, Data Sheets 96-162 & 163 LCS-1-N3B, Data Sheets 96-164 & 165 LCS-1-N3C, Data Sheets 96-166 & 167 LCS-1-N3D, Data Sheets 96-168 & 169 Due to the configuration of the nozzle no exams were performed from the nozzle side. This limits the coverage achieved to: 00° 57.85% 450 = 61.60% 609= 60.40% Total composite coverage a 59.95% U') 0o REPORT NO.:
)Vuet,ý- - ,-:/?. 4If , 2 GE REVIEWED BY LEVEL DATE UTILITY REVIEW DATE SMAD EVIEWDATE PACE:~ - OF: 2 GE REVIEWE BY EIWLEE>AEUul
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 1993 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: LAS ALI-*/ I PAGE: OF PROCEDURE: NDT- i 3 REV. _2 DATA SHEET NO.: DATE: ____-___ CALIBRATION SHEE NO.(S) ST. BEAM: /VA ANGLE BEAM: axial C r6--)c-- circ. 6-COMPONENT INSPECTED SYSTEM: iYS WELD 0: /CS-/-AJ3D WELD TYPE: A/_S _ PIPE SIZE: j ". THICKNESS/SCHEDULE: 7. MATERIAL: C COMPONENT TEMPERATURE: S 9q F I SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: , 4/ .. ANGLE BEAM AXIAL: COUPLANT/ 13ATCH *: Q4t71&1AA-.L 7*- q5~32a ANGLE BEAM CIRC.z ______ EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam
/ \ 2) Angle Beam-Normal-Against Flow >
- 3) Angle Beam-Normal-With Flow ><
- 4) Angle Beam-Along Weld-CW >
- 5) Angle Beam-Along Weld-CCW <>
L 6) Straight Beam of Weld w 7) Thickness Across Weld & Bass Metal -IA Al N/A N/A UP STEM WiELD 0f STR ADDITIONAL COMMENTS AtYa1 PtAc d XAH.W r ( 0'
,M/D)CArjor.JS e>6.pijq~jp yo Ai13 WAfLL A6*rp agelov, N~O A/07_2 Si5 Cf-A e t ec~b C1X,4i,Mlwlg5 b&C 7D 1Aop- d.C Co't4,F-16a O4Tjo.
EXAMINER:* LEVEL: _ ___ DATE: Z"/'" 7 REVIEWER: LEVEL:
- DATE: 1t7 7
*LEVEL: J DATE: * /
STATION: C.e- DATE: - ANII: - - -- DATE: -2 -, Page 52
CormEd Page 19 of 2 Procedure No. NDT-C-2 Rev. 22 September, 1 ULTRASONIC TESTING DATA SETNDT-DS-C2A STATION/UNIT: Z4S f//t114- PAGE: _ _oF PROCEDURE: NDT- a-LREV.,~ DT HE O:' DATE: ~/-~ CALIBRATION SHEET NO. (S) ST. BEAM: ,_ ____ ANGLE BEAMs axial _ -_ __"7 2- circ. C- 7 . COMPONENT INSPECTED S YSTEM: "fI&i WELD I:#t/fl-. WELD TYPE:- PIPE SIZE: - THICKNESS/SCHEDULE: . MATERIAL: C.5 COMPONENT TEMPERATURE:es /i ,-c-, SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: W_/0 ANGLE BEAM AXIAL: 5_0.A_ COUP/ANT BATCH O I: 7fqe,ý -g-~ /*g..rji* I ANGLE BEAM CIRC *: old - EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam
/ \ 2) Angle Beam-Normal-Against Flow
- 3) Angle Beam-Normal-With Flow
- 4) Angle Beam-Along Weld-CW S) Angle Beam-Along Weld-CCW L 6) Straight Beam of Weld 0
W 7) Thickness Across Weld & Base Metal . ,#/" ,,j-2 I .,//Al UP STRM WELD DN STR ADDITIONAL COMMENTS IS4
' s 1.f-'- 4td "oA'S AeA o =C, 2O gg,~ tji EAIE:LEVEL: ~7DATE. 6,2 7-9 REVIEWER: LEVEL: . - DATE:
OTHER: LEVEL. DATE: '3106/f STATIONe 6 - DATE: ANII: DATE: 0-1 Page 53
WALL THICKNESS SITE: LaSalle Unit I REPORT NO.: GE NuclearEnergy PROFILE SHEET PROJECT: LIR07 SYSTEM: 9#6/ _ COMPONENT ID I HX/l
. -1i Po0M ON 0 w 1w 27r-I CROWN HEIGHTT_ .,/ L 2 2/ C RO WN WID TH : 1 r "_ /_ -.
, / * /'/'/* NOM DIAMETER' 4 W f FLO-6 4~~~ WELD LENGTH: PLO LO (0
RH-HXIB-1
- 1. Due to the configuration of the nozzle, no axial exams were performed on the base material of the nozzle.
- 2. Due to the cladding on the ID two direction coverage from one side Is not possible.
Because of these two limiting factors, 80% coverage of the code required volume was achieved. DRAWN BY LEVEL DATE GE REVIEWED BY LEVEL DATE
NDT-D-2 Revision 10 October, 1994 FORM NDT-D-2-FI Page 47 of 48 LIQUID PENETRANT EXAMINATION DATA SHEET DATE: /-Z?49f STATION & UNIT: LaSalle UnitI DATA SHEET # - 6 EXAMINER:- '5/Th V6ýý/ C ,4~&LEVEL:________ SYSTEM:_ __ /__C.5 MATERIAL: C5 COMPONENT:5 SECTION XI EDITION & ADDENDA: 1989 Edition, No Addenda CODE CLASS: SECTION XI CATEGORY: C" 6 _ ACCEPTANCE STD.: //,</fC "J5/5-PROCEDURE # & REVISION: NDT-D-2 Rev. 10 SKETCH SHEET USED: YES ____ NO COMMENTS: Configuration: - 7n(' ,/p4 -_ - ,- A/ , , " Ivo r X r*/u *v) ,A7A?4Z- 7"£ % <,,
- A/_- .2,,4 i,,J e,*-*
LIQUID PENETRANT EXAM: MATERIAL: MATERIAL MANUFACTURE: Magnaflux TYPE BATCH PRE-EXAM CLEANER: SKC-S DRYING 2ffi MINUTES PENETRANT: SKL-SP L 56 0//k" PENETRATION -Jo- MINUTES PENETRANT CLEANER: SKG-S /' DRYING MINUTES DEVELOPER: SKD-S2 DEVELOPING -MITES POST EXAM CLEANER: SKC-S SURFACE TEMPERATURE: !720 . /ff793 _-- LIGHT SOURCE: EXAMINATION RESULTS: ACCEPT V REJECT A/ REVIEWED BY: EXAMINER:______________ ____ LEVEL: 2 T DATE: REVIEWER: _ _ _ __ LEVEL: / DATE: _______ OTHER: LEVEL: ___ ___ DATE: STATION:6 _DAATE: ANII: ____________ DATE:-~ ~~ ( Page 55
99 6ed Revision 10 October, 1994 ofID-2-V2 UDT Page 48 of 48 8UT.H W F*OR =TQUC= PJNN]t2UT UINA -CU IM 1-ER:-9 B~~hTZORI La5# Z46-£4~L*1IU/ D~ sl7-r2 T-6 1/,0A) .A62___ z mxzm
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& ze7 1 o CL6,6A-A1CF FOR 40C "976F///)/,/ /A-
_ _ _ _ _ _ _ _ _ _ _ U V L.. a i _ _*__ DAT!. _______,_. _ _ _ __-_ _ _ _ _ _ _ _ Lm'.v* , :J D A,.I- _ _. _- _._ _ AZuWED DIM
4 EXAMINATION
SUMMARY
SHEET Repw No.: GE NUCLEAR ENERGY LaSalle Unit I LIR08 9.0,4 11.0083.2 LCS-1-N6A N-SH GEL-1109 RPV B-D ID Number: Component ID: Configuration: Drawing: System: ASME Cat.: Examination Cert Exam Exams Data Cal Procedure Calibration Personnel Level Completed Performed Sheet Sheet Revision Block CE Frakes II 11/04/99 0 D-147 D-147 (,r-DRD-300V3 R.0 01-91-03 45S D-148 D-148 LT-DRD-30OV$ R.0 01-91-03 60S D-149 D-149 LT-DRD-300V3 R-0 01-91-03 Examination Results: Ultrasonic examinations were performed using a combination of 0°, 45" and 60* shear wave search units. No examination performed from the nozzle side due to configuration. No recordable indications were detected. 69.5% coverage of the required ASME Section X1 volume was achieved. Examination results were comparedto data report D673,675,677 from LIR03 outage with X .Vo Change These examinations wereperformed under Work Order: N/A Change This Summary and the following data sheets have been reviewed and accepted by thefollowingpersonrnel: RWP: 1107 _____Dose: 10 mr. Rovi By* Level: Date: Station Reviewed By:
Title:
Date: Reviewed By: Level: Date: ANII Rltw-- By:
Title:
Date: Page 1 of 9 Page 57
LaSalle UaIt I N6 Nouie Examination coverage obtaned no limitations . CROSS SECTIONAL AREA (per uike) TOTAL CODE COVEtRAGE code cross area area % of code area % of code area degrees degrees percent percent sectional scanned scanned scanned scanned scanned scanned scanned scanned area automated manually automated manually automated manually automated manually 0, wm 62.4 0.0 32.3 0.0 51.6 0.0 360.0 0.0 51.8 45" T-scan 62.4 0.0 51.2 0.0 82.1 0.0 360.0 0.0 82.1 60" T-scan 62.4 0.0 54.6 0.0 87.5 0.0 360.0 0.0 87.5 45" P-scan CW 62.4 0.0 40.1 0.0 64.3 0.0 360.0 0.0 64.3 45" P-scan CW 62.4 0.0 40.1 0.0 84.3 0.0 3600 0.0 64.3 60" P-scan CW 62.4 0.0 42.6 0.0 68.3 0.0 360.0 0.0 68.3 60' P-scan CCW 62.4 0.0 42.6 0.0 68.3 0.0 360.0 0.0 68.3 cO L0 0.0 69.5 Manual scans were not restricted. No credit taken for initial 1/4" of matera in Code coverage calculations due to nea field effects. Total Composite Coverage - 69.5% L.Z7 ?,/0/97 Pcjý, Lasalle 1 LPCI 45" and 60" T-scon exammination coverage 0* L-wave scan coverage a) 60"T CO 7: --# %7 /',,9/'
,,7/,,k-*./ .
Lasalle 1 LPCI 45" and 60" P-scan examination coverage 60"1 P"7 e- ;7'2
- -2A)
EXAMINATION
SUMMARY
SHEETReotN. GENUCLEARENERGY LaSalle Unit I LIR08 O.0,s ( 11.0085.2 LCS-1-N6C N-SH GEL-1 109 RPV B-D ID Number: Component ID: Configuration: Drawing: System.. ASME Cat.: Examination Cert Exam Exams Data Cal Procedure Calibration Personnel Level Completed Performed Sheet Sheet Revision Block CE Frakes If 11/04/99 0 D-150 D-150, LT-DRD-300V3 R.0 01-91-03 45S D-151 D-5I1 UT-DRD-300V3 R.0 01-91-03 60S D-152 D-152 UT--DRD-30OV3 R.0 01-91-03 Examination Results: Ultrasonic examinations were performed using a combination of 0", 45" and 60° shear wave search units. No examination performed from the nozzle side due to configuration. No recordable indications were detected. 69.5% coverage of the required ASME Section XI volume was achieved. Examination results were compared to data report D674.676,678 from L IR03 outage with X Vo Change These examinations were performed under Work Order: NJA Change This Summary and the following data sheets hav'e been reviewed and accepted by the following personnel. RWP: 1107 Dose: 100 mr. Reviewed B Level: Station Reviewed By:
Title:
Date: Reviewed By: Level: Date ANII R64wed By
Title:
Date: Page I of 9 Page 61
LaSalle Unit I N6 Nozzle Examination coverage obtained no limitabons. CROSS SECTIONAL AREA (per ofice) TOTAL CODE COVERAGE code cross area area % of code area % of code area degrees degrees percent percent sectional scanned scanned scanned scanned scanned scanned scanned scanned area automated manually automated manually automated manually automated manually 0* wm 624 0.0 32.3 0.0 51.8 0.0 360.0 0.0 51.8 45" T-scan 62.4 0.0 51.2 0.0 82.1 0.0 360.0 0.0 82.1 60" T-scan 62-4 0.0 54.6 0.0 87.5 0.0 360.0 0.0 87.5 45" P-scan CW 62.4 0.0 40.1 0.0 64.3 0.0 360.0 0.0 64.3 45" P-scan CW 62.4 0.0 40.1 0.0 64.3 0.0 360.0 0.0 64.3 60* P-scan CW 62.4 0.0 42.6 0.0 68.3 0.0 360.0 0.0 68.3 60" P-scan CCW 62.4 0.0 42.6 0.0 68.3 0.0 360.0 0.0 68.3 0.0 89 5 Manual scans were not restricted. No credit taken for initial 1/4" of materia in Code coverage calculations due to near field effects. Total Composite Coverage - 69.5%
, OR ST .o.-
. / o..)
-, ,/',,/
Lasalle 1 LPCI 45* and 60" T-scan exammination coverage 0' L-wave scan coverage CD (0O 0) Aq-no/?.. 4 4y* )-
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AD -,,,/,5-/ /,-2 J.. A..,_z' .i/... o
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Lasalle 1 LPCI 45' and 60" P-scan examination coverage I
'60*P D14 -. .o 1 6 -i,/, ,/5 ,
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I, Report No.: EXAMINATION
SUMMARY
SHEET 1R9-016 GE NUCLEAR ENERGY Site and Unit: LaSalle Component /D: LCS-I-N10 Outage: L1 R09 N-SH System: RPV ASME Cat.: B-0 ASME Item B3 90 Aug Requirements: NIA Exams Performed Data Sheet Cal Sheet Procedure I Calibration Block Examination Cert Leveli Date Personnel 60 Shear RPV-036 N/A UT-EXLN-300 V4 01-91-03 Paul Anderson II 01/17/2002 01 Log. . RPV-037 N/A UT-EXLN-300 V4 01-91-03 Paul Anderson II 01/17/2002 45* Shear RPV-035 N/A UT-EXLN-300 V4 01-91-03 Paul Anderson II 01/17/2002 Examination Results: Manual O0 weld and base metal, 450/600 S transverse and parallel scans were performed on the N1O Recirculation inlet nozzle in accordance with procedure UT-EXLN-300 V4. Manual scanning was performed 3600 around the nozzle. There were no recordable indications. Due to the nozzle configuration it is not possible to examine 100% of the ASME code required area. Ultrasonic examination results were acceptable to the requirements of ASME B&PVC Section Xl 1989 Edition, no Addenda, Category B-D welds and USNRC Reg. Guide 1.150 Revision 1 (Alternate Method). Previous examination results were reviewed, no change. Manual composite coverage = 72.4% Examination results were comparedto data report D-680, 682, 684 from R03 outage with Wj No Change These examinations were performed under Work Order: 99270105 Li Change This Summary and the following data sheets have been reviewed and accept~ec t e foltowing personnel:
" . , -RWP: N/A
~j4 ///o' ~Dose: N/A mr.
Prepared By: Level: Date: Utility Reviewed By:
Title:
Date: Reviewed By: / Level: Date: ANII Reviewed By:
Title:
Date: Page I of _. Page 65
LaSalle Unit1 CRD (N10 NOZZLE) Jan-02 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned % of Area Scanned Degrees Scanned % Scanned 0 2 Area Inch Auto Manual Auto Manual Auto Manual Auto Manual 0° WELD METAL N 60.51 0.0 32.6 0.0 53.9 0.0 360.0 0.0 53.9 450 T-SCAN N 60.51 0.0 49.4 0.0 81.7 0.0 360.0 0.0 81.7 450 T-SCAN N/A 60.51 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 450 T-SCAN N/A 60.51 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 600 T-SCAN N 60-51 0.0 52.1 0.0 86.1 0.0 360.0 0.0 86.1 600 T-SCAN N/A 60.51 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 600 T-SCAN NIA 60.51 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 45° P-SCAN CW N 60.51 0.0 47.7 0.0 78.9 0.0 360.0 0.0 78.9 600 P-SCAN CW N 60.51 0.0 50.7 0.0 83.8 0.0 360.0 0.0 83.8 450 P-SCAN CCW N 60.51 0.0 47.7 0.0 78.9 0.0 360.0 0.0 78.9 600 P-SCAN CCW N 60.51 0.0 26.2 0.0 43.3 0.0 360.0 0.0 43.3 Coverages 0.0 72.4 Total Composite Coverage 72.4 COMMENTS: Manual UT scans were limited due to the OD blend radius. CovCalc.xls 10/6/00 \4
LaSalle 1 CRD (N10) Code Required GO 450 and 600 T-Scan Exam Volume - 60.51 Sq. In. 00 Exam Volume - 32.61 Sq. In. co 450 T-Scan Exam Volume - 49.42 Sq. In. 4600 T-Scan Exam Volume - 52.07 Sq. In. 50.
LaSalle 1 CRD (N10) Code Required 450 and 600 P-Scan Exam Volume - 60.51 Sq. In. 45 0 F'-Scan Exam Volume - 47.72 Sq. In. 60 0 F'-Scan Exam Volume - 50.72 Sq. In. 600
Report No.: GREXAMINATION GE NUCLEAR ENERGY
SUMMARY
SHEET 1R9-017 Site and Unit: LaSalle Component ID: LCS-1 -N2B Outage: LI R09 N-SH System: M ASME Cat.: B.1 ASME Item B3. 90 Aug Requirements: N/A Exams Performed Cal Sheet Procedure Calibration Block Examination Cert Level Date 60
- Shear RPV-012 N/A UT-EXLN-300 V41 01-91-03 Charles Barrett II 01/15/2002 0° Long. RPV-O04 N/A UT-EXLN-300 Vr4 01-91-03 Todd Ginder II _ 01/15/2002 4
" .. Shee. ...... RPV-O08 N/A L UT-EXLN-300 Vy 01-91-03 Edward Mazyck II 01/15/2002 Examination Results:
Manual 00 weld and base metal, 450/600 S transverse and parallel scans were performed on the N2B Recirculation inlet nozzle in accordance with procedure UT-EXLN-300 V4. Manual scanning was performed 3600 around the nozzle. There were no recordable indications. Due to the nozzle configuration it is not possible to examine 100% of the ASME code required area. Ultrasonic examination results were acceptable to the requirements of ASME B&PVC Section Xl 1989 Edition, no Addenda, Category B-D welds and USNRC Reg. Guide 1.1 50 Revision 1 (Alternate Methodi. Previous examination results were reviewed, no change. Manual composite coverage = 70.9% Examination results were compared to data report D-117,126,136 from Li R04 outage with , No Change These examinations were performed underWork Order 99270105 7- Change This Summary and the following data sheets have been reviewed and accepted by th following personnel: RWP: N/A _ J. / I//s.- , ,/ , Dose: N/A mr.
*repared By: ' Level: Date: Utility Reviewed By:
Title:
ate: Reviewed By: Level: Date: ANII Reviewed By:
Title:
Date: Page I of -2 Page 69
LaSalle Unit1 N2B Recirculation Inlet JAN. 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned % of Area Scanned Degrees Scanned % Scanned 2 0 Area Inch Auto Manual Auto Manual Auto Manual Auto Manual 00 WELD METAL N 76.82 0.0 41.1 0.0 53.4 0.0 360.0 0.0 53.4 45' T-SCAN N 76.82 0.0 63.1 0.0 82.2 0.0 360.0 0.0 82.2 450 T-SCAN NIA 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 450 T-SCAN NIA 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 600 T-SCAN N 76.82 0.0 66.1 0.0 86.1 0.0 360.0 0.0 86.1 60° T-SCAN NIA 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 600 T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 450 P-SCAN CW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 60' P-SCAN CW N 76.82 0.0 64.6 0.0 70.9 0.0 360.0 0.0 70.9 450 P-SCAN CCW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 60' P-SCAN CCW N 76.82 0.0 54.5 0.0 70.9 0.0 360.0 0.0 70.9 Coverages 0.0 70.9 Total Composite Coverage 70.9 COMMENTS: Manual UT scans were limited due to nozzle radius. ~J'x r.0
-0
'3/4 CovCalc.xls 10/6/00 N
=
LaSalle 1 Recirculation Inlet (N2) 0* L-Wave Scan examination coverage 450 and 600 T-Scan examination coverage I CD 6\,
-Q
LaSalle 1 Recirculation Inlet (N2) 45° and 600 P-Scan examination coverage "0 CD (.0
--4 IQ "4 .-o N
'N
Report No.: (UiERi) GE NUCLEAR ENERG Y EXAMINATION
SUMMARY
SHEET IR9-018 Site and Unit: LaSalle Component ID: LCS-1-N2C Outage: LI R09 N-SH System: RPV ASME Cat.: 1-0 ASME Item B3. 90 Aug Requirements: Exams Performed DaaSet T Cal Sheet~ Procedure {Calibration Blc Personnel
!xmnton Lee Cart Lvl Date 600' Shear RPV-013 N/A UT-EXLN-300 1./S/ 01-91-03 fCharles Barrett 11I 01 /15/2002-0° Long. RPV-005 N/A UT-EXLN-300 01-91-03 Todd Glnder . II 01/15/2002 Sheear RPV-OO9 J N/A UT-EXLN-300 01-91-03 Edward Mazyck I1 01/15/ i2002 Examination Results:
Manual 00 weld and base metal, 4501600 S transverse and parallel scans were performed on the N2C Recirculation inlet nozzle in accordance with procedure UT-EXLN-300 V4.' Manual scanning was performed 3600 around the nozzle. There were no recordable indications. Due to the nozzle configuration it is not possible to examine 100% of the ASME code required area. Ultrasonic examination results were acceptable to the requirements of ASME B&PVC Section Xl 1 989 Edition, no Addenda, Category B-D welds and USNRC Reg. Guide 1.150 Revision 1 (Alternate Method). Previous examination results were reviewed, no change. Manual composite coverage = 70.9% Examinat/on results were compared to data report D-118, 127,137 from L1R04 outage with W No Change These examinations were performed under Work Order: 99270105 El Change This Summary and the following data sheets have been revwewed and by faccep personnel: tollowing
< -* - ,, _ I* /i/- . "RWP:. .. /.. N/A 4 /4 - z: Dose: N/A mr.
Prepared By: Level: Date: Utility Reviewed By:
Title:
Da e: Reviewed By: Level: Date: ANII Reviewed By: Title. Date: Page 1 of 7 Page 73
i 1ý LaSalle Unitil N2C Recirculation Inlet JAN. 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned % of Area Scanned Degrees Scanned % Scanned 0 Area Inch" Auto Manual Auto Manual Auto Manual Auto Manual 0° WELD METAL N 76.82 0.0 41.1 0.0 53.4 0.0 360.0 0.0 53.4 45' T-SCAN N 76.82 0.0 63.1 0.0 82.2 0.0 360.0 0.0 82.2 450 T-SCAN NIA 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 45' T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 60* T-SCAN N 76.82 0.0 66.1 0.0 86.1 0.0 360.0 0.0 86.1 600 T-SCAN NIA 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 600 T-SCAN NWA 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 450 P-SCAN CW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 60° P-SCAN CW N 76.82 0.0 54.6 0.0 70.9 0.0 360.0 0.0 70.9 45° P-SCAN CCW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 60' P-SCAN CCW N 76.82 0.0 54.5 0.0 70.9 0.0 360.0 0.0 70.9 Coverages 0.0 70.9 Total Composite Coverage = 70.9 COMMENTS: Manual UT scans were limited due to nozzle radius. ~I0~ A
-,0 N CovjCa(c.x~s 10/6100
LaSalle 1 Recirculation Inlet (N2) 450 and 600 P-Scan examination coverage I r600 O\ -II
-0 03
LaSalle 1 Recirculation Inlet (N2) CD 00 L-Wave Scan examination coverage -.4
- 0) 450 and 600 T-Scan examination coverage
-ýQ
Report No.: EXAMINATION
SUMMARY
SHEET IRerN19 GE NUCLEAR ENERGY I Site and Unit: LaSalle Component ID: LCS-1 -N2D Outage: Li R09 N-SH System: ASME Cat.: B-0 ASME Item B3. 90 Aug Requirements: NIA Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date Personnel 0° Long. 45° Shear W6 Siea, ,, RPV-017 RPV-018 RPV--019 N/A N/A N/A UT-EXLN-300 V4 UT-EXLN-300 V4 UT-EXLN-300 V4 [ 01-91-03 01-91-03 01-91-03 Hermann Schlortt Hermann Schlortt Hermann Schlortt Ill Ill Ill 01/15/2002 01/15/2002 01115/2002 Examination Results: Manual 0* weld and base metal, 450/600 S transverse and parallel scans were performed on the N2D Recirculation inlet nozzle in accordance with procedure UT-EXLN-300 V4. Manual scanning was performed 3600 around the nozzle. There were no recordable indications. Due to the nozzle configuration it is not possible to examine 100% of the ASME code required area. Ultrasonic examination results were acceptable to the requirements of ASME B&PVC Section X( 1989 Edition, no Addenda, Category B-D welds and USNRC Reg. Guide 1.150 Revision 1 (Alternative Method). Previous examination results were reviewed, no change. Manual Composite Coverage = 70.9% Examination results were compared to data report D-119, 128, 138 from Li R04 outage with No t Change These examinationswere performed under Work Order 99270105 D Change This Summary and the following data sheets have been reviewed and accepted by the following personnel: RWP: N/A
-, iitot~
____ j~j Dose: N/A mr. Prepared By: Level: Date: Utility Reviewed By:
Title:
- ate:
Reviewed By: Level: Date: ANII Reviewed By:
Title:
Date: Page I of 7 Page 77
LaSalle Unit1 N2D Recirculation Inlet JAN. 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE V U 2 Area Scanned % of Area Scanned Degrees Scanned % Scanned o Area Inch2 Auto Manual Auto Manual Auto Manual Auto Manual 0' WELD METAL N 76.82 0.0 41.1 0.0 53A4 0.0 360.0 0.0 53.4 45' T-SCAN N 76.82 0.0 63.1 0.0 82.2 0.0 360.0 0.0 82.2 45' T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 -O 45' T-SCAN NWA 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 CD 60' T-SCAN N 76.82 0.0 66.1 0.0 86.1 0.0 360.0 0.0 86.1 co 60° T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 60' T-SCAN N/A 76,82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 45' P-SCAN CW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 60' P-SCAN CW N 76.82 0.0 54.5 0.0 70.9 0.0 360.0 0.0 70.9 45' P-SCAN CCW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 60- P-SCAN CCW N 76.82 0.0 54.5 0.0 70.9 0.0 360.0 0.0 70.9 Coverages 0.0 70.9 OD Total Composite Coverage = 70.9 COMMENTS: Manual UT scans were limited due to nozzle radius. CovCatc.xis 1016100
-o
LaSalle 1 Recirculation Inlet (N2) CD -.4 00 L-Wave Scan examination coverage (n 450 and 600 T-Scan examination coverage 00
-7'
LaSalle 1 Recirculation Inlet (N2) 450 and 600 P-Scan examination coverage 1600 0 -o ,.N
Report No.: EXAMINATION
SUMMARY
SHEET 1R9-020 Lw GE NUCLEAR ENERG Y Site and Unit: LaSalle Component ID: LCS-1 -N2E Outage: Li R09 N-SH System: ASME Cat: B42 ASME Item S3_90 Aug Requirements: N/A Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date Exams Performed I S t CPersonnel I I 0" Long. RPV-014 N/IA UT-EXLN-300 V4 01-91-03 Chad Olson II 01/15/2002 45* Shear RPV-01 5 N/A UT-EXLN-300 V4 01-91-03 Chad Olson Ii 01115/2002 60:!Shear-~ RPV-016 N/A UT-EXLN-300 V4 01-91-03 Chad Olson II 01/15/2002 Examination Results: Manual 00 weld and base metal, 450/600 S transverse and parallel scans were performed on the N2E Recirculation inlet nozzle in accordance with procedure UT-EXLN-300 V4. Manual scanning was performed 3600 around the nozzle. There were no recordable indications. Due to the nozzle configuration it is not possible to examine 100% of the ASME code required area. Ultrasonic examination results were acceptable to the requirements of ASME B&PVC Section X1 1989 Edition, no Addenda, Category B-D welds and USNRC Reg. Guide 1.150 Revision 1 (Alternative Method). Previous examination results were reviewed, no change. Manual Composite Coverage = 70.9% Examination results were comparedto datareport D-120,129,139 from L1 R04 outage with
- No Change These examinations were penrormedunder Work Order: 99270105 L Change This Summary and the following data sheets have been reviewed and accepted bylhe foWlowing personnel: RWP: N.A
*; . *Ž/
/"i,/a.' '2 4~.* ,L Dose: N/A mr.
Prepared By: Level: Date: Utility Reviewed By:
Title:
Date: Reviewed By:( Level: Date ANII Reviewed By:
Title:
Date: Page 1 of -7 Page 81
LaSalle Uniti N2E Recirculation Inlet JAN. 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned % of Area Scanned Degrees Scanned % Scanned 0 Area Inch 2 Auto Manual Auto Manual Auto Manual Auto Manual 0
°WELDMETAL N 76.82 0.0 41.1 0.0 53.4 0.0 360.0 0.0 53.4 450 T-SCAN N 76&82 0.0 63.1 0.0 82.2 0.0 360.0 0.0 82.2 45* T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 450 T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 600 T-SCAN N 76.82 0.0 66.1 0.0 86.1 0.0 360.0 0.0 86.1 60° T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,0 600 T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 450 P-SCAN CW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 60' P-SCAN CW N 76.82- 0.0 64.5 0.0 70.9 0.0 360.0 0.0 70.9 45' P-SCAN CCW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 600 P-SCAN CCW N 76.82 0.0 54.5 0,0 70.9 0.0 360.0 0.0 70.9 Coverages 0.0 70.9 Total Composite Coverage = 70.9 COMMENTS:
Manual UT scans were limited due to nozzle radius. k CovCatc.xls 10/6100
LaSalle 1 Recirculation Inlet (N2) 00 L-Wave Scan examination coverage 450 and 60° T-Scan examination coverage C
-Qe N Ok
LaSalle 1 Recirculation Inlet (N2) 450 and 600 P-Scan examination coverage Co P, I 0
Report No.: EXAMINATION
SUMMARY
SHEET 1RS-021 GE NUCLEAR ENERGY Site and Unit: LaSalle Component ID: LCS-1-N2F Outage: LIR09 N-SH System: RPV ASME Cat.: B-0 ASME Item B3,90 Aug Requirements: NIA Exams Performed 0° Long. DataSheet RPV-032 CalShet N/A Procedure UT-EXLN-300 V4 CalibrationBlock I_____________ 01-91-03 J Examination Personnel Paul Anderson J Cert Level 3 II Date 01/17/2002 60 Shear RPV-033 N/A UT-EXLN-300 V4 01-91-03 Paul Anderson J 1 0117/2002 464 Sheer- : RPV-034 N/A UT-EXLN-300 V4 01-91-03 Paul Anderson J 1 01/17/2002 Examination Results: Manual 00 weld and base metal, 450/600 S transverse and parallel scans were performed on the N2F Recirculation inlet nozzle in accordance with procedure UT-EXLN-300 V4. Manual scanning was performed 3600 around the nozzle. There were no recordable indications. Due to the nozzle configuration it is not possible to examine 100% of the ASME code required area. Ultrasonic examination results were acceptable to the requirements of ASME B&PVC Section Xl 1989 Edition, no Addenda, Category B-0 welds and USNRC Reg. Guide 1.150 Revision 1 (Altqrnate Method). Previous examination results were reviewed, no change. Manual composite coverage = 70.9% Examination results were comparedto data report D-121,130, 140 from R04 outage with v No Change These examinations were peronnedunder Work Order 99270105 Change C This Summary and the following
! date sheets have been 7r~v/wed .*f:- and accepted by the following personnel.
*!f..RWP: R N/A
- a. A L~z~A /~Ž~< ~ 4~~Dose: N/A mr.
Prepared By: Level: Date: Utility Reviewed By:
Title:
ate: Reviewed By: Level: Date: ANII Reviewed By:
Title:
Date: Page 1 of Page 85
LaSalle Unit1 N2F Recirculation Inlet JAN. 2002 CODE CROSS-SEC71ONAL AREA TOTAL CODE COVERAGE Area Scanned % of Area Scanned Degrees Scanned % Scanned 2 Auto Manual 0 Area Inch Auto Manual Auto Manual Auto Manual 0
° WELD METAL N 76.82 0.0 41.1 0.0 53.4 0.0 360.0 0.0 53.4 45' T-SCAN N 76.82 0.0 63.1 0-0 82.2 0.0 360.0 0.0 82.2 45' T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 450 T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
-o ,CD CO 600 T-SCAN N 76.82 0.0 66.1 0.0 86.1 0.0 360.0 0.0 86.1 00 60' T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 600 T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 450 P-SCAN CW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 60° P-SCAN CW N 76.82 0.0 54.5 0.0 70.9 0.0 360.0 0.0 70.9 450 P-SCAN CCW N 76.82 0.0 61.1 0.0 66.5 0.0 360.0 0.0 66.5 600 P-SCAN CCW N 76.82 0.0 54.5 0.0 70.9 0.0 360.0 0.0 70.9 Coverages 0.0 70.9 Total Composite Coverage 70.9 COMMENTS: Manual UT scans were limited due to nozzle radius.
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LaSalle 1 Recirculation Inlet (N2) 0° L-Wave Scan examination coverage 450 and 600 T-Scan examination coverage -u Co C, N
LaSalle 1 Recirculation Inlet (N2) 450 and 600 P-Scan examination coverage CD 0O
'600
Report No.: G UA) EXAMINATION
SUMMARY
SHEET IR9-022
'~' GE NUCLEAR ENERGY Site and Unit: LaSalle Component ID: LCS-1-N2J Outage: Li R09 N-SH System: . RPV ASME Cat.: B-D ASME Item 63.90 Aug Requirements: N/A I II Exams Performed Data Sheet ICal Sheet Procedure Calibration Block Examination Cert Level Date
_________ ___________ Personnel-60 *Shear RPV-01 I N/A UT-EXLN-300 vV 01-91-03 Charles Barrett I11 01115/2002 00 Long._ RPV-003 NIA UT-EXLN-300 vy j 01-91-03 Todd Ginder 3 II 01/15(2002 46' Sheer- " RPV-007 NIA UT-EXLN-300 01-91-03 Edward Mazyck J II 01115/2002 Examination Results: Manual 0* weld and base metal, 450/600 S transverse and parallel scans were performed on the N2J Recirculation inlet nozzle in accordance with procedure UT-EXLN-300 V4. Manual scanning was performed 360* around the nozzle. There were no recordable indications. Due to the nozzle configuration it is not possible to examine 100% of the ASME code required area. Ultrasonic examination results were acceptable to the requirements of ASME B&PVC Section XI 1989 Edition, no Addenda, Category B-D welds and USNRC Reg. Guide 1.150 Revision 1 (Alternate Methodl. Previous examination results were reviewed, no change. Manual composite coverage = 70.9% Examination results were compared to data report D-115,133,143 from Li R04 outage with No Change These examinationswere performed under Work Order 99270105 Change Zhis Summary and the folowing date sheets have been review d and Prepared By: Level: Date: Utility Reviewed Ey Reviewed By: Level: Date: ANII Reviewed B Page 89
LaSalle Unit1 N2J Recirculation Inlet JAN. 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE "0 Area Scanned % of Area Scanned Degrees Scanned % Scanned 2 Area Inch Auto Manual Auto Manual Auto Manual Auto Manual 0* WELD METAL N 76.82 0.0 41.1 0.0 534 0.0 360.0 0.0 53.4 450 T-SCAN N 76.82 0.0 63.1 0.0 82.2 0.0 360.0 0.0 82.2 45* T-SCAN NIA 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 45' T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 600 T-SCAN N 76.82 0.0 66.1 0.0 86.1 0.0 360.0 0.0 86.1 600 T-SCAN NWA 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 60° T-SCAN NWA 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 45' P-SCAN CW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 60' P-SCAN CW N 76.82 0.0 64.5 0.0 70.9 0.0 360.0 0.0 70.9 45' P-SCAN CCW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 60' P-SCAN CCW N 76.82 0.0 54.5 0.0 70.9 0.0 360.0 0.0 70.9 Coverages 0.0 709 Total Composite Coverage = 70.9 COMMENTS: Manual UT scans were limited due to nozzle radius. 4." CovCalc~xls 101,6100 0 N
LaSalle 1 Recirculation Inlet (N2) (0 CC) 0* L-Wave Scan examination coverage CD (9
\I 450 and 600 T-Scan examination coverage 6\,
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LaSalle 1 Recirculation Inlet (N2) 450 and 600 P-Scan examination coverage CD I CD Pi N N
Report No.: GE NUCLEAR ENERGY EXAMINATION
SUMMARY
SHEET 1R9.023 Site and Unit: LaSalle Component ID: LCS-1 -N2K Outage: LIR09 N-SH System: REV ASME Cat.: . ASME Item 83.90 Aug Requirements: N/A Exanms Performed Data Sheet Cal Sheet Procedure Calibration Block! Examination 'Cart Level DateI I I I Personnel I 0' Long. RPV-002 N/A UT-EXLN-300 4qlj 01-91-03 -Todd Ginder if 01/151l2002 45* Shear RPV-006 N/A UT-EXLN-300 Vq1 01-91-03 Edward Mazyck II 01/1512002 W6GShea"r- . RPV-010 NIA UT-EXLN-300 vy 01-91-03 Charles Barrett it 01(15/2002 Examination Results: Maoual 00 weld and base metal, 450/600 S transverse and parallel scans were performed on the N2K Recirculation inlet nozzle in accordance with procedure UT-EXLN-300 V4. Manual scanning was performed 3600 around the nozzle. There were no recordable indications. Due to the nozzle configuration it is not possible to examine 100% of the ASME code required area. Ultrasonic examination results were acceptable to the requirements of ASME B&PVC Section Xl 1989 Edition, no, Addenda, Category B-D welds and USNRC Reg. Guide 1.150 Revision 1 (Alternate Method). Previous examination results were reviewed, no change. Manual composite coverage = 70.9% Examinationresults were comparedto data report 0-124,134, 144 from LI R04 outage with F No Change These examinations were performed under Work Order: 99270105 L Change This Summary and the following data sheets have been re wed and accep0%by t following personnel: RWP: N/A
~ '~' ~7 f Dose: N/A mr.
Prepared By: Level: Date. UtilityReviewed By: //
Title:
Da Reviewed By: Level: Date: ANII Reviewed By:
Title:
Date: Page 1 of 7 Page 93
LaSalle Unit1 N2K Recirculation Inlet JAN. 2002 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned % of Area Scanned Degrees Scanned % Scanned 0 Area Inch 2 Auto Manual Auto Manual Auto Manual Auto Manual 0* WELD METAL N 76.82 0.0 41.1
- 0.0 53.4 0.0 360.0 0.0 53.4 450 T-SCAN N 76.82 0.0 63.1 0.0 82.2 0.0 360.0 0.0 82.2 45' T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 45° T-SCAN NIA
") 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 CD 600 T-SCAN N 76.82 0.0 66.1 0.0 86.1 0.0 360.0 0.0 86.1 (.o 60' T-SCAN N/A 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 -P, 600 T-SCAN NIA 76.82 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 45' P-SCAN CW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 600 P-SCAN CW N 76.82 0.0 54.5 0.0 70.9 0.0 360.0 0.0 70.9 45° P-SCAN CCW N 76.82 0.0 51.1 0.0 66.5 0.0 360.0 0.0 66.5 60 P-SCAN COW N 76.82 0.0 54.5 0.0 70.9 0.0 360.0 0.0 70.9 Coverages 0.0 70.9 Total Composite Coverage = 70.9 COMMENTS: Manual UT scans were limited due to nozzle radius. I
.z~I N No OVa.CX.s 10/6/00 :*U IUIU/UU Xl vt*CllL;,
LaSalle 1 Recirculation Inlet (N2) 45° and 600 P-Scan examination coverage CD CD 0"1 I M -,0
LaSalle 1 Recirculation Inlet (N2) CD (.0 00 L-Wave Scan examination coverage CYD 450 and 600 T-Scan examination coverage 00 hO "4 --o 0
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET REPORT NO: 1R9-024 PROJECT LaSalle Unit 1 - L1RO9 WELD ID: LCS-1-N4A SYSTEM: RPV- FEEDWATER INITIAL CALIBRATION ID: NOZ.IN.1, 70RL.IN1 CALIBRATION VERIFICATIONS: N4A.2, N4A.3, N4A.70RL.1, N4A.70RL.2 DATA SHEETS: n4a.tl. 1, n4a.tI.2, n4a.tl.3, n4a.p1.1, n4a. p2.1, n4a.70rl.1 FINAL CALIBRATION ID: SEE
SUMMARY
SECTION BELOW MANUAL CALIBRATION: N/A EXAMINERA::. J. Kent Montgomery, Lv II, Mark Hilborn, Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section Xl, 1989 Edition no Addenda, Category B-D welds and USNRC Reg Guide 1.150 Revision 1 (Alternative Method). Automated 0°, 2.25 L-Wave; 450 and 600 Shear 1.0 MHz and 70° RL 2.0 MHz Transverse and Parallel scans were performed in accordance with procedure GE-UT-702 Version 2. Initial calibrations for the 0°, 450 and 60° Shear automated examinations were performed on code vessel block - S/N - 01-91-03. Calibration for the 700 RL automated examinations were performed on GENE sizing block, SIN -CAL-DPTH-60 ( Refer to G2K-CAL-1 Initial Calibration Summary Sheet). For final automated calibrations and linearities, refer to Calibration Summary Sheet - G2K-CAL-3. The GERIS 2000 OD automated UT system 0' reference is located 90° CW of nozzle TDC. The GERIS 2000 OD system recorded the following non-relevant indications: 00 Weld Metal - Entry Surface Noise, Geometry - Clad Noise 45' Transverse - Entry Surface Noise, Geometry - Clad Noise, Non-Relevant Reflector 60° Transverse - Entry Surface Noise, Geometry - Clad Noise, Geometry - Nozzle Bore 45' Parallel - Geometry - Clad Noise 600 Parallel - Entry Surface Noise, Geometry - Clad Noise 700 Transverse - Entry Surface Noise 70° Parallel - Entry Surface Noise These non-relevant indications were flagged and excluded from the final report. The GERIS 2000 OD system recorded one (1) indication with the 450 Tranverse search unit over 20% DAC which was found to be acceptable. No other indications requiring evaluation according to ASME B&PV Code Section Xl or USNRC Reg Guide 1.150 Revision 1 (Alternative Method) were recorded. Due to nozzle configuration it is not feasible to examine 100% of the ASME Code required volume. Automated 0',45* and 600 UT Coverage = 72.3%. Credit for the 45°/60° near field taken with the 70'. Automated 70° Near Surface UT Coverage = 44.7% Previous data was reviewed prior to the examination, changes are noted below. The GERIS 2000 Automated system records the complete RF data during scanning, it also utilizes search units with lower frequency elements and improved ultrasonic coupling. The GERIS 2000 Automated System has shown that with its improvements in examination techniques, indications have better reflectivity with a 1 MHz search unit over a 2.25 MHz., which could explain why this indication was not recorded during the prior manual inspection. PREPARED BY DATE REVIOWED BY DATE UTILITY REVE/ IAIE ANII REIEW DATE LA SALLE SUMNV.DOC 0, PAGE OF ___ Page 97
LaSalle Unit 1 N4A Jan-02 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned % of Area Scanned Degrees Scanned % Scanned 2 0 Area Inch Auto Manual Auto Manual Auto Manual Auto Manual 00 WELD METAL N 59.12 31.12 0.0 52.6 0.0 360.0 0.0 52.6 0.0 450 T-SCAN N 59-12 47.77 0.0 80.8 0.0 360.0 0.0 80.8 0.0 60' T-SCAN N 59.12 50.16 0.0 84.8 0.0 360.0 0.0 84.8 0.0 N 59.12 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 450 P-SCAN CW N 0, 59.12 37.90 0.0 64.1 0.0 360.0 0.0 64.1 0.0 (0 60' P-SCAN CW N 59.12 47.15 0.0 79.8 0.0 360.0 0.0 79.8 0.0 450 P-SCAN CCW N 59.12 37.90 0.0 64,1 0.0 360.0 0.0 64.1 0.0 600 P-SCAN CCW N 59.12 47.15 0.0 79.8 0.0 360.0 0.0 79.8 0.0 72.3 0.0 Total 0°, 45° and 60° Coverage = 72.3 70' T-SCAN N 21.13 11.75 0.0 55.6 0.0 360.0 0.0 55.6 0.0 700 P-SCAN CW N 21.13 8.28 0.0 39.2 0.0 360.0 0.0 39.2 0.0 700 P-SCAN CCW N 21.13 8.28 0.0 39.2 0.0 360.0 0.0 39.2 0.0 44.7 0.0 Total 70°Coverage = 44.7 COMMENTS:
"I Automated UT scans were limited due to the nozzle radius.
Credit for the initial 114" of material in code coveraue taken with the 70° I 02129/01 02/29/01
Lcsclle I FEED]WATER Cocde Required Exam Volume -ý 59.12 Sq. In. O0 L-W/ave Exam Volume - 31.12 Sq. In. 45* T-Scan Exam Volume - 47,77 Sq. In, 60 T-Scan Exam Volume 50.16 Sq. In. C0 (0 (o i
L asos((e 1 FEEDWAATER Code Required Exam Votume - 59,12 Sq, In, Co CD 450 P-Scan Exam Votume - 37.90 Sq, In. 600 P-Sccan Exam Volume 47,15 Sq. In, I--
Lasaole 1 FEEDWATER Code Required Exam Volume - 26.13 Sq. In, (0 CD 0 700 T-Scan Exam Volume - 11,75 Sq, In, 70° P-Scan Exam Volume 8,25 Sq. In. 70°T o-
Nozi _r((3) GOD-SL6C.xls LaSalle I 09118/00 N4 FEEDWA TER GERIS-2000 NOZZLE-TO-VESSEL SCANNING UMITS NOZOD 25 VSLIR 127 WALL 6.69 WELD RAD 17.25 ODBR 4 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 4 0.0* B 3.66 0.00 0.00 0.8" 0.501 0.150 0 19.74 91 47 79 56 I 0.0" W 3.66 0.00 0.00 0.8" 0.320 0.150 0 6.36 91 - - 56 - 2 45.0" T 13.26 3.00 0.00 0,8. 0.418 0.150 0 13.61 235 - 7.2 -7.2' 3 60.0° T 14.15 -3.00 0.00 0.8" 0.501 0.150 0 19.74 328 354.0" 6.0° 2 45.0 P1 13.26 3.00 0.00 0.8" 0.341 0.150 0 7.94 235 300.5° 59.5 (ccw) 3 60.0" P1 14.15 -3.00 0.00 0.8' 0.383 0.150 0 10.97 328 295.6' 64,4" (ccw) 2 45.0 P2 13.26 3.00 0.00 0.8" 0.341 0.150 0 7.94 235 - 78,1" -78.1* (cw) 3 60.0" P2 14.15 -3.00 0.00 0.8° 0.383 0.150 0 10.97 328 47.8" -47.8° (cw) r'- 1/17/2002 Page I
No0 GOD-SL6C.xls LaSalle 1 09/18100 N4 FEEDWA TER GERIS-2000 NOZZLE-TO-VESSEL SCANNING UNITS NOZOD 25 VSLIR 127 an WALL 6.69 CD WELD RAD 17.25 ODBR 4 CA) TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 1 70.0" T 1200 0.00 0.00 0.8" 0.387 0.150 0 11.27 54 0.0° 0-0" 2 70.0° P1 12.00 3.00 0.00 0.81 0.316 0.150. 0 6.10 54 287.5" 72.5* (ccw) 3 70.0" P2 12.00 -3.00 0.00 0,8" 0,316 0,150 0 6,10 54 72-5' -72,5' (cw) C> 1/17/2002 Page I
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET REPORT NO: 1R9-025 PROJECT LaSalle Unit 1 - L1RO9 WELD ID: LCS-1-N4B SYSTEM: RPV - FEEDWATER INITIAL CALIBRATION ID: NOZ.IN.1, 70RL.IN.1 CALIBRATION VERIFICATIONS: N4B 1, N48.2, N4B.70RL.1, N4B.70RL.2 DATA SHEETS: n4c.tI.1, n4c.pl.1, n4c.p2.1, n4c.70r0.1 FINAL CALIBRATION ID: SEE
SUMMARY
SECTION BELOW MANUAL CALIBRATION: N/A EXAMINERS- J. Kent Montgomery, Lv II, Mark Hilborn, Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, Category B-D welds and USNRC Reg Guide 1.150 Revision 1 (Alternative Method). Automated 0°, 2.25 L-Wave; 450 and 600 Shear 1.0 MHz and 700 RL 2.0 MHz Transverse and Parallel scans were performed in accordance with procedure GE-UT-702 Version 2. Automated scanning was limited due to the nozzle OD blend radius. Initial calibrations for the 00, 450 and 600 Shear automated examinations were performed on code vessel block - S/N - 01-91-03. Calibration for the 70* RL automated examinations were performed on GENE sizing block, S/N -CAL-DPTH-60 ( Refer to G2K-CAL-1 Initial Calibration Summary Sheet). For final automated calibrations and linearities, refer to Calibration Summary Sheet - G2K-CAL-3. The GERIS 2000 OD automated UT system 0° reference is located 90' CW of nozzle TDC. The GERIS 2000 OD system recorded the following non-relevant indications: 00 L-Wave - Entry Surface Noise, Geometry - Clad Noise 45° Transverse - Entry Surface Noise, Geometry - Clad Noise, Geometry - Nozzle bore 60° Transverse - Entry Surface Noise, Geometry - Clad Noise, Geometry - Nozzle Bore 45° Parallel - Entry Surface Noise, Geometry - Clad Noise 600 Parallel - Entry Surface Noise, Geometry - Clad Noise 700 Transverse - Entry Surface Noise, Non-Relevant Reflector 700 Parallel - Non-Relevant Reflector These non-relevant indications were flagged and excluded from the final report. The GERIS 2000 OD system recorded one (1) indication with the 70' Tranverse search unit that was found to be acceptable per the requirements of ASME B&PV Code Section XI, 1989 Edition No Addenda Table IWB 3510-1 No other indications requiring evaluation according to ASME B&PV Code Section XI or USNRC Reg Guide 1.150 Revision 1 (Alternative Method) were recorded. Due to nozzle configuration it is not feasible to examine 100% of the ASME Code required volume. Automated 00,450 and 600 UT Coverage = 72.3% Automated 700 Near Surface UT Coverage = 44.7% Credit for the 45°/60' near field taken with the 70°. Previous data was reviewed prior to the examination, changes are noted below. There was no previous 700 Near Surface data to review or compare.
.... UN
.L L 'Lj "1.*2K1"-.U-'/ -
FIREPARED BY DATE BREVUdE 3Y DATE U-* UIEVEW1 Dl* AINI REVIEW DATE LA SALLE SUMNV.DOC R ,, q Pane 104 Parr
. *v . v ,
LaSalle Unit I N4B Jan-02
*:*i Jan-02 N4B I*
LaSalleUnit CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE U Area Scanned % of Area Scanned Degrees Scanned % Scanned 2 0 Area Inch Auto Manual Auto Manual Auto Manual Auto Manual 00 WELD METAL N 59.12 31.12 0.0 52.6 0.0 360.0 0.0 52.6 0.0 450 T-SCAN 59.12 47.77 N 0.0 80.8 0.0 360.0 0.0 80.8 0.0 60° T-SCAN N 59.12 50.16 0.0 84.8 0.0 360.0 0.0 84.8 0.0 N 59.12 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 450 P-SCAN CW 59.12 37.90 N 0.0 64.1 0.0 360.0 0.0 64.1 0.0 600 P-SCAN CW N 59.12 47.15 0.0 79,8 0.0 360.0 0.0 79.8 0.0 45' P-SCAN CCW N 59.12 37.90 0.0 64.1 0.0 360.0 0.0 64.1 0.0 60' P-SCAN CCW N 59.12 47.15 0.0 79.8 0.0 360.0 0.0 79.8 0.0 72.3 0.0 Total 0O,450 and 60* Coverage = 72.3 700 T-SCAN N 21.13 11.75 0.0 55.6 0.0 360.0 0.0 55.6 0.0 700 P-SCAN CW N 21.13 8.28 0.0 39.2 0.0 360.0 0.0 39.2 0.0 70 P-SCAN CCW N 21-13 8.28 0.0 39.2 0.0 360.0 0.0 39.2 0.0 44.7 0.0 Total 700 Coverage = 44.7 C, COMMENTS: IAa #- A, I"'"r . . . . I -:* . J.-.-. . .I - :.. ICredit for~the initial 114" of material in code coveraoe taken with the 70=
.*UL diU wee UIslamUsclns dewe U 1,0 10zzi7 radIus.
Credit for the initial 114" of material in code coveraae taken with the 70' I 02/29/01I ,\
Lcxsci.e 1 FEEDWATER Coole Required Exam Volume - 59,12 Sq. In, 0* L-Wave Exam Volume - 31,12 Sq. In. 45* T-Scan Exam Volume - 47,77 Sq, In, 60* T-Scan Exam Votume 50,16 Sq, In. CD M J,J,
Lctscl~e 1 FEEDWATER Code Required Exam Volume . 59.12 Sq, In, 45° P-Scan Exam VoLume - 37.90 Sq. In. 60° P-Scan Exam VoLume 47,15 Sq. In, Co 'CD. 4 .
Lo~scle I FEEDWATER Code Required Exo.m Volume - 26,13 Sq, In, C) o 70' T-Scacn Exam Volume - 11.75 Sq, In, 70* P-Scmn Exalm Volume 8.25 Sq. In, 17O*T ( 70 P
-7Q* 70-T
NozT_,m(3) GOD-SL6C.xls LaSalle I 09/18/00 N4 FEEDWA TER GERIS-2000 NOZZLE-TO-VESSEL SCANNING LIMITS NOZOD 25 VSLIR 127 WALL 6.69 WELD RAD 17.25 ODBR 4 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 4 0.0' 8 3.66 0.00 0.00 0.8" 0.501 0.150 0 19.74 91 47 79 56 1 0.0" W 3.66 0.00 0.00 0.8° 0.320 0.150 0 6.36 91 - 56 2 45.0' T 13.26 3.00 0.00 0.8' 0.418 0.150 0 13.61 235 - - 7.22 -7.2' 3 60.0* T 14.15 -3.00 0.00 0.86 0.501 0.150 0 19.74 328 - 354.0' 6.0' 2 45.0' P1 13.26 3.00 0.00 0.8" 0.341 0.150 0 7.94 235 - 300.5' 59.5' (ccw) 3 60,0' P1 14.15 -3.00 0.00 0.8* 0.383 0.150 0 10.97 328 - 295.6' 64.4' (ccw) 2 45.0' P2 13.26 3.00 0.00 0.8° 0.341 0.150 0 7.94 235 - 78.1' -78.1° (cw) 3 60.0" P2 14.15 -3.00 0.00 0.8° 0.383 0.150 0 10.97 328 47.8' -47.8" (cw) 1/17/2002 Page I .3NA Di4
Nozi WU GOD-SL6C.xls LaSalle 1 09/18/00 N4 FEEDWA TER GERIS-2000 NOZZLE-TO-VESSEL SCANNING LIMITS NOZOD 25 VSLIR 127 WALL 6.69 CD WELD RAD 17.25 ODBR 4 0 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 1 70.0' T 12.00 000 0.00 0.8" 0.387 0.150 0 11.27 54 0.0" 0.0" 2 70.0" PI 12.00 3.00 0.00 0.8" 0.316 0.150 0 6.10 54 287.5" 72.5" (ccw) 3 70.0' P2 12.00 -3.00 0.00 0.8" 0.316 0.150 0 6.10 54 72.5" -72,5" (cw) 01f 1/17/2002 Page 1 3:10 PM
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET REPORT NO: 1R9-026 PROJECT LaSalle Unit 1 - L1RO9 WELD ID: LCS-1-N4C SYSTEM: RPV - FEEDWATER INITIAL CALIBRATION ID: NOZ.IN.1, 70RL.IN.1 CALIBRATION VERIFICATIONS: N48.2, N4C. 1, N4D. 70RL. 1, N4C. 70RL. I DATA SHEETS: n4c.tI. 1, n4c.pl. 1, n4c.p2.1, n4c.70rl. I FINAL CALIBRATION ID: SEE
SUMMARY
SECTION BELOW MANUAL CALIBRATION: N/A EXAMINERS: J. Kent Montgomery, Lv II, Mark Hilborn, Lv II SUlfiasonc examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, Category B-D welds and USNRC Reg Guide 1.150 Revision I (Alternative Method). Automated 0°, 2,25 L-Wave; 45° and 60* Shear 1.0 MHz and 700 RL 2.0 MHz Transverse and Parallel scans were performed in accordance with procedure GE-UT-702 Version 2. Initial calibrations for the 0°, 45° and 600 Shear automated examinations were performed on code vessel block - S/N - 01-91-03. Calibration for the 70' RL automated examinations were performed on GENE sizing block, S/N -CAL-DPTH-60 ( Refer to G2K-CAL-1 Initial Calibration Summary Sheet). For final automated calibrations and linearities, refer to Calibration Summary Sheet - G2K-CAL-3. The GERIS 2000 00 automated UT system 00 reference is located 900 CW of nozzle TDC. The GERIS 2000 OD system recorded the following non-relevant indications: 00 L-Wave - Entry Surface Noise, Geometry - Clad Noise 0' Base Metal - Entry Surface Noise 45° Transverse -Geometry - Clad Noise, Non-Relevant Reflector, Geometry - Nozzle bore 600 Transverse - Entry Surface Noise, Geometry - Clad Noise, Non-Relevant Reflector, Geometry - Nozzle Bore 450 Parallel - Geometry - Clad Noise 600 Parallel - Geometry - Clad Noise, Non-Relevant Reflector 700 Transverse - Entry Surface Noise 700 Parallel - Entry Surface Noise These non-relevant indications were flagged and excluded from the final report. The GERIS 2000 OD system recorded one (1) indication with the 450 Tranverse search unit over 20% DAC which was found to be acceptable. No other indications requiring evaluation according to ASME B&PV Code Section X1 or USNRC Reg Guide 1.150 Revision 1 (Alternative Method) were recorded. Due to nozzle configuration it is not feasible to examine 100% of the ASME Code required volume. Automated 00,45' and 600 UT Coverage = 72.3%. Credit for the 45'/60" near field taken with the 700. Automated 700 Near Surface UT Coverage = 44.7% Previous data was reviewed prior to the examination, changes are noted below. The GERIS 2000 Automated system records the complete RF data during scanning, it also utilizes search units with lower frequency elements and improved ultrasonic coupling. The GERIS 2000 Automated System has shown that with its improvements in examination techniques, indications have better reflectivity with a 1 MHz search unit over a 2.25 MHz., which could explain why this indication was not recorded during the prior manual inspection. l'... A4B DAE RMEVIE BY DATE 'fUffA DATE A 1I MEV IEW DATE LA SALLE SUMNV.DOC lR -i Page 111 PAfC
LaSalle Unit I N4C Jan-02 CODE CROSS-SECTIONAL AREA TOTAL CODE OQVERAGE Area Scanned % of Area Scanned Degrees Scanned % Scanned
.0 2
Area Inch Auto Manual Auto Manual Auto Manual Auto Manual 0° WELD METAL N 59.12 31.12 0.0 52.6 0,0 360.0 0.0 52.6 0.0 45° T-SCAN N 59.12 47.77 0.0 80.8 0.0 360.0 0.0 80.8 0.0 600 T-SCAN N 59.12 50.16 0.0 84.8 0.0 360.0 0.0 84.8 0.0 N 59.12 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 CD 450 P-SCAN CW N 59.12 37.90 0.0 64.1 0.0 360.0 0.0 64.1 0.0 600 P-SCAN CW N 59.12 47.16 0.0 79.8 0.0 360.0 0.0 79.8 0,0 450 P-SCAN CCW N 59.12 37.90 0.0 64.1 0.0 360.0 0.0 64.1 0.0 60° P-SCAN CCW N 59.12 47.15 0.0 79.8 0.0 360.0 0.0 79.8 0.0 1 72.3 0.0 Total 0°, 45° and 60° Coverage 72.3 700 T-SCAN N 21.13 11.75 0.0 55.6 0.0 360.0 0.0 55.6 0.0 70" P-SCAN CW N 21.13 8.28 0.0 39.2 0.0 360.0 0.0 39.2 0.0 70° P-SCAN CCW N 21.13 8.28 0.0 39.2 0.0 360.0 0.0 39.2 0.0 44[7 0.0 Total 70° Coverage = 44.7 COMMENTS: yAutomated UT scans were limited due to the nozzle radius. Credit for the initial 114" of material in code coverage taken with the 70° I ....... 102)29/01
Lasalle 1 FEE]DW~ATER Code Required Exam Volume - 1 59.12 Sq. In, 00 L-Wave Exam Volume - 31.12 Sq. In, 45° T-Scan Exam Volume - 47.77 Sq. In, 600 T-Scan Exam Volume 50,16 Sq, In, 0, (0 CD CA~
Lasotte 1 FLFEEDWATE -R Code Req uired Exam Volume - 5912 Sq, I n, 45* P-Sc an Exam Volume - 37,90 Sq. In. 60 P-Sc an Exam Volume 47,15 Sq. In, 600 °p 45 JJ
Laisa((e 1 FEEDWAbTER Code Required Exam Volume - 26.13 Sq. In. 70° T-Scan Exam Volume - 11.75 Sq. In. 700 P-Scan Exam Volume 8.25 Sq. In. 70P'ý 0 1700T
Noz.i -r(3) GOD-SL6C.)xs LaSaIle I 09118J00 N4 FEEDWA TER GERIS-2000 NOZZLE-TO-VESSEL SCANNING UMITS NOZOD 25 VSLIR 127 WALL 6.69 WELD RAD 17.25 ODBR 4 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 4 0.0' B 3.66 0.00 0.00 0.8" 0.501 0.150 0 19.74 91 47 79 56 1 0.0" W 3.66 0.00 0.00 0.8* 0.320 0.150 0 6.36 91 56 - 2 45.0' T 13.26 3.00 0.00 0.8" 0.418 0.150 0 13.61 235 - 7.2" -712 3 60.01 T 14.15 -3.00 0.00 0.8* 0.501 0.150 0 19.74 328 354.0' 6.0" 2 45.0' P1 13.26 3.00 0.00 0.8" 0.341 0.150 0 7.94 235 300.5' 59,5 (ccw) 3 60.0' P1 14.15 -3.00 0.00 0.81 0.383 0.150 0 10.97 328 295.6' 64.4' (ccw) 2 45.0 P2 13.26 3.00 0.00 0.8" 0.341 0.150 0 7.94 235 '78.1" -78.1* (cw) 3 60.0' P2 14.15 -3.00 0.00 0.8" 0.383 0.150 0 10.97 328 47.8 -47.86 (cw) 1/17/2002 Page 1 TnoDOi
Noz, 10 GOD-SL6C.xls LaSalle 1 09/18/00 N4 FEEDWA TER GERIS-2000 NOZZLE-TO-VESSEL SCANNING LIMITS NOZOD 25 VSLIR 127 WALL 6,69 WELD RAD 17.25 ODBR 4 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 1 70.0' T 12.00 0.00 0.00 0.8. 0.387 0.150 0 11.27 54 0.0' 0.0" 2 70.0' P1 12.00 3.00 0.00 0,8° 0.316 0.150 0 6.10 54 287.5' 72.5° (ccw) 3 70.0* P2 12.00 -3.00 0.00 0.8* 0.316 0.150 0 6.10 54 72.5" -72.5- (cw) __ -- I - 1/17/2002 Page 1
(GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET REPORT NO: 1R9-027 PROJECT LaSalle Unit 1 - L1RO9 WELD ID: LCS-1-N4D SYSTEM: RPV - FEEDWATER INITIAL CALIBRATION ID: NOZ.IN.1, 70RL.IN.1 CALIBRATION VERIFICATIONS: N4D.1, N4C.70RL.1 DATA SHEETS: n4d.tI.1, n4d.tI.2, n4d.pl.1, n4d p1.2, n4d.p2.1, n4d.70rl.1 FINAL CALIBRATION ID: SEE
SUMMARY
SECTION BELOW MANUAL CALIBRATION: N/A EXAMINERS: J. Kent Montgomery, Lv II, Mark Hilborn, Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section Xl, 1989 Edition no Addenda, Category B-D welds and USNRC Reg Guide 1.150 Revision 1 (Alternative Method). Automated 00, 2.25 L-Wave; 450 and 600 Shear 1.0 MHz and 700 RL 2.0 MHz Transverse and Parallel scans were performed in accordance with procedure GE-UT-702 Version 2. Initial calibrations for the 00, 45' and 600 Shear automated examinations were performed on code vessel block - S/N - 01-91-03. Calibration for the 700 RL automated examinations were performed on GENE sizing block, SIN -CAL-DPTH-60 ( Refer to G2K-CAL-1 Initial Calibration Summary Sheet). For final automated calibrations and linearities, refer to Calibration Summary Sheet - G2K-CAL-3. The GERIS 2000 OD automated UT system 0° reference is located 900 CW of nozzle TDC. The GERIS 2000 OD system recorded the following non-relevant indications: 0' L-Wave - Entry Surface Noise, Geometry - Clad Noise, Non-Relevant Reflector 450 Transverse - Geometry - Clad Noise, Non-Relevant Reflector, Geometry - Nozzle bore 600 Transverse - Geometry - Clad Noise, Non-Relevant Reflector, Geometry - Nozzle Bore 450 Parallel - Geometry - Clad Noise 600 Parallel - Entry Surface Noise, Geometry - Clad Noise 70° Transverse - Entry Surface Noise, Electrical Noise 70* Parallel - Entry Surface Noise, Electrical Noise These non-relevant indications were flagged and excluded from the final report. The GERIS 2000 OD system recorded three (3) indications with the 450 Tranverse search unit and one (1) indication with the 60* Transverse search unit that were over 20% DAC, all were found to be acceptable. No indications were recorded over 50% DAC. No other indications requiring evaluation according to ASME B&PV Code Section XI or USNRC Reg Guide 1.150 Revision 1 (Alternative Method) were recorded. Due to nozzle configuration it is not feasible to examine 100% of the ASME Code required volume. Automated 0',45* and 600 UT Coverage = 72.3% Automated 70* Near Surface UT Coverage = 44.7% Credit for the 45'/60' near field taken with the 700. Previous data was reviewed prior to the examination, changes are noted below. The GERIS 2000 Automated system records the complete RF data during scanning, it also utilizes search units with lower frequency elements and improved ultrasonic coupling. The GERIS 2000 Automated System has shown that with its improvements in examination techniques, indications have better reflectivity with a 1 MHz search unit over a 2.25 MHz., which could explain why this indication was not recorded during the prior manual inspection. REPARED BY DATE R D BY DATE Ut0i-lI"Y REVIE( DATE ANII REVIEW DATE SUMNV.DOC LA SALLE R 1'2 nAfr I .' Page 118
LaSalle Unit I N40 Jan402 I*. Uit La~ale CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Area Scanned % of Area Scanned Degrees Scanned % Scanned Area Inch 2 Auto Manual Auto Manual Auto Manual Auto Manual 0
° WELD METAL N 59.12 31.12 0.0 52.6 . 0.0 360.0 0.0 52.6 0.0 450 T-SCAN N 59.12 47.77 0.0 80.8 0.0 360.0 0.0 80.8 0.0 60° T-SCAN N 59.12 50.16 0.0 84.8 0.0 360.0 0.0 84.8 0.0 N 59.12 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 450 P-SCAN CW N 59.12 37.90 0.0 64.1 0.0 360.0 0.0 64.1 0.0 600 P-SCAN CW N 59.12 47.15 0.0 79.8 0.0 360.0 0.0 79.8 0.0 450 P-SCAN CCW N 59-12 37.90 0.0 64.1 0.0 360.0 0.0 64.1 0.0 60' P-SCAN CCW N 59.12 47.15 0.0 79.8 0.0 360.0 0.0 79.8 0.0 72.3 0.0 Total 0', 450 and 60* Coverage 72.3 700 T-SCAN N 21.13 11.75 0.0 55.6 0.0 360.0 0.0 55.6 0.0 700 P-SCAN CW N 21.13 8.28 0.0 39.2 0.0 360.0 0.0 39.2 0.0 700 P-SCAN CCW N 2113 8.28 0.0 39.2 0.0 360.0 0.0 39.2 0.0 44.7 0.0 Total 70' Coverage 44.7 .7) -?
COMMENTS: I I~ iAuwomaea u I scans were IlmIte due to the nozzle radius. ICredit for the initial 1/4" of material in code converaa taken with fht 7n° I.... . . . . . .. . .. . . . . . . .. .i a, . . . ... I02d29U10 .7)
~1 'JJ
LascLle I FEEDWATER Cocle Requiired ExamI Volum~e 59-18 Sq. In, K 0* L-Wave Exam Volume - 31,18 Sq. In. 45' T-Scan Exam Votume - 47.77 Sq, In. 60* T-Scan Exam Volume 50.16 Sq. In, .~J 0 I-N ~'~1
Lasacde 1 FEEDWATER Code Required Exam. Volume 59.12 <;q. In, 45° P-Scan Exam Volume - 37.90 Sq. In. 60* P-Scan Exam Volume 47,15 Sq, In, In
Lasace I FEEDWATER Code Required Exam Votume -26,13 Sq, In, 70° T-Scan Exam VoLume - 11,75 Sq, In, 70° P-Scan Exam Volume 8,25 Sq, In. "13 CD 707T -Q 701P70 mI C-L r-
Noz -R(3) GOD-SL6C.xls LaSalle I 09/18/00 N4 FEEDWA TER GERIS-2000 NOZZLE-TO-VESSEL SCANNING LIMITS NOZOD 25 VSLIR 127 WALL 6.69 WELD RAD 17.25 ODBR 4 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 4 0.0' B 3.66 0.00 0.00 0.8" 0.501 0.150 0 19.74 91 47 79 56 1 0.0" W 3.66 0M00 0.00 0.8* 0.320 0.150 0 6.36 91 - 56 - 2 45.0' T 13.26 3.00 0.00 0.8" 0.418 0.150 0 13.61 235 7.2 -7,27 3 60.0* T 14.15 -3.00 0.00 0.8" 0.501 0.150 0 19.74 328 354.0' 6.0" 2 45.0' P1 13126 3.00 0.00 0.8" 0.341 0.150 0 7.94 235 300.5" 59.5' (ccw) 3 60.0* P1 14.15 -3.00 0.00 0.8" 0.383 0.150 0 10.97 328 295.6" 64.4* (ccw) 2 45.0° P2 13.26 3.00 0.00 0.8* 0.341 0.150 0 7.94 235 78.1* -78.1- (cw) 3 60.0" P2 14.15 -3.00 0.00 0.8" 0.383 0.150 0 10.97 328 47.8 -47.8- (cw) A-------------------------------------------------------- 1/17/2002 Page 1
N,, /0 GOD-SL6C.xls LaSalle 1 09/18&00 N4 FEEDWA TER GERIS-2000 NOZZLE-TO-VESSEL SCANNING LIMITS NOZOD 25 VSLIR 127 WALL 6.69 WELD RAD 17.25 CD ODBR 4 N) TYPE F (F-FLANGE OR B-BARREL) K_2 3 CH 70.0 70_0 70.0" TYPE T P P2 Delay usec 12.00 12.00 12.00 X 0.00 3.00
-3.00 Y
0.00 0.00 0.00 INDEX INDEX DEG INCHES 0.8" 0.8 0.8" 0.387 0.316 0.316 STEP INCHES 0.150 0.150 0.150 RADIAL DISTANCE AGATE START 0 0 0 STOP STOP 11-27 6.10 6.10 54' 54 54 BE GATE START STOP C GATE STOP FIXTURE CPU ANGLE ANGLE 0.0. 287.5' 72.5' 00" 725
-72.5-(ccw)
(cw) 1/17/2002 Page 1 3:10 PM k*J
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET REPORT NO: 1R9-028 PROJECT LaSalle Unit I - L1RO9 WELD ID: LCS-1 -N4E SYSTEM: RPV - FEEDWATER INITIAL CALIBRATION ID: NOZ.IN1, 70RL.IN.1 CALIBRATION VERIFICATIONS: N4D.1, N4E.1, N4F.1, N4E.70RL.1, N4F.70RL.1 DATA SHEETS: n4e.tl 1, n4e.tI.2, n4etl.3, n4e.tl.4, n4e.pl.1, n4ep2.1, n4e.70r1.1 FINAL CALIBRATION ID: SEE
SUMMARY
SECTION BELOW MANUAL CALIBRATION: N/A EXAMINERS- J. Kent Montgomery, Lv II, Mark Hilborn, Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, Category B-D welds and USNRC Reg Guide 1.150 Revision I (Alternative Method). Automated 00, 2.25 L-Wave; 450 and 600 Shear 1.0 MHz and 70* RL 2.0 MHz Transverse and Parallel scans were performed in accordance with procedure GE-UT-702 Version 2. Initial calibrations for the 0', 450 and 600 Shear automated examinations were performed on code vessel block - S/N - 01-91-03. Calibration for the 700 RL automated examinations were performed on GENE sizing block, S/N -CAL-DPTH-60 ( Refer to G2K-CAL-1 Initial Calibration Summary Sheet). For final automated calibrations and linearities, refer to Calibration Summary Sheet - G2K-CAL-3. The GERIS 2000 OD automated UT system 00 reference is located 900 CW of nozzle TDC. The GERIS 2000 OD system recorded the following non-relevant indications: 00 Base Metal - Geometry - Clad Noise, Non-Relevant Reflector 450 Transverse - Geometry - Clad Noise, Non-Relevant Reflector 60° Transverse - Geometry - Clad Noise, Non-Relevant Reflector, Geometry - Nozzle Bore 450 Parallel - Geometry - Clad Noise, Entry Surface Noise 60° Parallel - Entry Surface Noise, Geometry - Clad Noise, Non-Relevant Reflector 70° Transverse - Entry Surface Noise, Non-Relevant Reflector 70° Parallel - Entry Surface Noise These non-relevant indications were flagged and excluded from the final report. The GERIS 2000 OD system recorded one (1) indication with the 450 Tranverse search unit over 20% DAC which was found to be acceptable. No other indications requiring evaluation according to ASME B&PV Code Section XI or USNRC Reg Guide 1.150 Revision 1 (Alternative Method) were recorded. Due to nozzle configuration it is not feasible to examine 100% of the ASME Code required volume. Automated 00,450 and 600 UT Coverage = 72.3%. Credit for the 450/600 near field taken with the 70*. Automated 70* Near Surface UT Coverage = 44.7% Previous data was reviewed prior to the examination, changes are noted below. The GERIS 2000 Automated system records the complete RF data during scanning, it also utilizes search units with lower frequency elements and improved ultrasonic coupling. The GERIS 2000 Automated System has shown that with its improvements in examination techniques, indications have better reflectivity with a 1 MHz search unit over a 2.25 MHz., which could explain why this indication was not recorded during the prior manual inspection. PREPARED BY DATE REVtWED BY DATE UTILITY A CA " ANII DATE LA SALLE SUMNV.00C R -1
....... * ~PAGE ' OF 3 2-rage -125
LaSalle Unit 1 N4E Jan-02 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE V Area Scanned % of Area Scanned Degrees Scanned % Scanned 2 Area Inch Auto Manual Auto Manual Auto Manual Auto Manual 0° WELD METAL N 59.12 31.12 0.0 52.6 0.0 360.0 0.0 52.6 0.0 45' T-SCAN N N 59.12 47.77 0.0 80.8 0.0 360.0 0.0 80.8 0.0 60° T-SCAN N 59.12 50.16 0.0 84.8 0.0 360.0 0.0 84.8 0.0 59.12 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 N CD 450 P-SCAN CW N 59.12 37.90 0.0 64.1 0.0 360.0 0.0 64.1 0.0 600 P-SCAN CW 59.12 47.15 0.0 79.8 0.0 360.0 0.0 79.8 0.0 45° P-SCAN CCW N N 59.12 37.90 0.0 64.1 0.0 360.0 0.0 64.1 0.0 600 P-SCAN CCW 59.12 47.15 0.0 79,8 0.0 360.0 0.0 79.8 0.0 1 72.3 0.0 Total 00, 45°and 60°Coverage = 72.3 70' T-SCAN N 70° P-SCAN CW N 700 P-SCAN CCW N Total 70* Coverage = 44.7 COMMENTS:
2 0 J* I A CD 1800
-000 Thermocouptes T-Scan00 S t art _ T4s lUb 800 Stop
Lascdle I FEEDWATER 60° T-Scan Exor i Volume 50,16 Sq. In. 60° T-Scmn Excr q Limited to 16,05' from 108° CCW to 80* due to thermocouples on vessel wcatt 600 T-Scan Exarn Volume wacs not limited 16.05' I
LasacWe 1 FEEDWATER Code Required Exam VoLume - 59.12 Sq, In. 0* L-Wave Exam Volume - 31.12 Sq, In. 450 T-Scan Exam Volume - 47,77 Sq, In, 600 T-Scan Exam Volume 50,16 Sq. In,
~, 1~.
CT' 4
LascW~e 1 FEEDWATER Code Requir -ed Exam Volume - 59,12 Sq, In, 45° P-Scan Exam Volume - 37.90 Sq, In, 60* P-Scan Exam Volume 47.15 Sq. In, 1°P r-fI 600
LQsoLUe 1 FEEDWATER Code Required Exam Volume - 26.13 Sq. In, 70° T-Scan Exam VoLume - 11.75 Sq, In, 70 P-Scan Exam VoLume 8,25 Sq, In, (0 CD 70°T I.,
Noz, _iR(3) GOD-SL6C.xls LaSalle I 09118/00 N4 FEEDWATER GERIS-2000 NOZZLE-TO-VESSEL SCANNING LIMITS
.NOZOD 25 VSLIR 127 WALL 6.69 WELD RAD 17.25 ODBR 4 TYPE F (F-FLANGE OR B-BARREL) a, (0 Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CD CH TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 4 0.0* B 3.66 0.00 0.00 0.8" 0.501 0.150 0 19.74 91 47 79 56 1 0.0" W 3.66 0.00 0.00 0.8" 0.320 0.150 0 6.36 91 - 56 -
2 45.0' T 13.26 3.00 0.00 0.8" 0.418 0.150 0 13.61 235 7.2" -7.27 3 60.0' T 14.15 -3.00 0.00 0.8" 0.501 0.150 0 19.74 328 354.0* 6.0* 2 45.0' P1 13.26 3.00 0.00 0.8" 0.341 0,150 0 7.94 235 300.5' 59.5 (ccw) 3 60.0" P1 14.15 -3.00 0.00 0.8' 0,383 0.150 0 10.97 328 295.6" 64.4" (ccw) 2 45.0' P2 13-26 3.00 0.00 0.8" 0.341 0.150 0 7.94 235 78.1' -78.1" (cw) 3 60.0' P2 14.15 -3.00 0.00 0.8' 0.383 0.150 0 10.97 328 47,8" -47.8 (cw) (-.
'- 2 1/17/2002 Page I 3:08 PM
No-, 1O GOD-SL6C.xls LaSalle 1 09/18/OO N4 FEEDWA TER GERIS-2000 NOZZLE-TO-VESSEL SCANNING uMITS NOZOD 25 VSLIR 127 WALL 6.69 WELD RAO 17.25 ODBR 4 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 1 70.0' T 12.00 0.00 0.00 0.8" 0.387 0.150 0 11.27 54 0'.0"-' 0.0" 2 70,0" P1 12.00 3.00 0.00 0.8' 0.316 0.150 0 6.10 54 287.5' 72.5' (ccw) 3 70.0' P2 12.00 -3.00 0.00 0.8" 0.316 0.150 0 6.10 54 72.5' -72.5° (cw) 1117/2002 Page I
GE NUCLEAR ENERGY UT EXAMINA TION
SUMMARY
SHEET REPORT NO: 1R9-029 PROJECT LaSalle Unit 1 - L1RO9 WELD ID: LCS-1-N4F SYSTEM: RPV - FEEDWATER INITIAL CALIBRATION ID: NOZ.IN.1, 70RL.IN.1 CALIBRATION VERIFICATIONS: N4F.1, N4A.1, N4F.70RL.1, N4A.70RL.1 DATA SHEETS: n4f.tl.2, n4f.pl.2, n4f.p2.1, n4f.70rd.1 FINAL CALIBRATION ID: SEE
SUMMARY
SECTION BELOW MANUAL CALIBRATION: N/A
.,E..EXAMINERS:... J. Kent Montgomery, Lv II, Mark Hilborn, Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, Category B-D welds and USNRC Reg Guide 1.150 Revision 1 (Alternative Method).
Automated 00, 2.25 L-Wave; 450 and 60° Shear 1.0 MHz and 700 RL 2.0 MHz Transverse and Parallel scans were performed in accordance with procedure GE-UT-702 Version 2. Initial calibrations for the 0°, 450 and 600 Shear automated examinations were performed on code vessel block - SIN - 01-91-03. Calibration for the 700 RL automated examinations were performed on GENE sizing block, S/N -CAL-DPTH-60 ( Refer to G2K-CAL-1 Initial Calibration Summary Sheet). For final automated calibrations and linearities, refer to Calibration Summary Sheet - G2K-CAL-3. The GERIS 2000 OD automated UT system 00 reference is located 900 CW of nozzle TDC. The GERIS 2000 OD system recorded the following non-relevant indications: 0° Weld Metal - Geometry - Clad Noise, Non-Relevant Reflector 450 Transverse - Geometry - Clad Noise, Non-Relevant Reflector 600 Transverse - Geometry - Clad Noise, Non-Relevant Reflector, Geometry - Nozzle Bore 450 Parallel - Geometry - Clad Noise 600 Parallel - Entry Surface Noise, Geometry - Clad Noise 70° Transverse - Entry Surface Noise, Non-Relevant Reflector 700 Parallel - Entry Surface Noise, Non-Relevant Reflector These non-relevant indications were flagged and excluded from the final report. The GERIS 2000 OD system recorded one (1) indication with the 700 Tranverse search unit over 20% DAC which was found to be acceptable. No other indications requiring evaluation according to ASME B&PV Code Section XI or USNRC Reg Guide 1.150 Revision I (Alternative Method) were recorded. Due to nozzle configuration it is not feasible to examine 100% of the ASME Code required volume. Automated 00,450 and 60° UT Coverage = 72.3%. Credit for the 450/600 near field taken with the 700. Automated 700 Near Surface UT Coverage = 44.7% Previous data was reviewed prior to the examination, changes are noted below. There was no previous 70' Near Surface data to review or compare. _REPARED BY DATE uTu UTILITY RL=YDATE REVIEW DATE SUMNV.DOC LA SALLE PAGE OF.. Page 134
LaSalle Unit I N4F Jan-02 CODE CROSS-SECTIONAL AREA TOTAL CODE GOVERAGE Area Scanned % of Area Scanned Degrees Scanned % Scanned 2 0 Area Inch Auto Manual Auto Manual Auto Manual Auto Manual 0 59.12 O WELD METAL N 31.12 0.0 52.6 0.0 360.0 0.0 52.6 0.0 45* T-SCAN N 59.12 47.77 0.0 80.8 0.0 360.0 0.0 80.8 0.0 60° T-SCAN N 59.12 50.16 0.0 84.8 0.0 360.0 0.0 84.8 0.0 "0 N 59.12 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 (0) 450 P-SCAN CW N 59.12 37.90 0.0 64.1 0.0 360.0 0.0 64-1 0.0 CD 60° P-SCAN CW N 59.12 47.15 0.0 79.8 0.0 360.0 0.0 79.8 0.0 450 P-SCAN CCW N 59.12 37.90 0.0 64.1 0.0 360.0 0.0 64.1 0.0 600 P-SCAN CCW N 59.12 47.15 0.0 79.8 0.0 360.0 0.0 79.8 0.0 72.3 J 0.0 Total 0, 45° and 60' Coverage = 72.3 700 T-SCAN N 21.13 70° P-SCAN CW N 21.13 700 P-SCAN CCW N 21.13 Total 70. Coverage = 44.7 COMMENTS: Automated Credit UTinitial for the scans1)4" were limited due of matnrial to theicnverana in codn nozzle radius. tnkan with tha 70l
~
Credit~~~~~~~~ ~ ~ ~~ ncdecvraatkeUih ~ foUh h iiil0 4 f aeia
.N
Lasalle 1 FEEDWATER Cocle Required Exam Volume 59,12 Sq, In, 0° L-Wave Exam Volume - 31,12 Sq. In. 45* T-Scan Exam Volume - 47.77 Sq, In, 60* T-Scan Exam Volume 50,16 Sq, In,
Lasatte1 I~ 2~ 6J3 Sq. FEEDp WAT LXQP-M Votue
~C 11.75 Sq. in~,
Votume 70- T-Scc 0 r ExamY In, 8.25 Sq.
~ VO(UME' 70 -gD 700 oll
}.
Noz._.,A(3) GOD-SL6C.xls LaSalle I 09/18/00 N4 FEEDWA TER GERIS-2000 NOZZLE-TO-VESSEL SCANNING UNITS NOZOD 25 VSLIR 127 WALL 6.69 WELD RAD 17.25 ODBR 4 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CD Co CH TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 00) 4 0,0' B 3.66 0.00 0.00 0.8" 0.501 0.150 0 19.74 91 47 79 56 1 0.0" W 3.66 0.00. 0.00 0.8' 0,320 0.150 0 6.36 91 - - 56 - 2 45.0' T 13.26 3.00 0.00 0.8' 0.418 0.150 0 13.61 235 - 7.2' -7.2' 3 60.0" T 14.15 -3.00 0.00 0.8' 0.501 0.150 0 19,74 328 354.0' 6.0" 2 45.0* P1 13.26 3.00 0.00 0.8" 0.341 0,150 0 7.94 235 300.5' 59.5" (ccw) 3 60.0' P1 14.15 -3.00 0.00 0.8' 0.383 0.150 0 10.97 328 295.6- 64.4- (ccv) 2 45.0' P2 13.26 3.00 0.00 0,8' 0.341 0.150 0 7.94 235 781. -78.1. (cw) 3 60.0' P2 14.15 -3.00 0.00 0.8 0.383 0,150 0 10.97 328 47,8 -47.8" (cw)
.1 -
I-1/17/2002 Page 1
Nol,/0 GOD-SL6C.xls LaSalie 1 09/18/00 N4 FEEDWA TER GERIS-2000 NOZZLE-TO-VESSEL SCANNING LIMITS NOZOD 25 VSLIR 127 WALL 5.69 CD WELD RAD 17.25 ODBR 4 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 1 70.0* T 12.00 0.00 0.00 0.8" 0.387 0.150 0 11.27 54 0.0* 0.01 2 70.0' P1 12,00 3.00 0.00 0.81 0.316 0.150 0 6.10 54 287.5" 72,5" (ccw) 3 70.0* P2 12.00 -3.00 0.00 0.8" 0.316 0.150 0 6.10 54 72,5' -72.5 (cw) I- - - - -I I 1V17/2002 Page I
Report No.: GE NUCLEAR ENERG Y EXAMINATION
SUMMARY
SHEET 1Ro-136 Site and Unit: LaSalle Component ID: IRH-HXlB-08A Outage: LIR09 I Lua System: BUR ASME Cat.: C-C ASME Item C3.10 Aug Requirements: N/A Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date I Personnel 0 / 12 0 N/A MT-001 N/A MT-EXLN-102 N/A I Judith Ousley II j 01/11/2002 Examination Results: During the magnetic particle examination of the above referenced weld, no indications were recorded. 76% of the code required surface area was examined. This examination meets the requirements of ASME Section XI, 1989 Edition, no Addenda. Exarrinationresults were comparedto data report D579 from 1989 outage with
- No Change These examinations were performed under Work Order: 99270178 . Change This Summary and the fogowing
. data sheets have been reviewed
.* and accepted
. ... by
. th folWowing
.. personnel: R68 RW Pý 6
~ - ,'?~- *~ /~ I /2 4Ž Dose: N/A mr.
Pre!aedB_ f.. Level: Date: Utity Reviewed By:
Title:
Datý: Reviewed By: Level: Date: ANII Reviewed By:
Title:
Date: Page I of _ Page 140
Weld No.: IRH-HXlB-O8A Configuration: I Lu, Drawing: GEL-1104 System: RHR Procedure No.: MT-EXLN-102 Version / Revision 0 DRR: N/A Material: Surface Condition: Item: Carbon Steel Ground Weld- Final Magnetizing Apparatus Black Light Mfg: ParkerResearch Yoke Calibration: AC- 10 lb. Lift Model Serial Number Model: ProbeB300 Blacklight NIA NIA Serial No. 8164 Yoke Spacing: 6" Light Meter N/A N/A Thermometer: 216052 Surface Temperature: 60_ IF Technique Examination Medium Blacklight Intensity Magnetization: AC Magnetic Particles: Dry N/A Blacklight Intensity: Technique: Continuous MaLnaflux 8A Red 93A045 Manufacturer: Particle Type: Batch No 11 0111 Level Date Level Date Page Z of Page 141
GE lnsogctlon Services Luas IRH-HXIB-AgA& IOA PSI.. Page 142
GE NUCLEAR ENERG Y SUT EXAMINA Tr ON
SUMMARY
SHEET -SummaryNo: P 1!U~ PROJECT 1,1Saa~e Unit 1 LF WELD 10: SYSTEM: {CALIBRATION 10: NLA Manual DATA: UT-02t022,023, and 024 OPERATORS: 5 F,,c ksvr Lv 1,T iu~ Ultrasonic oixamnavion ro-ulls weýre aecevfa~bie ?n t'he requirerren~s ot ASP/ B&PV ~iISecltn X1, 198J9 Edtkton rto
.Icrenila also Sec~txn xl. tii5 Editoonowtti 'he 131'6 Arddar'da as alodtifed by the P'L) p~r:aqm descr'pf~on and !ho F.cdefal Registfer. Flail INuýJcsi Regulat.ony ;',X-rrsT7.ssinn. 10 CFR Part XC10'Ga*+/-i B-A ý4"tJfct Prft-Sssjte Vessel ,lRPV)
Assemibly Adelcs. Manus( frwsvlerse anod parallel scans wve'e lerformed frcm' the vassMl 00 6urffdCe ,1 3ICCOrdanoe. with procedute GE-UT- 300 V101 using 500 RL search units. Manual, parallel scanrnang was restricted due ro the F:arge rc weld eontfgLr,3t,0f1 The manuai exams recorded no indicalions Previous dot& was rveyvieed with no significant charnges. Manual UT 'emr-os'lav cwerage Magnetic ParliCle axammnalion was perform~ed in acccrdamca with pinc-edLre GE-M.T- 100 V6, data 4,)eets - MT. OCA8and MT.COr Itrtee .vere no recordat~le ndiratio-is ID0% :)f the fiýquired atla was exammnc .
'/7 ~j Ci. .7 1~
y~ ~/..- 2 tzrV ~ e1 ezoZ Lý-Ik R4 R 1Y -,1Ai~ 411ýiEWED By CA TIE TILITY RE.vtEW SAE- AN11~ PEVIEW IA!*E 1" 'In: 3, I .RiQY Pag Page 143
(p 0~ LaSalle Unit-1 GEL- 1009-AG Spring 2006 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length a 791. Required Exam Area Scanned of Area Weld Length PFroent Exam Volume a 22.2 Area !3. In. Manual Manual Manual Manual 60' NS T-Scar, A ' 7 9 . .... 35.9 __6%/. 395,5_.__-__ 60$...6.T-Scan A 11 i1 49,5% 395 12 4k 60" 54 T-Scan A 33 3 14 9% 3955 60' NS P-Scan. A 7.9 74 333% 395.5 d___3%__ CD 395 5 11.7 1° 60' S5 P-S*cir A 11 104 '468% 60' S4 P-Sca' A 3 3 31 14 0% 3965 _ -55 650 NS T-SScan _.... '__ 60" $S T-Scan
*50 .34_T.Scan .... ... _ ...
60' NS P-Sca _'_. 60' S6 P-Scar ... ........ . . 60'"S4 P-Scan - I i _ _ _ _ _ _ _
% Total Composate CoWerage ' 49" 0
Uhfl id'~Iw ,ni, , .N - t wii. re 8- P.Scan res-trmcd ake to wela to flange configuration hN,-te - R'-Ln{*ding m-ýelvs rMai affect calculatee vaiies.
LaSalle Unit 1
,b Flange to Top Head C*
S60" NS Exam Volume = 7.9 Sq. in. 60 F'V S6 Exam Volume = 11.0 Sq. In. 0 60" P S4 Exam Volume = 3.3 Sq. In. 00-60" NS T-Scan achieved = 7.9 Sq. In. 60* Fd S6 T-Scan achieved = 11.0 Sq. In. 60" FV S4 T-Scan achieved = 3.3 Sq. In. (0 CD __ 60" NS P-Scan achieved = 7.4 Sq. In. 60" Pd S6 P-Scan achieved = 10.4 Sq. In. 60" FP S4 P-Scan achieved = 3.1 Sq. In. 11.6"- 4.1 60"T 601T6 3.A t<. 2- --
GE NuclearEnergy MAGNETIC PARTICLE EXAMINATION REPORT Site: LaSalle Station Unit: I Project: LIf Report Number: IRI1-025 Sheet No.: MT-006 Weld No.: GEL-1009-AG Configuration:. Top Head- Flange Drawing: GEL-1O09 System: RPV Procedure No.: GE-NT-100 Version / Revision: V6 DRR: N/A Material: Surface Condition: Item: Carbon Steel Cleaned Weld - Final Magnetizing Apparatus Black Light Mfg: ParkerResearch Yoke Calibration: 215M0 Model Serial Number Model: B-300 Blacklight: N/A N/A Serial No. 5522 Yoke Spacing: 3"4" Light Meter: N/A N/A Thermometer 246434 Surface Temperature: 870 F Technique Examination Medium Blacklight Intensity Magnetizaton: AC Magnetic Particles: t. N/A Technique: Continuous ParkerResearch RP-6 11793 Blacbeit ensdr Manufacturer. Patlicle Type: Batch No.: Indicakion Numbe r~ Ies 0,lptin -Rsls Comments: Inspected from 180" to 270° Azimuth. No recordable indications. Clay Sut / 52002 Utility Review Date lnGtEeainer Level Date A GE Review - Level Date iANII Review Date Page 6 Of Page 146
l eGE Nuclear Energy MAGNETIC PARTICLE EXAMINATION REPORT A Site: LaSalle Station Unit: I Project: LIRII Report Number: IRl1-025 Sheet No.: MT-007 Weld No.: GEL-1009-AG Configuration: Tog Head- Flanoe Drawing: GEL-1009 System: RPV Procedure No.: GE-MT-100 Version 1Revision: V6 DRR: N/A Material: Surface Condition: Item: Carbon Steel Cleaned Weld - Final Magnetizing Apparatus Black Light Mfg: Par*erResearch Yoke Calibration: 2115/06 Model Serial Number Model: B-300 Blacklight: NIA N/A Serial No. 8104 Yoke Spacing: 3-f- Light Meter: N/A N/A Thermometer: 246434 Surface Temperature: 87' F Technique Examination Medium Blacklight Intensity Magnetization: AC Magnetic Particles: Dry N/A Technique: Continuous ParkerResearch RP-6 11793 SlackIigt hins4. Manufacturer Paflioje Type: Btch No.: Comments: Inspected from 270' to 360° Azimuth. No rewonable indications. Ala . .K . . . 2.
- Utility Review Date Initial ner Level Date GE Review Level Date ANII Review Date Page of Page 147
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 1R 11-007 PROJECT LaSalle Unit 1, L1R11 WELD ID: GEL-1006-AJ - Bottom Hd. Circumferential Weld SYSTEM: RPV CALIBRATION ID: N/A MANUAL DATA: UT-061, 062, 063, 064 OPERATORS: W. Reid Lv II, S. Snyder Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, and Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II,Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Pressure Vessel (RPV) Assembly Welds. Manual transverse and parallel scans were performed from the vessel OD surface in accordance with procedure GE-UT-300 V10; using 600 RL search units. Manual scanning was performed from the top side only, 1-scans and P-scans were restricted due to the RPV vessel skirt. The manual exams recorded no indications. Previous data was reviewed with no significant changes. Manual UT composite coverage = 19 %
/ 1__
REPARED BY DATE REVIEWED BY DATE UTILITY REVIEW' DATE ANII REVIEW DATE T Level: UT Level: LaSalle Unit-l, L1R11, 2006 Page 1 of Page 148
,,'-* ,Ivi/ p Report No. I R11 -9071ý U)
LaSalle Unit-1 oc0 ' GEL-1006-AJ Bott. Hd. Circ. Weld Spring 2006 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE N. Percent Weld Length = 657.3 Required Exam Area Scanned of Area Weld Length Percent T Exam Volume = 36.5 Area Sq. In. Manual Manual Manual Manual 600 NS T-Scan A 11.3 2.3 6,3% 328.6 1,6% 600 S6 T-Scan A 19.9 13.3 36.4% 328.6 9.1% 600 S4 T-Scan A 5.3 5.2 14.2% 328.6 3.6% 600 NS P-Scan A 11.3 1.6 4.4% 328.6 11% 60' S6 P-Scan A 19.9 4.1 11.2% 328.6 2.8% CD 60° S4 P-Scan A 5.3 1.1 3.0% 328.6 0.8% 60' NS T-Scan _ 600 S6 T-Scan 60' S4 T-Scan 60° NS P-Scan 600 S6 P-Scan 60' S4 P-Scan
~I I
% Total Composite Coverage = 19%
Comments.- A - Examined accessible weld length ftrom 180' cw to 360" top side only, T-scans and P-scans were limited due to the RPV vessel skirt. Note - Rounding methods may affect calculated values.
C-60 NS Exam Volume =11.3 Sq. In. LaSalle Unit 1 60' FV S6 Exam Volume = 19.9 Sq. In. Co 60' FV S4 Exam Volume = 5.3 Sq. In. Bottom Head (AJ) 600 NS T-Scan achieved = 2.3 Sq. In. Circ. Weld 60° FV S6 T-Scan achieved = 13.3 Sq. In. C3 60' FV S4 T-Scan achieved = 5.2 Sq. In.
"- 60' NS P-Scan achieved = 1.6 Sq. In.
600 FV S6 P-Scan achieved = 4.1 Sq. In. 600 FV S4 P-Scan achieved = 1.1 Sq. In. C,' 60 0 T 1-.- 9.8"-
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET REPORT NO: 1RI1-003 PROJECT LaSalle Unit 1 - LIR1I WELD ID: LCS BG SYSTEM: RPV INITIAL CALIBRATION ID: VES.91.IN.1 (L1 R09) FINAL CALIBRATION ID: VES.91.OUT.1 (L1RO9) GERIS DATA: (See weld LCS-1-BG reports from L1RO9) MANUAL CALIBRATION: NIA MANUAL DATA: N/A Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, Category B-A Reactor Pressure Vessel (RPV) Assembly Welds. Automated 0', 2.25 MHz Weld and Base Metal, 45°S, 1.0 MHz, 601, 2.0 MHz and 70°RL, 2.0 MHz Transverse and Parallel scans were performed per the requirements of procedure GE-UT-704 V4, in accordance with Appendix VIII. Automated scanning was restricted on both sides of "BG" due to Instrumentation Nozzle N12-A. These examinations were performed during the L1R09 outage in 2002 which did not permit single side coverage. Reevaluation of this recorded data was performed in accordance with procedure GE-UT-704 V8 which is qualified for single sided access. The coverage was recalculated and resulted in an increase in coverage of 9.2%, taking the coverage from 66.1% to 75.3% Automated UT Composite Coverage = 75.3% GERIS 2000 Software Revision 5.26 was used for aquisition and analysis. 11 I II LaSalle Unit 1, LIR11, 2006 Page I of 2 Page 151
Summary No.: lR11-003 LaSalle Unit-1 LCS-1 -BG VX Spring 2006 CODE CROSS-SECTIONAL AREA LENGTH CALCULATIONS Percent Weld Length = 109.38 Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 52.69 Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 8.38 8.38 15.9% 83.88 6.1% 45° T-Scan A 36.25 36.25 68.8% 83.88 26.4% 60 T-Scan A 8.06 8.06 15.3% 64.63 4.5% 70' P-Scan A 8.38 8.38 15.9% 83.88 6.1% 450 P-Scan A 36.25 36.25 68.8% 83.88 26.4% 600 P-Scan A 8.06 8.06 15.3% 1 64.63 4.5% 70' T-Scan 45' T-Scan 60' T-Scan B 8.06 4.03 7.6% 19.25 0.7% 70' P-Scan 450 P-Scan 60' P-Scan B 8.06 4.03 7.6% 19.25 0.7% 70* T-Scan 450 T-Scan 60° T-Scan 70' P-Scan 450 P-Scan 600 P-Scan
% T otal Composite Coverage = 75.3%
I Comments: A - Examined accessible length. Weld length reduced by 3.0" due to the N12-A instrumentation nozzle. B - Automated exam restricted due to the proximity of the N12-A nozzle pad. Note - Rounding methods may affect calculated values.
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET REPORT NO: 1R9-010 PROJECT LaSalle Unit 1 - L1RO9 WELD ID: LCS BG SYSTEM: RPV INITIAL CALIBRATION ID: VES.91.N.i CALIBRATION VERIFICATIONS: BM. 1 FINAL CALIBRATION ID: VES.91.OUT.1 GERIS DATA: bgr.1, bgr.2, bgl.1, bgl.6, bgl.7, bgl.8 MANUAL CALIBRATION: N/A MANUAL DATA: N/A Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, Category B-A Reactor Pressure Vessel (RPV) Assembly Welds. Automated 0°, 2.25 MHz Weld and Base Metal, 450S, 1.0 MHz, 600L, 2.0 MHz and 70°RL, 2.0 MHz Transverse and Parallel scans were performed per the requirements of procedure GE-UT-704 V4, in accordance with Appendix VIII. The GERIS 2000 OD system recorded the following indications: 0° Weld Metal - No Recordable Indications 45' Transverse - No Recordable Indications 60° Transverse - No Recordable Indications 70o Transverse - No Recordable Indications 450 Parallel - No Recordable Indications 60° Parallel - No Recordable Indications 700 Parallel - No Recordable Indications Plate segregates on both sides of weld 'BG" were observed. Automated scanning was restricted on both sides of "BG' due to Instrumentation Nozzle N1 2-A. Previous examination results were reviewed and there are no changes. Automated UT Composite Coverage = 66.1% GERIS 2000 Software Revision 5.26 was used for aquisition and analysis. ( REPARED BY REVI"ED BY UTILITY REVIEW ANII REVIEW SATE.'DATE . DATE DATE SUMNV.OC LA SALLE 1R(' Page 153
I :
.; ?.
Y= 459.50 454.63// BG Area Scanned CD C.,, Area not scanned on LeFt side N6-A 40.5' Y= 390.00 N12-A X4 /I) Y= 349.50 3482,5" Y= 332.25
Y= 464.00 454,63" BG Ar-ea Scanned CD C., N6MA Y= 378.00 Area not scanned on right side 47.75' 3 4 225"
LaSalle Unit-1 Weld BG Jan-02 CODE CROSS-SECTIONAL AREA I TOTAL CODE COVERAGE Weld Length e Area Scanned I % of Area Scanned I Wel Length Scanned I % Scanned 8 1 Area Inch Auto Manual Auto Manual Auto Manual Auto Manual RIGHT SIDE 70" T-SCAN N/A 8.38 0.00 000 0.0 0.0 0.0 0.0 0.0 0.0 RIGHT SIDE 405 T-SCAN N/A 36325 0.00 000 0.0 0.0 0.0 0.0 0.0 0.0 RIGTTSIDE60T-SCAN WA 8.06 0.00 000 0.0 0.0 0.0 00 0.0 0.0 70' P-SCAN UP NIA 8.38 0.00 000 0.0 0.0 0.0 00 0.0 0.0 450 P-SCAN UP N/A 36.25 000 0,00 00 0.0 0.0 00 0.0 0.0 60 P-SCAN UP NWA 8.06 0,00 0.00 0.0 0.0 0.0 0.0 0.0 0.0 Unrestricted Scant LEFT SIDE 70" T-SCAN N/A 838 838 0.00 100.0 0.0 0.0 00 0.0 0.0 LEFT SIDE 45" T-SCAN N/A 36.25 36.25 0.00 100.0 0.0 0.0 00 0.0 0.0 LEFT SIDE 60 T-SCAN N/A 8.08 8.06 0.00 100.0 0.0 0.0 00 0.0 0.0 70" P-SCAN DOWN N/A 8.38 8.38 0.00 100.0 0.0 0.0 0.0 0,0 0.0 45" P-SCAN DOWN WA 36.25 36.25 0.00 100.0 0,0 0.0 0.0 0.0 0.0 80WP-SCAN DOWN N/A 806 8.06 0.00 100.0 0.0 0.0 00 00. 0.0 Restr*cted Scans RIGHT SIDE 70* T-SCAN Y 8.38 8.38 0.00 100.0 00 7663 0.0 108 0.0 RIGHT SIDE 45"T-SCAN Y 3625 36.25 0.00 100.0 0.0 76.63 00 46.9 0.0 RIGHTSIDE 60 T-SCAN Y 8.06 8,06 0.00 100.0 0.0 76.63 0.0 10.4 0.0 70r P-SCAN UP Y 8.38 8.38 0.00 100.0 0.0 76.63 0.0 10.8 0.0 45 P-SCAN UP Y 36.25 36.25 0.00 100.0 0.0 76.63 0.0 46.9 0.0 60 P-SCAN UP Y 8.06 8.06 0.00 1000 0.0 7663 00 10.4 0.0 Restricted Scans LEFT SIDE 70" T-SCAN Y 8.38 8.38 0.00 100.0 00 71.88 00 102 0.0 LEFT SIDE 45* T-SCAN Y 36.25 36.25 0.00 100.0 0.0 71.88 0.0 44.0 0,0 LEFT SIDE 601 T-SCAN Y 8.06 8.06 0,00 100.0 00 71.88 0.0 9.8 0.0 70 P-SCAN DOWN Y 8.38 8.38 0.00 100.0 0.0 7188 0.0 10.2 0.0 45" P-SCAN. DOWN Y 36.25 36.25 0.00 100.0 0.0 71.88 0.0 44.0 0.0 60" P-SCAN DOWN Y 808 8,06 0.00 100.0 0.0 71.88 00 9.8 0.0 Coverage 66.1 0.0 Total Composite Coverage= 66.1 Comments: Aulomated Scanning was restricted on both sdes due to Instrumentalion Nozzle N12-A 1I!~t1f~9 CovCak As 1122,12002 b LA SALLE 1R.(,q Page 156
LaSalle 1 Shell Course 3 Required 450 Exam Volume - 36.25 Sq In. Required 600 Exam Volume - 8.06 Sq In. Required 700 Exam Volume - 8.38 Sq In. CRight and Left Sides -4 m
*7
LaSalle 1 Shell Course 3 (Required Required 60° P-Scan CD Exam Volume - 8.06 Sq In. 450 P-Scan Exam Volume - 36.25 Sq In. i450 and 600 P-Scan
LaSalle I Shell Course 3 Required 700 P-Scan Exam Volume - 8.38 Sq In. CD
;10 "I- "" T h' I~71r
VesUI pk) LaSalle I GOD-SL6C.xls VESSEL SCANNING LIMITS 09118100 PDI SHELL COURSE: 3 i <-Normal Package Position (1 or 0) PULSER OFFSET 0 counts VSLIR 127 COUNTS/INCH 1 WALL 6.75 BE-gate C-gate CH Beam TYPE ROT DELAY X Y START STOP A-GATE START STOP STOP 6 0O 0 B 3.66 0.00 0.00 -19.09 5.58 76 47 91 - 1 0° 0 W 3.66 0.00 0.00 -5.58 5.58 76 - - 64 2 45' 90 T 13.26 1.72 3.14 -14.61 3.86 237 3 60' 90 T 14.15 -0.83 3.14 -18.26 6.41 188 4 45* 180 P 13.26 3.27 0:00 -8.85 2.31 237 5 60° 180 P 14.15 3.27 6.12 -8.85 2.31 188 7 70' 90 T 12.00 0.00 6.12 -10.52 5.58 54 8 70° 180 P 12.00 4.27 3.14 -9.85 1.31 54 ) - 1/25/2002 Page 1 11), 4A.,A^
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET REPORT NO: 1R11-004 PROJECT LaSalle Unit 1 - L1 R11 WELD ID: LCS BH SYSTEM: RPV INITIAL CALIBRATION ID: VES.91'IN 1 (L1RO9) FINAL CALIBRATION ID: VES.91.OUT.1 (L1RO9) GERIS DATA: (See weld LCS-1-BG reports from L1RO9) MANUAL CALIBRATION: N/A MANUAL DATA: N/A Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section Xl, 1989 Edition No Addenda, Category B-A Reactor Pressure Vessel (RPV) Assembly Welds. Automated 00, 2.25 MHz Weld and Base Metal, 45°S, 1.0 MHz, 60"L, 2.0 MHz and 70'RL, 2.0 MHz Transverse and Parallel scans were performed per the requirements of procedure GE-UT-704 V4, in accordance with Appendix VIII. Automated scanning was restricted on both sides of "BH" due to Instrumentation Nozzle N6-A. These examinations were performed during the LiR09 outage in 2002 which did not permit single side coverage. Reevaluation of this recorded data was performed in accordance with procedure GE-UT-704 V8 which is qualified for single sided access. The coverage was recalculated and resulted in an increase in coverage of 6.6%, taking the coverage from 82.2% to 88.8% Automated UT Composite Coverage = 88.8% GERIS 2000Software Revision 5.26 was used for aquisition and analysis. PREPARED BY REVIEWED BY UTILITYIREfVIEW ANII REVIEW VATE Z--4*-, DATE 3/s7'l,& DATE DATE LaSalle Unit 1, LIR11, 2006 Page I of 2 Page 161
Summary No.: `1Rl-004 LaSalle Unit-1 LCS-1-BH Spring 2006
'4 CODE CROSS-SECTIONAL AREA LENGTH CALCULATIONS Percent N Weld Length = 87.5 Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 52.69 Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 8.38 8.38 15.9% 79.38 7.2%
I' 450 T-Scan A 36.25 36.25 68.8% 79.38 31.2% 60' T-Scan A 8.06 8.06 15.3% 57.65 5.0% 700 P-Scan A 8.38 8.38 15.9% 79.38 7.2% 450 P-Scan A 36.25 36.25 68.8% 79.38 31.2% 60' P-Scan A 8.06 8.06 15.3% 57.65 5.0% 70' T-Scan 45* T-Scan 600 T-Scan B 8.06 4.03 7.6% 21.73 0.9% 70' P-Scan 450 P-Scan 600 P-Scan B 8.06 4.03 7.6% 21.73 0.9% 70' T-Scan 450 T-Scan 60' T-Scan 70* P-Scan 450 P-Scan 60' P-Scan
% Total Composite Coverage = 88.8%
r" Comments: A - Examined accessible length. Weld length reduced by 25.23" due to N6-A nozzle cutout B - Automated exam restricted due to the proximity of the N6-A nozzle Note - Rounding methods may affect calculated values.
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET REPORT NO: 1R9-011 PROJECT LaSalle Unit 1 - L1RO9 WELD ID: LCS BH SYSTEM: RPV INITIAL CALIBRATION ID: VES.91.IN. 1 CALIBRATION VERIFICATIONS: BM. 1 FINAL CALIBRATION ID: VES.91 .OUT. 1 GERIS DATA: bhr.3, bhr.4, bhr.5, bhr.6, bhr.7, bhl.1, bhl.2, bhl.3, bhl.4 MANUAL CALIlOTtON: N/A MANUAL DATA: N/A Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, Category B-A Reactor Pressure Vessel (RPV) Assembly Welds. Automated 00, 2.25 MHz Weld and Base Metal, 450S, 1.0 MHz, 600 L, 2.0 MHz and 70°RL, 2.0 MHz Transverse and Parallel scans were performed per the requirements of procedure GE-UT-704 V4, in accordance with Appendix VIII. The GERIS 2000 OD system recorded the following indications: 0' Weld Metal - No Recordable Indications 45° Transverse No Recordable Indications 600 Transverse - No Recordable Indications 700 Transverse - (2) Indications Recorded - See Indication Data sheet - BH-001, BH-002 450 Parallel - No Recordable Indications 600 Parallel - No Recordable Indications 70' Parallel - No Recordable Indications The two (2) indications recorded above were evaluated and found to be acceptable per the requirements of IWB-3000. Plate segregates on both sides of weld "BH" were observed. Automated scanning was restricted on the both sides of weld "BH" due to Nozzle N6-B. Automated scanning was also limited at the top of weld "BH" due to the proximity of the thermocouple pads. Previous examination results were reviewed and changes are noted. (see below) The previous examination was performed with an earlier automated GERIS System which did not record the the RF data and only recorded reflectors over 20%. The present GERIS 2000 Automated system records the complete RF data during scanning, it also utilizes new search units with lower frequency elements and improved ultrasonic coupling. This examination is also in accordance with ASME Section XI Appendix VIII which is considered more critical of the examination volume, thus, more indications were recorded during this examination than the previous one. This change in results is not considered to be indicative of changes in the condition of the weld or associated base material. Automated UT Composite Coverage = 82.2% GERIS 2000 Software Revision 5.26 was used for aquisition and analysis. P EPARED BY YEVIW ANII REVIEW ATE DATE DATE /, DATE
, M.D .- "- ,C ____tE.____ - __/_.-__-
SUMNV.DOC " t -1# " 1 Page 163
T/C PADS BH N1O "0 Area Scanned CD Y= 398.00 Area due to N6-B Nozzle N6-B N12-B m
*4 Y= 464.75 -
00 T/C PADS AD BH N1O Area o) Y= 390.00 Area restrictedc due to N6-B Nozzle N6-IB N12-B Y= 349,50 Area~ Scarnned Y= 332-25
LaSalle Unit-1 Weld BH Jan-02 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length Area Scanned % of Area Scanned Weld Length Scanned %Scanned
.- I Area IrsXtW Auto Manuel Auto Manual Auto Manual Auto Manual Unpreatifated ge RIGHT SIDE 70° T-SCAN N 8.38 0.00 000 0,0 0.0 0.0 0.0 0.0 0.0 RIGHT SIDE 45'T-SCAN N 36.25 0.00 0.00 0.0 0.0 0.0 00 0.0 0.0 RIGHT SIDE 60° T-SCAN N 8.08 000 000 00 0.0 0.0 0.0 0.0 0,0 70* P-SCAN UP N 8.38 000 0.00 0.0 0.0 0,0 0.0 0.0 0.0 45" P-SCAN UP N 36.25 0.00 000 00 0.0 0.0 00 U 0.0 0.0 60' P-SCAN UP N 8.06 0,00 0.00 0,0 0.0 0.0 1 00 00 0.0 Unrestricted Scans LEFT SIDE 7T T-SCAN N 8.38 0.00 0.00 0,0 0.0 0,0 00 0.0 0.0 LEFT SIDE 45" T-SCAN N 36.25 0.00 0,00 00 00 0.0 00 0.0 0.0 LEFT SIDE 60T-SCAN N 8.06 0.00 0.00 0.0 00 0.0 00 0,0 0.0 70" P-SCAN DOWN N 8.38 0.00 0.00 0.0 0.0 0.0 0.0 0.0 00 45"P-SCAN DOWN N 36.25 0.00 000 00 0.0 0.0 00 0.0 0.0 6W P-SCAN DOWN N 8.06 0.00 0.00 0.0 00 0.0 030 0,0 0.0 Resticted S*ans RIGHT SIDE 70"T-SCAN Y 8,38 8.38 0-00 100.0 0,0 71.38 00 13.0 0.0 RIGHT SIDE 45° T-SCAN Y 36.25 36.25 0.00 100.0 0.0 71.38 0.0 56.3 0.0 RIGHT SIDE W T-SCAN Y 8.06 806 0.00 100.0 0.0 71.38 0.0 12.5 0.0 70' P-SCAN UP Y 8.38 838 000 100,0 0.0 7138 0.0 13.0 0.0 45* P-SCAN UP Y 36,25 36.25 0.00 1000 0,0 71.38 0.0 56.3 0.0 60" P-SCAN UP Y 8.06 8.06 0,00 100.0 0.0 71 38 00 125 00 Rest*tcted Scans
( LEFT SIDE 70° T-SCAN LEFT SIDE 45T-SCAN Y Y 838 36.25 8.38 M8.25 0.00 0.00 100.0 100.0 0.0 0(0 71.88 71,88 0.0 0.0 13.1 56.7 0.0 0.0 LEFT SIDE 60 T-SCAN Y 8,06 8.06 0.00 100.0 0.0 71.88 0.0 12.6 0.0 70 P-SCAN DOWN Y 8.38 8.38 0.00 100.0 0.0 71,88 0.0 13.1 0.0 45* P-SCAN DOWN Y 36.25 38.25 0.00 100.0 0.0 71.88 0.0 56.7 0.0 60° P-SCAN DOWN Y 8086 8.06 0.00 100.0 0.0 71.88 0.0 12.8 0.0 Coverage4 82.2 0.0 Total Composite Coverage 82.2 Comments: Weld length reduced 25.23" due to NB-B Nozzle cut-Out Automated scanning was restricted on both sides of "'H" due to N6-8 Nozzle. CovCalcxts V2212002 LA SALLE IR - Page 166
LaSalle 1 Shell Course 3 Required 450 Exam Volume - 36.25 Sq In. Required 600 Exam Volume - 8.06 Sq In. Required 700 Exam Volume- 8.38 Sq In. Right and Left Sides
;*0- 45 700 I
.. .f . ..
I 0 I1I Tra..)- tYze J
LaSalle 1 Shell Course 3 Required 600 P-Scan Exam Volume - 8.06 Sq In. Required 450 P-Scan Exam Volume - 36.25 Sq In. T1'450 and 600 P-Scan rM 11')
- SW*
T(ddl)* 7J7/* j
LaSalle 1 Shell Course 3 Required 70' P-Scan Exam Volume - 8.38 Sq In. TOW-)- F,-T Adwl- . IWE J
Vest/pk) LaSalle 1 GOD-SL6C.xls VESSEL SCANNING LIMITS 09118/00 PDI SHELL COURSE: 3 1 <-Normal Package Position (1 or 0) PULSER OFFSET 0 counts VSLIR 127 COUNTS/INCH 1 WALL 6.75 BE-gate C-gate CH Beam TYPE ROT DELAY X Y START STOP A-GATE START STOP STOP 6 00 0 8 3.66 0.00 0.00 -19.09 5.58 76 47 91 - 1 0° 0 W 3.66 0.00 0.00 -5.58 5.58 76 64 2 45' 90 T 13.26 1.72 3.14 -14.61 3.86 237 3 600 90 T 14.15 -0.83 3.14 -18.26 6.41 188 4 45° 180 P 13.26 3.27 0.00 -8.85 2.31 237 5 60' 180 P 14.15 3.27 6,12 -8.85 2.31 188 7 70° 90 T 12.00 0.00 6.12 -10,52 5.58 54 8 700 180 P 12.00 4.27 3.14 -9.85 1.31 54 I-I- V 1/25/2002 Page I
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 1R 11-021 PROJECT LaSalle Unit 1, L1RII WELD ID: GEL-1009-DR Top Hd Meridional SYSTEM: RPV CALIBRATION ID: N/A MANUAL DATA: UT-036 and 37 OPERATORS: W. Reid Lv II, Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, and Section X1, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part I, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Pressure Vessel (RPV) Assembly Welds. Manual transverse and parallel scans were performed from the vessel OD surface in accordance with procedure GE-UT-300 VI1; using 600 RL search units. Manual scanning was restricted due to the top head lifting lug and top hd. flange. The manual exams recorded no indications. Previous data was reviewed with no significant changes. Manual UT composite coverage = 68 % ( ~REPARED BY DATE REVIEWED BY UT Level: DATE " 'UTILITY REVIEW DATE ANII REVIEW DATE LaSalle Unit-i, L1R11, 2006 Page1 of , Page 171
C-/ Report No. 1R11-021 C, LaSalle Unit-1 "w GE-1009-DR Spring 2006 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent N Weld Length = 67. Required Exam Area Scanned of Area Weld Length Percent
~hj Exam Volume = 23.3 Area Sq. In. Manual Manual Manual Manual N 60' NS T-Scan A 5.5 5.5 23.6% 46 8.1%
60 S6 "T-Scan A 14.4 14.4 61.8% 46 21.2% 60' S4 T-Scan A 3.4 3.4 14.6% 46 5.0% 600 NS P-Scan A 5.5 5.5 23.6% 46.0 8.1% 600 S6 P-Scan A 14.4 14.4 61.8% 46.0 21.2% 60' S4 P-Scan A 3.4 3.4 14.6% 36.0 3.9% 60' NS T-Scan 600 S6 T-Scan 600 S4 T-Scan B 3.4 1.7 7.3% 10 0.5% 60' NS P-Scan 60' S6 P-Scan 60' S4 P-Scan I - I Tv % Total Composite Coverage = 68% (D Comments:- A - Examined accessible weld length. B - P-Scan restricted due to lifting lug and top hd. Flange. 0 Note - Rounding methods may affect calculated values.
LaSalle Unit 1 Closure Head Meridionals 60' NS Exam Volume = 5 5 Sq. In 60' FV S6 Exam Volume = 14.4 Sq. In. 6W3FV S4 Exam Volume = 3.4 Sq. In. 60- NS T-Scan achieved = 5.5 Sq in.
'V60' FV S6 T-Scan achieved = 14.4 Sq In 60' FV S4 T-Scan achieved 3.4 Sq. In.
60' NS P-Scan achieved = 55 Sq In. 60- FV S6 P-Scan achieved = 14.4 Sq Inr 60- FV S4 P-Scan achieved = 1.7 Sq, in. 11.6" 60*T/p , IT 60'T6P 60:'T 1- 3,0" *1I60'T 0 - Ko, 0
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 1R 11-023 PROJECT LaSalle Unit 1, Li R11 WELD ID: GEL-1009-DT Top Hd Meridional SYSTEM: RPV CALIBRATION ID: N/A MANUAL DATA: UT-038 and 39 OPERATORS: W. Reid Lv II, I Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, and Section X1, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part I1,Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Pressure Vessel (RPV) Assembly Welds. Manual transverse and parallel scans were performed from the vessel OD surface in accordance with procedure GE-UT-300 VIO; using 600 RL search units. Manual scanning was restricted due~to the top head lifting lug and top hd. flange. The manual exams recorded no indications. Previous data was reviewed with no significant changes. Manual UT composite coverage = 68 % Ko P EPARED BY DATE REVIEWED BY DATE UTILITY REVIEW DATE ANII REVIEW DATE ITT Level: _ UT Level: LaSalle Unit-l, L1R11, 2006 Pagel of , Page 174
(- Report No. 1Rll-023 LaSalle Unit-1 C 0-- 2. GE-1009-DT Spring 2006 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 67. Required Exam Area Scanned NI' Exam Volume = 23.3 Area Sq. In. Manual of Area Weld Length Percent Manual Manual Manual N 6600 NS T-Scan A 5.5 5.5 23.6% 46 8.1% 600 S6 T-Scan A 14.4 14.4 61.8% 46 21.2% 600 S4 T-Scan A 3.4. 3.4 14.6% 46 5.0% 600 NS P-Scan A 5.5 5.5 23.6% 46.0 8.1% 600 S6 P-Scan A 14.4 14.4 61.8% 46.0 21.2% 600 S4 P-Scan A 3.4 3.4 14.6% 36.0 3.9% 60' NS T-Scan 60' S6 T-Scan 60' S4 T-Scan B 3.4 1.7 7.3% 10 0.5% 600 NS P-Scan 600 S6 P-Scan 60'"S4 P-Scan ___L I "0 % Total Composite Coverage = 68% Comments.- A - Examined accessible weld length. B - P-Scan restricted due to lifting lug and top hd. Flange Note - Rounding methods may affect calculated values.
_LaSalle Unit 1 C Closure Head N) Meridionals 0 o 60' NS Exam Volume = 5.5 Sq. In. 0*,, W60FV S6 Exam Volume ý 14 4 Sq. In. 60: FVS4 Exam Volume = 3.4 Sq. In. 60' NS T-Scan achieved = 5 5 Sq. In. 60' FV S6 T-Scan aclhieed = 14 4 Sq In 60 FV S4 T-Scan achieved = 3 4 Sq. In. 60'.NS P-Scan achieved = 5 5 Sq in 60' FV S6 P-Scan achieved ý 14.4 Sq. In 601 FV S4 P-Scan achieved = 1 7 Sq In 11.6" 601/P 60'TIP 60'T 1- 3.0' 60'T
ManuoJ. scanl area Manuat scanning restricted due to Uifting tug N ~A 0 0 36.00' Manual scan area
/11ý
*GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 1R 11-028 PROJECT LaSalle Unit 1, LR1i1, 2006 WELD ID: LCS-1-N2A SYSTEM: Recirculation CALIBRATION ID: NOZIN EXAMINATION DATA: N2A-01 OPERATORS: C. Gauthier Lv II; S. Gauthier Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V5, using 45° Shear wave, 600 RL, and 70° RL search units, supplemental 0° L-Wave scans were also performed. Scanning for the inner 15% T volume for radial flaws was performed using 45° Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. Automated scanning was restricted due to the nozzle configuration. The GERIS 2000 OD automated UT system 0 reference is located at 900 CW of nozzle TDC. For calibrations refer to report G2K-CAL. Seven (7) relevant indications were recorded that were found to be acceptabled per the requirements of IWB-3000, no further evaluations were required. Previous examination data was reviewed, no indications were recorded. Automated Composite Coverage = 83.1%. REPARED BY DATE REVIEWED BY DATE UTILITY REVIEW DATE ANII REVIEW DATE UT Level, .. T.LI UT Level: & LaSalle Unit 1, L1R11, 2006 Page I of ZI Page 178
03 r7 LaSalle 1 7N2 xNozzle l - Recirculation Inlet 11.6 Sq. In 70* Exam 45* Exam Volume Volume = = 51.4 Sq. In Inner 15%T Exam Vaolume (60'T & IRS) = 10.6 Sq. In 700 T-Scan achieved = 6.7 Sq. In AY5T-Scan achieved1= 46.9 Sq. In
= 10.6 Sq. In 600 T-Scan achieved
'OT 60'T T-Sca s70*T 4 .I
-I a r T
U-CO LaSalle 1 N2 Nozzle - Recirculation Inlet 70' Exam Volume = 11.6 Sq. In 450 Exam Volume = 51.4 Sq. In Inner 15%T Exam Volume (60*T & IRS) = 10.6 Sq. In 700 P-Scan achieved = 5.5 Sq. In 450 P-Scan achieved = 42.0 Sq. In Inner 15% P-Scan achieved = 10.6 Sq. In P-Scans 70°P 45 0 P
Summary No.: 1R11-028 LaSalle Unit-1, LIR11 LCS-1-N2A Spring 2006 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 73.6 Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 11.6 6.7 9.1% 360 4.6% 450 T-Scan .A 51.4 46.9 63.7% 360 31.9% 60' T-Scan A 10.6 10.6 14.4% 360 7.2% 70' P-Scan A 11.6 5.5 7.5% 360 3.7% 450 P-Scan A 51.4 42 57.1% 360 28.5% IRS P-Scan A 10.6 10.6 14.4% 360 7.2% 700 T-Scan _ 450 T-Scan 600 T-Scan 70* P-Scan 450 P-Scan IRS P-Scan 700 T-Scan 450 T-Scan 600 T-Scan 70' P-Scan 450 P-Scan IRS P-Scan .......... Io otal t.omposii Coverage = O.J. 117o r Comments: A - Scanned 360 deg., Scanning limited due to nozzle configuration. Note - Rounding methods may affect calculated values.
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 1R11-029 PROJECT LaSalle Unit 1, L1R1, 2006 WELD ID: LCS-1-N2G SYSTEM: Recirculation CALIBRATION ID: NOZ.IN EXAMINATION DATA: N2G-01 OPERATORS: C. Gauthier Lv II; S. Gauthier Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V5, using 450 Shear wave, 60* RL, and 70° RL search units, supplemental 0° L-Wave scans were also performed. Scanning for the inner 15% T volume for radial flaws was performed using 45* Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. Automated scanning was restricted due to the nozzle configuration. The GERIS 2000 OD automated UT system 0 reference is located at 900 CW of nozzle TDC. For calibrations refer to report G2K-CAL. Eleven (11) relevant indications were recorded that were found to be acceptable per the requirements of IWB-3000, no further evaluations were required. Previous examination data was reviewed, no indications were recorded. Automated Composite Coverage = 83.1%. 11 II LaSalle Unit 1, LIR11, 2006 Page _1 of~2~ Page 182
CO 7-0 0, LaSalle I N2 Nozzle - Recirculation Inlet 700 Exam Volume = 11.6 Sq. In 450 Exam Volume = 51.4 Sq. In Inner 15%T Exam Volume (60°T & IRS) = 10.6 Sq. In 700 T-Scan achieved = 6.7 Sq. In 450 T-Scan achieved = 46.9 Sq. In 600 T-Scan achieved = 10.6 Sq. In 0 707T 45 T 60°T w
0C r) (D 7r LaSalle 1 N2 Nozzle - Recirculation Inlet 700 Exam Volume = 11.6 Sq. In 450 Exam Volume = 51.4 Sq. In Inner 15%T Exam Volume (607T & IRS) = 10.6 Sq. In 700 P-Scan achieved = 5.5 Sq. In 45° P-Scan achieved = 42.0 Sq. In Inner 15% P-Scan achieved = 10.6 Sq. In P-Scans 70°P 45 0 P CD3
Summary No.: 1R11-029 LaSalle Unit-i, LiR1I LCS-1 -N2G Spring 2006 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 73.6 Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 11.6 6.7 9.1% 360 4.6% 450 T-Scan A 51.4 46.9 63.7% 360 31.9% 60 T-Scan A 10.6 10.6 14.4% 360 7.2% 70' P-Scan A 11.6 5.5 7.5% 360 3.7% 450 P-Scan A 51.4 42 57.1% 360 28.5% IRS P-Scan A 10.6 10.6 14.4% 360 7.2% 70' T-Scan _ 450 T-Scan 600 T-Scan 700 P-Scan 450 P-Scan IRS P-Scan 70' T-Scan 450 T-Scan 60' T-Scan 70' P-Scan 450 P-Scan IRS P-Scan 70 I oiI omposite Coverage = 83.17 Comments: A - Scanned 360 deg., Scanning limited due to nozzle configuration. Lr Note - Rounding methods may affect calculated values.
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: IR 11-030 PROJECT LaSalle Unit 1, LR1l1, 2006 WELD ID: LCS-1-N2H SYSTEM: Recirculation CALIBRATION ID: NOZIN MANUAL DATA: UT-182 EXAMINATION DATA: N2H-01 OPERATORS: C. Gauthier Lv II; S. Gauthier Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part I1,Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V5, using 45° Shear wave, 600 RL, and 700 RL search units, supplemental 0° L-Wave scans were also performed. Scanning for the inner 15% T volume for radial flaws was performed using 45° Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. Automated scanning was restricted due to the nozzle configuration and the proximity of the N9-B nozzle. Manual supplemental scanning was performed inthe restricted area from 114.80 to 155.4". Manual transverse and parallel scans were performed from the vessel OD surface in accordance with procedure GE-UT-300 VIC; using 60" RL search units The GERIS 2000 OD automated UT system 0 reference is located at 900 CW of nozzle TDC. For calibrations refer to report G2K-CAL. Two (2) relevant indications were recorded that were found to be acceptable per the requirements of IWB-3000, no further evaluations were required. Previous examination data was reviewed, no indications were recorded. Automated and Manual Composite Coverage = 83.1%.
-5 "IA 3//( ~ A f-§&
P EPARED BY DATE REVIEWED EN DATE UTILITY REVIEW DATE ANII REVIEW DATE Level: l UT Level: LaSalle Unit i, L1R11, 2006 Page t, of "5 Page 186
r-LaSalle 1 N2 Nozzle - Recirculation Inlet _0 700 Exam Volume = 11.6 Sq, In "-3 51.4 Sq. In 450 Exam Volume = 0)Inner 15%T Exam V olume (60=T & IRS) = 10.6 Sq. In CD C% 70" T-Scan achieved : = 6.7 Sq. In 0*
-450 T-Scan achievedS= 46.9 Sq. In 4 ,600 T-Scan achieved = 10.6 Sq. In
-. 4-.
OT 607T T-Sca 70T4 II I oj
- IN (f 5
0 LaSalle 1 N2 Nozzle - Recirculation. Inlet 700 Exam Volume = 11.6 Sq. In 450 Exam Volume = 51.4 Sq. In Inner 15%T Exam Volume (60T & IRS) = 10.6 Sq. In CD 70o P-Scan achieved = 5.5 Sq. In 00 00 \I 45* P-Scan achieved = 42.0 Sq. In Inner 15% P-Scan achieved = 10.6 Sq. In 3-Scans 70 0P 45 0 P 2 4~) 0-.. 2 03
N2-J N2-H 155.40 Z3. r C) N9-B 0 114.80 TIC PADS Automated Scanning restricted due to the proximity of the N9-B nozzle L
Summary No.: 1R11-030 LaSalle Unit-i, LI R1 I LCS-1-N2H Spring 2006 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 73.6 Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 11.6 6.7 9.1% 360 4.6% 450 T-Scan A 51.4 46.9 63.7% 360 31.9% 600 T-Scan A 10.6 10.6 14.4% 319.4 6.4% 70' P-Scan A 11.6 55 7.5% 360 3.7% 450 P-Scan A 51.4 42 57.1% 360 28.5% IRS P-Scan A 1 10.6 10.6- 14.4% 319.4 6.4% 700 T-Scan _ _ l_ _ _ _ _ _ 450 T-Scan " 600 T-Scan B 10.6 10.6 14.4% 40.6 0.8% 700 P-Scan 4 50 P -Sca n 10 .6 IRS P-Scan B10.6 10.6 14.4% 40.6 0.8% 700 T-Scan .... 450 T-Scan 600 T-Scan 70_P-Scan 450 P-Scan IRS P-Scan _"
% Total Composite Coverage = 83.1%
Comments: A'- Scanning restricted due to nozzle configuration and due to the proximity of the N9-B nozzle. B - Manual supplemental scanning performed in area restricted by N9-B nozzle. F Zk Note - Rounding methods may affect calculated values. I I I
*- GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 1 R 11-031 PROJECT LaSalle Unit 1, L1R11, 2006 WELD ID: LCS-1-N5 SYSTEM: Core Spray CALIBRATION ID: NOZ.IN EXAMINATION DATA: N5-01 OPERATORS: C. Gauthier Lv II; S. Gauthier Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V5, using 450 Shear wave, 60° RL, and 70° RL search units, supplemental 0" L-Wave scans were also performed. Scanning for the inner 15% T volume for radial flaws was performed using 450 Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. Automated scanning was restricted due to the nozzle configuration. The GERIS 2000 OD automated UT system 0 reference is located at 900 CW of nozzle TDC. For calibrations refer to report G2K-CAL. Eleven (11) relevant indications Were recorded that were found to be acceptable per the requirements of IWB-3000, no further evaluations were required. Previous examination data was reviewed, no indications were recorded. Automated Composite Coverage = 85.5%., p EPARED BY DATE REVIEWED BY DATE -- UTILITY REVIEW DATE ANII REVIEW DATE U4 Level: sm- UT Level: LaSalle Unit 1, LiR11, 2006 PageJ_ of 4 Page 191
r-C) LaSalle 1 N5 Nozzle - Core Spray 70' Exam Volume = 9.4 Sq. In 450 Exam Volume = 38.3 Sq. In Inner 15%T Exam Volume (607T & IRS) = 8.2 Sq. In 70° P-Scan achieved = 5.0 Sq. In 450 P-Scan achieved = 32.4 Sq. In Inner 15% P-Scan achieved = 8.2 Sq. In P-SIcans 70'P 45°P I m n
-u
I"- r-C-a 0LaSalle 1 N5 Nozzle - Core Spray 13 700 Exam Volume = 9.4 Sq. In 45* Exam Volume = 38.3 Sq. In D Inner 15%T Exam Vc)lume (60°T & IRS) = 8.2 Sq. In
- O 700 T-Scan achieved = 6.2 Sq. In A450 T-Scan achieved = 35.6 Sq. In 600 T-Scan achieved = 8.2 Sq. In Scas 70°T 4501 r 60°T I I CD 0
Summary No.: IR11-031 LaSalle Unit-l, L1R11 LCS-1-N5 Spring 2006 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 55.9 Area Sq. In. Auto Auto Auto Auto 70* T-Scan A 9.4 6.2 11.1% 360 5.5% 450 T-Scan A 38.3 35.6 63.7% 360 31.8% 600 T-Scan A 8.2 8.2 14.7% 360 7.3% 700 P-Scan A 9.4 5.0 8.9% 360 4.5% 45' P-Scan A 38.3 32.4 58.0% 360 29.0% IRS P-Scan A 8.2 8.2 14.7% 360 7.3% 70' T-Scan 45' T-Scan 60' T-Scan' 70_P-Scan 450 P-Scan +_ IRS P-Scan 70' T-Scan 450 T-Scan 600 T-Scan 70' P-Scan 450 P-Scan IRSP-Scan
% Total Composite Coverage = 85.5%
Comments: A - Scanned 360 deg., Scanning limited due to nozzle configuration. II-Note - Rounding methods may affect calculated values.
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 1R 11-032 PROJECT LaSalle Unit 1, Li R1 1, 2006 WELD ID: LCS-1-N6B SYSTEM: LPCI CALIBRATION ID: NOZINIT IN EXAMINATION DATA: N6B-01 OPERATORS: C. Gauthier Lv II; S. Gauthier Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V5, using 450 Shear wave, 60° RL, and 70° RL search units, supplemental 0° L-Wave scans were also performed. Scanning for the inner 15% T volume for radial flaws was performed using 45° Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements' sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. Automated scanning was restricted due to the nozzle configuration. The GERIS 2000 OD automated UT system 0 reference is located at 900 CW of nozzle TDC. For calibrations refer to report G2K-CAL. Six (6) relevant indications were recorded that were found to be acceptable per the requirements of IWB-3000, no further evaluations were required. Previous examination data was reviewed, no indications were recorded. Automated Composite Coverage = 83.7%. (PEPARED BY DATE REVIEWED BY DATE UTILITY REVIEW DATE ANII REVIEW DATE TLevel: UiUT Level LaSalle Unit 1, Li Ri 1, 2006 PagejIOf Page 195
I-- U, r-0 0 LaSalle 1 0)J N6 Nozzle - LPCI 700 Exam Volume = 12.0 Sq. In 450 Exam Volume = 44.8 Sq. In Inner 15%T Exam Volume (60'T & IRS) 9.6 Sq. In 70° T-Scan achieved = 7.1 Sq. In 450 T-Scan achieved = 40.8 Sq. In 600 T-Scan achieved = 9.6 Sq. In T-Scans 7 0OT 45°T 60°T WV I I I
-D; 02
ta-LaSalle 1 N6 Nozzle - LPCI 700 Exam Volume = 12.0 Sq. In 45' Exam Volume = 44.8 Sq. In Inner 15%T Exam Volume (60°T & IRS) = 9.6 Sq. In 700 P-Scan achieved = 5.9 Sq. In 450 P-Scan achieved = 38.2 Sq. In Inner 15% P-Scan achieved = 9.6 Sq. In 450 P-Scans P-Scans 70= p II 0o
Summary No.: 1R11-032 LaSalle Unit-i, LI R1 1 LCS-1-N6B Spring 2006 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 66.4 Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 12 7.1 10.7% 360 5.3% 450 T-Scan A 44.8 40.8 61.4% 360 30.7% 600 T-Scan A 9.6 9.6 14.5% 360 7.2% 70' P-Scan A 12 5.9 8.9% 360 4.4% 450 P-Scan A 44.8 38.2 57.5% 360 28.8% IRS P-Scan A 9.6 9.6 14.5% 360 7.2% 700 T-Scan i 450 T-Scan 600 T-Scan 70' P-Scan 45' P-Scan IRS P-Scan 70' T-Scan 450 T-Scan 600 T-Scan 70' P-Scan 450 P-Scan IRS P-Scan r- % Total Composite Coverage =
;-,0 83.7%
Comments: A - Scanning restricted due to nozzle configuration. Note - Rounding methods may affect calculated values. P
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 1RI 1-033 PROJECT LaSalle Unit 1, LiR1l WELD ID: LCS-1-N7 Top Head Nozzle SYSTEM: RPV CALIBRATION ID: N/A MANUAL DATA: UT-103, 104,113 and 114 OPERATORS: S. Snyder Lv II, Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section Xl, 1989 Edition no Addenda, and Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Pressure Vessel (RPV) Assembly Welds. Manual transverse and parallel scans were performed from the vessel OD surface in accordance with procedure GE-UT-300 V1 0; using 600 RL search units. Manual parallel scans of the inner 15%T volume were performed in accordance with procedure GE-UT-31 1 VI4, using model validated shear wave search units. Manual scanning was restricted due to the nozzle configuration. The manual exams recorded no indications. Previous data was reviewed with no significant changes. Manual UT composite coverage = 87 % (T evl 3~L 11 UT Leo l / 12 a REPARED BY DATE REVIEWED BY DATE UTILITY REVIEW DATE ANII REVIEW DATE TUee : 7 -L T L e ve l :. Z ! Z LaSalle Unit-i, LIR11, 2006 Page I of "_ Page 199
Report No. 1R11-033 C/) LaSalle Unit 1, L1R11 C LCS-1-N7 Spring 2006
':3 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 22. Area Sq. In. Manual Manual Manual Manual 60' T-Scan S4 A 2.2 2.2 10.0% 180.0. 2.5%
60' T-Scan S6 A 19.8 16.6 75.5% 180.0 18.9% IRS P-Scan S4 A 2.2 2.2 10.0% 180.0 2.5% 60' P-Scan S6 A 19.8 15.0 68.2% 180.0 17.0% Exam Volume __21.7 60' T-Scan S4 B 3.8 3.8 17.5% 180.0 4.4% 60' T-Scan S6 B 17.9 16.7 77.0% 180.0 19.2% IRS P-Scan S4 B 3.8 3.8 17.5% 180.0 4.4% 60' P-Scan S6 B 17.9 15.8 72.8% 180.0 18.2% D 600 T-Scan _4 60' T-Scan S6 IRS P-Scan S4 600 P-Scan S6 600 T-Scan S4 60' T-Scan S6 IRS 600 P-Scan_4 P-Scan S6 - (Dj
% Total Composite Coverage = 87%
Comments: A - Top side of offset nozzle. Examined 1800 length. Scanning limited due to nozzle configuration. B - Bottom side of offset nozzle. Examined 1800 length. Scanning limited due to nozzle configuration. Weld length in degrees. IRS examination coverage determined by modeling. 0 Coverage sheet modified for offset nozzle configurations. [Note - Rounding methods may affect calculated values.
Top Side Coverage LaSalle Unit 1 60' NS Exam Volume = 7.3 Sq. In. 600 FV S6 Exam Volume = 12.5 Sq. In. Top Hd. Spray / Spare 600 FV S4 Exam Volume = 2.2 Sq. In. 600 NS T-Scan achieved = 4.2 Sq. In. 600 FV S6 T-Scan achieved = 12.4 Sq. In. Bottom Side Coverage 600 FV S4 T-Scan achieved = 2.2 Sq. In. 60' NS Exam Volume = 6.09 Sq. In. 600 NS P-Scan achieved = 3.8 Sq. In. 600 FV S6 Exam Volume = 11.8 Sq. In. 600 FV S6 P-Scan achieved = 11.2 Sq. In. 600 FV S4 Exam Volume = 3.8 Sq. In. Inner 15%T IRS-Scan achieved = 2.2 Sq. In. 60° NS T-Scan achieved = 4.9 Sq. In. 60' FV S6 T-Scan achieved = 11.8 Sq. In. 600 FV S4 T-Scan achieved = 3.8 Sq. In. 60' NS P-Scan achieved = 4.3 Sq. In. 600 FV S6 P-Scan achieved = 11.5 Sq. In. Inner 15%T IRS-Scan achieved = 3.8 Sq. In. 45°P 60°T/P I -,
,2' 60O'T 9.
100 45°P 11.00 60P 60 T
-v M3
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 1R 11-034 PROJECT LaSalle Unit 1, L1R11 WELD ID: LCS-1-N8 Top Head Nozzle SYSTEM: RPV CALIBRATION ID: N/A MANUAL DATA-. UT-115, 116, and 117 OPERATORS: W. Reid Lv II, Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section X1, 1989 Edition no Addenda, and Section Xl, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II,Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Pressure Vessel (RPV) Assembly Welds. Manual transverse and parallel scans were performed from the vessel OD surface in accordance with procedure GE-UT-300 V1 0; using 60° RL search units. Manual parallel scans of the inner 15%T volume were performed in accordance with procedure GE-UT-31 I V14, using model validated shear wave search units. Manual scanning was restricted due to the nozzle configuration. The manual exams recorded no indications. Previous data was reviewed with no significant changes. Manual UT composite coverage = 79 %
'P EPAkED BY DATE REVIEWED BY DATE UTIL-ITY REVI W DATE ANII REVIEW DATE UT Level: "* UT Level:
LaSalle Unit-i, L1R11, 2006 Page 1 of 7 Page 202
Report No. 1R11-U34 U-) LaSalle Unit 1, LIR11 C LCS-1-N8 Spring 2006 I-" CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 24.8 Area Sq. In. Manual Manual Manual Manual 600 NS T-Scan A 7.6 3.5 14.1% 360 7.1% 60' S6 T-Scan A '14 13.7 55.2% 360 27.6% 60° S4 T-Scan A 3.2 3.2 12.9% 360 6.5% 600 NS P-Scan A 7.6 3.1 12.5% 360 6.3% 60' S6 P-Scan A 14 12.5 50.4% 360 25.2% 60' S4 P-Scan A 3.2 3.2 12.9% 360 6.5% 600 NS T-Scan 60' S6 T-Scan 60' S4 T-Scan ....... 60' NS P-Scan 60°'S6 P-Scan 60' S4 P-Scan I . . .. -0 % Total Composite Coverage = 79% lu Comments: A - Manual scanning restricted due to nozzle configuration. o Note - Rounding methods may affect calculated values.
600 NS Exam Volume = 7.6 Sq. In. 600 FV S6 Exam Volume = 14.0 Sq. In. LaSalle Unit 1 60' FV S6 Exam Volume = 3.2 Sq. In. LCS-1-N8 Top Hd. Vent 60' NS T-Scan achieved = 3.5 Sq. In. 60' FV S6 T-Scan achieved = 13.7 Sq. In. 60° FV S4 T-Scan achieved = 3.2 Sq. In. 600 NS P-Scan achieved = 3.1 Sq. In. 60' FV S6 P-Scan achieved = 12.5 Sq. In. 60' FV S4 P-Scan achieved = 3.2 Sq. In.
GE NUCLEAR ENERGY I UT EXAMINA TION
SUMMARY
SHEET Summary No: 1R 11-026 PROJECT LaSalle Unit 1, L1R11, 2006 WELD ID: LCS-1-N16 SYSTEM: Core Spray CALIBRATION ID: NOZIN EXAMINATION DATA: N16-01 OPERATORS: C. Gauthier Lv II; S. Gauthier Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section Xl, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V5, using 45° Shear wave, 60° RL, and 70° RL search units, supplemental 0° L-Wave scans were also performed. Scanning for the inner 15% T volume for radial flaws was performed using 45° Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. Automated scanning was restricted due to the nozzle configuration. The GERIS 2000 OD automated UT system 0 reference is located at 900 CW of nozzle TDC. For calibrations refer to report G2K-CAL. Six (6) relevant indications were recorded that were found to be acceptable per the requirements of IWB-3000, no further evaluations were required. Previous examination data was reviewed, no indications were recorded. Automated Composite Coverage = 85.5%. SEPARED BY DATE REVIEWED BY DATEi- UTILI~` EVIEW. DATE ANII REVIEW DATE Level: T~IIUT Level: ~ LaSalle Unit 1, L1R11, 2006 Page I of I S" Page 205
(0 i4 r-. LaSalle 1 N16 Nozzle - Core Spray 700 Exam Volume = 9.4 Sq. In 450 Exam Volume = 38.3 Sq. In D Inner 15%T Exam Vc olume (607T & IRS) = 8.2 Sq. In 70* T-Scan achieved = 6.2 Sq. In 450 T-Scan achieved = 35.6 Sq. In 600 T-Scan achieved = 8.2 Sq. In
"- -T-Scals 70*T 450- 600T
C c-U, if
>16 C4 CL)
Cr1 Cý > 0 C-Ocn 00 I') oU)U) CU 'r-CL ( Uo CL LaSalle 1 - LIR1l, 2006 Page IS of __ B Page 207
Summary No.: 1R 11-026 LaSalle Unit-i, L1R11 LCS-1-N16 Spring 2006 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 55.9 Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 9.4 6.2 11.1% 360 5.5% 450 T-Scan A 38.3 35.6 63.7% 360 31.8% 600 T-Scan A 8.2 8.2 14.7% 360 7.3% 700 P-Scan A 9.4 5.0 8.9% 360 4.5% 450 P-Scan A 38.3 32.4 58.0% 360 29.0% IRS P-Scan A 8.2 8.2 14.7% 1 360 73% 70_T-Scan 450 T-Scan 600 T-Scan "__ 70' P-Scan 450 P-Scan IRS P-Scan 70' T-Scan _'_.... . 450 T-Scan 600 T-Scan 70_P-Scan 450 P-Scan IRS P-Scan
% Total Composite Coverage = 85.5%
Comments: A - Scanned 360 deg., Scanning limited due to nozzle configuration. ari Note - Rounding methods may affect calculated values.
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 1R 11-027 PROJECT LaSalle Unit 1, L1R11 WELD ID: LCS-1-N18 Top Head Nozzle SYSTEM: RPV CALIBRATION ID: N/A MANUAL DATA: UT-099, 100, 129 and 130 OPERATORS: S. Snyder Lv II, Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section Xl, 1989 Edition no Addenda, and Section X1, 1995 Edition with the 1996 Addenda as modified by the PD1 program description and the Federal Register, Part II,Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Pressure Vessel (RPV) Assembly Welds. Manual transverse and parallel scans were performed from the vessel OD surface in accordance with procedure GE-UT-300 Vi0; using 600 RL search units. Manual parallel scans of the inner 15%T volume were performed in accordance with procedure GE-UT-311 V14, using model validated shear wave search units. Manual scanning was restricted due to the nozzle configuration. The manual exams recorded no indications. Previous data was reviewed with no significant changes. Manual UT composite coverage = 87 % [d Ii LaSalle Unit-l, LIR11, 2006 PagelIof4 Page 209
Report No. IR11-027 u) LaSalle Unit 1, LIR11 C LCS-1-N18 Spring 2006 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 22. Area Sq. In. Manual Manual Manual Manual 600 T-Scan $4 A 2.2 2.2 10.0% 180.0 2.5% 600 T-Scan S6 A 19.8 16.6 75.5% 180.0 18.9% IRS P-Scan S4 A 2.2 2.2 10.0% 180.0 2.5% 60' P-Scan S6 A 19.8 15.0 68.2% 180,0 17.0% Exam Volume= 21.7 ) 600 T-Scan S4 B 3.8 3.8 17.5% 180.0 4.4% 600 T-Scan S6 B 17.9 16.7 77.0% 180.0 19.2% IRS P-Scan S4 B 3.8 - 3.8 17.5% 180.0 4.4% 600 P-Scan S6 B 17.9 15.8 72.8% 180.0 18.2% 600 T-Scan S4 '" 600 T-Scan S6 IRS P-Scan S4 60' P-Scan S6 60' T-Scan S4
,,4 60' T-Scan S6 IRS P-Scan _4 60- P-Scan S6
-V
£0
% Total Composite Coverage = 87%
Comments: A - Top side of offset nozzle. Examined 1800 length. Scanning limited due to nozzle configuration. B - Bottom side of offset nozzle. Examined 1800 length. Scanning limited due to nozzle configuration. Weld length in degrees. IRS examination coverage determined by modeling. 0
-h Coverage sheet modified for offset nozzle configurations.
Note - Rounding methods may affect calculated values.
Top Side Coverage LaSalle Unit 1 600 NS Exam Volume = 7.3 Sq. In. 600 FV S6 Exam Volume = 12.5 Sqln. Top Hd. Spray / Spare 600 FV 54 Exam Volume = 2.2 Sq. In. 60' NS T-Scan achieved = 4.2 Sq. In. 60' FV S6 T-Scan achieved = 12.4 Sq. In. Bottom Side Coverage 60' FV 54 T-Scan achieved 2.2 Sq. In. 600 NS Exam Volume = 6.09 Sq. In. 60' NS P-Scan achieved = 3.8 Sq. In. 60° FV S6 Exam Volume = 11.8 Sq. In. 60° FV S6 P-Scan achieved = 11.2 Sq. In. 60' FV S4 Exam Volume = 3.8 Sq. In. Inner 15%T IRS-Scan achieved = 2.2 Sq. In. 600 NS T-Scan achieved = 4.9 Sq. In. 60' FV S6 T-Scan achieved = 11.8 Sq. In. 600 FV S4 T-Scan achieved - 3.8 Sq. In. 60' NS P-Scan achieved = 4.3 Sq. In. 600 FV S6 P-Scan achieved = 11.5 Sq. In. Inner 15%T IRS-Scan achieved = 3.8 Sq. In. 45°P 60 TIP 5.2- 4.6" 0 60OT 6, °P 9. 10- 45°P lir60' r-IN -IN
Report No.- GENCER GE NUCLEAR ENERGY NRYEXAMINATION YRI-
SUMMARY
SHEET 11-ol Site: LaSalle Station Component ID: RPV-S$-I Outage: LI R11 System: RPV ASME Cat.: B-K ASME Item B10.10 Aug Req.: ASME Sec.Xl Peened Date Sheet RProcedure c alibration Bot aiatton Perfored,,*: * .Personnel PT PT-01 i .. 0.0--V.rr;ReV-*S GE.P---- NIA l- Alicia Hutton t 1. - 3/5/2006 Vr- V-00_1 ER-A-33o01 e.,,.*.,vo,., R2 NA AliciaHutton 11- 1.j3i5/20 Examination Resul: During the liquid penetrant and the visual examination of the above referenced weld, no recordable indications were detected. Due to adjacent structures only 66% of the required exam area was accessible for PT inspections. Due to this limiting condition a VT-r examination was performed on 100% of the required examination area. This examination meets the requirements of ASME Section X1, 1989 Edition with no Addenda. Examination results were comparedto data report: 0-733 from 1989 outage with '1_J No Change These examinations were performedunder Work Order: 704866 Change This Summary and the following data sheets have been reviewed and accepted by the foWlowing personnel: Utility Review: Date: GE Review By: Level: Date: ANII Review: Date: Page 212
GE Nuclear Energy LIQUID PENETRANT EXAMINATION REPORT Site: LaSalle Station Unit: I Project: LIR1 iReport Number: IRII-061 Sheet No.: PT-011 Weld No.: RPV-SS- I Configuration: LuM Drawing: GEL-1109 System: RPV Procedure No.: GE-PT-100 Ver/Rev.: V5 DRR: N/A Material: Surface Condition: Item: Carbon Steel Ground Weld - Final Technique: Cleaner Penetrant Developer Visible Solvent RemovableIB-3) Manufacturer Muiltnx Masnaflux MafaNluo Thermometer 2459f Brand / Type sm-S SKL-SPi SK-Temperature: "WE Batch No. 046Q O10K/ Black Light: -WA Light Moter WA Blacklight Intensity. -VAiWlcm' Pre Clean Method: SPray & Wi0e Drying Time: 5 min. Penetrant Application Brushina Dwell Time: 0 min. Penetrant Removal Wipe wi dry towel Wipe with, damp towel Drying Time: mi. Developer Application: Snrav Developing Time: 1o mrin. IniainNumber: _ ___ _ _
Description:
_ _ _ _ Results comments: Exam Stygt 1010. Exam was Deformed on th~e accessible area's 66%. too and both sides. AVT-i- examination was nerfomaed on 1009t of 'hA i 5~am,VT-I Rn,,wt UT-r Exam 11111 ft"was rpqita mr(ormed the accOSSM9 NO rprOlhiA rnni ni-mfir areil's 66% too a boM sides, A VT-1 examinati was nerform I f)n% af tha I VT-1 R-m VT-
.......................... ........... M' IAlicia Hutton ll3SM Giffy Review Date Exarni Level Date GE Review Level Date ANII Review Date Page ,2 of 3 I
Page 213
GE Nuclear Energy VISUAL EXAMINATION REPORT Site: LaSalle Station Unit: I Project: LR1_. Report Number IRII-061 Sheet No.: VT0O01 Weld No.: RPV-SS-1 Configuration: LuA ASME Code Class: I ASME Category: B-K ASME Item: B10.10 Drawing: GEL-1109 System: RPV Procedure No.: ER-AAA-335-014 Version: R2 DRR: N/A TECHNIQUE EQUIPMENT LIGHTING TOOLS oRESUT9ON* Exam Type: vr Mirrr V Flasrl-g1 V Six inch Scale Gray Card Technique: 2LO 0- Magnifer t2Rmot SdW Video Ki-.Amblf Sentr:~~fA
, e i
_jemol Coorvideo N/A Thread Gaug F-i ol0,e N/A NIA COMPONENT DATA Material Surface Condition Equipment Condition Component car""e Sm Gmum WA* e Indication Number
Description:
, Results:
Comments: A VT-1 examination was performed on 100% of the lug. Lug is 14" w "7" h. No Recordable Indications Kaminer Level Date uAility Review Date GReiwLevel Date ANtI Review Date Page ~3 of Page 214
Report No.: EXAMINATION
SUMMARY
SHEET 1R11-073 GE NUCLEAR ENERGY Site: LaSalle Station Component I/: IHP-PUI-04 Outage: LIR1. Plate-Shell System: HPCs ASME Cat.: C-C ASME Item: C3.30 Aug Req.: ASME Sec.Xl Exams Cal I Data Sheet I Procedure Calibration Block Examination Cert Level. Date Performed Personnel MT AMT-00i GE-WT-lOo VmRev VS WA AlIcia Hutton 1 II 2/2212006 Examination Results: During the magnetic particle examination of the above referenced weld, no recordable indications were detected. 16% of the required exam area was examined. This examination meets the requirements of ASME Section XI, 1989 Edition with no Addenda. Examination results were comparedto data report' N/A from N/A outage with No Change These examinations were perlormed under Work Onrer 704866 Change This Summary and the following data sheets have been reviewed and accepted by ft following personnel iew: Date: GE Review By: ANII Reviewv Date: Page 215
Site: LaSalle Station Unit: 1 Project: LIR11 Report Number: IR11-073 Sheet No.: MT-O01. Weld No.: IHP-PUI-04 Configuration: Plate-Shell Drawing: GEL-1049 System: HPCSS Procedure No.: GE-MT-100 Version I Revision: V6 DRR: N/A Material: Surface Condition: Item: Carbon Steel Cleaned Weld - Final Magnetizing Apparatus Black Light Mfg: Parker Research Yoke Calibration: 2-15-06 Model Serial Number Model: B-300 Blacklight: N/A NIA Serial No. 5522 Yoke Spacing: 4!-6' Light Meter: N/A N/A Thermometer 245993 Surface Temperature: 822 F Technique Examination Medium Blacklight Intensity Magnetization: AC Magnetic Particles: Dry NIA Technique: Continuous ParkerResearch RP-6 11793 Blacklight Intensity: Manufacturer Particle Type: Batch No.: Indication Number,
Description:
Results: NRI Comments: Examined only 28" of the 171.25' due to concrete pedestal surrounding the pump. See attached photo. No recordable indications. Alicia Hon 2/222006 Util Rvew Date lniuta iner Level Date GE Review Level Date ANII Review Date Page -. of 3 Page 216
GE.Vuclear Energi, SKETCH SHEET Report No: IRI1-073 Component ID: IHP-PU 1-04 Accessable portion of weld prior to paint removal -,4 Examiner Lv.f Daew: 2 -,, zv'z Reviewed By_______________ Date: //2
ý/c' Pagee o Utility Reviewed By: Lv. v..a Date: ý --1(* -6 DP 3 of 3
Report No.: EXAMINATION
SUMMARY
SHEET 1R111-O74 GE NUCLEAR ENERGY Site: LaSalle Station Component/O: ILP-PU-04 Outage: LIR1I. Plate-Shell System: LPCS ASME Cat.: C-C ASME Item: C3.30 Aug Req,: ASME Sec.Xl Exams Cal / Data Sheet I Procedure I Calibration Blockl Examination :Ceit Leveli Date Performed Personnel
.MT -003 . GE-MW-,0OVer/e~v6 WA Clay Suhler I ii 2/23/2006
-xamination Results: During the magnetic particle examination of the above referenced weld, no recordable indications were detected. 24% of the required exam area was examined. This examination meets the requirements of ASME Section X1, 1989 Edition with no Addenda. Examinationresults were compared to data report N/A from N/A outage with lNoChange These examinations were perkbmned under Work Order. 704866 Change This Summary and the following data sheets have been reviewed and accepted by the following personnel: RWP: ALA R-3s-040 Dose: 3 mr. tiity R~view: Date: GE Review By: ANII Review: Date: paw I of 3 Page 218
Site: LaSalle Station Unit: I Project: LIRII Report Number: IRI1-074 Sheet No.: MT-003 Weld No.: ILP-PU-04 Configuration: Plate-Shell Drawing: GEL-10 System: LPCS Procedure No.: GE-MT-1O0 Version I Revision: V6 DRR: N/A Material: Surface Condition: Item: Carbon Steel Cleaned Weld - Final Magnetizing Apparatus Black Light Mfg: ParkerResearch Yoke Calibration: 2f15/06 Model Serial Number Model: B300 Blacklight: N/A N/A Serial No. 5522 Yoke Spacing: 6" Light Meter N/A N/A Thermometer 246641 Surface Temperature: 84° F Technique Examination Medium Blacklight Intensity Magnetization: AC Magnetic Particles: ftr N/A Continuous ParkerResearch RP-6 11793 Blaxkfght ntensity: Technique: Manufacturer Partide Type: Batch No.: Indication Number
Description:
- Results:
Comments: Examined only 28" of the 117.20" due to concrete pedestal surrounding the Pump. See attached photo. No recordable indications. Clay Suhler 0 1 2/23/2006 UtLtReiew Date Ii iner Level Date GE Review Level Date ANII Review Date Page Z. of 3 Page 219
SGEEneriS, Nuclear SKETCH SHEET Report No: IRII-074 Component ID: ILP-PU-04 Accessable portion of weld Reviewed By. Lv. Date:_____ Reviewed By, Data-Utiliy Reviewed By- -&I ý (§0v- ~ t.~5( a-as-6 Lv--ýDate: Page ae.o Of 3
O ~Report No-:. GE NUCLEAR ENERGY........ EXAMINATION
SUMMARY
SHEET IRII-75 Site: LaSalle Station Component ID: IRH-PUIC-04 Outage: LIRI1 Plate - Shell System: RHR ASME Cat.: C-C ASME Item C3.30 Aug Req.: ASME Sec.Xl Exams Data Sheet Procedure Calibration Block I Examination cDt e ate Performed Personnel MT I MT_009_ _ _ GE-_MT-_0VrRvV8 NIA Alan Kelly II. j 2/28/2006 Examination Results: During the magnetic particle examination of the above referenced weld, no recordable indications were detected. 21% of the requk'ed exam area was examined. This examination meets the requirements of ASME Section XI, 1989 Edition with no Addenda. Examination results were compared to data report: N/A from N/A outage with No Change These examinations were performedunder Work Order: 704866 Change This Summary and the following data sheets have been reviewed and ac epted by the folilowing personnel:
*via RWP: N/A D Dose: mr.
G Bete y Review: Date: GE Review By: Level: Date: ANII Review: Date: Page -1. of3 Page 221
0 GE NuclearEnergy MAGNETIC PARTICLE EXAMINATION REPORT Site: LaSalle Station Unit: / Project L Report Numberi 1Rl-075 Sheet No.: MT-009 Weld No.: IRH-PUIC-04 Configuration: Plate - Shel Drawing: GEL-1003 System: RHR Procedure No.: GE-MT-.O0 Version I Revision: V6 DRR: N/A Material: Surface Condition: Item: Carbon Steel Cleaned Weld - Final Magnetizing Apparatus Black Light Mfg: ParkerResearch Yoke Calibration: 2/15406 Model Serial Number Model: B300 Blacklight: N/A N/A Serial No. 8184 Yoke Spacing: 3"-S4 Light Meter N/A WA Thermometer 246541 Surface Temperature: Z3- F Technique Examination Medium Blacklight Intensity Magnetization: AC Magnetic Particles: Dry N/A Technique: Continuous ParkerResearch RP-6 11793 BIaCkMht lntensit-ftanufw, Paride Type Batch No.: Indication Number! Descriptin: Results: Comments: Examined 25" of 116.375" due to concrete Pedestal surrounding the Pump. See attached photo. No recordable indications. Alan Ke#V 2/820! R./ Date InGiaE e/vwLevel Date Level Date ANII Review Date Page of 3 Page 222
GEN'ucleurEnerey SKETCH SHEET Report No: IRII-075 Component ID: IRH-PU IC-04 Accessable portion of 00* weld CA) q Reviewed By. ILV flntp. r dp( Reviewed By: 6,etJa. tzq " Date: 0_______ Utility Reviewed By,.., g.C-A&S Lv. =4E Dater Pag Page J3 off 3
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COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 199. ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: /*7 *//* / '- PAGE:-. / OF / PROCEDURE: NDT- < 30 REV. DATA SHEET NO.: b- / /'?- DAl /alz - CALIBRATION SHEET NO.(S) ST. BEAM: ____f ___ ANGLE BEAM: axial /,4- circ. /?9-COMPONENT INSPECTED SYSTEM: /_ TD, WELD #: L-10-0C-/?6- WELD TYPE: -1* - Fa.
- PtPJ SIZE: _______ THICKNESS/SCHEDULE: *. /O MATERIAL: l COMPONENT TEMPERATURE: '611 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: C' d? ANGLE BEAM AXIAL:. /1 COUPLANT/
BATCH 0: F-4(--&3L: 7L -S2-5 ANGLE BEAM CIRC.: H /1: EXAMINATION SCANS Performed Indications YES NO NO YES I) Base Metal Straight Beam
/I \ 2) Angle Beam-Normal-Against Flow - _
- 3) Angle Beam-Normal-With Flow /. -
- 4) Angle Beam-Along Weld-CW .,/i l/j
- 5) Angle Beam-Along Weld-CCW . 7 F
L 6) Straight Beam of Weld , V 0 W 7) Thickness Across Weld & Base Metal i i4/* // UP STRM WELD ODNSTR ADDITIONAL COMMENTS At C EXAMINER: LEVEL:_____ DATE:/Cf-'2 REVIEWER: LEVEL: =7 DATE:- /&',Z9<11 OTHER: 5,*0Z LEVEL:_____ DATE:/t 9' STATION: 6DATE: /0__z_01____ ANII:____ ____ ____ ____ ____ ____ ____ DATE: I 2 Page 252
COMMONWEALTH EDISON COMPANY Page 20 of 2 Procedure No. NDT-C-30 Rev. 2 December, 19 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A ( STATION/UNIT:. l <'//_ / J- PAGEf,:.__ OF PROCEDURE: NDT- C' 30 REV.-2 DATA SHEET NO.: /-- S DAT : /7 "- CALIBRATION SHEET NO.(S) ST. BEAM.: _ __ ANGLE BEAM: axial / circ. - COMPONENT INSPECTED SYSTEM: 2 P V WELD #: C-/C*, - /?Cr WELD TYPE: T7/ - CPIPONEN TM R THIC SS/SCHEDULE . ATERIAL: COMPONENT TEMPERATURE: SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: t-4 /A ANGLE BEAM AXIALs .5 d COUPLANT/ E -- a-X I ANGLE BEAM CIRC.: 'q BATCH *"- 0,"R (2 EXAMINATION SCANS Perforned Indications YES NO NO YES 1.) Base Metal Straight Beam *. __ _
/ \ 2) Angle Beam-Normal-Against Flow
- 3) Angle Beam-Normal-With Flow ____
K 4) Angle Beam-Along Weld-CW 7
- 5) Angle Beam-Along Weld-CCW 7 F
L 6) Straight Beam of Weld / H/, 0 W 7) Thickness Across Weld & Base Metal //9 UP STRM1 WELD DN STR ADDITIONAL COMMENTS ca&qr-r- r-'PýEL /0 -30t
.92q~a-qNA Xm EXAMINER
- LEVEL: ________DATE: /o-0 . -
REVIEWER: LEVEL: I DATE:___________ OTHER: J-P.o E-*A*--- . LLEVEL: DATE:__________ STATION: 6 . DATE: _______ ANII: DATE: Page 253
COMMONWEALTH EDISON COMPANY Page 20 of 2 Procedure No. NDT-C-30 Rey. 2 December, 19 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: /A*/z , PAGE:r / OF PROCEDURE: NDT- C.30 RV. . DATA SHEET NO.: L--/?gc_- DATE: /0 - _--7 CALIBRATION SHEET NO.(S) ST. BEAM: ,_ zIl_ ANGLE BEAM: axial )( C-292 circ. 7-COMPONENT INSPECTED SYSTEM: ,P WELD #: 6E/-/o1 o -A'& WELD TYPE: 7C4 - FL
.ZE:
,.',: 2$ / THICKNESS/SCHEDULE:- 5/0 MATERIAL: ?
COMPONENT TEMPERATURE:j f SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: t4 1 ANGLE BEAM AXIAL:
- Y, COUPLANT/
BATCH #: U21-A CF 2C 2c ANGLE BEAM CIRC.: c_ _ _ _ EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam 11/ _
/ \ 2) Angle Beam-Normal-Against Flow "
- 3) Angle Beam-Normal-With Flow
- 4) Angle Beam-Along Weld-CW *
- 5) Angle Beam-Along Weld-CCW -
F L 6) Straight Beam of Weld P-/A W 7) Thickness Across Weld & Base Metal p/q t4 /r4* H/ UP STRM WELD DN STR ADDITIONAL COMMENTS t'dZ /0C EXMINER: .2E LEVEL: DATE:______ _ REVIEWER: 'LEVEL: - 2 DATE: /_ _ _ /_*__ OTHER: .-- ,1-6,. LEVEL: 72E.DATE: / SATION: e6 DATE: ______ Page 254
GE Nuclear Energy Typical design for Top Head to Flange Weld number GEL-1060-AG REPORT NO.: Exam coverage is limited due to the flange configuration
-/s " or:
,AGE:_L_..
0% 45° W0. Exam Area 66.70% 66.70% 66.70% CW Circ scans 66.70% 66.70% CCW Circ scans GE REVIEWED BY LEVEL DATE 100.0% 100.0% Ax Down 0.0% 0.0% Ax Up 88.90% 91.30% Base Metal 66.70% 64.46% 64.94% UTIUTY REVIEW DATE Total composite coverage for Weld GEL-1 060-AG 65.37% SUAD REVIEW DATE 60 0S 450S 450S 600S
NDT-B-I Revision 6 December 1 i 1993 Page 4 of 44 FORM NDT-B-I-F1 MAGNETIC PARTICLE EXAMINATION DATA SHEET DATE /9///e* STATION & UNIT LaSalle Unit 2 1 L2R07 DAT ASHEET# # --(aO EXAMINER &el" AQ A *77-
&L2 LEVEL 7-
. SYBT, Reactor Pressure Vessel COMPONENT GEL-1060-AG SECTION XI EDITION & ADDENDA 1989 Edition, No Addenda CODE CLASS Class I SECTION XI CATEGORY B-A ACCEP TANCE STD. IWB-3510 PROCEDURE # & REVISION NOT-B-1 Rev. 6 SKETCH SHE IT USED: YES NO COMMENTS: Configuration: TH-FL
/17*5 V MAGNETIC PARTICLE EXAM:
Manufacturer Model/Type S/N Yoke Parker uojuu L/.c ." 4 Current AC X DC Particles Magnaflux A14. I , , Z-63y Color GRAV Black Light N/A N/A NIA B.L.M. Readings NIA B.L.M. Time Checks Initial NIA Final N/A EXAM RESULTS ACCEPT 17 REJECT REVIEWED BY: AN LVEL: DATE: /':6'/, /.9 4 DATE:
/o. /2 .?
REVIEWER: _________________LEVEL: =/7' OTHER., LEVEL: ______ DATE: /5 -Ji- n DATE: ANTII DATE: Page 256
COMMONWEALTH EDISON COMPANY CiPage 20 of 22 Procedure No. NDT-C-30 Rev. 2 SDecember, 199i ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: .277 PAGE: / OF PROCZDURE: NDT- C-30 REV. .. DATA SHEET NO.: b- 164,4 DAT6/ CAL:BRATION SHEET NO.(S) ST. BEAM: - -- ANGLE BEAM: axial ____'_" circ. _ __1 __ COMPONENT INSPECTED SYSTEM: WELD -? /A
?:IC WELD TYPE: ./-A .Ipp,. SIZE: ?.Y/ THICKNESS/SCHEDULE: -7115- MATERIAL: ..
COMPONENT TEMPERATURE: 76i /*56,5c SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: 36 1 'ANGLE BEAM AXIAL: A-/ 4 COUPLANT / BATCH #: YirA4&E4 *i Tii ANGLE BEAM CIRC.: EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam X X
/ \ 2) Angle Beam-Normal-Against Flow X
- 3) Angle Beam-Normal-With Flow x i 4) Angle Beam-Along Weld-CW IX
- 5) Angle Beam-Along Weld-CCW /
L 6) Straight Beam of Weld X 0 W 7) Thickness Across Weld & Base Metz- fx ,-/ UPSTRM WELD DN STR ADDITIONAL COMMENTS
,0 /*O! /4/TI//A (* '
A7Ar~~~zQU 7-0~ IYCI611
- A1A&e /~/r~'/D
~/271A _/,/ ,!d-?70 5 4
EXAMINER: /~ .0Ib -Ji.-.... DATE: /O/ / REVIEWER: DATE:___________ OTHER: 'i -Zoe Z5 - ZZVEL: DATE: / STAT::' EVE: -_7_- j,-7 z;- .E: 2- - Page 257
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 199 ULTRASONIC TESTING DATA SHEET MDT-DS-C2A STATION/UNIT: LASALtF /v r Z PAGE: OF PROCEDURE: NDT- if_-30 REV. _- DATA SHEET NO.: -/' ' 3 DAThi ILI 1 CALIBRATION SHEET NO.(S) ST. BEAM: /L.//4 ANGLE BEAM: axial C O6 circ. - COMPONENT INSPECTED SYSTEM: RPV WELD #: LCS- 2-A" WELD TYPE: s5m- FL ,ZPa SIZE: __ -/" THICKNESS/SCHEDULE: 7.'YS MATERIAL: cS COMPONENT TEMPERATURE: 76o_:F ,$6S8B89 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: /VA ANGLE BEAM AXIAL: 4O. o d8 COUPLANT/ I BATCH 0: ULT &AE-.L 7M 1.532S ANGLE BEAM CIRC.: _ 6_o_od_8 EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam x ,/.v
/ \ 2) Angle Beam-Normal-Against Flow -
- 3) Angle Beam-Normal-With Flow VIA
- 4) Angle Beam-Along Weld-CW X x_
- 5) Angle Beam-Along Weld-CCW L 6) Straight Beam of Weld W(IV/A 0
W 7) Thickness Across Weld & Base Metal IVI/A W A'/ UP STRM WELD DN STR ADDITIONAL COMMENTS 5,6A/ G-A1N 5E7-rA1 - To /7A/NvTAIM 1/A/ - 3o,, oe /- .L 0&SEIZVE*yF / D tP sL Arp,,S L3ELo*. REIDI,&A L&"
. PA&rThAL ExAAm1 DuE TO FLAN&E C I67F&N*,AT-i6V E)(~4~.A~~,Ad7,, 27h3,6d-8~
EXAMINER: ILEVEL: *'6 0 - DATE: 1- - 6 REVIEWER: R:4-.* LEVEL:_ _ DATE: __,_________ OTHER: 6Z ' -- _ J" e LEVEL:_ _ DATE: /,ý" ,9. STATION DATE: ____________ [ANII DATE: 2-Z -17? 7 Page 258
COMMONWEALTH EDISON COMPANY Paqe F1 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 199. ULTRASONIC TESTING DATA SHEET NDT-DS-C2A ( STATION/UNIT: LS L.L 1,2 PAGE: .. OF L PROCEDURE: NDT-. C.- REV... DATA SHEET NO.: _ -/__ _ 1AT~k
*O9 CALIBRATION SHEET NO.(S)
ST. B*EAM. A"1/4 ANGLE SEAM: axial -_ -7 circ. C-6)T-7 COMPONENT INSPECTED SYSTEM: APV WELD #: LC/-.-- AE WELD TYPE: .H-L PIP ,oJIZE: THICKNESS/SCHEDULE: H5"/
- MATERIAL: CS COMPONENT TEMPERATURE: L /
S*CA GAIN CONTROL SETTINGS STRAIGHT SEAM: Al--ANGLE. SEAM AXIAL: _________ COUPLANT /__________________ ANGLE BEAM CIRC.: BATCH 1: "LL7TA& -E&I J qii5.*32-4 i-,circ. EXAMINATION SCANS PerfozUd Indications YES NO NO YES
- 1) Base Metal Straight Beam V. /4 .
/ \ 2) Angle Beam-Normal-Against Flow
- 3) Angle Beam-Normal-With Flow .-
- 4) Angle Beam-Along Weld-CW V,
- 5) Angle Beam-Along Weld-CCW F/
L 6) Straight Beam of Weld W7/ 0 W 7) Thickness Across Weld & Base Metal V -./. , UP STRM WELD DN STR ADDITIONAL COMMENTS o*e 4/7"-44pI A 10
- 4 14 1e5 . &
AS'N.cob EXAMINER: <. LEVEL: _______ DATE:_____ REVIEWER: _______________LEVEL: -77r- DATE:_______ OTHER: . .5ivLEVEL:== DATE:/-.~ STT0:,.;2_,,.cý DATE: /a____ LAN I I - DATE: -l-V Page 259
Vessel to Flange Weld, LCS-2-AE. This exam was performed from 180° to 270° to 3600. Due to the configuration of the Flange the following coverage was achieved: d GE NuclearEnergy 0o 45* 60* Exark Adkrea 54.56% 54.56% 54.56% CW C*rc scans 54.56% 54.56% CCWCirc scans 100.0% 100.0% M Down 0.0% 0.0% Ax UV 62.51% 66.35% Base Metal 54.56% 54.32% 55.09% Total Composite Coverage 54.65% I.,
-. FLANGE 450S 6~~6~41 REPORT NO.:
UTILITY REVIEW DATE GE REVIEWED BY LEVEL DATE SMAD REVIEW DATE PAGE: _-_Z O: Page 260,
COMMONWEALTH EDISON COMPANY t.Page 20 of 22 December, Procedure No. NDT-C-30 Rev. 2 199 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: /4Ai~/QPAGE: LJ.OF PRCCEDURE: NDT-C 30 REV. 0- DATA SHEET NO.: _ -- _____A 10__7-_F6 CALIBRATION SHEET NO.(S) ST. BEAM: C-o . AGLE BEAM_ axial ___ /_ circ.__ COP* ONENT INSPECTED SYSTEM: RPV WELD 0: LCS-a"AlIA WELD TYPE: /VZ -5W OOENT T U NESS/SCHEDULE: (0. MA-TERIAL: - 2 COM PONENT TEMPERATURE: p L' ~~ij lSTRAI GHT SCAN GAIN CONTROL SETTINGS BEAM 4? 49.** 0 aw ~AGEBAANGLE XA:_______ BEAM AXIAL: / COUPLANT/ U BATCH #T ULrRA E L IT 9.75 3. ANGLE BEAM CIRC.: i EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam X X
/ 2) Angle Beam-Normal-Against Flow X v//__
- 3) Angle Beam-Normal-With Flow X 14/
- 4) Angle Beam-Along Weld-CW ). _"14_
- 5) Angle Beam-Along Weld-CCW X A L 6) Straight Beam of Weld ,,
0 W 7) Thickness Across Weld & Base Metal X( *.4/A1 /VIA UP STRM WELD DN STR ADDITIONAL COMMENTS SCA NNEO 4 10, ' TO IAINrA'rA &0% 13AC < REFLECTION. NO RECORDABL6E JNDOCATZIONS 0 / LOv&r-GrTDrNAL EXAM:'NER: LEVEL: DATE: L 1- q6 REVIZ;ýER: LEVEL: ___. DATE: / -Z/' 2 OTHER: LEVEL: DATE: //-op,-AW STATi. DATE: -
!ANII :
D)ATE: Page 261
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rov. 2 December, 199: ULTRASONIC TESTING DATA SHEET NDT-DS-C2A + STATION/UNIT: 4 A 5ALLF*L*4)T .Z , PAGE:'+LOF / PROCEDURE: NDT- e-L3_ REV. __ DATA SHEET NO.- b-/74/3 DATfI 1o-7-16 CALIBRATION SHEET NO.(S) ST. BEAM: A), _ ANGLE BEAM: axial __ -- ___ circ. __ -____ COMPONENT INSPECTED SYSTEM: _,V,_ WELD 0: ZCS -. Z/A WELD TYPE: 0V.- Si4
.. P2L4ZE: 2 4.0 THICKNESS/SCHEDULE: i' I.'q MATERIAL: C 5
'+ +.i+';;."+",+ +. COMPONENT TEMPERATURE: 8 1 *88 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: ANGLE BEAM AXIAL: 54. 8f COUPLANT/ BATCH 0: L-T .A -E ZU 75132"5 ,ANGLE BEAM CIRC.: 56-3 J9 EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam >4 _____'_
/ \ 2) Angle Beam-Normal-Against Flow NIA/
- 3) Angle Beam-Normal-With Flow X
- 4) Angle Beam-Along Weld-CW X F 5) Angle Beam-Along Weld-CCW L 6) Straight Beam of Weld < tv1A 0
W 7) Thickness Across Weld & Base Metal 2 / A1/A -I/A UP STRM WELD DN STR ADDITIONAL COMMENTS 5 e*-/AA'ED O1f RE-.L'rsCT5 1o% T*/O IDb oLL. O85ERV9P /IP G-CorMETrRY REI.8o- . AEiZOAAoLE LEEv'L-. 6N F SI~';t Ex44m Pu E To A/ Z.ZL E 014P,C L,4TAM1 u
-SI4FA9 EXAMINER: LEVEL-:22 DATE. O.?'
RVEELEVEL.: L.. DATE: / /~ OTHER :I i
- yl LEVEL: - DATE: /O,-9t*
STATION: DATE: ANII: DATE: Page 262
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 3 December, 199 ULTRASONIC TESTING DATA SHEET NDT-D8-C2A T. STATION/UNIT: L- A4:5A /" /t PAGE: OF - PROCEDURE: NDT- REV. DATA SHEET NO.: (-/)C..(Z_ DAT19 /-7-91 CALIBRATION SHEET NO.(S) ST. BEAM* A_/4 ANGLE BEAM: axial _ -_ _ _ circ. _ _-_O __ COMPONENT INSPECTED SYSTEM: R?)y ELD i: L CS-. 4A' I WELD TYPE: N z$ I, -- PIP2 ,SIZE: Qj THICKNESS/SCHEDULE: ,. MATERIAL: CS COMPONENT TEMPERATURE: jq-SCAN GAIN CONTROL SETTINGS STRAIGHT SEAM: /V/A_ ANGLE OEAN AXIAL: 5,6 COUPLANT/ L BATCH P: LA____________ ANGLE, BEA CIC. ______ EXAMINATION SCANS Performed Indications YEe NO NO YES
- 1) Base Metal Straight Beam X VI/A
/ \ 2) Angle Beam-Normal-Against Flow X dV/A
- 3) Angle Beam-Normal-With Flow x X
- 4) Angle Beam-Along Weld-CW X
- 5) Angle Beam-Along Weld-CCW 'X _
F L 6) Straight Beam of Weld X NA// W 7) Thickness Across Weld & Base Metal X ,I//jA N/A ,V/A UP STRM WELD DN STR ADDITIONAL COMMENTS SCANW&t' CH9 RC-f 6-C /07-703oZ7, .__ 2o0l-4 s~j~D xD &&O"A6TR'B4v to'J 6C0O91:AZL,6LVa, ()N3E !5iD45 6X(AA ILA(- T'0 A/VOtLE--O-.&N,,AA VO(I'J-EXAMINER:
- LEVEL: DATE: /c- 1- flK REVIEWER.*- LEVEL:.= DATE: /o./-.,4 OTR fwo LEVEL.~ DATE: /~7 STATION:1 7ý DATE:_______
PANII: *DATE:______
!/ -
Page 263
OGE Nuclear Energy Typical design for Recirculation (NI) RPV Nozzle Assemblies. REPORT NO.: Due to the configuration of Nozzle N1A, weld number LCS-2-N1A examination coverage is as follows: GE EEDBYPAGL2EVETOF:
- 0. 45* 60° Exam Area 65.42% 65.42% 65.42% CW Circ scans G&1 EVLDT 65.42%
100.0% 65.42% 100.0% CCW Circ scans Ax Down 0.0% 0.0% Ax Up 89.22% 93.40% Base Metal LITILIY REVIEW DATE 65.42% 64.85% 64.01% Total Composite Coverage = 64.76% SMAD REVIEW DATE I HALF SCALE 60 S 45
COMMONWEALTH EDISON COMPANY Page 20 of 2 Procedure No. NDT-C-30 Rev. 2 December, 19 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A ( STATION/UNIT: Z,4SAI~ I A' PAGEVJ OF I PROCEDURE: NDT-eC30 REV. .2 DATA SHEET NO.: tŽ O/DA:P99 CALIBRATION SHEET NO.(S) ST. BEAM- ANGLE BEAM: axial --VA circ. COMPONENT INSPECTED SYSTEM. A'PV wELD -SXwELD WE LC*-.- TYPE: _M!& IZE: 251 THICKNESS/SCHEDULE: ?, q5- MATERIAL: es 'i C I CC COMPONENT TEMPERATURE: _____ 4"C .s- I SCAN GAIN CONTROL SETTINGS STRAIGHT SEAM: *S o wg ANGLE BEAM AXIAL: COUPLANT/ itA61 ,'IT3~ ANGLE BEAM CIRC.. [V4 EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam
\ 2) Angle Beam-Normal-Against Flow 1-"
- 3) Angle Beam-Normal-With Flow I' 4) Angle Beam-Along Weld-CW w / _/_
F 5) Angle Beam-Along Weld-CCW A 1'4 _/_ L 6) Straight Beam of Weld 0 w 7) Thicknes. Across Weld a Base Metal UP STRM WELD DN STR ADDITIONAL COMMENTS 4- .5faMJJD ýOf1J4 A T- ,'WAWAW1J S 11o oK'S1 0A*W f?,69167YdA' 0XhAf1Ar6OW1 I7IED 7DT* P*ef JeUL R/IA) DOE 7TO e~ogv/cuRw4rkwo ,'j mv' Z4o
/WV ,icfcWLOlA6 £tV/06M77WA)
EXAMINER: -44LEVEL.______ DATE: .1o - 9 REVIEWER: LEVEL ______ DATE:___________ OTHER: c*Aý- -.--- ll* LEVEL: *-2Z DATE: //- 0 STATION: $ DATE: ANII:_ DATE:_ *_-__-_7 Page 265
COMMONWEALTH EDISON COMPANY Page 20 of 2: Procedure No. NDT-C-30 Rew. 2 December, 19S . ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: 4A 5ALLE' ON, T - PAGEf'2 / OF / PROCEDURE: NDT 4-30 REV. ;Z DATA SHEET NO.: t 0 DAME /0-4? -96 CALIBRATION SHEET NO.(S) ST. BEAM: //4- ANGLE BEAM: axial C- I *9--" circ. C-'75 COMPONENT INSPECTED SYSTEM: RpV WELD #: LC- 22- IV34 WELD TYPE: /y7E -il "IVIP'*IZE: .- / THICKNESS/SCHEDULE: 7. 1I1- MATERIAL: LS COMPONENT TEMPERATURE:. *nB 0 J56a9 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: _______ ANGLE BEAM AXIAL:.- COUPLANT/ BATCH #t _20A,46-l- 17 9532.f ANGLE BEAM CIRC.: _______ EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam > S/4
/ \ 2) Angle Beam-Normal-Against Flow Il-e
- 3) Angle Beam-Normal-With Flow - <. J
- 4) Angle Beam-Along Weld-CW F S) Angle Beam-Along Weld-CCW K L 6) Straight Beam of Weld A A*__V __
0 W 7) Thickness Across Weld & Base Metal A. /d/M IA/V I /VA UP STEM WELD DN STR ADDITIONAL COMMENTS No Re&ARLE /t'JC)CAfLWAS - CAAl W 5771,V6 MA1zy'A/T/N/p/E 'o-o IV' RoLL 10 6OoI34ETRI 0Z1SERV60 BEL-OL. RE9COPARLE LEVELS 0SHEA'R EXAMINER:
- LEVEL: DATE: i>-96 REVIEWER:_f~______________ LEVEL: -i-- DATE: IC 2'~
OTHER:.cL ,7~t LEVEL: DAkTE: .//- o i"-Af' STATION:( DATE: AN1I: - DATE: _ 2-_ )-j_ 7 Page 266
COMMONWEALTH EDISON COMPANY Page 20 of 2: Prccedure No. NDT-C-30 Rav. 2 December, 1§9 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: __._ALLF / 2 PAGE:: / OF PROCEDURE: NDT-_ REV. DATA SHEET NO.: /2 DATE: CAL:BRAT:ON SHEET NO.(S) ST. BEAM: _ _ _ _ANGLE BEAM: axial _ - _ _ circ. COMPONENT INSPECTED SYSTEM: 19 PV WELD 10: LS-a-. WELD TYPE: AllZ-sH pipi!"9-i -E: 1-57 THICKNESS/SCHEDULE: . MATERIAL: CS COMPONENT TEMPERATURE: &3!LIl.A/. RQ SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: A) ANGLE BEAM AXIAL: la.A COUPLANT/ BATCH 44: aLLTpA& iLT zr ' - ANGLE BEAM CIEC.: EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam , __ __ __ _
/J\ 2) Angle Beam-Normal-Against Flow - i__
- 3) Angle Beam-Normal-With Flow ./V
( 4) Angle Beam-Along Weld-CW -v./
- 5) Angle Beam-Along Weld-CCW L 6) Straight Beam of Weld 0
W 7) Thickness Across Weld & Base Metal 1,' JJ/A J/4 AJ/A UP STRM WELD DN STR ADDITIONAL COMMENTS AIAZ- MAIN'I-A1£ 202F El) ESH XQRopLL.. 1Lo &. O ExhQ ,* AW.z4,~M e EXAM2:NER: -LEVEL: .*-DATE:___________ RE!-WEtLEVEL: 122276 7 DATE:. /0 ,,2 y' OTHER: fe y L.-EP4L: L DATE: 11-0,- 5,4. STAT:.:3,: DATE: ANI 1: ___ DATE: __...? -,97 Page 267
t ; GE NuclearEnergy Typical design for Main Steam ( N3 ) RPV Nozzle Assemblies. REPORT NO.: _L)-.!.... PA.* _, O: I_ Due to the configuration of Nozzle N3D, weld number LCS-2-N3D examination coverage is as follows: 05 45° 60° Exam Area 62.15% 62.15% 62.15% CW Circ scans GE REVIEWED BY 62.15% 62.15% CCW Circ scans LEVEL DATE 100.0% 100.0% Ax Down 0.0% 0.0% Ax Up 84.76% 88.73% Base Metal \\ UTIUTY REVIEW DATE 62.15% 61.81% 62.60% Total Composite Coverage = 62.19% SMAD REVIEW DATE HALF SCALE
COMMONWEALTH EDISON COMPANY . Page 20 of Procedure No. NDT-C-30 Rev. 2 December, lS ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: 24SAL6L / PAGEtK.J10o / PROCEDURE: NDT- -30 REV. _f DATA SHEET NO.: / 97'/ DAT= /7. 9 ': CALIBRATION SHEET NO.(S) ST. BEAM: C-t5~ANGLE BEAM: axial ___14____ circ. COMPONENT INSPECTED A)b Z zzC SYSTEM: 9PV WELD i:Z A'-'
/ 4
.%9WELD TYPE: -_"-_--_____/ _
I 4/T MATERIAL: 7-fl E!SIZE: Y_______ THICKNESS/SCHEDULE: COMPOENT TEMPERATURE: *69*f f w /*64 Sf SCAN GAIN CONTROL SETTINGS STRAIGHT DEAM: 3 J? _.l ANGLE BEAM AXIAL: _________ COUPLANT/ BATCH 1: TEA.5 AG BEAM CIRC.: EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam
/ \ 2) Angle Beam-Normal-Against Flow - __._
- 3) Angle Beam-Normal-With Flow .VXN
- 4) Angle Beam-Along Weld-CW -4/
5.) Angle Beam-Along Weld-CCW A4 L 6) Straight Beam of Weld 0 W 7) Thickness Across Weld & Base Metal UP STEM WELD DN STRt ADDITIONAL COMMENTS SSCANJAJD 4Pt1 6 Aff 7-0 IAAIJAIAN 90% FIN4 13AJC REFl~CflOA1 E*AmI-1A ,,OmLi,-rT"Eo 7Z) QPPER SHELL J?"IA6 DUE" 7-0 eoa)J6uIA7170 6F A16,LE. NJO IZC6ORA61E vOtAToJ EXAMINER: LEVEL: . DATE: /0- 9 ?6 REVIEWER: LEVEL: L DATE: /10,-2 2' OTHER: (f.4 l--"0,4? LEVEL: DATE: Y/-:*4 STATION: 6 DATE:_______ ANII: _______________DATE:-- Z-V)-j 7 Page 269
COMMONWEALTH EDISON COMPANY Page 20 of 2 Procedure No. NDT-C-30 Rev. 2 December, 19 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: tA 54Lzr ON I"- 4 2-- PAGEI'_ OF PROCEDURE: NDT- Cý-3 REV. ;L DATA SHEET NO.: -)- 9 9DAt:6 CALIT
. B "A Io/uz. . zNO. %0) E.- - circ. 0-7 S"-
ST. BEAM, /1/ A- ANGLE SEAM- axial. (f_____
-irc Ce 7 COMPONENT INSPECTED SYSTEM: ApV WELD #. _Z65 AJ3P WELD TYPE: AJ/-L,-
P~SZE ~THICKNESS/SCHEDULEt ~- MATERIAL: CS .COMPONENT TEMPERATURE: / 42 0Z - SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: __________ ANGLE BEAM AXIAL: __________ COUPLANT/ BATCH I: t*-r7,Z -EL I 9532-5 ANGLE BEAM CIRC.: 6b.odg _ EXAMINATION SCANS Performed Indications YES No No YES
- 1) Base Metal Straight Beam IV/A
/ \ 2) Angle Beam-Normal-Against Flow
- 3) Angle Beam-Normal-With Flow NIA
- 4) Angle Beam-Along Weld-CW
- 5) Angle Beam-Along Weld-CCW F
L 6) Straight Beam of Weld 0 W 7) Thickness Across Weld & Base Metal LI //VA I /A 1 'IA UP STRM WELD DN STR ADDITIONAL COMM9ENTS NQ 9CoRt3ABLE X1401CA7-At4v5 - &A/D)SEErrp& 1",41WMINELS /,% 34 )o Ro1L IP ~-wi~gy 08SAFgVfl BJi6o'-'-' AE?&ODA0LC LEVE-LS 9SSHEAR~ EXAMINER: o9 LEVEL: _ DATE: REVIEWER: LEVEL: _ _ DATE: , OTHER: LEVEL: DATE: STATION:, . .. DATE: ...- , .. ... ANII: _ DATE: L 17j, Page 270
COMMONWEALTH EDISON COMPANY Page 20 of 2. Procedure No. NDT-C-30 Rev. 2 December, 19¶ ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: *jALLP E PAGE:ý OF / PROCEDURE: NOT-£-0 REV. _a_ DATA SHEET NO.: />-?/C.. DATE: 10119/& CALSBRAT:ON SHEET NO.(S) ST. BEAM: ___ ____ANGLE BEAM: axial ________ -io ________ CO:4PONENT INSPECTED SYST-=M: RPV WELD 0: LC.S-g 2- pD WELD TYPE: /Z.-SY
~P~~ZE £257 THICKNESS /SCHEDULE: 7 L. MATERIAL-. CS COMPONENT TEMPERATURE:
SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: Al/AN ANGLE BEAM AXIAL: COUPLANT/BEMCC. BATCH #: aLriQ .E ANGLE BEAM CAC.GL EXAMINATION SCANS Performed Indications YES NO no YES
- 1) Base Metal Straight Beam .j */..
/ I\ 2) Angle Beam-Normal-Against Flow -
- 3) Angle Beam-Normal-With Flow
- 4) Angle Beam-Along Weld-CW
- 5) Angle Beam-Along Weld-CCW F
L 6) Straight Beam of Weld W 7) Thickness Across Weld & Base Metal L/ ,g l 4 IX UP STRM WELD DN STR ADDITIONAL COMMENTS
,IRrT- MeIIFtarnwJ-D ip-To aol ;ýHs _rn RL-L-.
17 rb6Q)E e~WP.15R~ ~~S 4/O5,fgQ EXAIA:.ER: i~LEVEL: _______DATE:__________ REVIE-WEIA: LEVEL:.:72 DATE: /~.Z2 OTHER: . J,-, 40
- LEVEL: DATE: . //- I" 95 STAT:0I1: DATE: _ ___-
AM I: _______________ __DATE: - > ? Page 271
GE Nuclear Energy Typical design for Main Steam ( N3 ) RPV Nozzle Assemblies. REPORT NO.: Due to the configuration of Nozzle N3C, weld number LCS-2-N3C examination coverage I) o PAGL-' I OF: is as follows:
- 0. 45. 602 Exam Area 62.15% 62.15% 62.15% CW Circ scans GE REvIEwED BY iEEL DATE 62.15% 62.15% CCW Circ scans 100.0% 100.0% Ax Down 0.0% 0.0% Ax Up 84.76% 88.73% Base Metal
- UTIUTY REVIEW DATE 62A15% 61.81% 62.60%
K Total Composite Coverage = 62.19% SMAD REVIEW DATE HALF SCALE
COIMcL4CWEALTH EDISON COMPANY i.Page 20 of 22 December, Prccedure No. NDT-C-30 Rev. 2 1993 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATZCIN !UNIT: LA ALLZE: UL',7i I IT . PAGE: / OF / PRoc2:U?: NDT-C-30 REV. 2 DATA SHEET NO.: I>- 01/4 DATE:i 10-12-'1 CAL:MRAT:ON SHEET NO.(S) ST. BE:.: (2C
-0? ANGLE BEAM: axial i/( cir=.
COX"O N-a INSPE=cTED sYST-Z: RPV WELD #: IC5-2-147 WELD TYPE: /Vy- -Z 144P!**:::
- 'I Z THICKNESS/SCHEDULE: 3. 2" MATERIAL: r-S COMPO*NT TEMPERATURE:1 "* ] ,s SC.N GAIN CONTROL. SETTINGS STRAIGHT BEAM: 5"7.2 ANGLE BEAM AxIAL: ,1A/A COUPLMJT/5 BATCH________________________ ANGLE BEAM CIRC.: A/IA EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam I
- 2) Angle Beam-Normal-Against Flow p- /4
- 3) Angle Beam-Normal-With Flow
- 4) Angle Beam-Along Weld-CW w
- 5) Angle Beam-Along Weld-CCW ..-
L 6) Straight Beam of Weld 0 W 7) Thickness Across Weld Q Base Mera. T UP STRM WELD DZI STR ADDIT::ONAL COMMENTS S-CA,.j &AI S.L77AIJ MA/,,1J7-AiyFrs Eds AC (ec~7 _z_ _ _17:: DATE: 10-12-1-46
-_7VEL: -LL DATE: /O,/.504y
~~ ~~ DATE:_____
STAT:::6 _________ :ATE: __________ :AT_!: > - Page 273
COMMONWEALTH EDISON COMPANY Page 20 of 2: Procedure No. NDT-C-30 Rev. 2 December, 19. ULTRASONIC TESTING DATA SHEET NDT-DS-C2A f STATION/UNIT: LA -ALL F N uNIT PAGE[I[ / OF PROCztURF-: NOT- C -30 REV. DATA SHEET NO.: 3- .2 / /3 DATt: /p-12.1?6 CALIBRATION SHEET NO.(S) ST. BEAM: __ __ _ANGLE BEAM: axial _ __ _7 circ. Cf-0e,97 COMPONEK2 INSPECTED SYSTEM: iPV WELD #: LCS 2-A/7 WELD TYPE: , e*"S, PTPEr'SIZE: ____ THICKNESS/SCHEDULE: 3,62" MATERIAL: CS COMPONENT TEMPERATURE: jAfF /* <'R7a SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: /V/A ANGLE BEAM AXIAL: .O0 s COUPLANT/_ _ _ -- __- BATCH 0: CA1OTEe_- #1/QS65 ANGLE BEAM CIRC.z: _60._ _ EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam f/A/
V
\ 2) Angle Beam-Normal-Against Flow ,, I.-
- 3) Angle Beam-Normal-With Flow _____ /
- 4) Angle Beam-Along Weld-CW
- 5) Angle Beam-Along Weld-CCW 7' F
L 6) Straight Beam of Weld / fl/A 0 W 7) Thickness Across Weld & Base Metal UP STRM WELD DN STR ADDITIONAL COMMENTS SCAN SF7 I/ 6r, mA /4J 7-A/,,j b- 1o -3,o 5,/, z/- L (0) No ExA,41,A*A-,aV Dy- T-ro AJogRLE Co vF7 4 7gAn,,
/ .,7I-EXA.M INER: LEVEL: DATE: IO-2-'6
_. LEVEL:__________ DATE: /e'/--' ,
. L'_; rý4 0 LEVEL:
- DATE: /_-__- __
SmA-_ON: DATE: 3-7f lqlýl DATE: 3-'?7ia Page 274
COMMONWEALTH EDISON COMPANY Page 20 of 2: Procedure No. KDT-C-30 Rev. 2 December, 19S ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: L.A*ALL L)A Aj PAGE.:. OF / PRocCDtUR: NDT- 30 REV EV. DATA SHEET NO.: b-2 2OI C DAtt: laO 2 - CALIBRATON SHEET NO.(S) ST. BEAM: P/A ANGLE BEAM: axial C-c52? circ. (f_-_ COMPONENT INSPECTED SYSTEM: Spy WELD P: $S -. Al7 WELD TYPE: 514-/ PI:SI ZE: __-5--_ '" THICKNESS/SCHEDULE: 3. 2 MATERIAL: C.5 COMPONENT TEMPERATURE: Zj7z... 0 SCAME GAIN CONTROL SETTINGS STRAIGHT BEAM: /L/ ANGLE BEAM AXIAL:. 6 62 COUPLANT/ BATCH #: 96 P*/l44 ANGLE BEAM CIRC.: EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam V //
/1\ 2) Angle Beam-Normal-Against Flow ,-/
- 3) Angle Beam-Normal-With Flow
- _ _ __/_
- 4) Angle Beam-Along Weld-CW V--
- 5) Angle Beam-Along Weld-CCW V-F L 6) Straight Beam of Weld
- A _/_
0 W 7) Thickness Across Weld & Base Metal , [- - UP STRM WELD DN STR ADDITIONAL COMMENTS SCAM AhV 5=N&.V6 M,41AI-MAJ,!ýp 107,,30'7, RtAOLL
, o
/d EX A*,-1,JA T77 0oJ P V F 7-0 WA Z- 'aZL- 4-'V:,- L-VA77 gA4 EXAMINER: LEVEL: DATE: 0* -/2-96 LEVEL: i DATE: /0', /'-9,'
0LELT____________: L DATE:,i/',9 S_A 0::ýDAE
' DATE: -7 Page 275
OGE NuclearEnergy Typical design for Top Head Nozzle LCS-2-N7 REPORT NO.: Exam coverage is limited due to the nozzle configuration b .... PAGE*IOF:k 0o 45.. 60" Exam Area 62.75% 62.75% 62.75% CW Circ scans 62.75% 62.75% CCW Circ scans 100.0% 100.0% Ax Down GE REVIEWED BY LEVEL DATE 0.0% 0.0% Ax Up 90.20% 94.30% Base Metal 62.76% 63.14% 63.96% WiLJTY REVIEW Total composite coverage for Weld LCS-2-N7 = 63.28% SMAD REVIEW DATE N N' N. 60*:
COMMONWEALTH EDISON COMPANY .:,Page 20 of 22 Rev. 2
""December, 1993 Prccedure No. NDT-C-30 ULTRASONIC TESTING DATA SHEET NDT-DS-C2-SThr:O/N1UNIT: ZA5ALL F UNrIT- * ;L PAGE: : / OF PRCCE0UPi:.NOT-C-30 REV. 2- DATA SHEET NO.: )- z,,g DATit.10-12-q6 sCAL:BRATON SHEET NO.(S). -.
ST. RE.!ýZ: __2___'D___ ANGLE 13EAN4: axial /V 114- circ. CO"APONEN'T INSPECTED SYSTE"X: lqptV WELD 1: I-C5 / - WELD TYPE: /V 7- SH
- 2p.iz"':"T: HC-"
mIcxxEss/SCHEDULE: 3. 2. ()TERIAL: C 5 COMPONENT TEMPERATURE: 7 76 '. _-" 1A A 70 SC.'Ji GAIN CONTROL SETTINGS STR.AIGHT BEAM- 5-7 2-,B ANGLE sEAK AxIAL: ____/4 ____ COUPLANT/ 11*',-,? &-x,. BATCH $4/rpcJ0 4 39S q5_ ANGLE SEAK CIRC.:z 4/ EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam .
/I\ 2) Angle 3eam-Normal-Against Flow _ _/_/_
- 3) Angle Beam-Normal-With Flow , A1/14______
- 4) Angle Beam-Along Weld-CW ____/I__._
- 5) Angle Beam-Along Weld-CC= -
L 6) Straight Beam of Weld 0 W 7) Thickness Across Weld .& Base Metal Al UP STRM WELD DN STR ADDITIONAL COMMENTS A/ O'L SCANJ C-A 114 S 77N& MA /,NT-A//,v1EP Es,-/ 8AC/ct re/Lg nog LEVEL:DAE R 4F:LEVEL:______ DATE: /4) 116-76 c~ 07u~ 1- 7A.: LEVEL:______ DATE: /0 3-? _____________________DATE:_____ L1( <Z ATE:______ Page 277
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 199 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A ( STATION/UNIT: L4 5A4LE- UNiT-r PAGEi / OF / PROCSDUW--: NOT-Cf-3I REV. X DATA SHEET NO.: t)- z 1223 DATE: 0Mg CALIBRATION SHEET NO.(S) ST. BEAM: V/P- ANGLE BEAM: axial _2--_ _ 7-C circ. 27 COMPONENT INSPECTED SYSTEM: RP0v WELD P: I-CS - Z - A/S WELD TYPE: NV? 5-1b E SSI Z Z: o l THICKNESS/SCHEDULE:* 3.6 MATERIAL: C COMPONENT TEMPERATURE: 7 o I/5B7B SCAN GAIN CONTROL SETTINGS
,STRAIGHT BEAM: 1ivA ANGLE BEAM AXIAL: 0. 0 dE COUPLANT/
BATCH #: SON OT // W jg5-r5 ANGLE BFA CIRC.: _ 60_ *_ _ EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam - 7 /
\ 2) Angle Beam-Normal-Against Flow
- 3) Angle Beam-Normal-With Flow i
- 4) Angle Beam-Along Weld-CW 7 ___
- 5) Angle Beam-Along Weld-CCW /V L 6) Straight Beam of Weld 7 4/ _
0 W 7) Thickness Across Weld & Base Metal 1 UP STRM WELD DN STR ADDITIONAL COMMENTS 5cAN &A/AJ sF5 7-/,,Vy IIA1N-T1A1pD /,% - 3o7, /) 90LL (2) /VO EXA&IJA/4ThA7*' DL TO _L - CVltA-77aIi/ EXA I IER: cLEVEL:______ DATE: J~ RVZE LEVEL:; ZL DATE: _______ oT~iE~ ~z: c..4. ~75A--- -ý,v40 LEVEL: ~DT:/-/ OTHER: DATE:. _____ Hf~ DATE: *;j-/7,4) Page 278
COMMONWEALTH EDISON COMPANY Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 199 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A ( STATION/UNIT: A'T-LIALL/- t5'A :2 . PAGE4 / OF PRC&TDuRF: NDT-C-3o REV. ___ DATA SHEET NO.: 1)- 02c C. DAT: qJ-S CALIBRATION SHEET NO.(S) ST. BEAM: _) 1A ANGLE BEAM: axial _ -- ___ circ. C-cD2 COMPONENT INSPECTED SYSTEM: RPV WELD LA'-, -: 3 WELD TYPE: /IV - SkI
" *'S I ZE j- THICKNESS/SCHEDULE: _ 3. " MATERIAL: C-5 COMPONENT TEMPERATURE: 7 " /"78 g
SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: A/A ANGLE BEAM AXIAL:
- 5. 6 dR COUPLANT/
BATCH #= SOAIO7"-CA, ' ANGLE BEAM CIRC.: 65.6dO EXAMINATION SCANS Per for-med -d Indications, YES NO NO YES i1) Base Metal. Straight Beam v _ __..
/ \ 2) Angle Beam-Normal-Against Flow
- 3) Angle Beam-Normal-With Flow (b 7_/_
f 1 4) Angle Beam-Along Weld-CW ' -
- 5) Angle Beam-Along Weld-CCW 7 F
L 6) Straight Beam of Weld A M'/A 0 _ W 7) Thickness Across Weld & Base Metal A UP STRM WELD DN STR ADDITIONAL COMMENTS SCAN &AIA) 5E-Tr,v&- /JA INT7A/NED I0% -30% it) ,OLL AVO ND FXAP4INATA7OA P2VE F-2 A1,0- -a - C.Ae&,6ukATpio,,j I r">, . . LEVEL: ; DATE: JT-, - 9 ii REV: EWEP: LEVEL: _ DATE: /4', 20.?P h OTHER: e., .z j* LEVEL: DATE: /.31-96 _______DATE:__________ DATE:: 3-0E-?_ Page 279
GE NuclearEnergy 0* Typical design for Top Head Nozzle LCS-2-N8 REPORT NO.: Exam coverage is limited due to the nozzle configuration G PAGE_ L
- 0. 45' 60' Exam Area 63.92% 63.92% 63.92% CW Circ scans 63.92% 63.92% CCW Circ scans 100.0% 100.0% Ax Down GE REVIEWED BY LEVELE -- DATE 0.0% 0,0% Ax Up 91.45% 94.86% Base Metal 63.92% 63.86% 64.54%
U~fLrI~Y REVIEW DATE Total composite coverage for Weld LCS-2-N8 = 64.10% R, e vE0 D31-TE SMAD REVIEW DATE 'N 45°S
Page 20 of COMMONWEALTH EDISON COMPANY December, I Procedure No. NDT-C-30 Rev. 2 ( ULTRASONIC TESTINGDATA SET NT-DS-C2A ::- STATION/UNIT: L-AAii/ PAG2ti / oF / PROCEDURE: NDT- L.._. REV. . DATA SHEET NO.: -_o /,.*,- DATE: - - CALIBRATION SHEET NO.(S) ST. BEAM: (~I~ANGLE BEAM: axial _ ______ciro. "VIA-____ COMPONENT INSPECTED "S'T WELD IWELD ,, TYPE:. PIPE SIZE: ý/C THI~CRNSS/ SCHEDULE:x KATERIALz C.5 COMPONENT TEMPERATURE: ~ /~ 2~ SCAN GAIN CONTROL SETTINGS STRAIGHT BEAN: ANGLE BEAM AXIAL. VI COUPLANT/ BATCH 1: tZA &61.2zJr 53 AS ANGLEIBEAK CIRC..: EXAMINATION SCANS Performed Indications yES NO nO YES
- 1) Base Metal Straight Beam X
/1\2) Angle Beam-Normal-Against Flow X NA
- 3) Angle Beam-Normal-With Flow X ,V/A
- 4) Angle Beam-Along Weld-CW_____ ____
5 ) Angle Beam-Along Weld-CCW , 1//A F
*_X_,_ _
L 6) Straight Beam of Weld W 7) Thickness Across Welda SBarn. Metal A' v//- I,,4 IVI A11A UP STRM WELD ON STR ADDITIONAL COMMENTS
/%4 ?erCobA-6L6 ,AJD1CA-rtcp.S Z0OLN&i -r-4 DiN A L EXAMINER* LEVEL: - ~ DATE:___________
REVIEWER:_______________ LEVEL: j2Z7DATE: /C? 2 7e, OTHER: C~~~s----LEVEL:~ DATE:// STATION 6. DATE:__/__, __, C JN, . DATE: III Page 281
COMONWEALTH EDISON COMPANY Page 20 of Procedure No. NDT-C-30 Rev. 2 December, 1 ( ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: *A*L. /~ 2PGi / or PROCEDutE: NDT- 30 REV. - DATA SHEET NO.: 43--21-8 DATE: _.W-,_-96 CALIBRATION SHEET NO/(S) ST. BEAM: t)/4ANGLE BEAM, axial c* ') i.(j/0 7 COMPONENT INSPECTED U;EM: WELD f:i ICS. IA'/e2 WELD TYPE: -PZ__-_5W PIPE SIZE: O THICKNESS/SCHEDULE: ' MATERIAL: CS COMPONENT TEMPERATURE: 7a0?- sN /159-Z-3 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: -VIA_____ ANGLE BEAM AXIAL: (2 ~e' COUPLANT/ BATCH i: UL-"RA(eL tS' ANGLE 1EAH cIRc.: 4 EXAMINATION SCAMS P Performed Indications
'YES NO NO YES
- 1) Base Metal Straight Beam /
/ I\ 2) Angle Beam-Normal-Against Flow
- 7
- 3) Angle Beam-Normal-With Flow _
- 4) Angle Beam-Along Weld-CW F
- 5) Angle Beam-Along Weld-CCW 7 __________
L 6) Straight Beam of Weld ' #/-,__" W 7D Thickness Across Weld & Base Metal UP STFU4 WELD ON STR ADDITIONAL COMMIENTS A-R X - ].Q. GEOA1F'rRV 03SlvF0 BELOW Aee6RD4rLR L-y 0zrVe- e11aeS.rv, 4151 SHvi C 608 L~7~/~9Z~ Ot 'e~i4/ LEVEL: . DATE:_/_______ LEVEL: DATE:___________ LEVEL: DATE: C DATE: ___1_1_5_11pw DATE: 0I_1____ Page 282
COMMONWEALTH EDISON COMPANY Page 20 of 2: Procedure No. NDT-C-30 Rev. 2 December, 19i ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: /A 5VNL-- 4tt/ 2. PAGEf:r / OF / PRCCEDURE: NDT- C-30 REV. 2_- DATA SHEET NO.: - DATE: J 2 ?6 CALIBRATION SHEET NO.(S) ST. BEAM:, /74 ANGLE BEAM: axial C -16 circ. C -/0 COMPONENT INSPECTED SYSTEM: PV WELD #: k COq WELD TYPE: A/I a 5 H ?IPit SIZE:, .0 THICKNESS/SCHEDULE: MTERIAL: MAqq C5 COMPONENT TEMPERATURE: t78 #*16S!723 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: 111, ANGLE BEAM AXIAL: 6 -. isO COUPLANT/ BATCH #: 5R2. ANGLE BEAM CIRC.: EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam v / VIA
/I\ 2) Angle Beam-Normal-Against Flow.
- 3) Angle Beam-Normal-With Flow 111A
- 4) Angle Beam-Along Weld-CW
- 5) Angle Beam-Along Weld-CCW F.
L 6) Straight Beam of Weld ' A// VIA 0 W 7) Thickness Across Weld & Base Metal V/IA A/ A //A UP STRM WELD DN STR ADDITIONAL COMMENTS W TRI - W S,4E .
.4.pGEo/1"E'7_> OSSF.VFZ> 8S4Lo-..j LEVELS SCAN G-A/IA 5.--77(6-s /"IA INT7-A/l£p /O - Zo% ,p ga*1.
~e7 NO A rv ~4F To- 7 z.e- L_ C 0u'-/6 4 /??- 7-/0.t'L)
/ Al.
LEVEL: DATE: /p15-4 REV:E-WER: LEVEL: ______ DATE: _ /0 _2 7_-6 0OTHE?:6'.,9 "- LEVEL: DATE: __-___-f_ DATE:,_____'___ ANl: I_ DATE: r Page 283
'.4 GE Nuclear Energy Typical design for CRD Nozzle LCS-2-N1OA Exam coverage is limited due to the nozzle configuration REPORT NO.:
- 0. 45. 60° Exam Area 16 R BPAGEJ- OF: DAT 70.21% 70.21% CW Circ scans 70,21%
70.21% 70.21% CCW Circ scans 100.0% 100.0% Ax Down 0.0% 0.0% Ax Up GE'REVIEWE6 Eli LEVEL DATE 92.65% 95.96% Base Metal 70.21% 66.61% 67.27% UTILITY REVIEW DATE Total composite coverage for Weld LCS-2-N1 OA = 68.04% _ __REVIEW/ DAT-SMAD REVIEW DATE Half Scale "I t = (.. 60* 450S
COMMONWEALTH EDISON COMPANY , Page December, 20 of 22 Prccedure No. KDT-C-30 Rev. 2 199: ULTRASONIC TESTING DATA SKEET NDT-DS-C2A ( STATION/UNIT: -ASALtg- UL)4/7- *t 27 PAGE:.i / OF PROCEDURE: NDT-C-3_ REV. ;__ DATA SHEET NO.: l- DATtit -- CAL:BRATZON SHEET NO.(S) sT. BE:-%: - ZD , ANGLE BEAM: axial / circ. ._/._- C0*1P0NENT INSPECTED SYST*M: APV WELD #: Los-S2-NI8 WELD TYPE: A/.-S5/
'iii l " *[-- :zz. * "I THICKNESS/SCHEDULE: 3. &2" MATERIAL: Cs COMPOtZEIT TEMPERATURE: 'p : 16 ,5 789 SC:AN GAIN CONTROL SETTINGS STRAIGHT SEAM: 52 2 ds ANGLE S3EM AXIAL: AI/A COUP LANT / A/""" '-
BATCH *: Sewo~htU m~ ANGLE BEAM CIRC.: 14 EXAMINATION SCANS' Performed Indications YES NO NO YES I) Base Metal Straight Beam .
- 2) Angle Beam-Normal-Against Flow 'VIA
- 3) Angle Beam-Normal-With Flow
)e-W
- 4) Angle Beam-Along Weld-CW VIA
- 5) Angle Beam-Along Weld-CC14 /
F L 6) Straight Beam of Weld W 7) Thickness Across Weld & Base Meral UP STRM WELD DN STR ADDITIONAL COl)DENTS 0 0 1-SCA/ C-A11 SE75r//,*6 /1i,A.//'A1N- 8% FSH 0-cAr I",5 c7-o,,. LEVEL: ar . DATE: 10" ---9
.J~. I LEVEL: _217 DATE:____________
LEVEL:-Zý_ DATE:/O39 DATE. /6_________ DATE: <?' Page 285
COMMONWEALTH EDISON COMPANY Page 20 of 2 Procedure No. NDT-C-30 Rev. 2 December, 19 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: L A*ALLE.L I17IPr ;2 PAGEfýi / OF / PROCTDURE" NDT- C-30 REV. ;2- DATA SHEET NO.: _ -_L.___? DATk: jj-j CALIBRATION SHEET NO.(S) ST. BEAM: A)A4 ANGLE BEAM: axial 2- 0 77 circ.- - ý 7 COMPONENT.INSPECTED SYSTEM: RPV WELD #: L*CS -/IV WELD TYPE: /H A
*T1E SIZE: ;5-/ THICKNESS/SCHEDULE: 3. 2 MATERIAL: C_5 COMPONENT TEMPERATURE: '7 A 4 / 58 78 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: l/A ANGLE BEAM AXIAL: k/).p ,04R COUPLANT/ /V BATCH #: 5OAOTT-C H 4 i95AS ANGLE BEAM CIRC.: . od EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam NI/A
- 2) Angle Beam-Normal-Against Flow 7 1
- 3) Angle Beam-Normal-With Flow NA/A
- 4) Angle Beam-Along Weld-CW 77
- 5) Angle Beam-Along Weld-CCW 7 __
F L 6) Straight Beam of Weld , IA% " W 7) Thickness Across Weld & Base Metal 7 I A / UP STRM WELD DN STR ADDITIONAL COMMENTS SCAAu 6-4a1 SE'y-T-tMa- 1AZ/ATA/IAEi 10%" 3,0% Jb IZoLL () O EXAA-iri4AT7A/ DL)E T7 1OZ,?L" C IjJ.fu)ZA.To,, EXAMINER:, LEVEL: ~ DATE: _______ IREV-.EWER: LEVEL: ~t~-DATE: AVI- 4 OTHR: ~ Vc~- LEVEL: DATE: /0 -3 STATIN, i DATE::zf ANI:: ~ gj\ ~ ~ ~ c~ DATE:______ Page 286
COMMONWEALTH EDISON COMPANY - Page 20 of 22 Procedure No. NDT-C-30 Rev. 2 December, 199 ULTRASONIC TESTING DATA SHEET NDT-DS-C2A STATION/UNIT: ,AAr , 2 PAGE i OF -/ PROCEDURE- NOT- C-30 REV. 2- DATA SHEET NO.: 2,2C',3 C DA't: Jp -J, CALIBRATION SHEET NO.(S) ST. BEAM: _ /t___:4 ANGLE BEAM: axial 2 - circ. (-6 ? COMPONENT INSPECTED SYSTEM: Rpy WELD 0: /via WELD TYPE: _/Z -'SH PIPE SIZE: 25- THICKNESS/SCHEDULE: 3.62" MATERIAL: CS5 COMPONENT TEMPERATURE: L- *- IjA.6 79 SCAN GAIN CONTROL SETTINGS STRAIGHT BEAM: _ _} _ _ ANGLE BEAM AXIAL: 153 6 d'6 COUPLANT/ //e t- i BATCH #: $(Q T7--_H
- l9f*"4 ANGLE BEAM CIRC.t (95 dB EXAMINATION SCANS Performed Indications YES NO NO YES
- 1) Base Metal Straight Beam 7 /
/ \ 2) Angle Beam-Normal-Against Flow
- 3) Angle Beam-Normal-With Flow V IA 4), Angle Beam-Along Weld-CW
- 5) Angle Beam-Along Weld-CCW F
L 6) Straight Beam of Weld - / W 7) Thickness Across Weld & Base Metal e- AIi'-* j --- UP STRM WELD DN STR ADDITIONAL COMMENTS
... /yeq/ 6O" AFAA SC-AA &-AJIN SEi7AJII6- M /114A/14,6~P %30 ico (V IVO EXAMtI/,NAT7AI DUET-0 AIO2-Lr7- CoN/76-v9qE-T/AI EXA.MINER: ,-.6 g ,1 LEVEL: ~ DATE: j-p2g/
REVIEWER: LEVEL: . DATE: /_. /_'____ OTHER: JI"..D7 LEVEL:, DATE: /e'-3 STATION:-6 DATE:~ ~ ANII: 1AA-~--.DATE: . 2r Page 287
- GE Nuclear Energy Typical design for Top Head Nozzle LCS-2-N 18 Exam coverage is limited due to the nozzle configuration REPORT NO.:
- 0. 45° 60° Exam Area 62.75% 62.75% 62.75% CW Circ scans 62.75% 62.75% CCW Circ scans 100.0% 100.0% Ax Down
/0, /, - '9 GE REVIEWED BY LEVEL DATE 0.0% 0.0% Ax Up 90.20% 94.30% Base Metal 62.75% 63.14% 63.96%
UTIUTY REVIEW DATE Total composite coverage for Weld LCS-2-N1 8 = 63.28% SMAD REVIEW DATE 6(
EXAMINATION
SUMMARY
SHEET Report No: 2118-0011 GE NUCLEAR ENERGY LaSalle Unit 2 L2R08 LCS-2-N1B 21.0039 N-SH RPV B-D Component ID: Line ID.. Configuration: System: ASME Cat.: Examination Cert Exam Exams Data Cal Procedure Calibration Personnel Level Completed Performed Sheet Sheet Revision Block Paul Hayes if 11/15/00 0°L D-070 D-070 UT-DRD-300V3 R.1 01-92-01 Credit 450S D-071 D-071 UT-DRD-300V3 R.P- 01-92-01 60 0S D-072 D-072 UT-DRD-30OV3 R.1 01-92-01 Section X! Examination Results: Manual ultrasonic examination results were acceptable to the requirements of ASME Section Xl, 1989 Edition, No Addenda and Regulatory Guide 1.150. Examinations were performed from the vessel wall with 00, 450 and 600 search units. The angle beam examinations were performed transverse and parallel to the weld. No recordable indications were detected. 60.4% coverage of the examination volume was obtained. Examination results were comparedto data report 303,306,309 from L2R02 outage with X No Change These examinations were performed under Work Order: N/A Change This Summary and the following data sheets have been reviewed and acceptedby thefollowing personnel: RWP: 2221
-* "/Y/,, .i. /Dose: 80 mr.
GE Reviewed By: Level: Date: Station Reviewed By:
Title:
Date: Reviewed By: Level: Date: ANII Reewed By:
Title:
Date: Page_ 1 of 7 Page 289
LA Salle Unit 2 NI Nozzle CROSS SECTIONAL AREA (per slice) TOTAL CODE COVERAGE code cross area area % of code area % of code area degrees degrees percent percent sectional scanned scanned scanned scanned scanned scanned scanned scanned area automated manually automated manually automated manually automated manually 00 wm 60.1 0.0 25.5 0.0 42.4 0.0 360.0 0.0 424 45' T-scan. 60.1 0-0 44.4 0.0 73.9 0.0 360.0 0.0 73.9 60' T-scan 60.1 0.0 48.9 0.0 81.4 0.0 360.0 0.0 81.4 45' P-scan CW 60.1 0.0 31.2 0.0 51.9 0.0 360.0 0.0 51.9 60* P-scan CW 60.1 0.0 36.5 0.0 60.7 0.0 360.0 0.0 60.7 45° P-scan CCW 60.1 0.0 31.2 0.0 51.9 0.0 360.0 0.0 51.9 60' P-scan CCW 60.1 0.0 36.5 0.0 60.7 0.0 360.0 0.0 60.7 0.0 60.4 Manual scans were not restricted, No credit taken for initial 1/4" of material in Code coverage calculations due to near field effects, Total Composite Coverage = 60.4%
'zv2- R ?C A19',',ý- _!r Y 7
///el-/
L2Zl~ c' 474
Lasalle 2 Recirculation Outlet N1 Nozzle 0* L-wave weld metal, 45* and 60C T-scan coverage 600 45*T~ e-.
Lasalle 2 Recirculation Outlet N1 Nozzle 45* and 60° P-scan coverage CD CD N) 60T 45
/j2e 7 AP9- z
EXAMINATION
SUMMARY
SHEET Repor No: GE NUCLEAR ENERGY LaSalle Unit 2 L2R08 2RS-002 LCS-2-N6A 21.0061 N-SH RPV B-D Component ID: Line ID: Configuration: System: ASME Cat.: Examination Cert Exam Exams Data Cal Procedure Calibration Personnel Level Completed Performed Sheet Sheet Revision Block Paul Hayes H1 11/16/00 00L D-096 D-096 UT-DRD-300V3 R.1 01-92-01 Credit 450S D-097 D-097 UT-DRD-30OV3 R.1 01-92-01 600S D-0" D-098 UT-DRD-300V3 R.A 01-92-01 Section XI Examination Results: Manual ultrasonic examination results were acceptable to the requirements of ASME Section XI, 1989 Edition, No Addenda and Regulatory Guide 1.150. Examinations were performed from the vessel wall with 00, 45* and 60* search units. The angle beam examinations were performed transverse and parallel to the weld. No recordable indications were detected. 68.4% coverage of the examination volume was obtained. Examination results were comparedto data report D457 from L2R03 outage with X No Change These examinations were performed under Work Order: 990139382 N/A Change This Summary and the following data sheets have been reviewed and accepted by the following personnel:' RW:: 2221
.__1____ Dose: 240 mr.
GE Reviewed By: Level: Date: Station Reviewed By:
Title:
Date: Reviewed By: Level: Date: ANll R&ewed By:
Title:
Date: Page _1 of 7 Page 293
La Sate Unit2 N6 Nozzle CROSS SECTIONAL AREA (per slice) TOTAL CODE COVERAGE code cross area area % of code area % of code area degrees degrees percent percent sectional scanned scanned scanned scanned scanned scanned scanned scanned area automated manually automated manually automated manually automated manually 0* wm 58.7 0.0 30.1 0.0 51.3 0.0 360.0 0.0 51.3 45' T-scan 58.7 0.0 47.5 0.0 80.9 0.0 360.0 0.0 80.9 60* T-scan 51.7 0.0 50.5 0.0 86.0 0.0 360.0 0.0 86.0 45" P-scan CW 58.7 0.0 34.8 0.0 59.3 0.0 360.0 0.0 59.3 60' P-scan CW 58.7 0.0 41.6 0.0 70.9 0.0 360.0 0.0 70.9 45* P-scan CCW 58.7 0.0 34.8 0.0 59.3 0.0 360.0 0.0 59.3 60" P-scan CCW 58.7 0.0 41.6 0.0 70.9 0.0 360.0 0,0 70.9 0.0 68.4 Manual scans were not restricted. No credit taken for initial 1/4" of material in Code coverage calculations due to near field effects. Total Composite Coverage = 68.4% Ry -'-C - 4t.J. 4.&t~- '0* x- i
Lasalle 2 LPCI N6 Nozzle (r L-wave weld metal, 45" and 60 T-scan coverage 60T 7./ /
Lasalle 2 LPCI N6 Nozzle IQ 45" and 60r P-scan coverage
/e4 L70,
Report No: EXAMINATION
SUMMARY
SHEET GENUCLEAR ENERGY LaSalle Unit 2 L2R08 2RS-003 LCS-2-N6C 21.0063 N-SH RPV B-D Component ID: Line ID: Configuration: System: ASME Cat: Examination Cert Exam Exams Data Cal Procedure Calibration Personnel Level Completed Performed Sheet Sheet Revision Block Jason Breza !! 11/17/00 00 L D-093 D-093 UT-DRD-300V3 R.1 01-92-01 II Credit 4500S D-094 D-094 UT-DRD-300V3 R.1 01-92-01 Credit 60 S D-095 D-095 UT-DRD-300V3 R.1 01-92-01 Section XI Examination Results: Manual ultrasonic examination results were acceptable to the requirements of ASME Section X1, 1989 Edition, No Addenda and Regulatory Guide 1.150. Examinations were performed from the vessel wall with 00, 450 and 600 search units. The angle beam examinations were performed transverse and parallel to the weld. No recordable indications were detected. 68.4% coverage of the examination volume was obtained. Examination results were compared to data report D454 from L2R03 outage with X No Change These examinations were performed under Work Order: 990139382 N/A Change This Summary and thefollowing datasheets have been revienwed and accepted by thefollowingpersonnel: RWP: 2221 Ix -- S,,A*_6 Dose: 300 mr. GE Reviewed By: Level: Date: Station Reviewed By:
Title:
Date: Reviewed By: Level: Date: AN1I Re wed By:
Title:
Date: Page I of Pager297
La Salle Unit 2 N6 Nozzle CROSS SECTIONAL AREA (per slice) TOTAL CODE COVERAGE code cross area area % of code area % of code area degrees degrees percent percent sectional scanned scanned scanned scanned scanned scanned scanned scanned area automated manually automated manually automated manually automated manually 0, wm 58.7 0.0 30.1 0.0 51.3 0,0 360.0 0.0 51.3 45° T-scan 58.7 0.0 47.5 0.0 80.9 0.0 360.0 0,0 80.9 60' T-scan 58.7 0.0 50.5 0.0 86.0 0.0 360.0 0.0 86.0 45' P-scan CW 58.7 0.0 34.8 0.0 59.3 0.0 360.0 0.0 59.3 60" P-scan CW 58.7 0.0 41.6 0.0 70.9 0.0 360.0 0.0 70.9 45* P-scan CCW 58.7 0.0 34.8 0.0 59.3 0.0 360.0 0.0 59.3 600 P-scan CCW 58 7 0.0 41.6 0.0 70.9 0.0 360.0 0.0 70.9 0.0 68.4 Manual scans were not restricted. No credit taken for initial 114" of material in Code coverage calculations due to near field effects. Total Composite Coverage - 68.4%
~pg- 1 2Q3 7e-6<A~
IZ4W /LZcL 11-;Z3~ f-vz
Lasalle 2
.LPCI N6 Nozzle 0" L-wave weld metal, 45" and 60" T-scan coverage C.0 Q0
*-' ad-6.4* 3/4/L
Lasalle 2 LPCI N6 Nozzle. 45' and 60r P-scan coverage CD 0 45)
/~;ye 00
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 2R9-012 WO No: 430431 PROJECT LaSalle Unit 2 WELD ID: LCS-2-N4A SYSTEM: RPV N4A N-SH INITIAL CALIBRATION ID: NOZ.N, NOZ.70.IN FINAL CALIBRATION ID: NOZ.OUT, NOZ.70.OUT GERIS DATA: n4a.70.1, n4a.tl.1, n4atl.2, n4a.pl.1, n4a.p2.1
-.M;,ANUAL:oDAA:'_ N/A OPERATORS: M. Hilbom Lv II; L. Benicki Lv II; CE Frakes Lv II; J.Guillote Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section Xl, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II,Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds.
Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V2, using 45* Shear wave, 600 RL, and 70* RL search units, 0° L-Wave supplemental scans were also performed. Automated scanning was performed from the nozzle OD surface, 360° around the nozzle, with no restrictions. For initial calibrations refer to report G2K-CAL-1. For final calibrations refer to report G2K-CAL-3. The GERIS 2000 OD automated UT system 0° reference is located at 900 CW of nozzle TDC. The GERIS 2000 OD system recorded no indications. 45° S I T-scan, No recordable indications. 60' RL / T-scan, No recordable indications. 45° S I P1-scan, No recordable indications. 450 S I P2-scan, No recordable indications. 70° RL / T-scan, No recordable indications. 700 RL I P-ccw No recordable indications. 70° RL / P-cw No recordable indications. Automated Composite Coverage = 78.1%. I I I LaSalle Unit-2, 2RO9 Page I ofII Page 301
SRimary No.: 2R9-012 LaSalle Unit-2 Weld LCS-2-N4A Spring 2003 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE' Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59. Area Sq. In. Auto Auto Auto Auto 70° T-Scan A 11.4 5.6 9.5% 360 4.7% 45° T-Scan A 39.1 33.5 56.8% 360 28.4% 60° T-Scan A 8.5 8.5 14.4% 360 7.2% 70° P-Scan A 11.4 4.9 8.3% 360 4.2% 450 P-Scan A 39.1 31.2 52.9% 360 26.4% IRS P-Scan A 8.5 8.5 14.4% 360 7,2% 70° T-Scan 450 T-Scan 600 T-Scan 70' P-Scan 450 P-Scan IRS P-Scan _, __ 70* T-Scan 450 T-Scan 60* T-Scan _ 70_P-Scan 450 P-Scan IRS P-Scan_
% Total Composite Coverage = 78.1%
Comments: A - Examined 3600. Scanning limited due to nozzle configuration. Note - Rounding methods may make calculated values appear in error. LaSalle Unit-2, 2RO9 Page __ of I
LaSalle Unit-2 Feedwater 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS &60°T) = 8.5 Sq. In. 70° T-Scan achieved = 5.6 Sq. In. 45° T-Scan achieved = 33.5 Sq. In. 600 T-Scan achieved = 8.5 Sq. In. 70"T 457 f I I I j-. 7-
LaSalle Unit-2 Feedwater 70° Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 70° P-Scan achieved = 4.9 Sq. In. 45° P-Scan achieved = 31.2 Sq. In. IRS P-Scan achieved = 8.5 Sq. In.
/ I 710P 45'P I IRS I I 7-C) I----. ) r.1 I
I
LaSalle 2 G.- .L6-JG1.xls GOD-SL6E LaSalle 2 NOZZLE EXAMINATION PLAN 1/21/2003 Feedwater GERIS-2000 NOZZLE-TO-VESSEL SCANNING LIMITS NOZOD 26.25 VSLIR 126.69 WALL 6.44 iJ WELD RAD 17.25 ODBR 3.56 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH ANGLE TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 1 0.00 W 3.66 0.00 0.00 0.80 0.317 0.150 0 18.97 88 54 - 2 45.00 T 13.26 3.00 0.00 0.8" 0.411 0.150 0 13.12 235 - - 7.33 -7.3 3 60.0" T 14.15 -3.00 0.00 0.8° 0.490 0.150 0 18.97 185 - 353.9' 6.10 4/6 45.Q0 P1 13.26 3.00 0.00 0,8" 0.336 0.150 0 10.00 235 -
- 298.00 62.00 :(cw) 5/7 45.0' P1 13.26 -3.00 0.00 0.8* 0.336 0.150 0 10.00 235 - 62.00 -62.0' (cw) 416 45.0° P2 13.26 3.00 0.00 0.8 " 0.336 0.150 0 10.00 235 - 321.30 38.70 (ccw) 5/7 45.0° P2 13.26 -3.00 0.00 0.80 0.336 0.150 0 10.00 235 - 38.7' -36.70 (cw) 1 70.00 T 12.00 0.00 0.00 0.80 0.380 0.150 0 10.87 52 - 0.00 0-0° 2 70.0' P 12.00 3.00 0.00 0.8" 0.313 0.150 0 6.25 52 - 287.20 72V80 (ccw) 3 70.0' P. 12.00 -3.00 0.00 0.80 0.313 0.150 0 6.25 52 72.8' -72.8° (cw) 1 49.00 ZIR 17.48 2.50 0.00 1.70 0,500 0.070 60 90 395 - 335.5' 24.5' (ccw) 2 49.00 ZiR 17.48 -2.50 0.00 1.7° 0.500 0.070 60 90 395 - 24.5' -24.5' (cw) 1 68.00 Z2A 17.28 2.50 0.00 1.70 0.500 0.070 50 90 281 - 348.40 11.6° (ccw) 2 68.00 Z2A 17.28 -2.50 0.00 1.70 0.500 0.070 50 90 281 - 11.60 -11.60 (cw) 2 30.00 Z2B 17.28 2.50 0.00 1.50 0.354 0.070 - - 237 - 300.0° 60.00 (cw) 1 30.00 Z2B 17.28 -2.50 0.00 1.50 0.354 0.070 - 237 - 60.0' -60.00 (ccw) 2 20.0' Z3 17.28 2.50 0.00 1.50 0.354 0.070 - 188 - 270.00 90.00 (cw) 1 20.00 Z3 17.28 -2.50 0.00 1.50 0.354 0.070 188 90.0° -90.00 (ccw) rn 1129/2003
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 2R9-013 WO No: 430431 PROJECT LaSalle Unit 2 WELD ID: LCS-2-N4B SYSTEM: RPV N4B N-SH INITIAL CALIBRATION ID: NOZ.IN, NOZ.70.IN FINAL CALIBRATION ID: NOZ.OUT, NOZ.70.OUT GERIS DATA: n4b.tl.1, n4b.pl.1, n4b.p2.1, n4b.70.1, n4b.70.2 ".,MANUAL DATY&- N/A OPERATORS: M. Hilborn Lv II; L. Benicki Lv II; CE Frakes Lv II; J.Guillote Lv ii Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V2, using 45' Shear wave, 60* RIL, and 70* RIL search units, 0° L-Wave supplemental scans were also performed. Automated scanning was performed from the nozzle OD surface, 360* around the nozzle, with no restrictions. For initial calibrations refer to report G2K-CAL-1. For final calibrations refer to report G2K-CAL-3. The GERIS 2000 OD automated UT system 0° reference is located at 90' CW of nozzle TDC. The GERIS 2000 OD system recorded no indications. 45' S / T-scan, No recordable indications. 60* RL I T-scan, No recordable indications. 45* S / P1-scan, No recordable Indications. 45* S / P2-scan, No recordable indications. 70* RL / T-scan, No recordable indications. 70' RL / P-ccw No recordable indications. 70' RL / P-cw No recordable indications. Automated Composite Coverage = 78.1%.
ýjll LaSalle Unit-2, 2R09 0__ .4-, a Page 306
Siprnlmary No.: ZKU-U13 LaSalle Unit-2 Weld LCS-2-N4B1 Spring 2003 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59. Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 11.4 5.6 9.5% 360 4.7% 450 T-Scan A 39.2 33.5 56.8% 360 28.4% 60° T-Scan A 8.5 8.5 14.4% 360 7.2% 700 P-Scan A 11.4 4.9 8.3% 360 4.2% 45° P-Scan A 39.2 31.2 52.9% 360 26.4% IRS P-Scan A 8.5 8.5 14.4% 360 7.2% 708 T-Scan 450 T-Scan 600 T-Scan 700 P-Scan 45° P-Scan IRS P-Scan 730 T-Scan 450 T-Scan 60* T-Scan ..... 700 P-Scan ......... .. 450 P-Scan IRS P-Scan
% Total Composite Coverage = 78.1%
Comments: A - Examined 3600. Scanning limited due to nozzle configuration. Note - Rounding methods may make calculated values appear in error. LaSalle Unit-2, 2RO9 Paqe 3 ,f
4; LaSalle Unit-2 Feedwater 70* Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60*T) 8.5 Sq. In. 70° T-Scan achieved = 5.6 Sq. In. 458 T-Scan achieved = 33.5 Sq. In. 60° T-Scan achieved = 8.5 Sq. In.
/
$Ua I
LaSalle Unit-2 Feedwater 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 70° P-Scan achieved = 4.9 Sq. In. 450 P-Scan achieved = 31.2 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. r--
/ 70*P I
45P I (RS I 7. I--- t"13 ) I
LaSalle 2 G(- .L6-JG1.xls GOD-SL6E LaSalle 2 NOZZLE EXAMINATION PLAN 1/21/2003 Feedwater GERIS-2000 NOZZLE.TO-VESSEL SCANNING LIMITS NOZOD 26.25 VSLIR 126.69 WALL 6.44 WELD RAD 17.25 ODBR 3.56 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH ANGLE TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 1 0.0° W 3.66 0.00 0.00 0.80 0.317 0.150 0 18.97 88 54 - 2 45.00 T 13.26 3.00 0.00 0.8* 0.411 0.150 0* 13.12 235 - 7.3' -7.37 3 60.06 T 14.15 -3.00 0.00 0.8° 0.490 0.150 0 18.97 185 353.90 6.1 4/6 45.0' P1 13.26 3.00 0.00 0.8" 0.336 0.150 0 10.00 235 298.00 62.00 (ccw) 5/7 45.0' P1 13.26 -3.00 0.00 0.8* 0.336 0.150 0 10.00 235 62.0' -62.00 (cw) 4/6 45.00 P2 13.26 3.00 0.00 0.80 0.336 0.150 0 10.00 235 321.3° 38.7" (ccw) 517 45.00 P2 13.26 -3.00 0.00 0.80 0.336 0.150 0 10.00 235 38.7* -38.7* (ow) 1 70.00 T 12.00 0.00 0.00 0.8° 0.380 0.150 0 10.87 52 - 0.00 0.00 2 70.0° P 12.00 3.00 0.00 0.8° 0.313 0.150 0 6.25 52 287.2' 72.80 (ccw) 3 70.0" P 12.00 -3.00 0.00 0.8° 0.313 0.150 0 6.25 52 72.80 -72.8° (cw) 1 49.00 ZIR 17.48 2.50 0.00 1.70 0.500 0.070 60 .90 395 - 335.5' 24.5° (ccw) 2 49.0° Z1R 17.48 -2.50 0.00 1.7" 0.500 0.070 60 90 395 24.50 -24.5' (cw) 1 68.0* Z2A 17.28 2.50 0.00 1.7" 0.500 0.070 50 90 281 - 348.4' 11.60 (ccw) 2 68.0° Z2A 17.28 -2.50 0.00 1.7° 0.500 0,070 50 90 281 - 11.60 -11.60 (cw) 2 30.00 Z2B 17.28 2.50 0.00 1.5° 0.354 0.070 - 237 - 300.0' 60.00 (cw) 1 30.00 Z2B 17.28 -2.50 0.00 1.5" 0.354 0.070 - 237 60.00 -60.00 (ccw) 2 20.00 Z3 17.28 2.50 0.00 1.5* 0.354 0.070 - 188 - 270.00 90.00 (cw) 1 20.00 Z3 17.28 -2.50 0.00 1.50 0.354 0.070 - 188 - 90.00 -90.0" (ccw) a U-U- 1/29/2003
- GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 2R9-014 WO No: 430431 PROJECT LaSalle Unit 2 WELD ID: LCS-2-N4C SYSTEM: RPV N4C N-SH INITIAL CALIBRATION ID: NOZIN, NOZ.70.1N FINAL CALIBRATION ID: NOZ.OUT, NOZ.70.OUT GERIS DATA: n4c.ti.1, n4c.tl.3, n4c.pl.1, n4c.p2.1, n4c.p2.2, n4c.70.1
-MANUA4 £1A.TAX N/A OPERATORS: M. Hilborn Lv II; L. Benicki Lv II; CE Frakes Lv II; J.Guillote Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds Automated transverse and parallel scans were performed In accordance with procedure GE-UT-705 V2, using 450 Shear wave, 600 RL, and 700 RL search units, 00 L-Wave supplemental scans were also performed.
Automated scanning was performed from the nozzle 00 surface, 3600 around the nozzle, with no restrictions. For initial calibrations refer to report G2K-CAL-1. For final calibrations refer to report G2K-CAL-3. The GERIS 2000 OD automated UT system 00 reference is located at 90° CW of nozzle TDC. The GERIS 2000 OD system recorded no indications. 450 S / T-scan, No recordable indications. 600 RL / T-scan, No recordable indications. 450 S / P1-scan, No recordable indications. 450 S / P2-scan, No recordable Indications, 700 RL / T-scan, No recordable indications. 700 RL / P-ccw No recordable Indications. 700 RL / P-cw No recordable indications. Automated Composite Coverage = 78.1%. i HI I LaSalle Unit-2, 2RO9 -'_- . 0 Page 311
Summary No.: 2R9-014 LaSalle Unit-2 Weld LCS-2-N4C Spring 2003 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGEr Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59. Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 11.4 5.6 9.5% 360 4.7% 450 T-Scan A 39.2 33.5 56.8% 360 28.4% 60° T-Scan A 8.5 8.5 14.4% 360 7.2% 70° P-Scan A 11.4 4.9 8.3% 360 4.2% 45' P-Scan A 39.2 31.2 52.9% 360 26.4% IRS P-Scan A 8.5 8.5 14.4% 360 7.2% 70° T-Scan 450 T-Scan 600 T-Scan 70° P-Scan 450 P-Scan IRS P-Scan 70° T-Scan 450 T-Scan 60_ T-Scan " 700 P-Scan 45' P-Scan IRS P-Scan 70-6 otat Composiie Coverage = 785.1o Comments: A - Examined 360*. Scanning limited due to nozzle configuration. Note - Rounding methods may make calculated values appear in error. LaSalle Unit-2, 2RO9 Page 3 , of q
LaSalle Unit-2 Feedwater 70" Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 600T) = 8.5 Sq. In. 70° T-Scan achieved = 5.6 Sq. In. 45° T-Scan achieved = 33.5 Sq. In. 60° T-Scan achieved = 8.5 Sq. In. W0r 45T 6o' A-
LaSalle Unit-2 Feedwater 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS &60-T) = 8.5 Sq. In. 70° P-Scan achieved = 4.9 Sq. In. 450 P-Scan achieved = 31.2 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. I I 70'P 46*P I MR I I/ / I-" m
LaSalle 2 GC. L6-JG1 ;xis GOD-SL6E LaSaile 2 NOZZLE EXAMINATION PLAN 112112003 Feedwater GERIS-2000 NOZZLE-TO.VESSEL SCANNING LIMITS NOZOD 26.25 VSLIR 126.69 WALL 6.44 WELD RAD 17.25 ODBR 3.56 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH ANGLE TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 1 0.00 W 3.66 0.00 0.00 0.80 0.317 0.150 0 18.97 88 54 - 2 45.0' T 13.26 3.00 0.00 0.80 0.411 0.150 0 13.12 235 - 7.3' -7.3' 3 60.00 T 14.15 -3100 0.00 0.8° 0.490 0.150 0 18.97 185 - 353.90 6.1° 4/6 45.00 P1 13.26 3.00 0.00 0.80 0.336 0.150 0 10.00 235 - - 298.0° 62.0" (ccw) 517 45.0* P1 13.26 -3.00 0.00 0.8° 0.336 0.150 0 10.00 235 - 62.00
- -62.0 (cw) 416 45.0' P2 13.26 3.00 0.00 0.80 0.336 0.150 0 10.00 235 - - 321.3' 38.7* (ccw)
'1 5/7 45.0" P2 13.26 -3.00 0.00 0.80 0.336 0.150 0 10.00 235 - 38.70
- -38.70 (cw) 1 70.0" T 12.00 0.00 0.00 0.80 0.380 0.150 0 10.87 52 0.00
-- 0.00 2 70.0" P 12.00 3.00 0.00 0.8° 0.313 0.150 0 6.25 52 - 287.2' 72.8 {(ccw) 3 70.0* P 12.00 -3.00 0.00 0.8° 0.313 0.150 0 6.25 52 - 72,80 -72.80 (cw) 1 49.00 Z1R 17.48 2.50 0.00 1.7' 0.500 0.070 60 90 395 335.50 24.5* (cCw) 2 49.00 ZIR 17.48 -2.50 0.00 1.70 0.500 0.070 60 90 395 24.5' -24.5* (cw) 1 68.0' Z2A 17.28 2.50 0.00 1.7' 0.500 0.070 50 90 281 348.4 11.6 (ccw) 2 68.0' Z2A 17.28 -2.50 0.00 1.7° 0.500 0.070 50 90 281 11.60 -11.60 (cw) 2 30.0' Z28 17.28 2.50 0.00 1.5° 0.354 0.070 - - 237. " 300.00 60.00 (cw) 1 30.0' Z2B 17.28 -2.50 0.00 1.50 0.354 0.070 237 60.00 -60.0* (ccw) 2 20.0* Z3 17.28 2.50 0.00 1.50 0.354 0.070 188 270.00 90.0 (cw) 1 20.0' Z3 17.28 -2.50 0.00 1.5" 0.354 0.070 188 90.00 -90.00 (ccw) 0-i m
1129/2003
*,. GE NUCLEAR ENERGY W UT EXAMINATION
SUMMARY
SHEET Summary No: 2R9-015 WO No: 430431 PROJECT LaSalle Unit 2 WELD ID: LCS-2-N4D SYSTEM: RPV N4D N-SH INITIAL CALIBRATION ID: NOZ.IN, NOZ.70.IN FINAL CALIBRATION ID: NOZ.OUT, NOZ.70.OUT GERIS DATA: n4d.tl.1, n4d.70.1, n4d.70.2, n4d.pl.1, n4d.pl.2, n4d.p2.1
, MANUAL D.A'TA: N/A OPERATORS: M. Hilborn Lv II; L. Benicki Lv II; CE Frakes Lv. II; J.Guillote Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section Xl, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II,Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V2, using 45° Shear wave, 60° RL, and 70° RL search units, 0° L-Wave supplemental scans were also performed.
Automated scanning was performed from the nozzle OD surface, 3600 around the nozzle, with no restrictions. For initial calibrations refer to report G2K-CAL-1. For final calibrations refer to report G2K-CAL-3. The GERIS 2000 OD automated UT system 0° reference is located at 900 CW of nozzle TDC. The GERIS 2000 OD system recorded ten (10) indications. 45' S / T-scan, One (1) acceptable indication. 60' RL / T-scan, No recordable indications. 450 S / P1-scan, Four (4) acceptable Indications. 45° S / P2-scan, Four (4) acceptable indications. 70° RL / T-scan, One (1) acceptable indication. 70° RL / P-ccw No recordable indications. 70* RL / P-cw No recordable indications. The indications recorded above have no determinable through wall dimension and are acceptable to the requirements of IWB-3000. Automated Composite Coverage = 78.1% P,,YEPARED BY DATE REVIEWED BY DATE LI EVDE ANl REVIEW DATE UTLeaeI:rt-2 O9 137_v7_ l7 jP*f3 '"z_ LaSalle Unit-2, 2R09 D n 4rpan^ E i etf '7-4
Summary No.: 2R9-015 LaSalle Unit-2 Weld LCS-2-N4D Spring 2003 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59. Area Sq. In. Auto Auto Auto Auto 70* T-Scan A 11.4 5.6 9.5% 360 4.7% 450 T-Scan A 39.2 33.5 56.8% 360 28.4% 60° T-Scan A 8.5 8.5 14.4% 360 7.2% 70' P-Scan A 11.4 4.9 8.3% 360 4.2% 450 P-Scan A 39.2 31.2 52.9% 360 26.4% IRS P-Scan A 8.5 8.5 14.4% 360 7.2% 70* T-Scan 450 T-Scan 600 T-Scan 70' P-Scan 450 P-Scan IRS P-Scan 70° T-Scan 450 T-Scan 60' T-Scan " 70_P-Scan 450 P-Scan IRS P-Scan Total Composite Coverage = 78.1% Comments: A - Examined 3600. Scanning limited due to nozzle configuration. Note - Rounding methods may make calculated values appear in error. LaSalle Unit-2, 2R09 Page /D of ?q
LaSalle Unit-2 Feedwater 70' Exam Volume = 11.4 Sq. In. 45° Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS &60°T) 8.5 Sq. In. 70' T-Scan achieved = 5.6 Sq. In. 450 T-Scan achieved = 33.5 Sq. In.
-60 T-Scan achieved = 8.5 Sq. In.
/ I 70T 43-r I---- I--- I
LaSalle Unit-2 Feedwater
*70° Exam Volume = 11.4 Sq. In.
450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS &60T) = 8.5 Sq. In. 70' P-Scan achieved = 4.9 Sq. In. 45' P-Scan achieved = 31.2 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. I 70P 45P J IRS I I
- e I /
I-- I
LaSalle 2 G(, .. ,L6-JG1.xLs GOD-SL6E LaSalle 2 NOZZLE EXAMINATION PLAN 1/21/2003 Feedwater GERIS-2000 NOZZLE-TO-VESSEL SCANNING LIMITS NOZOD 26.25 VSLIR 126.69 WALL. 6.44 WELD RAD 17.25 ODBR 3.56 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH ANGLE TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 1 0.0* W 3.66 0.00 0.00 0.8° 0.317 0.150 0 0 18.97 88 54 - 2 45.0* T 13.26 3.00 0.00 0.8" 0.411 0.150 0 13.12 235 - - 7.33 -7.3 3 60.0* T 14.15 -3.00 0.00 0.80 0.490 0.150 0 18.97 185 - - 353.90 6.1' 4/6 45.0* P1 13.26 3.00 0.00 0.8* 0.336 0.150 0 10.00 235 - - 298.0* 62.00 (ccw) 5/7 45.0* P1 13.26 -3.00 0.00 0.8" 0.336 0.150 0 10.00 235 - - 62.00 -62.0' (cw) 4/6 45.0' P2 13.26 3.00 0.00 0.80 0.336 0.150 0 10.00 235 321.3° 38.7 (ccw) 5/7 45.0' P2 13.26 -3.00 0.00 0.80 0.336 0.150 01 10.00 235 38.7 -38.7' (cw) 1 70.0' T 12.00 0.00 0.00 0.80 0.380 0.150 0 10.87 52 0.0" 0.00 2 70.00 P 12.00 3.00 0.00 0.8° 0.313 0.150 0 6.25 52 287.20 72.80 (ccw) 3 70.0* P 12.00 -3.00 0.00 0.8' 0.313 0.150 0 6.25 52 72.80 -72.8' (cw) 1 49.00 ZiR 17.48 2.50 0.00 1.70 0.500 0.070 60 90 395 335.50 24.5' (ccw) 2 49.0' ZIR 17.48 -2.50 0.00 1.7° 0.500 0.070 60 90 395 24.5* -24.5' (cw) 1 68.00 Z2A 17.28 2.50 . 0.00 1.7° 0.500 0.070 50 90 281 348.40 11.6* (ccw) 2 68.0' Z2A 17.28 -2.50 0.00 1.7' 0.500 0.070 50 90 281 - 11.68 -11.6* (cw) 2 30.0° Z2B 17.28 2.50 0.00 1.50 0.354 0.070 - - 237 - 300.0° 60.00 (cw) 1 30.00 Z2B 17.28 -2.50 0.00 1.50 0.354 0.070 - - 237 60.00 -60.0° (ccw) 2 20.00 Z3 17.28 2.50 0.00 1.5° 0.354 0.070 - 188 270.00 90.0 (cw) 1 20.0' Z3 17.28 -2.50 0.00 1.5° 0.354 0.070 - 188 90.0° -90.0" (Cckw) mr 1/28/2003
GE NUCLEAR ENERGY UT EXAMINATION
SUMMARY
SHEET Summary No: 2R9-016 WO No: 430431 PROJECT LaSalle Unit 2 WELD ID: LCS-2-N4E SYSTEM: RPV N4E N-SH INITIAL CALIBRATION ID: NOZ.IN, FINAL CALIBRATION ID: NOZ.OUT GERIS DATA: n4e.pl.2, n4e.p2.1, n4e.tI.1, n4e.70.1, n4e.70.2 MANUAL DATA:! N/A OPERATORS: M. Hilborn Lv II; L. Benicki Lv II; CE Frakes Lv II; J.Guillote Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V2, using 450 Shear wave, 60° RL, and 70° RL search units, 0* L-Wave supplemental scans were also performed. Automated scanning was performed from the nozzle OD surfacer 3600 around the nozzle, with no restrictions. For initial calibrations refer to report G2K-CAL-1. For final calibrations refer to report G2K-CAL-3. The GERIS 2000 OD automated UT system 0° reference is located at 90° CW of nozzle TDC. The GERIS 2000 OD system recorded three (3) indications. 450 S / T-scan, No recordable indications. 600 RL / T-scan, No recordable indications. 45° S / P1-scan, One (1) acceptable indication. 450 S / P2-scan, No recordable indications. 70* RL / T-scan, Two (2) acceptable indications. 700 RL / P-ccw No recordable indications. 700 RL / P-cw No recordable indications. The indications recorded above have no determinable through wall dimension and are acceptable to the requirements of IWB-3000. Automated Composite Coverage = 78.1%. MP EPARED BY "qLevel:i~ DATE nt_77-C33 REVIEWED BY TevI u3
'T~ \r-nDATE LaSalle Unit-2, 2RO9 Page 321
Summary No.: 2R9-U01 LaSalle Unit-2 Weld LCS-2-N4E Spring 2003 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59. Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 11.4 5.6 9.5% 360 4.7% 450 T-Scan A 39.2 33.5 56.8% 360 28.4% 600 T-Scan A 8.5 8.5 14.4% 360 7.2% 70* P-Scan A 11.4 4.9 8.3% 360 4.2% 450 P-Scan A 39.2 31.2 52.9% 360 26.4% IRS P-Scan A 8.5 8.5 14.4% 360 7.2% .CD co3 70* T-Scan 450 T-Scan 600 T-Scan 700 P-Scan 450 P-Scan IRS P-Scan 700 T-Scan __ 450 T-Scan 600 T-Scan 700 P-Scan " 450 P-Scan IRS P-Scan
...... U mpsie.. vea g....
To I Composite Coverage = 78.1% Comments: A - Examined 3600. Scanning limited due to nozzle configuration. Note - Rounding methods may make calculated values appear in error. LaSalle Unit-2, 2RO9 Page of
LaSalle Unit-2 Feedwater 70° Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 700 T-Scan achieved = 5.6 Sq. In. 45° T-Scan achieved = 33.5 Sq. In. 60° T-Scan achieved = 8.5 Sq. In.
/ 70T 4WIT T0 I I I I
~CA I-I- N
LaSalle Unit-2 Feedwater 70* Exam Volume = 11.4 Sq. In. 45° Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 700 P-Scan achieved = 4.9 Sq. In. 45° P-Scan achieved = 31.2 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. I 701P I 45"P I IRS I 7-I- r-" m-, A I
LaSalle 2 Gt,- sL6-JG1.xis GOD-SL6E LaSalle 2 NOZZLE EXAMINATION PLAN 112112003 Foewater GERIS-20W0 NOZZLE-TO-VESSEL SCANNING LIMiTS NOZOD 26.25 VSLIR 126.69 WALL 6.44 WELD RAD 17.25 ODBR 3.56 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAL DISTANCE AGATE BE GATE C GATE FIXTURE CPU CH ANGLE TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 1 0.00 W 3.66 0.00 0.00 0.8° 0.317 0.150 0 18.97 88 54 - 2 45.00 T 13.26 3-00 0.00 0.81 0.411 0.150 0 13.12 235 - 7.3° -7.30 3 60.00 T 14.15 -3.00 0.00 0.81 0.490 0.150 0 18.97 185 - 353.9* 6.1" 4/6 45.0V PI 13.26 3.00 0.00 0.8' 0.336 0.150 0 10.00 235 . 298.0° 62.00 (ccw) 5/7 45.0' P1 13.26 -3.00 0.00 0.80 0.336 0.150 0 10.00 235 - - 62.0' -62.0* (cw) 4/6 45.00 P2 13.26 3.00 0.00 0.81 0-336 0.150 0 10.00 235 - - - 321.30 38.7- (cow) 5/7 45.0' P2 13.26 -3.00 0.00 0.8" 0.336 0.150 0 10.00 235 - - - 38.7" -38.7' (cw) 1 70.0" T 12.00 0.00 0.00 0.8° 0.380 0.150 06 10.87 52 - - - 0.0 0,0 2 70.0° P 12.00 3.00 0.00 0.8" 0.313 0.150 0 6.25 52 - - - 287.20 72.8 (cow) 3 70.0° P 12.00 -3.00 0.00 0.8* 0.313 0.150 0 6.25 52 - - - 72.8 -72.8° (cw) 1 49.0° ZIR 17.48 2.50 0.00 1.7 0.500 0.070 60 90 395 - - 335.5' 24.5' (ccw) 2 49.00 ZIR 17.48 -2.50 0.00 1.71 0.500 0.070 60 90 395 - - - 24.5' -24.5* (cw) 1 68.00 Z2A 17.28 2.50 0.00 1.7* 0.500 0.070 50 90 281 - - - 348.40 11.60 (ccw) 2 68.0" Z2A 17.28 -2.50 0.00 1.70 0.500 0.070 50 90 281 - - - 11.60 -11.6 (cw) 2 30.00 Z2B 17.28 2.50 0.00 1.50 0.354 0.070 - - 237 - - - 300.0* 60.0 (cw) 1 30.0° Z2B 17.28 -2.50 0.00 1.50 0.354 0.070 237 - - - 60.0° -60.0 (ccw) 2 20.00 Z3 17.28 2.50 0.00 1.50 0.354 0.070 188 - - 270.0" 90.00 (cw) 1 20.0' Z3 17.26 -2.5.0 0.00 1.50 0.354 0.070 188 90.00 -90.0° (ccw) r-i-' 1/28/2003
GE NUCLEAR ENERGY UT EXAMINA TION
SUMMARY
SHEET Summary No: 2R9-017 WO No: 430431 PROJECT LaSalle Unit 2 WELD ID: LCS-2-N4F SYSTEM: RPV N4F N-SH INITIAL CALIBRATION ID: NOZ.IN, NOZ.70.IN FINAL CALIBRATION ID: NOZ.OUT, NOZ.70.OUT GERIS DATA: n4f.p2.1, n4f.tI.1, n4f.tl.2, n4f.pl.1, n4f.70.1, n4f.70.2 MIANUAL DATA.: N/A OPERATORS: M. Hilborn Lv II; L. Benicki Lv II; CE Frakes Lv II; J.Guillote Lv II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section XA,1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II,Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V2, using 45* Shear wave, 60° RL, and 70° RL search units, 0° L-Wave supplemental scans were also performed. Automated scanning was performed from the nozzle OD surface, 3600 around the nozzle, with no restrictions. For initial calibrations refer to report G2K-CAL-1. For final calibrations refer to report G2K-CAL-3. The GERIS 2000 OD automated UT system 0° reference is located at 900 CW of nozzle TDC. The GERIS 2000 OD system recorded no indications. 450 S / T-scan. No recordable indications. 60° RL I T-scan, No recordable indications. 45° S I P1-scan, No recordable indications. 450 S/ P2-scan, No recordable indications. 700 RL / T-scan, No recordable indications. 70° RL / P-ccw No recordable indications. 70° RL / P-cw No recordable indications. Automated Composite Coverage = 78.1%.
\\~ ~.___ __A ,OREPARED BY DAEREVIEWED BY DATE J t I4IDW DATE 1XIIe ve1:~im3 UJTLevel: _'
LaSalle Unit-2, 2RO9 Page 326
SuMmary No.: 2R9-017 LaSalle Unit-2 Weld LCS-2-N4F Spring 2003 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE-Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59. Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 11.4 5.6 9.5% 360 4.7% 450 T-Scan A 39.1 33.5 56.8% 360 28.4% 60° T-Scan A 8.5 8.5 14.4% 360 7.2% 700 P-Scan A 11.4 4.9 8.3% 360 4.2% 450 P-Scan A 39.1 31.2 52.9% 360 26.4% IRS P-Scan A 8.5 8.5 14.4% 360 7.2% 70_T-Scan 450 T-Scan 600 T-Scan 70_P-Scan 450 P-Scan IRS P-Scan 70' T-Scan '_.... 450 T-Scan 60° T-Scan 70' P-Scan 45' P-Scan IRS P-Scan "" 70I ow I Composite Coverage = 78.i1% Comments: A - Examined 360*. Scanning limited due to nozzle configuration. Note - Rounding methods may make calculated values appear in error. LaSalle Unit-2, 2RO9 Page 3 ofj~
LaSalle Unit-2 Feedwater 70° Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 70° P-Scan achieved = 4.9 Sq. In. 45" P-Scan achieved = 31.2 Sq. In. IRS P-Scan achieved = 8.5 Sq. In.
/ I 70P I
45'P / IRS 7 I-I- I I
LaSalle Unit-2 Feedwater 70' Exam Volume = 11.4 Sq. In. 45' Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 700 T-Scan achieved = 5.6 Sq. In. 45° T-Scan achieved = 33.5 Sq. In. 600 T-Scan achieved = 8.5 Sq. In. 70"T 45'T 60"T I I I rn )
LaSalle 2 GO.. L6-JG1.xIs GOD-SL6E LaSalle 2 NOZZLE EXAMINATION PLAN 1/21/2003 Foedwater GERIS-2000 NOZZLE-TO-VESSEL SCANNING UMITS NOZOD 26.25 VSLIR 126.69 WALL 6.44 WELD RAD 17.25 ODBR 3.56 TYPE F (F-FLANGE OR B-BARREL) Delay INDEX INDEX STEP RADIAI DISTANCE AGATE BE GATE C GATE FIXTURE CPU CCH ANGLE TYPE usec X Y DEG INCHES INCHES START STOP STOP START STOP STOP ANGLE ANGLE 1 0.0. W 3.66 0.00 0.00 0.8° 0.317 0.150 0 18.97 88 - 54 - 2 45.0° T 13.26 3.00 0.00 0.8' 0.411 0.150 0 13.12 235 - - 7.3' -7.3° 3 60.0* T 14.15 -3.00 0.00 0.80 0.490 0.150 0 18.97 185 - - 353.90 6.10 416 45.00 P1 13.26 3.00 0.00 0.8" 0.336 0.150 0 10.00 235 - 298.00
- 62.0' (ccw) 5/7 45.0' P1 13.26 -3.00 0.00 0.8° 0.336 0.150 0 10.00 235 - 62.0' -62.0' (cw) 4/6 45.0 " P2 13.26 3.00 0.00 0.80 0.336 0.150 0 10.00 235 321.3 38.70 (ccw) 5/7 45.00 P2 13.26 -3.00. 0.00 0.8° 0.336 0.150 0 10.00 235 38.7° -38.7* (cw) 1 70.0° T 12.00 0.00 0.00 0.8° 0.380 0.150 0 10.87 52 - 0.00 0.00 2 70.0° P 12.00 3.00 0.00 0.80 0.313 0.150 0 6.25 52 287.20 72.8°" (ccw) 3 70.00 P 12.00 -3.00 0.00 0.86 0.313 0.150 0 6.25 52 72.8" -72.80 (cw) 1 49.0' ZIR 17.48 2.50 0.00 1.7' 0.500 0.070 60 90 395 335.50 24.5° (ccw) 2 49.00 Z1R 17.48 -2.50 0.00 1.7* 0.500 0.070 60 90 395 24.5° -24.5' (cw) 1 68.00 Z2A 17.28 2.50 0.00 1.70 0.500 0.070 50 90 281 348.40 11.6' (ccw) 2 68.0' Z2A 17.28 -2.50 0.00 1.70 0.500 0.070 50 90 281 11.60 -11.60 (cw) 2 30.0° Z2B 17.28 2.50 0.00 1.5' 0.354 0.070 - - 237 300.00 60.00 (cw) 1 30.00 Z2B 17.28 -2.50 0.00 1.50 0.354 0.070 237 60.0' -60.0° (cow) 2 20.0' Z3 17.28 2.50 0.00 1.5 0.354 0.070 188 270.00 90.00 (cw) 1 20.0' Z3 17.28 -2.50 0.00 1.50 0.354 0.070 188 90.0° -90.00 (ccw) r-
) 1/30/2003
Report No.: EXAMINATION
SUMMARY
SHEET 2R9-060 GE NUCLEAR ENERGY Site and Unit: LaSalle Unit 2 Component ID: IRH-HX2B-08D Outage: L2R09 1Lug System, RHR ASME Cat.: C-C ASME Item C3.10 Aug Requirements: N/A Exams Performed Data Sheet Cal Sheet Procedure Calibration Block ! Examination 'Cert Level; Date i Personnel M - MTMT-004 MT-0-4N/A I / MT-EXLN-102V0 N/A Michiael KempT 11 1/22/2003 Examination Results: During the magnetic particle examination of the above referenced weld, 1 indication was recorded. Indication was acceptable in accordance with ASME Section X1, Table IWC-3510-3. 74.4% of the code required surface area was examined. This examination meets the requirements of ASME Section Xl, 1989 Edition, no Addenda. Examination results were compared to data report D-307 from 1990 outage with No Change These examinationswere performed under Work Order 430436 Change This Summary and the following data sheets have been revieWed and ao Prepared By: Level: Date: Utility Reviewed N/A " N/A N/A Reviewed By: Level: Date: ANII Reviewed By: Page 331
r ,GE Nuclear Energy MAGNETIC PARTICLE EXAMINATION REPORT Site: LaSalle Unit: 2 Project: L2R09 Report Number: 2R9-060 Sheet No.: MT-004 Weld No.: IRH-HX2B-08D Configuration: I Luo Drawing: GEL-1111 System: RHR Procedure No.: MT-EXLN-102VO Version / Revision Rev. 0 DRR: N/A Material: Surface Condition: Item: Carbon Stee Smooth Weld - Final Magnetizing Apparatus Black Light Mfg: ParkerResearch Yoke Calibration: AC -10 lb. Lift Model Serial Number Model: B-300 Blacklight N/A N/A Serial No. 8140 Yoke Spacing: 6." Light Meter N/A N/A Thermometer: 222229 Surface Temperature: 65° F Technique Examination Medium Blacklight Intensity Magnetization: AC Magnetic Particles: Dry N/A Continuous ParkerResearch RP-6 11793 Blacklight Intensity: Technique: Manufacturer: Particle Type: Batch No Indication Number:
Description:
Results: 1/8'"Un ear on IRH-HX2B-O8D RI Comments: See attached sketch #2 for indication details. See attached sketch #1 for exam limitation. Michael KemP Initial Examiner H
-level 1122/2003 Date ag1e Utility Review - /
Date GE Review Level Date ANII Review Date Page '* of6 Page 332
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Report No: 2R9-060 Location of the IRH-HX2B-08D MT Indication Indication is on the edge of the plate in the center of the marked area. Page V of Page 334
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Page 335
Report No: 2R9-060 IRH-HX2B-08D, 09D, and O0OD General view of the support showing the 8, 9, and 10 welds. Location of the limitation on the 8 weld Page 6/ of 6 Page 336
GE Energy Nuclear UT Examination Summary Report No. 2R10-007 Project: LaSalle Unit-2, L2R10 Component ID: LCS-2-AE System: RPV Calibration ID: -Ne4lN- 03 *-. I ti *, J7a GERIS Data: UP and DN scan files Manual Data: RPV-010, RPV-011 Examiners: C. Gauthier Lv. II, S. Gauthier Lv. II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-704 V5 using 450 Shear wave, 60 RL° and 70° RL search units, supplemental 0° L-wave scans were also performed. Manual transverse and parallel scans were performed in accordance with procedure GE-UT-300 V8 using 60 RL° search units. Automated and manual scanning was performed from the vessel OD surface. For calibration records refer to report G2K-CAL-1. The GERIS 2000 OD automated UT system "0"references are located at Vessel 00 Azimuth and Vessel 0 Elevation. The GERIS 2000 OD system and manual examinations recorded no indications. Previous examination results were reviewed and no changes were noted. Automated and Manual Composite Coverage = 58% Calculated as % of 1800 length. 29% Calculated as % of 360°length. L I1 LaSalle Unit-2, L2RIO Page 1 of /Z-Page 337
Summary No.: 2R10-007 Nf) Weld LCS-2-AE LaSalle Unit-2, L2R10
- 0 CODE CROSS-SECTIONAL AREA LENGTH CALCULATIONS Percent Weld Length = 418.6 Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 75.6 Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 14.8 6.2 8.2% 370.5 3.6%
450 T-Scan A 48.9 42.4 56.1% 370.5 24.8% 600 T-Scan A 11.9 6.0 7.9% 370.5 3.5% 700 P-Scan A 14.8 4.9 6.5% 370.5 2.9% 450 P-Scan A 48.9 25.2 33.3% 370.5 14.8% 600 P-Scan A 11.9 5.3 7.0% 370.5 3.1% 70* T-Scan 45' T-Scan
- 0 60 T-Scan 700 P-Scan 450 P-Scan 600 P-Scan Manual 0.0%
600 S4 T-Scan B 11.9 5.0 6.6% 48 0.4% 600 S6 T-Scan B 63.7 52.3 69.2% 48 4.0% 600 S4 P-Scan B 11.9 5.3 7.0% 48 0.4% 60' S6 P-Scan B 63.7 5.3 7.0% 48 0.4%
% Total Composite Coverage = 58%
Comments: A - Automated coverage. B - Manual scanning in an area limited to the automated device due to thermocouple pads at 00 Az. Coverage calculated as percent of scheduled examination from 00 to 1800. Note - Rounding methods may affect calculated values.
Summary No.: 2R10-007 C, Weld LCS-2-AE LaSalle Unit-2, L2R10 CODE CROSS-SECTIONAL AREA LENGTH CALCULATIONS Percent Weld Length = 837.2 Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 75.6 Area Sq. In. Auto Auto Auto Auto 70* T-Scan A 14.8 6.2 8.2% 370.5 1.8% 450 T-Scan A 48.9 42.4 56.1% 370.5 12.4% 600 T-Scan A 11.9 6.0 7.9% 370.5 1.7% 700 P-Scan A 14.8 4.9 6.5% 370.5 1.4% 450 P-Scan A 48.9 25.2 33.3% 370.5 7.4% ii. 600 P-Scan A 11.9 5.3 7.0% 370.5 1.6% 700 T-Scan i__ 45' T-Scan 600 T-Scan 700 P-Scan 450 P-Scan 600 P-Scan Manual 0.0% 600 S4 T-Scan 8 11.9 5.0 6.6% 48 0.2% 60' S6 T-Scan B 63.7 52.3 69.2% 48 2.0% 60' S4 P-Scan B 11.9 5.3 7.0% 48 0.2% 600 S6 P-Scan B 63.7 5.3 7,0% 48 0.2% (0 % Total Composite Coverage = 29% Comments: A - Automated coverage. 0 B - Manual scanning in an area limited to the automated device due to thermocouple pads at 00 Az. Coverage calculated as percent of full weld. Note - Rounding methods may affect calculated values.
_ *LaSalle Unit-2 __ Shell to Flange Weld 70° Exam Volume = 14.8 Sq. In. 450 Exam Volume = 48.9 Sq. In. 600 Exam Volume = 11.9 Sq. In. 700 T-Scan achieved = 3.5 Sq. In. C450 T-Scan achieved = 2.9 Sq. In. 60° T-Scan achieved = 0.0 Sq. In. 700 P-Scan achieved = 4.9 Sq. In. 450 P-Scan achieved = 25.2 Sq. In. 600 P-Scan achieved = 5.3 Sq. In. _ i/
/
PITr-Scans 0 I 0.0 Looking ON Scans 60 I I L --------- - I
CD, LaSalle Unit-2 Shell to Flange Weld 700 Exam Volume = 14.8 Sq. In. 450 Exam Volume = 48.9 Sq. In. 60° Exam Volume = 11.9 Sq. In. 700 T-Scan achieved = 6.2 Sq. In. 450 T-Scan achieved = 42.4 Sq. In. 600 T-Scan achieved = 11.9 Sq. In. 700 P-Scan achieved = 4.9 Sq. In. 450 P-Scan achieved = 25.2 Sq. In. 600 P-Scan achieved = 5.3 Sq. In. 0 P-Scans 70°T 45°T I I I
*1
-1 Scanner Motion Looking UP Scans 0.0" -20.75"
- J- -- I
LaSalle Unit-2 SShell to Flange Weld 0 060° S4 Exam Volume = 11.9 Sq. In. 60° S6 Exam Volume = 63.7 Sq. In. 600 S4 T-Scan achieved = 11.9 Sq. In. LKUP 60° S6 T-Scan achieved = 52.3 Sq. In. LKUP 600 S4 T-Scan achieved = 0.0 Sq. In. LKDN 600 S6 T-Scan achieved = 6.9 Sq. In. LKDN 60' S4 P-Scan achieved = 5.3 Sq. In. CW/CCW 600 S6 P-Scan achieved = 30.0 Sq. In. CW/CCW
/
I 60rP 60'P-Scans
" 60°T I -I II I -D 0
- Report No.:
EXAMINATION
SUMMARY
SHEET 2ReO-o.4 GE NUCLEAR ENERGY Site. LaSalle Unit-2 Component ID: GEL-1061-DA Outage: L2R10 Bot. Hd. Meridional System RPV ASME Cat.: B-A ASME Item: BI.22 Aug Requirements: N/A (Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date Personnel 60 Long. RPV-003 N/A GE-UT-300 IIW2-047 Scott Erickson II 2/22/2005 60 Long. RPV-004 N/A - E-UT-300 01-92-06 Scott Erickson II 2/23/2005 Examination Results: Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Vessel (RPV) Assembly Welds. Manual transverse and parallel scans were performed in accordance with procedure GE-UT-300 V8, using 60° RL-wave search units. Scanning was performed from the vessel OD surface. qcanning was limited due to the vessel skirt attachment weld and an inaccessible inner skirt region.. No indications were recorded. Manual coverage = 66%. Examination results were compared to data report 4023,18011,3247 from PSI outage with V No Change These examinations were performed under Work Order 5849600 Change This Summary and the following data sheets have been rev e'ed and accepted by the following personnel: Prepared By: Level: Date: Utilit*yReview Date: ANII Review: Date: Page 1 of 4 Page 343
Inspection Report No.: 2R10-004 Bottom Head Meridionals GEL-1061-DA C-r'3 LaSalle Unit-2, L2R10 0 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 80.4 Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 60.2 Area Sq. In. Auto Auto Auto Auto 600 S4 P-Scan LKDN A 8.8 8.8 7.3% 53 2.4% 600 $4 P-Scan LKUP A 8.8 8.8 7.3% 53 2.4% 600 S6 P-Scan A 51.4 51.4 85.4% 53 28.1% 600 S4 T-Scan LKCW A 8.8 8.8 7.3% 53 2.4% 50 S4 T-Scan LKCCW A 8.8 8.8 7.3% 53 2.4% 60* S6 T-Scan A 51.4 51.4 85.4% 53 28.1% 60* S4 P-Scan LKDN 600 S4 P-Scan LKUP 60' S6 P-Scan 600 S4 T-Scan LKCW 60°S4 T-Scan LKCCW 60' S6 T-Scan 60" S4 P-Scan LKDN 600 S4 P-Scan LKUP 60' S6 P-Scan 600 $4 T-Scan LKCW 60' S4 T-Scan LKCCW_ 600 S6 T-Scan
% Total Composite Coverage = 66%
o Comments: A - Examined 53" of length. Scanning limited due to support skirt weld and inaccessible inner skirt region. Note - Rounding methods may make calculated values appear in error.
LaSalle Unit-2 Bottom Head Meridional D 60" S4 Exam Volume = 8.8 Sq. In. .7' 600 $6 Exam Volume = 51.4 Sq. In. 60' S4 P-Scan LKDN achieved = 8.8 Sq. In. 60" $4 P-Scan LKUP achieved = 8.8 Sq. In. 60 S6 P-Scan achieved = 51.4 Sq. In. 600 S4 T-Scan LKCW achieved = 8.8 Sq. In. 60' S4 T-Scan LKCCW achieved = 8.8 Sq. In. 60? S6 T-Scan achieved = 51.4 Sq. In. "1) D 601 "I
Lmax - 80.4" Lmin - 27.4" Weld Length - 80.4" Exam limited due to skirt weld. LA SALLE L R/O I~fR /-. -Page346~
Site: LaSalle Unit-2 Component ID: GEL-1061-DE Outage: L2RI0 Bot. Hd. Meridional System RPV ASME Cat.: B-A ASME Item: B1.22 Aug Requirements: NIA Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level. Date Personnel 60° Long. RPV-001 N/A GE-UT-300 IIW2-047 Wallace Reid II 2Y23/2005 60* Long. RPV-002 N/A GE-UT-300 01-92-06 Wallace Reid II 2/23/2005 Examination Results: Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Vessel (RPV) Assembly Welds. Manual transverse and parallel scans were performed in accordance with procedure GE-UT-300 V8, using 60" RL-wave search units. Scanning was performed from the vessel OD surface. Scanning was limited due to the vessel skirt attachment weld and an inaccessible inner skirt region. No indications were recorded. Manual coverage = 66%. Examination results were compared to data report 4023,18012,3247 from PSI outage with *' No Change These examinationswere performed under Work Order 5849600 Change This Summary and the following data sheets have been reviewed and accepted by the following personnel: pared By: Level: Date: Utility Review: / Date: ANII Review. Date: Page 1. of Page 347
r-Inspection Report No.: 2R10-005 C, C Bottom Head Meridionals GEL-1061-DE LaSalle Unit-2, L2R10
-U (0 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 80.4 Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 60.2 Area Sq. In. Auto Auto Auto Auto 600 S4 P-Scan LKDN A 8.8 8.8 7.3% 53 2.4%
60' S4 P-Scan LKUP A 8.8 8.8 7.3% 53 2.4% 60 S6 P-Scan A 51.4 51.4 85.4% 53 28.1% 600 S4 T-Scan LKCW A 8.8 8.8 7.3% 53 2.4% 600 S4 T-Scan LKCCW A 8.8 8.8 7.3% 53 2.4% 60 0 6 T-Scan A 51.4 51.4 85.4% 53 28.1% t-- 00 600 S4 P-Scan LKDN
'C 60° S4 P-Scan LKUPI 60° S6 P-Scan 60' S4 T-Scan LKCW 600 S4 T-Scan LKCCW I 60_S6 T-Scan (D) 600 S4 P-Scan LKDN 60 0 S4 P-Scan LKUP 600 S6 P-Scan 600 $4 T-Scan LKCW 600 S4 T-Scan LKCCW_
600 S6 T-Scan
% Total Composite Coverage = 66% -I 0 Comments: A - Examined 53" of length. Scanning limited due to support skirt weld and inaccessible inner skirt region.
Note - Rounding methods may make calculated values appear in error.
DLaSalle Unit-2 C Bottom Head Meridional o 600 S4 Exam Volume 88 Sq. In. 60* S6 Exam Volume = 51.4 Sq. In. 600 S4 P-Scan LKDN achieved = 8.8 Sq. In. 60* S4 P-Scan LKUP achieved = 8.8 Sq. In. 600 S6 P-Scan achieved = 51.4 Sq. In. 60° S4 T-Scan LKCW achieved = 8.8 Sq. In. 60° S4 T-Scan LKCCW achieved = 8.8 Sq. In. 60" S6 T-Scan achieved = 51.4 Sq. In. 4
Lmax - 80.4" Lmin - 27.4" f, Weld Length - 80.4" Exam limited due to skirt weld. LA SALLE 2 R /0* Page 350
Report No.: EXAMINATION
SUMMARY
SHEET 2RIO-o0e GE NUCLEAR ENERGY Site: LaSalle Unit-2 Component ID: GEL-1061-DF Outage: L2RI0 Bot. Hd. Meridional System RPV ASME Cat.: B-A ASME Item: B1.22 Aug Requirements: NIA Exams Performed Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date Personnel 60 Long. RPV-005 N/A GE-UT-300 IIW2-047 Scott Erickson II 2/23/2005 60° Long. RPV-006 N/A GE-UT-300 01-92-06 Scott Erickson II 2/23/2005 Examination Results: Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part I1,Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Vessel (RPV) Assembly Welds. Manual transverse and parallel scans were performed in accordance with procedure GE-UT-300 VSi using 60° RL-wave search units. Scanning was performed from the vessel OD surface. Scanning was limited due to the vessel skirt attacliment weld and an inaccessible inner skirt region. No indications were recorded. Manual coverage = 66%. Examination results were compared to data report 4032,18011,3247 from PSI outage with v No Change These examinationswere performed under Work Order: 5849600 Change This Summary and the following data sheets have been reviewd and accepted by the following personnel: Prepared By: Level: Date: UtDieW Date: ANII Review Date: Page I of Page 351
Inspection Report No.: 2R10-006 U/) Bottom Head Meridionals GEL-1061-DF LaSalle Unit-2, L2R10 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 80.4 Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 60.2 Area Sq. In. Auto Auto Auto Auto 600 S4 P-Scan LKDN A 8.8 8.8 7.3% 53 2.4% 600 S4 P-Scan LKUP A 8.8 8.8 7.3% 53 2.4% 60° S6 P-Scan A 51.4 51.4 85.4% 53 28.1% 60' S4 T-Scan LKCW A 8.8 8.8 7.3% 53 2.4% 60' S4 T-Scan LKCCW A 8.8 8.8 7.3% 53 2.4% 600 S6 T-Scan A 51.4 51.4 85.4% 53 28.1%
-0 60'$ 4 P-Scan LKDN 600 S4 P-Scan LKUP 600 S6 P-Scan 60° S4 T-Scan LKCW 60° S4 T-Scan LKCCW 60' S6 T-Scan 600 S4 P-Scan LKDN 60' S4 P-Scan LKUP 60' S6 P-Scan 60' S4 T-Scan LKCW
-) 600 S4 T-Scan LKCCW I 600 S6 T-Scan I I
% Total Composite Coverage = 66% -C 0-I Comments: A - Examined 53" of length. Scanning limited due to support skirt weld and inaccessible inner skirt region.
Note - Rounding methods may make calculated values appear in error.
LaSalle Unit-2 Bottom Head Meridional o 60° S4 Exam Volume = 8.8 Sq. In. 600 S6 Exam Volume = 51.4 Sq. In. 60° S4 P-Scan LKDN achieved = 8.8 Sq. In. 60' S4 P-Scan LKUP achieved = 8.8 Sq. In. 60° S6 P-Scan achieved = 51.4 Sq. In. 60' 54 T-Scan LKCW achieved = 8.8 Sq. In. 600 S4 T-Scan LKCCW achieved = 8.8 Sq. In. 60' $6 T-Scan achieved 51.4 Sq. In. LO V
ý-Pi
Lmax - 80.4" Lmin - 27.4" ( Weld Length - 80.4" Exam limited due to skirt weld. 7 7 LA SALLE 7 RIO Page 354
GE Energy Nuclear _ UT Examination Summary Report No. 2R10-010 Project: LaSalle Unit-2, L2R10 Component ID: LCS-2-N2B System: Recirculation Inlet Calibration ID: 01NOZIN GERIS Data: TL, P1 and 70TP scan files Manual Data: N/A Examiners: C. Gauthier Lv. II, S. Gauthier Lv. II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V4 using 457 Shear wave, 60 RL° and 70* RL search units, supplemental 0° L-wave scans were also performed. Scanning of the inner 15%T volume for radial flaws was performed using 450 and 600 Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. For calibration records refer to report G2K-CAL-1. The GERIS 2000 OD automated UT system "0" references are located at Vessel 00 Azimuth and Vessel 0 Elevation. The GERIS 2000 OD system recorded no indications. Previous examination results were reviewed and no changes were noted. Automated Composite Coverage = 70%. Date: A- A6 - o 6-1 ate z_;:7-o1 I LaSalle Unit-2, L2R1O Page 1 of _5_ Page 355
Inspection Report No.: 2R10-010 C Recirculation Inlet LCS-2-N2B Ir' LaSalle Unit-2, L2R10 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.1 Area Sq. In. Auto Auto Auto Auto 70* T-Scan A 11.4 5.8 9.8% 360 4.9% 450 T-Scan A 39.2 33.5 56.7% 360 28.3% 60* T-Scan A 8.5 8.5 14.4% 360 7.2% 700 P-Scan A 11.4 4.5 7.6% 360 3.8% 450 P-Scan A 39.2 22.5 38.1% 360 19.0% Inner 15%T P-Scan A 8.5 8.5 14.4% 360 7.2% 70' T-Scan 450 T-Scan 600 T-Scan '_" 70' P-Scan 45' P-Scan Inner 15%T P-Scan 70* T-Scan 450 T-Scan 600 T-Scan 70' P-Scan 450 P-Scan Inner 15%T P-Scan
% Total Composite Coverage = 70%
Comments: A - Examined 3600 of length. Scanning limited due to nozzle configuration. Inner 15%T P-Scan area by modeling. Note - Rounding methods may make calculated values appear in error.
CD) CD LaSalle Unit-2 Recirculation Inlet 70° Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 600 T) = 8.5 Sq. In. 70* T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 600 T-Scan achieved = 8.5 Sq. In. 0) 17.25"
/
707T 45°T 60'T I I I K--' ---- 4---- 0)
----1>
I
.0
- 0 t'3
- 0. LaSalle Unit-2 0'1 Recirculation Inlet 70° Exam Volume = 11.4 Sq. In.
450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 70° P-Scan achieved = 4.5 Sq. In. 450 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (Bymodel) 17.25"
/
70"P 45"P. I ____________ I-00 I 0 K
GE Energy Nuclear UT Examination Summary Report No. 2R10-011 Project: LaSalle Unit-2, L2R1O Component ID: LCS-2-N2C System: Recirculation Inlet Calibration ID: 01NOZIN GERIS Data: TL, P1 and 70TP scan files Manual Data: N/A Examiners: C. Gauthier Lv. II,S. Gauthier Lv. II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V4 using 45' Shear wave, 60 RL° and 700 RL search units, supplemental 0* L-wave scans were also performed. Scanning of the inner 15%T volume for radial flaws was performed using 45° and 60' Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. For calibration records refer to report G2K-CAL-1. The GERIS 2000 OD automated UT system "0"references are located at Vessel 00 Azimuth and Vessel 0 Elevation. The GERIS 2000 OD system recorded no indications. Previous examination results were reviewed and no changes were noted. Automated Composite Coverage = 70%. LaSalle Unit-2, L2R1O Page I of I I Page 359
I'- Inspection Report No.: 2R10-011 o0 Recirculation Inlet LCS-2-N2C LaSalle Unit-2, L2R10 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.1 Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 11.4 5.8 9.8% 308.4 4.2% 450 T-Scan A 39.2 33.5 56.7% 308.4 24.3% 600 T-Scan A 8.5 8.5 14.4% 308.4 6.2% 700 P-Scan A 11.4 4.5 7.6% 308.4 3.3% M 450 P-Scan A 39.2 22.5 38.1% 308.4 16.3% Inner 15%T P-Scan A 8.5 8.5 14.4% 308.4 6.2% r-70' T-Scan 8 11.4 5.8 9.8% 51.6 0.7% Co 450 T-Scan B 39.2 33.5 56.7% 51.6 4.1% 600 T-Scan 8 8.5 4.8 8.1% 51.6 0.6% 700 P-Scan B 11.4 4.5 7.6% 51.6 0.5% 450 P-Scan B 39.2 22.5 38.1% 51.6 2.7% Inner 15%T P-Scan B 8.5 8.5 14.4% 51.6 1.0% 700 T-Scan 450 T-Scan . 60° T-Scan 70_P-Scan 45' P-Scan 0t Inner 15%T P-Scan 03 % Total Composite Coverage = 70% Comments: A - Examined 308.40 of length. Scanning limited due to proximity of N9 nozzle. B - Examined 51.60 of length in area of N9 nozzle. Inner 15%T P-Scan area by modeling. Note - Rounding methods may make calculated values appear in error.
wn W LaSalle Unit-2 0 Recirculation Inlet 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) 8.5 Sq. In. 70° T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 600 T-Scan achieved = 8.5 Sq. In. 17.25* I 45°T 70'T 60'T I ________ I I ax I CO --- H (D I 0
CO Cn
- 3 23 LaSalle Unit-2 0n Recirculation Inlet 70° Exam Volume = 11.4 Sq. In.
450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 70° T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 600 T-Scan achieved = 6.6 Sq. In. Limited area due to N9. IT.25" 70°T 45*T 60*T I- - I I I I -o DO I 0 -I'
ED. 1'C LaSalle Unit-2 Recirculation Inlet 70' Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 70° P-Scan achieved = 4.5 Sq. In. 450 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model) 17.25"
/ 70'P 45"P I-
-U I 0h'
Unlimited scan area. 24" Arm
-7 E N2-D N j00 iS N9-A LL 0
GE Energy Nuclear UT Examination Summary Report No. 2R10-014 Project: LaSalle Unit-2, L2R1O Component ID: LCS-2-N2F System: Recirculation Inlet Calibration ID: 01NOZIN GERIS Data: TL, P1 and 70TP scan files Manual Data: N/A Examiners: C. Gauthier Lv. II,S. Gauthier Lv. II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V4 using 45' Shear wave, 60 RL° and 70" RL search units, supplemental 0* L-wave scans were also performed. Scanning of the inner 15%T volume for radial flaws was performed using 450 and 60" Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. For calibration records refer to report G2K-CAL-1. The GERIS 2000 OD automated UT system "0" references are located at Vessel 00 Azimuth and Vessel 0 Elevation. The GERIS 2000 OD system recorded no indications. Previous examination results were reviewed and no changes were noted. Automated Composite Coverage = 70%. Prepared By: Reviewed : Utility Reviewed By: ANII Reviewed By: Date: Date: Z - Date 7 z.S - Date: LaSalle Unit-2, L2R1Q Page 1 oft Page 365
I-aJ Inspection Report No.: 2R10-014 C/) w i. C Recirculation Inlet LCS-2-N2F LaSalle Unit-2, L2R10 0 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.1 Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 11.4 5.8 9.8% 360 4.9% 450 T-Scan A 39.2 33.5 56.7% 360 28.3% 60' T-Scan A 8.5 8.5 14.4% 360 7.2% 70° P-Scan A 11.4 4.5 7.6% 360 3.8% 450 P-Scan A 39.2 22.5 38.1% 360 19.0% Inner 15%T P-Scan A -8.5 8.5 14.4% 360 7.2% 700 T-Scan 450 T-Scan . __,_..... 60' T-Scan =..,__ _ __.,_,= 70' P-Scan ...... 450 P-Scan Inner 15%T P-Scan "" 70° T-Scan 450 T-Scan ........... 60* T-Scan 700 P-Scan -u 45° P-Scan Inner 15%T P-Scan
% Total Composite Coverage = 70%
0 Comments: A - Examined 3600 of length. Scanning limited due to nozzle configuration. H Inner 15%T P-Scan area by modeling. Note - Rounding methods may make calculated values appear in error.
0) (7' LaSalle Unit-2 Recirculation Inlet 70° Exam Volume-- 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In. 70° T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 600 T-Scan achieved = 8.5 Sq. In.
/ 17.25" 70T 45°T 60'T I
K---* m 0
C/ LaSalle Unit-2 I'3 Recirculation Inlet 70° Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60 0T) = 8.5 Sq. In. 700 P-Scan achieved = 4.5 Sq. In. 450 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model) 17.25" 70*P 45'P I I L -U CD i 0
-41
GE Energy Nuclear UT Examination Summary Report No. 2R10-015 Project: LaSalle Unit-2, L2R10 Component ID,: LCS-2-N2G System: Recirculation Inlet Calibration ID: 01NOZIN GERIS Data: TL, P1 and 70TP scan files Manual Data: N/A Examiners: C. Gauthier Lv. II, S. Gauthier Lv. II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V4 using 450 Shear wave, 60 RL° and 700 RL search units, supplemental 0* L-wave scans were also performed. Scanning of the inner 15%T volume for radial flaws was performed using 450and 60" Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. For calibration records refer to report G2K-CAL-1. The GERIS 2000 OD automated UT system "0"references are located at Vessel 00 Azimuth and Vessel 0 Elevation. The GERIS 2000 OD system recorded no indications. Previous examination results were reviewed and no changes were noted.. Automated Composite Coverage = 70%. LaSalle Unit-2, L2R10 Page 1 of Page 369
Inspection Report No.: 2R10-015 di C Recirculation Inlet LCS-2-N2G LaSalle Unit-2, L2R10 0 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.1 Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 11.4 5.8 9.8% 360 4.9% 450 T-Scan A 39.2 33.5 561% 360 28.3% 600 T-Scan A 8.5 8.5 14.4% 360 7.2% 700 P-Scan A 11.4 4.5 7.6% 360 .3.8% 450 P-Scan A 39.2 22.5 38.1% 360 19.0% Inner 15%T P-Scan A 8.5 8.5 14.4% 360 7.2% 70' T-Scan 450 T-Scan 600 T-Scan 70' P-Scan 450 P-Scan Inner 15%T P-Scan 70' T-Scan 450 T-Scan 60' T-Scan 70' P-Scan 450 P-Scan Inner 15%T P-Scan (0 %.Total Composite Coverage = 70% Comments: A - Examined 3600 of length. Scanning limited due to nozzle configuration. Inner 15%T P-Scan area by modeling. Note - Rounding methods may make calculated values appear in error.
I-
/)
0 C, LaSalle Unit-2 Recirculation Inlet 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 700 T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 600 T-Scan achieved = 8.5 Sq. In. 17.25" II 70°T 45°T ( I 607T I I w
-U 0)
(0 CD I 0
-I'
I-- U) LaSalle Unit-2 0 0 01 Recirculation Inlet 70° Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60 0T) = 8.5 Sq. In. 700 P-Scan achieved = 4.5 Sq. In. 450 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model) 17.25" I 70'P 45oP I I I-- ---- V I-
-----1 I
O
GE Energy Nuclear UT Examination Summary Report No. 2R10-016 Project: LaSalle Unit-2, L2R1O o Component ID: LCS-2-N2H System: Recirculation Inlet Calibration ID: 01NOZ.IN GERIS Data: TL, P1 and 70TP scan files Manual Data: N/A Examiners: C. Gauthier Lv. II, S. Gauthier Lv. II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V4 using 450 Shear wave, 60 RL° and 700 RL search units, supplemental 0QL-wave scans were also performed. Scanning of the inner 15%T volume for radial flaws was performed using 45° and 60° Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. For calibration records refer to report G2K-CAL-1. The GERIS 2000 OD automated UT system "0" references are located at Vessel 00 Azimuth and Vessel 0 Elevation. The GERIS 2000 00 system recorded no indications. Previous examination results were reviewed and no changes were noted. Automated Composite Coverage = 70%. L La -,c Prepared By: Reviewed B'y: Utiif Reviewed y: ANN Reviewed By: Date: Date: 3/12/s 5a Date Date: LaSalle Unit-2, L2RIO Page I of I Page 373
Inspection Report No.: 2RIO-016 Recirculation Inlet LCS-2-N2H LaSalle Unit-2, L2R10 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.1 Area Sq. In. Auto Auto Auto Auto 70* T-Scan A 11.4 5.8 9.8% 308.4 4.2% 450 T-Scan A 39.2 33.5 56.7% 308.4 24.3% 600 T-Scan A 8.5 8.5 14.4% 308.4 6.2% 700 P-Scan A 11.4 4.5 7.6% 308.4 3.3% Q-. 450 P-Scan A 39.2 22.5 38.1% 308.4 16.3% (D Inner 15%T P-Scan A 8.5 8.5 14.4% 308.4 6.2% 70° T-Scan B 11.4 5.8 9.8% 51.6 0.7% 450 T-Scan B 39.2 33.5 56.7% 51.6 4.1% 0 60* T-Scan B 8.5 4.8 8.1% 51.6 0.6% 700 P-Scan B 11.4 6.6 11.2% 51.6 0.8% 450 P-Scan B 39.2 22.5 38.1% 51.6 2.7% Inner 15%T P-Scan B 8.5 8.5 14.4% 51.6 1.0% 70* T-Scan 450 T-Scan 600 T-Scan 700 P-Scan 450 P-Scan Inner 15%T P-Scan
% Total Composite Coverage = 70%
Comments: A - Examined 308.40 of length. Scanning limited due to proximity of N9 nozzle. B - Examined 51.60 of length in area of N9 nozzle. Inner 15%T P-Scan area by modeling. Note - Rounding methods may make calculated values appear in error.
I-C LaSalle Unit-2 Recirculation Inlet 70° Exam Volume = 11.4 Sq. In. 45° Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 700 T-Scan achieved = 5.8 Sq. In. 45' T-Scan achieved = 33.5 Sq. In. 60° T-Scan achieved = 8.5 Sq. In.
* ~(*
17.25" 70"T 45°T 60'T I I I
---- I--
----- H 1-i 0
C/) C 2.3 LaSalle Unit-2 0) 0Y Recirculation Inlet 70° Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 70' T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 60Q T-Scan achieved = 6.6 Sq. In. II I 17.25" I 70'T I 4501 I Limited area due to N9. 6001 I "D 0 I
I-c ".o LaSalle Unit-2 0' 0 Recirculation Inlet 70° Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 607T) = 8.5 Sq. In. 700 P-Scan achieved = 4.5 Sq. In. 450 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model) 17-25"
/ 70'P 45*P L
F-- '0 CD H- -o I 0
Unlimited scan area. 24" Arm N2-J N9-B T/C PADS C-0
GE Energy Nuclear UT Examination Summary Report No. 2R10-017 Project: LaSalle Unit-2, L2R10 Component ID: LCS-2-N2J System: Recirculation Inlet Calibration ID: 01NOZ.IN GERIS Data: TL, P1 and 70TP scan files Manual Data: N/A Examiners: C. Gauthier Lv. II, S. Gauthier Lv. II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PD1 program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V4 using 450 Shear wave, 60 RL° and 700 RL search units, supplemental 0° L-wave scans were also performed. Scanning of the inner 15%T volume for radial flaws was performed using 450 and 600 Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. For calibration records refer to report G2K-CAL-1. The GERIS 2000 OD automated UT system "0"references are located at Vessel 0* Azimuth and Vessel 0 Elevation. The GERIS 2000 OD system recorded no indications. Previous examination results were reviewed and no changes were noted. Automated Composite Coverage = 70%. By:d tpareed By: tity7Revip-bd Y: ANII Reviewed By: LaSalle Unit-2, L2R1O Page 1 of Page 379
Inspection Report No.: 2R10-017 Cl) 2i C Recirculation Inlet LCS-2-N2J LaSalle Unit-2, L2R10 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.1 Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 11.4 5.8 9.8% 307.2 4.2% 450 T-Scan A 39.2 33.5 56.7% 307.2 24.2% 600 T-Scan A 8.5 8.5 14.4% 307.2 61% 700 P-Scan A 11.4 4.5 7.6% 307.2 3.2% 450 P-Scan A 39.2 22.5 38.1% 307.2 16.2% Inner 15%T P-Scan A 8.5 8.5 14.4% 307.2 6.1% (DJ 70' T-Scan B 11.4 5.8 9.8% 52.8 0.7% 450 T-Scan B 39.2 33.5 56.7% 52.8 4.2% 0 600 T-Scan B 8.5 7.5 12.7% 52.8 0.9% 700 P-Scan B 11.4 4.5 7,6% 52,8 0.6%. 450 P-Scan B 39.2 22.5 38.1% 52.8 2.8% Inner 15%T P-Scan B 8.5 8.5 14,4% 52.8 1.1% 700 T-Scan 45' T-Scan 60' T-Scan 70' P-Scan 450 P-Scan Inner 15%T P-Scan
% Total Composite Coverage = 70%
Comments: A - Examined 308.40 of length. Scanning limited due to proximity of N9 nozzle. B - Examined 51.60 of length in area of N9 nozzle. Inner 15%T P-Scan area by modeling. Note - Rounding methods may make calculated values appear in error.
C-LaSalle Unit-2 Recirculation Inlet 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In. 700 T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 600 T-Scan achieved = 8.5 Sq. In. C, CD3 0 17.25" I I 70°T 45°T 607T I ______ I I I I
C/) CD LaSalle Unit-2 Recirculation Inlet 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 600T) = 8.5 Sq. In. 700 T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 60° T-Scan achieved = 7.5 Sq. In. Limited area due to N9. 17.25"
/ 70'T 45°T 60'T I I
-D 0
K) LaSalle Unit-2 0 C0 Recirculation Inlet 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60 0T) = 8.5 Sq. In. 70° P-Scan achieved = 4.5 Sq. In. 450 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model) 17.25"
/
70*P 45*P F---- I I I I CD F---- -i 0 I -4%
Unlimited scan area. 24" Arm N2-H 0 N9-B T/C PADS I 1~ U
GE Energy Nuclear UT Examination.Summary Report No. 2R10-018 Project: LaSalle Unit-2, L2R10 Component ID: LCS-2-N2K System: Recirculation Inlet Calibration ID: 01NOZIN GERIS Data: TL, P1 and 70TP scan files Manual Data: N/A Examiners: C. Gauthier Lv. II, S. Gauthier Lv. II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V4 using 45' Shear wave, 60 RL° and 700 RL search units, supplemental 00 L-wave scans were also performed. Scanning of the inner 15%T volume for radial flaws was performed using 450 and 60* Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel OD surface. For calibration records refer to report G2K-CAL-1. The GERIS 2000 OD automated UT system "0"references are located at Vessel 0' Azimuth and Vessel 0 Elevation. The GERIS 2000 OD system recorded no indications. Previous examination results were reviewed and no changes were noted. Automated Composite Coverage = 70%. t I LaSalle Unit-2, L2R1O Page I of ____ Page 385
I-I~j Inspection Report No.: 2R10-018 C,) 03 C Recirculation Inlet LCS-2-N2K I~3 I-LaSalle Unit-2, L2R10 0 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 59.1 Area Sq. In. Auto Auto Auto Auto 70' T-Scan A 11.4 5.8 9.8% 360 4.9% 450 T-Scan A 39.2 33.5 56.7% 360 28.3% 60' T-Scan A 85 8.5 14.4% 360 7.2% 70* P-Scan A 11.4 4.5 7.6% 360 3.8% 450 P-Scan A 39.2 22.5 38.1% 360 19%0% Inner 15%T P-Scan A 8.5 8.5 14.4% 360 7.2% 70' T-Scan 45' T-Scan 600 T-Scan - 70' P-Scan ,__ _____ 450 P-Scan Inner 15%T P-Scan 700 T-Scan 450 T-Scan 600 T-Scan 70° P-Scan
-u 45' P-Scan 0)
Inner 15%T P-Scan
% Total Composite Coverage = 70%
0
) Comments. A - Examined 3600 of length. Scanning limited due to nozzle configuration.
Inner 15%T P-Scan area by modeling. Note - Rounding methods may make calculated values appear in error.
h) CD C 03 LaSalle Unit-2 Recirculation Inlet 70' Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. in. 700 T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 600 T-Scan achieved = 8.5 Sq. In. cc CD CO CA4 17.25"
/ 70"T 45°T 60°T I I
--- H
-D 0)
(0 CD I'. 0
I-Di C,) Di C N3 LaSalle Unit-2 N) 0 0 0i Recirculation Inlet 70° Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60 0 T) = 8.5 Sq. In. 700 P-Scan achieved = 4.5 Sq. In. 450 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model) F---- I 17.25" 70°P 45°P CD 0 I
GE Energy Nuclear UT Examination Summary Report No. 2R10-019 Project: LaSalle Unit-2, L2R110 Component ID: LCS-2-N3A System: Main Steam Calibration ID: 03NOZ.IN GERIS Data: TL, P1 and 70TP scan files Manual Data: N/A Examiners: C. Gauthier Lv. II, S. Gauthier Lv. II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V4 using 450 Shear wave, 60 RL° and 700 RL search units, supplemental 00 L-wave scans were also performed. Scanning of the inner 15%T volume for radial flaws was performed using 45* and 600 Shear wave search units as specified by the "Nozzle Inner Radius and Bore Requirements" sheet, which has been verified by modeling. Automated scanning was performed from the vessel 00 surface. For calibration records refer to report G2K-CAL-1. The GERIS 2000 OD automated UT system "0" references are located at Vessel 0° Azimuth and Vessel 0 Elevation. The GERIS 2000 OD system recorded no indications. Previous examination results were reviewed and no changes were noted. Automated Composite Coverage 68%. "1eparad BY , Reviewsd lfy: Utility Reviewed By: ANII Reviewed By: Date: 7-/ to" Date: A - ,Z e - Date O-. 7- -Date: LaSalle Unit-2, L2R1O Page 1 of Page 389
I- Inspection Report No.: 2R 10-036 C Main Steam LCS-2-N3A I-r'- LaSalle Unit-2, L2R10 0o CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 77.2 Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 14.1 6.3 8.2% 360 4.1% 450 T-Scan A 52.1 43.5 56.3% 360 28.2% 60' T-Scan A 11.0 11.0 14.2% 360 7.1% 700 P-Scan A 14.1 5.0 6.5% 360 3.2% 450 P-Scan A 52.1 28.2 36.5% 360 18.3% Inner 15%T P-Scan A 11.0 11.0 14.2% 360 7.1% 700 T-Scan 45' T-Scan
- 0 609 T-Scan K 700 P-Scan 450 P-Scan Inner 15%T P-Scan 700 T-Scan 450 T-Scan 60' T-Scan 70' P-Scan 450 P-Scan Inner 15%T P-Scan
% Total Composite Coverage = 68%
Comments: A - Examined 3600 of length. Scanning limited due to nozzle configuration. Inner 15%T P-Scan area by modeling. Note - Rounding methods may make calculated values appear in error.
C,) M.' LaSalle Unit-2 0 0 Main Steam 700 Exam Volume = 14.1 Sq. In. 450 Exam Volume = 52.1 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 11.0 Sq. In. 700 T-Scan achieved = 6.3 Sq. In. 450 T-Scan achieved = 43.5 Sq. In. 600 T-Scan achieved = 11.0 Sq. In.
/
70"T 45°T 60°T I I I _0
------ I I
I-C PQ LaSalle Unit-2 C) 0 0 Main Steam 70° Exam Volume = 14.1 Sq. In. 450 Exam Volume = 52.1 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 11.0 Sq. In. 70° P-Scan achieved = 5.0 Sq. In. 450 P-Scan achieved = 28.2 Sq. In. IRS P-Scan achieved = 11.0 Sq. In. (By model)
/ / 70=P45op I I I
-D
-------1
GE Energy Nuclear UT Examination Summary Report No. 2R10-020 Project: LaSalle Unit-2, L2R1O Weld ID: LCS-2-N3B System: Main Steam Calibration ID: 03NOZ.IN GERIS Data: TL, P1 and 70TP scan files. Manual Data: N/A Examiners: C. Gauthier Lv. II; S. Gauthier Lv. II Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code, Section XI, 1989 Edition No Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by. the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-A Reactor Pressure Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedure GE-UT-705 V4, using 45" Shear wave, 600 RL and 700 RL search units, supplemental 00 L-wave scans were also performed. Scanning of the inner 15%T volume for radial flaws was performed using 600 Shear waves as specified by the "Nozzle Inner Radius and Bore Requirements" sheet which has been verified by modeling. Automated scanning was performed from the vessel OD surface. For calibration records refer to report G2K-CAL-1. The GERIS 2000 OD automated UT system "0" references are located at Vessel 0" Azimuth and Vessel 0 Elevation. The GERIS 2000 OD system recorded no indications. Previous examination results were reviewed and no changes were noted. Automated Composite Coverage = 68%. Prepared)3y:/ Reviewed By: Utility Reviewed : .NII Reviewed By: Date: -/Z'Yo; Date:
. . - Date: "Date:
LaSalle Unit-2, L2R1O Page v of Page 393
Inspection Report No.: 2R10-020 Cn r"- N) Main Steam LCS-2-N3B LaSalle Unit-2, L2R10 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 77.2 Area Sq. In. Auto Auto Auto Auto 700 T-Scan A 14.1 6.3 8.2% 360 4.1% 450 T-Scan A 52.1 43.5 56.3% 360 28.2% 60 0 T-Scan A 11.0 11.0 14.2% 360 7.1% 70° P-Scan A 14.1 5.0 6.5% 360 3.2% 450 P-Scan A 52.1 28.2 36.5% 360 18.3% Inner 15%T P-Scan A 11,0 11.0 14.2% 360 7.1% 70' T-Scan 0', 45' T-Scan 600 T-Scan 70_P-Scan 450 P-Scan Inner 15%T P-Scan 70° T-Scan 450 T-Scan 60° T-Scan 700 P-Scan 0-450 P-Scan _ . . Inner 15%T P-Scan"
% Total Composite Coverage = 68%
Comments: A - Examined 3600 of length. Scanning limited due to nozzle configuration. Inner 15%T P-Scan area by modeling. Note - Rounding methods may make calculated values appear in error.
I-- U') CD c13 LaSalle Unit-2 Main Steam 70° Exam Volume = 14.1 Sq. In. 450 Exam Volume = 52.1 Sq. In. Inner 15%T Exam Volume (IRS & 60 0 T) = 11.0 Sq. In. 70' T-Scan achieved = 6.3 Sq. In. 45' T-Scan achieved = 43.5 Sq. In. 600 T-Scan achieved = 11.0 Sq. In. 70'T 45°T 60'T I F3 0
------ I.
C0 LaSalle Unit-2 01 *Main Steam 70' Exam Volume = 14.1 Sq. In. 450 Exam Volume = 52.1 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 11.0 Sq. In. 70' P-Scan achieved = 5.0 Sq. In. 45' P-Scan achieved = 28.2 Sq. In. IRS P-Scan achieved = 11.0 Sq. In. (By model)
/ \
- 71) T45-p (0
Report No: EXAMINATION
SUMMARY
SHEET 2R1o-o61 GE NUCLEAR ENERGY LaSalle Unit 2 L2R10 ATT ,V-SS-2 RPV B-K Sec. X, Component ID: Configuration: System: AISME Cat.: Exam Credit.: Examination Cert Exam Exams Data Cal Procedure Revision Calibration Personnel Level Completed Performed Sheet Sheet Block W. L DeBuSk 2126/05 PT PT-06 N/A GE-PT-I00Ver.4 N/A VT-I 05-198 N/A ER-AA-335-014*1A N/A Examination Results: During the liquid penetrant and visual examinations of the above referenced weld, no recordable indications were detected, Due to adajacent structures only 52% of the required examination area was accessable for inspections. Due to this limiting condition a VT-1 examination was performed on 100% of the required examination area. This examination meets the requirements of ASME Section X1, 1989 Edition, no Addenda Examinationresults were compared to data report None from N/A outage with N/A No Change These examinatonswere performed under Work Order: 5849600 N/A Change
- 2This Summary§2Wand the following datasheets have been reviewed and acceptedby the following personnel: RWP:: N/A
/
___ 4 m __ Dose: 20 Mr. GE B Level: Date: Reviewed By:
Title:
Date: Reviewed By: Level: Date: ANII Reviewed By:
Title:
Date: Page 1 of 3 Page 397
GE NuclearEnergy LIQUID PENETRANT EXAMINATION REPORT Site: LaSalle Unit: _2 Project: L2RIO- Report Number: 2RI0-061 Data Sheet: PT-06 Component ID: RPV-SS 2 Configuration: Attachmen* Drawing: GEL-If 19 / VPF 3073-080-2 System: RPV Procedure No.: GE-PT-100 Ver4 Material: Surface Condition: Item: SA-533 As-foundlCleaned Weld Technique Cleaner Penetrant Developer VisibleSolvent Removable 0-3) Manufacturer: Majajnflyx Manaflux Afr Thermometer: 241i Brand / Type: SKC- SKL-S SKQ-S Temperature: uF Batch No.: 03LK 01 W2AQ2 Black Light: &A Light Meter A,/ Blacklight Intensity. NA pW/crm2 Pre-Clean Method: Spray/ Wie Exam Start: 0240/2/26/05 Penetrant Application Brush Drying Time: Dwell Time: 10 Penetrant Removal: Wipe with dry towel Wipe with damp towel Drying Time: 5 Developer Application: sjor Developing Time: 7 Comments / Indications / Limitations: PT examination performed on accessable areas of the attachiment lug. See sketch for examination area. f /q 52% of the required area was examined. No recordable indications were detected. I C 36 3
/\C SS.~ L .* W. L DeBusk S2126/05 a Initials: Examiner- Level: Exam Date: Reviewed By: Date:
K~ FmPige Wto $ Alk-Level: Date: ANII Reviewed By: Date: Rcý,d 16 Page 398
ER-AA-335-.014 (4 125 evo
.A9 K ATTACHMENT I VT-I Visual Examination Record t°3.o 3 A3,, -
Pme 1 Iof+- 2LL Component Descriptlon: R*t ft. c A ,.,j-f Sheet No. .05 - I cl 8 Out Date: 2/2, (o/0WONo. S81960(oO0 Pc re: ER-AR-33S-/ Rev. I Thickness: J1'A Visual Method: Direct x Remote MaterialType: CSq- S3?3 VisualAids: FLasSki aLt /l;rror 18& Ng&C Suiftce: ID OD X M&TE: N/A te9msln*etde(EIN): R P v- SS aillTTau*A T Location:Orv4ellE( 804, A 90 I.D. IND# IND LENGTH WIDTH ACC RU INSPECTOR LEVEL NumberTYPE UNACC SIGTUREDATE & Comments/Sketch:
,/o reor-...Le ;,,.-i",'te,<.-d Defect Code:
wwear (~.. d1> i -v ef' S;~ sdes W
-7~A t/dCorroskio-CR VT-I INSPECTOR SIGNATURELEVELDATE Overall results: Acceptable QY99 [jij L L Dr dak Additional Actions: ,.,- ,-' "-
(Action Request Work Order, Condition R ort, etc. Initiated) ( LEVEL III SIGNATURE DATE ANII SIGNATURE DATE Page 399
Site: LaSalle Component ID: GEL-1060-AG Outage: L2R11 TOP HEAD FLANGE System: RPV ASME Cat.: B-A ASME Item 81.40 Aug Req SECT XI E, ams Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Date Performed Personnel 600 RL 0-007 N/A GE-UT-300 Ver/Rev 10 CAL-IlW2-026 Jack Reisewitz II 3/2/2007 60° RL D-008 N/A GE-UT-300 Ver/Rev 10 01-92-04 Jack Reisewitz !1 3/2/2007 600 RL D-009 N/A GE-UT-300Ver/Rev 10 CAL-IIW2-033 Mario Russomonno II 3/3/2007 60- RL D-010 N/A GE-UT-300 Ver/Rev 10 01-92-04 Mario Russomonno 1I 3/3/2007 MT MT-001 N/A GE-MT-100 Ver/Rev 8 N/A Wallace Reid II. 3/2/2007 Examination Results: During the manual ultrasonic examination of the above referenced weld, no recordable indications were detected utilizing a 60° refracted longitudinal wave search unit Amagnetic partide surface examination was also performed from 1800 to 3600 with no recordable indications. No recordable indications were detected. 80.6% Code coverage was achieved. This examination is acceptable per the requirements of ASME Section XI 1995 Edition, 1996 Addenda. Examination results were compared to data report D-188A from 1996 outage with V No Change rhese examinations were performed under Work Order: 00821549 Change This Summary and the following data sheets have been reviewed and accepted by the following personnel: RWP: N/A
'. L.-" l - ," Dose: 9 mr.
Prepared By: Date: Utility Review: Date: ANII Review: Dote: Page I of 8 Page 400
,GE Energy, Nuclear MAGNETIC PARTICLE EXAMINATION REPORT Site: LaSalle Unit: 2 Project: L2R11. Report Number: 2R11-005 Sheet No.: MT-O01 Weld No.: GEL-1060-AG Configuration: TOP HEAD FLANGE Drawing: GEL-1060 System: RPV Procedure No.: GE-MT-100 Version / Revision 8 DRR: N/A Material: Surface Condition: Item:
Carbon Steel Ground Smooth Weld - Final Magnetizing Apparatus Black Light Mfg: ParkerResearch Yoke Calibration: 2114108 Model Serial Number Model: 8-300 Blacklight N/A NIA Serial No.: 5502 Yoke Spacing: 6.0" Light Meter N/A N/A Thermometer: 251804 Surface Temperature: 75 F Technique Examination Medium Blacklight Intensity
'Magnetization: AC Magnetic Particles: DNI Technique: Continuous Hagnaflux 84 Red 93A4045 alocklight Intensity Manufocturer Particle Type: Batch No indication Number :
Description:
I Results:
.N. .. A NRI Comments:
No recordable indications. Light Source: Yoke with ECT Light 12V/1OW Exam Area Examined 1800 to 360° Wallace Reid ku)3/ /Io 3121M Utility Review Date cilial Examiner LPeel Date 6E, Reviv w Level Date . WNl Review Date Page 6 of 8 Page 401
IReactor PressureVessel C GE Energy - Nuclear jCoverage Calculation Sheet 0 LaSalle Unit-2, 2007 GEL-1060-AG L2R11 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 180. Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 35.8 Area Sq. In. Manual Manual Manual Manual 600 T-Scan (S4 UP) A 5.2 0 0.0% 180 00% 600 T-Scan (S4 DN) A 5.2 5.2 14.5% 180 3.6% 60' T-Scan (S6) A' 30.6 29 81.0% 180 40.5% 60' P-Scan (S4 CV) A 5.2 3.9 10.9% 180 2.7% 60' P-Scan (S4 CCW) A 5.2 3.9 10.9% 180 2.7% 60' P-Scan (S6) A 30.6 22.2 62.0% 180 31.0% ~0 600 T-Scan (S4 UP) 60' T-Scan (S4 DN) 600 T-Scan (S,6) 60' P-Scan (S4 CW) 60' P-Scan (S4 CCW) 60' P-Scan (S6) 60' T-Scan (S4 UP) __ 60' T-Scan (S4 DN) 60' T-Scan (S6) 60' P-Scan (S4 CW) 60' P-Scan (S4 CCW) 60' P-Scan (S6)
-. % Total Composite Coverage = 80.6%
Re,, 1 314!0O7 N Comments: Scanning limited looking up due to the flange configuration. Examined from 180' CW to 360' Az. as scheduled. A* - Single side access, 50% credit of the achieved Supplement 4 T-scan volume claimed.
-Note - Rounding methods may affect calculated values. Weld length in degrees.
LaSalle Unit-2 C C.>. Closure Head Flange t. K 600 S4 Exam Volume 5.2 Sq. In. 60' S6 Exam Volume = 30.6 Sq. In. 60' S4 P-Scan LKCW achieved = 3.9 Sq. In. u~. K 600 S4 P-Scan LKCCW achieved = 3.9 Sq. in. 600 S6 P-Scan achieved = 22.2 Sq. In. N 600 S4 T-Scan LKDN achieved = 5.2 Sq. In.
-,j 600 S4 T-Scan LKUP achieved = 0.0 Sq. In.
600 S6 T-Scan achieved = 29.0 Sq. In. 0.0 35 Flange Head Scan limited due to Flange configuration.
-'/
CQ Rodial Plate T NIom. = 5.125" Clad T Nom. = 0.1875" A tt,. , ... -
GE Energy Nuclear Examination Summary Sheet No.: 2R11-007 Site: LaSalle Unit-2 Component ID: LCS-2-N16A Outage: L2R11 Configuration: Nozzle to Shell System: RPV ASME Cat: B-D ASME Item: 83.90 Aug. Requirements: N/A Exams Calibration Calibration Examination NDE Performed: Sheetls): Block: Procedure: Personnel: Level: Date: 0°L NOZ 01-92-01 GE-UT-704/705 C. Gauthier II 3/3/07 45'S NO2 01-92-01. GE-UT-704/705 C. Gauthier II 3/3/07 60'L NOZ 01-92-01 GE-UT-704/705 C. Gauthier II 3/3/07 70°L NOZ 01-92-01 GE-UT-704/705 C. Gauthier II 3/3/07 45*S IRS 01-92-01 GE-UT-705 C. Gauthier II .3/4/07 60'S IRS 01-92-01 GE-UT-705 C. Gauthier II 3/4/07 Comments: Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part 11,Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel iRPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedures GE-UT-704 V8 and GE-UT-705 V5, using 450 Shear wave, 60' RL, and 700 RL search units, supplemental 0' L-Wave scans were also performed. Nozzle Inner 15%T circ scans were performed in accordance with Model validated searah unit angles. Automated scanning was performed from the vessel O surface. and was restricted due to the nozzle configuration. The GERIS 2000 OD automated UT system 0 reference is located at 900 CW of nozzle TDC. One acceptable indication was recorded. Automated Composite Coverage = 70.5% The examination results were compared with data report 0-436 from L2R03 outage with [],No Change These examinations were performed under Work Order: N/A [I Change This summary and the following data sheets have been reviewed and accepted by the following personnel: ((K?) Level: Z'jte: 74 ý-L ý t 1, Utiiity R.eviel By: 0'-te:
,411i Reevwod 3,i:
Pa-ige 1 o4 Page 404
U-C' Reactor Pressure Vessel. GE Energy - Nuclear Coverage Calculation Sheet 0 0 LaSalle Unit-2, 2007 LCS-2-N 16A L2R11 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Area Scanned Percent Exam Volume = 59.1 Area Sq. In. Auto. of Area Weld Length Percent 60' T-Scan (S4 UC) A* 8.5 8.5 14.4% 360 7.2% 450 T-Scan (S6 FV) A* 39.2 33.5 56.7% 360 28.3% 70° T-Scan (S6 NS) A' 11.4 5.8 9.8% 360 4.9% IRS P-Scan (S4 UC) A 8.5 8.5 14.4% 360 7.2% 450 P-Scan (S6 FV) A 39.2 22.5 38.1% 360 19.0% 70' P-Scan (S6 NS) A 11.4 4.5 7.6% 360 3.8% 600 T-Scan (S4 UC) ' '_. 450 T-Scan (S6 FV) 70* T-Scan (S6 NS) IRS P-Scan (S4 UC) 450 P-Scan (S6 FV) 70' P-Scan (S6 NS) 600 T-Scan (S4 UC) 450 T-Scan (S6 FV) 70' T-Scan (S6 NS), IRS P-Scan (S4 UC) 450 P-Scan (S6 FV) 70' P-Scan (S6 NS) ..... (D % Total Composite Coverage .70.5% Rev. 0 912317, Comments. 0 Scanning limited due to nozzle configuration. IRS P-Scan by modeling. A* - Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed iaw. 10CFR50.55a. Note - Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in degrees.
C-C/ LaSalle Unit-2 0 4 LCS-2-N 16A (HPCS) 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In. 700 T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 600 T-Scan achieved = 8.5 Sq. In. 17.25" 70'T 45'T 607T I I I ---- 4---- i-
---- H /
CD 0
LaSalle Unit-2 0 4 LCS-2-N16A (HPCS) 700 Exam Volume = 11 .4 Sq. In. 45' Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In. 70" P-Scan achieved = 4.5 Sq. In. 450 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model.) CD -P,. 0
-4 17.25" 70*P 45'P F-----
CD I
GE Energy Nuclear Examination Summary Sheet *Report No.: 2RII-008 Site: LaSalle Unit-2 Component ID: LCS-2-N2A Outage: 1-2R13 Configuration: Nozzle to Shell System: RPV ASME Cat: B-D ASME Item: 83.90 Aug. Requirements: N/A Exams Calibration Calibration Examination NDE Performed: Sheet(s): Block: Procedure: Personnel: Level: Date: 0°L NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/7/07 45*S NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/7/07 60°L NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/7/07 700L NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/7/07 45 0S IRS 01-92-01 GE-UT-705 K. Montgomery II 3/7/07 60°S IRS 01-92-01 GE-UT-705 K. Montgomery II 3/7/07 Comments: Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category 8-D Reactor Pressure Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedures GE-UT-704 V8 and GE-UT-705 VS. using 450 Shear wave, 600 RL, and 700 RL search units, supplemental 0° L-Wove scans were also performed. Nozzle Inner 15%T circ scans were performed in accordance with Model validated search unit angles. Automated scanning was performed from the vessel OD surface. and was restricted due to the nozzle configuration. The GERIS 2000 OD automated UT system 0 reference is located at 900 CW of nozzle TDC. One acceptable indication was recorded. Automated Composite Coverage = 70.5% The examination results were compared with data report 0-459 from L2RO3 outage with 0 No Change These examinations were performed under Work Order: N/A E] Change This summary and the following data sheets have been reviewed and accepted by the following personnel:
'_;-pored B_: Leel: Date' UtilityRe.,,Žv. B3y: )ate Page 1 of / 0 Page 408
r-Reactor PressureVessel 03 0h GE Energy - Nuclear Coverage Calculation Sheet LaSalle Unit-2, 2007 LCS-2-N2A L2R11 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume = 59.1 Area Sq. In. Area Scanned of Area Weld Length Percent 600 T-Scan (S4 UC) A* 8.5 8.5 14.4% 360 7.2% 450 T-Scan (S6 FV) A* 39.2 33.5 567% 360 28.3% 70' T-Scan (S6 NS) A* 11.4 5.8 9.8% 360 4.9% IRS P-Scan (S4 UC) A 8.5 8.5 14.4% 360 7.2% Co 450 P-Scan (S6 FV) A 39.2 22.5 38.1% 360- 19.0% 70' P-Scan (S6 NS) A 11.4 4.5 7.6% 360 3.8% !Q 60' T-Scan (S4 UC) " _.' 450 T-Scan (S6 FV) 700 T-Scan (S6 NS) IRS P-Scan (S4 UC) 45' P-Scan (S6 FV) 700 P-Scan (S6 NS) 600 T-Scan (S4 UC) 450 T-Scan (S6 FV), 70' T-Scan (S6 NS) IRS P-Scan (S4 UC) 450 P-Scan (S6 FV) 700 P-Scan (S6 NS),
% Total Composite Coverage = 70.5%
i Re. 0 9t-23/r,5 Comments: Scanning limited due to the nozzle configuration. IRS P-Scan by modeling. A* - Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed iaw. 10CFR50.55a.. Note - Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in degrees.
r, CD C LaSalle Unit-2 N~ LCS-2-N2A 70° Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 607T) = 8.5 Sq. In. 700 T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 600 T-Scan achieved = 8.5 Sq. In. i!/ 17-25" 70'T 45°T 60'T I I
---- H CD 0O
I-CD) CD LaSalle Unit-2 k)j 0 0 4 LCS-2-N2A 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In. 70° P-Scan achieved = 4.5 Sq. In. 450 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model) 17.25*
/
70'P 45*P I I F----- CD K---- ~0 I
GE Energy Nuclear Examination Summary Sheet Site: LaSolle Unit-2 Component ID: LCS-2-N2D Outage: L2R11 Configuration: Nozzle to Shell System: RPV ASME Cat: B-D ASME Item: 83.90 Aug. Requirements: N/A Exams Calibration Calibration Examination NDE Performed: Sheet(s): Block: Procedure: Personnel: Level: Date: O°L NOZ 01-92-01 GE-UT-704/705 C. Gauthier II 3/6/07 45°S NOZ 01-92-01 GE-UT-704/705 C. Gauthier II 3/6/07 60%L NOZ 01-92-01 GE-UT-704/705 C. Gauthier II 3/6/07 70%L NOZ 01-92-01 GE-UT-704/705 C. Gauthier II 3/6/07 45°S IRS 01-92-01 GE-UT-705 C. Gauthier II 3/7/07 60°S IRS 01-92-01 GE-UT-705 C. Gauthier II 3/7/07 Comments: Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section Xl, 1989 Edition no Addenda, also Section Xl, 1995 Edition with the 1996 Addenda as modified by the P0l program description and the Federal Register, Part II,Nuclear Regulatory Commission, 10 CFR Part 50 for Category 8-0 Reactor Pressure Vessel IRPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedures GE-UT-704 V8 and GE-UT-705 V5, using 450 Shear wave, 600 RL, and 70' RL search units, supplemental 00 L-Wave scans were also performed. Nozzle Inner 15%T circ scans were performed in accordance with Model validated search unit angles. Automated scanning was performed from the vessel OD surface. and was restricted due to the nozzle configuration and proximity of the. N9A nozzle. The GERIS 2000 OD automated UT system 0 reference is located at 900 CW of nozzle TDC. No relevant indications were recorded. Automated Composite Coverage = 70.3% The examination results were compared with data report D-463 .from L2R03 outage with . [ No Change I These examinations were performed under Work Order: N/A E]Chonge This summary and the following data sheets have been reviewed and accepted by the following personnel:
//ý/C' IrP*pc"Id ey: Level: Cate- Utility Rple y Cat P
Page 4 12 Page 412
CL) IReactor PressureVessel Sheet C GE Energy - Nuclear Coverage Calculation LaSalle Unit-2, 2007 LCS-2-N2D L2R11 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume = 59.1 Area Sq. In. Area Scanned of Area Weld Length Percent 600 T-Scan (S4 UC) A* 8.5 8.5 14.4% 315 6.3% 45'"T-Scan (S6 FV) A* 39.2 33.5 56.7% 360 28.3% 700 T-Scan (S6 NS) A* 11.4 5.8 9.8% 360 4.9% IRS P-Scan (S4 UC) A 8.5 8.5 14.4% 360 7.2% 450 P-Scan (S6 FV) A 39.2 22.5 38.1% 360 19.0%
-o4 70' P-Scan (S6 NS) A 11.4 4.5 7.6% 360 3.8%
600 T-Scan (S4 UC) B 8,5 6.8 11.5% 45 0.7% 450 T-Scan (S6 FV) 70° T-Scan (S6 NS) IRS P-Scan (S4 UC) 45' P-Scan (S6 FV) 700 P-Scan (S6 NS) T 600 T-Scan (S4 UC) _ ___ 450 T-Scan (S6 FV) 70' T-Scan (S6 NS) IRS P-Scan (S4 UC) 450 P-Scan (S6 FV) 70' P-Scan (S6 NS)
-i %Total Composite Coverage = 70.3%
Re., 0 9/23105 Comments:- 0 Scanning limited due to the nozzle configuration and proximity of the N9A nozzle. IRS P-Scan by modeling. A*- Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed iaw. 10CFR50.55a.. Note - Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in degrees.
Cl, CD C LaSalle Unit-2 LCS-2-N2D 70' Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 70' P-Scan achieved = 4.5 Sq. In. 0 45 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model) 17.25" I 70* - 5 F-CD 0~o H-----
U1) LaSalle Unit-2 LCS'2-N2D 700 Exam Volume = 11.4 Sq. In. Co 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In. 700 T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 60' T-Scan achieved = 8.5 Sq. In. CD C-n III 17.25" 70'T 45'T 60'T I I
---- H I -CD I
1--0
I-C 2-T- LaSalle Unit-2 0O N LCS-2-N2D 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60 0 T) = 8.5 Sq. In. 700 T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 60° T-Scan achieved = 6.8 Sq. In. Limited area due to N9. 17.25"
/
70°T 45'T 60'T I I I C10
0 GE Energy Nuclear Examination Summary Sheet ReportNo.: 2R11-010 Site: LaSalle Unit-2 Component I0: LCS-2-N2E Outage: L2R11 Configuration: Nozzle to Shell System: RPV ASME Cat: B-D ASME Item: B3.90 Aug. Requirements: N/A Exams Calibration Calibration Examination NDE Performed: Sheetls): Block: Procedure: Personnel: Level: Date: 0°L NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/7/07 45°S NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/7/07 60'L NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/7/07 70'L NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/7/07 45°S IRS 01-92-01 GE-UT-705 K. Montgomery II 3/7/07 60 0S IRS 01-92-01 GE-UT-705 K. Montgomery II 3/7/07 Comments: Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PD) program description and the Federal Register, Part II,Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel (RPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedures GE-UT-704 V8 and GE-UT-705 V5, using 450 Shear wave, 600 RL, and 70° RL search units, supplemental 00 L-Wave scans were also performed. Nozzle Inner 15%T circ scans were performed in accordance with Model validated search unit angles. Automated scanning was performed from the vessel OD surface. and was restricted due to the nozzle configuration. The GERIS 2000 OD automated UT system 0 reference is located at 900 CW of nozzle TDC. No relevant indications were recorded. Automated Composite Coverage 70.5% The examination results were compared with data report D-463 from L2R03 outage with [ No Change 1 These examinations were performed under Work Order: N/A DChange This summary and the following data sheets have been reviewed and accepted by the following personnel:
,.:,pared1 By' -ee Cute: 6tiliy Review By.: ate:
Pacie I at Page 417
r-01) Cf)
- 0) ReactorPressure Vessel GE Energy - Nuclear Coverage CalculationSheet C3
-4 LaSalle Unit-2, 2007 LCS-2-N2E L2R11 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume = 591 Area Sq. In. Area Scanned of Area Weld Length Percent 600 T-Scan (S4 UC) A* 8.5 8.5 14.4% 315 6.3%
450 T-Scan (S6 FV) A* 39.2 33.5 56.7% 360 28.3% 7(0 T-Scan (S6 NS) A' 11.4 5.8 9.8% 360 4.9% IRS P-Scan (S4 UC) A 8.5 8.5 14.4% 360 7.2% 45' P-Scan (S6 FV) A 39.2 22.5 38.1% 360 19.0% 70° P-Scan (S6 NS) A 11.4 4.5 7.6% 360 3.8% 0 600 T-Scan (S4 UC) ..... 450 T-Scan (S6 FV) 70° T-Scan (S6 NS) IRS 45' P-Scan (S4 UC) P-Scan (S6 FV) 70' P-Scan (S6 NS) 600 T-Scan (S4 UC) 450 T-Scan (S6 FV) 700 T-Scan (S6 NS) IRS P-Scan (S4 UC) 450 P-Scan (S6 FV) 70' P-Scan (S6 NS)
% Total Composite Coverage = 69.6%
Re.. * /23"5 Comments: Scanning limited due to the nozzle configuration. IRS P-Scan by modeling. A* - Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed iaw. 10CFR50.55a.. Note - Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in degrees.
I-" C') C LaSalle Unit-2 10, 0 LCS-2-N2E 70' Exam Volume = 11.4 Sq. In. 45' Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 607T) = 8.5 Sq. In. 70' T-Scan achieved = 450 T-Scan achieved = 5.8 Sq. In. 33.5 Sq. In. 600 T-Scan achieved = 8.5 Sq. In.
/ 17.25" 70'T 45=T 60'T I I I CD 00
U)~ CD LaSalle Unit-2 C) 0 LCS-2-N2E 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In. 70° P-Scan achieved = 4.5 Sq. In. 450 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model) 17.25" I 70'P 45 0P
'I NQ CM
- GE Energy Nuclear Examination Summary Sheet Report No.. 2R11-011 Site: LaSalle Unit-2 Component ID: LCS-2-NSA Outage: L2R11 Configuration: Nozzle to Shell System: RPV ASME Cat: B-D ASME Item: 83.90 Aug. Requirements: N/A Exams Calibration Calibration Examination NDE Performed: Sheetls): Block: Procedure: Personnel: Level: Date:
0OL NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/4/07 4505 NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/4/07 NOZ 01-92-01 GE-UT-704/705 K. Montgomery It 3/4/07 60'L 70*L NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/4/07 450 S IRS 01-92-01 GE-UT-705 K. Montgomery II 3/4/07 60*S IRS 01-92-01 GE-UT-705 K. Montgomery II 3/4/07 Comments: Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section X1, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II,Nuclear Regulatory Commission, 10 CFR Part 50 for Category 8-D Reactor Pressure Vessel IRPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedures GE-UT-704 V8 and GE-UT-705 V5, using 45° Shear wave, 600 RL, and 70' RL search units, supplemental 00 L-Wave scans were also performed. Nozzle Inner 15%T circ scans were performed in accordance with Model validated search unit angles. Automated scanning was performed from the vessel OD surface. and was restricted due to the nozzle configuration. The GERIS 2000 OD automated UT system 0 reference.is located at 900 CW of nozzle TDC. No relevant indications were recorded. Automated Composite Coverage = 70.5% The examination results were compared with data report D-434 from LZR03 outage with [No These examinations were performed under Work Order: N/A [Change This summary and the following data sheets have been reviewed and accepted by the following personnel: iepcred By: Le,.el: Date: liity Re,'ew y: Cote:
,214/f A _,
_____--ri;l Ro e
,_________ u 2v,,d6 D,.i.t:
Pnaqe I cf )f Page 421
IReactor PressureVessel GE Energy - Nuclear jCoverage Calculation Sheet LaSalle Unit-2, 2007 LCS-2-N5A L2R11 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Area Scanned Percent Exam Volume = 59.1 Area Sq. In. Manual of Area Weld Length Percent 600 T-Scan (S4 UC) A* 8.5 8.5 14.4% 360 7.2% 450 T-Scan (S6 FV) A* 39.2 33.5 56.7% 360 28.3% 70' T-Scan (S6 NS) A* 11.4 5.8 9.8% 360 4.9% (D IRS P-Scan (S4 UC) A 8.5 8.5 14.4% 360 7.2% 450 P-Scan (S6 FV) A 39.2 22.5 38.1% 360 19.0% 70' P-Scan (S6 NS) A 11.4 4.5 7.6% 360 3.8% 0 600 T-Scan (S4 UC) 45' T-Scan (S6 FV) 70' T-Scan (S6 NS) IRS P-Scan (S4 UC) 450 P-Scan (S6 FV) 70' P-Scan (S6 NS) 600 T-Scan (S4 UC) 45' T-Scan (S6 FV) 70 T-Scan (S6 NS) IRS P-Scan (S4 UC) 450 P-Scan (S6 FV) 70' P-Scan (S6 NS)
% Total Composite Coverage 70.5%
Re, G 9123;0 Comments. Scanning limited due to the nozzle configuration. IRS P-Scan by modeling. A* - Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed iaw. 10CFR50.55a.. Note - Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in degrees.
U-CD2 C LaSalle Unit-2 C
-4 LCS-2-N5A 70' Exam Volume = 11.4 Sq. In.
450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60'T) 8.5 Sq. In. 70° T-Scan achieved = 5.8 Sq. In. 45' T-Scan achieved = 33.5 Sq. In. 60° T-Scan achieved = 8.5 Sq. In. 17.25"
,I 70'T I
45°T I 60'T I
---- 1--~~~
I
---- 1 CD.
0
c', CD 0 LaSalle Unit-2 0 LCS-2-N5A 70° Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 600 T) = 8.5 Sq. In. 70' P-Scan achieved = 4.5 Sq. In. 450 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model)
/ 17.25" 7O*P 45'P K
F---
/ --- --
4 J F-- i II I I CD (0 I
GE Energy Nuclear Examination Summary Sheet2R-012 Site: LaSalle Unit-2 Component ID: LCS-2-N68 Outage: L2R11 Configuration: Nozzle to Shell System: RPV ASME Cat: B-D ASME Item: 83.90 Aug. Requirements: N/A Exams Calibration Calibration Examination NDE Performed: Sheetls): Block: Procedure: Personnel: Level: Date: 0°L NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/5/07 45°S NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/5/07 60 0L NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/5/07 700L NOZ 01-92-01 GE-UT-704/705 K. Montgomery II 3/5/07 450S IRS 01-92-01 GE-UT-705 C. Gauthier II 3/5/07 60°S IRS 01-92-01 GE-UT-705 C. Gauthier II 3/5/07 Comments: Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section Xl, 1989 Edition no Addenda, also Section XI, 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50 for Category B-D Reactor Pressure Vessel IRPV) Assembly Welds. Automated transverse and parallel scans were performed in accordance with procedures GE-UT-704 V8 and GE-UT-705 V5, using 450 Shear wave, 600 RL, and 700 RL search units, supplemental 0' L-Wove scans were also performed. Nozzle Inner 15%T circ scans were performed in accordance with Model validated search unit angles. Automated scanning was performed from the vessel OD surface. and was restricted due to the nozzle configuration. The GERIS 2000 OD automated UT system 0 reference is located at 900 CW of nozzle TDC. Note-The N6B is located at 315* Az. No relevant indications were recorded. Automated Composite Coverage = 70.5% The examination results were compared with data report D-453 from L2R03 outage with [ No Change These examinations were performed under Work Order: N/A E] Change This summary and the following data sheets have been reviewed and accepted by the following personnel: Pi,"Pared ey: LeDel 'ate: Utility Revie. 2y Date: rill Rpe, /ed ,', Dote
-'oqe I of ;
Page 425
03 03 IReactor PressureVessel C I'3 GE Energy - Nuclear jCoverage Calculation Sheet C 0 -4 LaSalle Unit-2, 2007 LCS-2-N6B L2R11 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume = 59.1 Area Sq. In. Area Scanned of Area Weld Length Percent 600 T-Scan (S4 UC) A* 8.5 8.5 14.4% 360 7.2% 450 T-Scan (S6 FV) A* 39.2 33.5 56.7% 360 28.3% 700 T-Scan (S6 NS) A* 11.4 5.8 9.8% 360 4.9% IRS P-Scan (S4 UC) A 8.5 8.5 14.4% 360 7.2% 45' P-Scan (S6 FV) A 39.2 22.5 38.1% 360 19.0% 700 P-Scan (S6 NS) A 11.4 4.5 7.6% 360 3.8% 600 T-Scan (S4 UC) 450 T-Scan (S6 FV) 70' T-Scan (S6 NS) IRS P-Scan (S4 UC) 450 P-Scan (S6 FV) 700 P:Scan (S6 NS) 600 T-Scan (S4 UC) 450 T-Scan (S6 FV) 70' T-Scan (S6 NS) IRS P-Scan (S4 UC) 450 P-Scan (S6 FV) 70' P-Scan (S6 NS) 03 9/o Iotai C..omposite Coverage= / U. 01o Rev 0 9/23,1'0 Uomments: 0_, Scanning limited due to the nozzle configuration. IRS P-Scan by modeling. A*- Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed iaw. 10CFR50.55a. Note - Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in degrees.
C/) C N)j LaSalle Unit-2 N) C0 CD 4. LCS-2-N6B 70' Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In. 700 T-Scan achieved = 5.8 Sq. In. 450 T-Scan achieved = 33.5 Sq. In. 600 T-Scan achieved = 8.5 Sq. In. I!/ 17.25" 70'T 45'T 60 'T I I
---A CD (0
CD
CD) C: M, N)j LaSalle Unit-2 0Q LCS-2-N6B 700 Exam Volume = 11.4 Sq. In. 450 Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60'T) = 8.5 Sq. In. 700 P-Scan achieved = 4.5 Sq. In. 450 P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model) -0 CD 00 17.25" I 70*P 45'P I I F-H--- --- H CD 0
Site: LaSalle Component ID: LCS-2-N9A Outage: L2R11 N-SH System: RPV ASME Cat.: B-D ASME Item 83.90 Aug Req SECT XI Exams Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level Dote Performed Personnel 600 Shear D-076 N/A GE-UT-311 Ver/Rev 15 01-92-01 Phillip Hopkins II 3/6/2007 600 RL D-074 N/A GE-UT-300 Ver/Rev 10 01-92-01 Wallace Reid If 3/6/2007 60* RIL D-075 N/A GE-UT-300 Ver/Rev 10 CAL-IIW2-017 Wallace Reid II 3/6/2007 Examination Results: Ultrasonic examination results were acceptable to the requirements of ASME 8&PV Code Section Xl, 1989 Edition no. Addenda, and Section X1. 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register, Part II,Nuclear Regulatory Commission, 10 CFR Part 50 of Category 8-D Reactor Pressure Vessel (RPVI Assembly Welds. Manual transverse and parallel scans were performed from the vessel OD surface in accordance with procedure GE-UT-300 V10, using 60° RIL search units. Manual parallel scans of the inner 15%T volume were performed in accordance with procedure GE-UT-311 V15 using model validated shear wave search units. Manual scanning was restricted due to the nozzle configuration. The manual exams recorded no indications. Manual UT composite coverage = 82.9% Examination results were compared to data report 95-472 from 3/31/1995 outage with , No Change These examinations were performed under Work Order: Change This Summary and the following data sheets have been reviewed and accepted by the following personnelR. RWP:
' 'CL,. "5"'e Dose: 164 mr.
Prepared By Date: Utility Review. Date: ANII Review. Dote: Page 1 of 1 Page 429
I-w C,)
- 0) EN ReactorPressureVessel C
GE Energy - Nuclear Coverage Calculation Sheet N N) C C LaSalle Unit-2, 2007 LCS-2-N9A L2R11 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume = 59.6 Area Sq. In. Area Scanned of Area Weld Length Percent 60" T-Scan (S4) A 8.5 8.5 14.3% 360 7.1% 600 T-Scan (S6) A 51.1 38.1 63.9% 360 32.0% IRS P-Scan (S4) A* 8.5 8.5 14.3% 360 7.1% 60' P-Scan (S6) A 51.1 43.7 73.3% 360 36.7% 600 T-Scan (S4). 600 T-Scan (S6) IRS P-Scan (S4) 60' P-Scan (S6) 600 T-Scan (S4) _ _ _ _ _ _H__ ____ 60' T-Scan (S6) "" IRS P-Scan (S4) 60' P-Scan (S6) 600 T-Scan (S4) ... ...
- 60. T-Scan S6) ,, .
IRS P-Scan (S4) 60° P-Scan (S6)
% Total Composite Coverage = 82.9%
-o Comments: A* - Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed iaw. 10CFR50.55a. Note - Rounding methods may affect calculated values. Weld length in degrees.
_ LaSalle Unit-2 MLCS-2-N9A 0J 60* S4 Exam Volume = 8.5 Sq. In. 60° S6 Exam Volume = 51.1 Sq. In. 60' S4 Inner 15%T IRS-Scan achie\ved = 8.5 Sq. In. 60' S6 P-Scan achieved = 38.1 Sq. In. 600 S4 T-Scan achieved = 8.5 Sq. Ir.i1. 60' S6 T-Scan achieved = 43.7 Sq. In.
/ 0.0" 0.0" 9.2" 15.6" 60°P 60°T I
NII CD H -----
Site: LaSalle Component ID: LCS-2-N98 Outage: L2R11 N-SH System: ASME Cot.: B-D ASME Item 83. 90 Aug Req SECT XI Exams Data Sheet Cal Sheet Procedure Calibration Block Examination Cert Level. Dote Performed Personnel 60"Shear D-083 N/A GE-UT-311 Ver/Rev 15 01-92-01 Wallace Reid I 3/7/2007 60 RL D-077 - N/A GE-UT-300 Ver/Rev 10 CAL-IIW2-017 Wallace Reid II 3/7/2007 600 RL D-078 N/A GE-UT-300 Ver/Rev 10 01-92-01 Wallace Reid II 3/7/2007 Examination Results: Ultrasonic examination results were acceptable to the requirements of ASME B&PV Code Section XI, 1989 Edition no. Addenda, and Section Xl. 1995 Edition with the 1996 Addenda as modified by the PDI program description and the Federal Register. Port II,Nuclear Regulatory Commission. 10 CFR Part 50 of Category B-D Reactor Pressure Vessel (RPV) Assembly Welds;. Manual transverse and parallel scans were performed from the vessel OD surface in accordance with procedure GE-UT-300 VIO, using 60° RI search units. Manual parallel scans of the inner 15%T volume were performed in accordance with procedure GE-UT-311 VIS using model validated shear wove search units. Reference nozzle inner radius and bore inspection requirement sheet included in report 2R11-025. Manual scanning was restricted due to the nozzle configuration. The manual exams recorded no indications. Manual UT composite coverage = 82.9% Examination results were compared to data report 95-474 from 3/31/1995 outage with ¢' No Change These examinations were performed under Work Order: Change This Summary and the following data sheets have been reviewed and accepted by the following personnel: RWP:
"7 . . , 7 Dose: 145 , mr.
Prepared By: . Date: Utility Review. Date: ANII Review. Dote: Page 1 of , Page 432
I-0) cn
- 0) ReactorPressureVessel C
GE Energy - Nuclear Coverage CalculationSheet N) N) 0 0
-4 LaSalle Unit-2, 2007 LCS-2-N9B L2R11 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume = 59.6 Area Sq. In. Area Scanned of Area Weld Length Percent 600 T-Scan (S4) A 8.5 8.5 14.3% 360 7.1%
60' T-Scan (S6) A 51,1 38.1 63.9% 360 32.0% IRS P-Scan (S4) A* 8.5 8.5 14.3% 360 7.1% 600 P-Scan (S6) A 51.1 43.7 73.3% 360 36.7% 600 T-Scan (S4) 60' T-Scan (S6) IRS P-Scan (S4) 60' P-Scan (S6) 60°'T-Scan (S4) 60' T-Scan (S6) IRS P-Scan (S4) 600 P-Scan (S6) _ i60* T-Scan (S4) 600 T-Scan (S6) IRS P-Scan (S4) N 600 P-Scan (S6)
/o I otal C;omposite Coverage = 82.9%
/ i ý - I I - Reý 0 9/2310 5
- 0) Comments: / h '. *'.- r~o~ U (0-A*- Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed iaw. 10CFR50.55a.
Note - Rounding methods may affect calculated values. Weld length in degrees.
I-- SLaSalle Unit-2 LCS-2-N9B 0D 60° S4 Exam Volume = 8.5 Sq. In. -- 60' S6 Exam Volume = 51.1 Sq. In. 600 S4 Inner 15%T IRS-Scan achie ved = 8.5 Sq. In. 60' S6 P-Scan achieved = 38.1 Sq. In. 60' S4 T-Scan achieved = 8.5 Sq. I n. 0., 60' S6 T-Scan achieved = 43.7 Sq. In.
/0.0" 9.2" 15.6" 16 60*
/ -- I--- ---
-9'
- Li "1 t
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Components Affected 0 Unit 1 Reactor Pressure Vessel (RPV) Top Head, Head to Flange Weld Weld Identification Number GEL-1009-AG Applicable Code Requirements IWB-2500, Table IWB-2500-1, Examination Category B-A, Item Number B1.40 and Figure IWB-2500-5 Impracticality of Compliance The RPV upper head plate and flange materials are carbon steel. The plate material is A-533 Grade B, Class 1 and the flange ring is SA-508 Class 2. During the ultrasonic examination of the head to flange weld, reduced coverage was obtained. The coverage reported represents the aggregate coverage from all scans performed on the weld and adjacent base material. Scanning is limited in the parallel direction. The ultrasonic transducers cannot maintain contact due to the curvature of the flange base material in the area of the weld. In order to scan all of the required volume for this weld, the head to flange joint would need to be redesigned to allow scanning from the flange side of the weld, which is impractical. Justification for Granting Relief Ultrasonic examination of approximately 50 percent of the circumferential length of the head to flange weld was conducted during the first inspection period of the second 10-year Inservice Inspection (ISI) interval using personnel, equipment and procedures qualified in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, 1989 Edition. Ultrasonic examination of approximately 50 percent of the remaining circumferential length of the head to flange weld was conducted during the third inspection period of the second 10-year ISI interval using personnel, equipment and procedures qualified in accordance with ASME Code, Section Xl, 1989/1995 Edition with 1996 Addenda and the applicable requirements of the Performance Demonstration Initiative (PDI). A magnetic particle examination of 100% of the required surface of the head to flange weld was also completed during the second interval. There were no recordable indications found during the inspections of this weld. Fifty percent of the head to flange weld has been re-examined in the first period of the current third 10-year ISI interval using personnel, equipment and procedures qualified in accordance with ASME Code, Section Xl, 2001 Edition with 2003 Addenda and the applicable requirements of the PDI. No indications were recorded with the ultrasonic examination. One indication, 0.125 inches in length was recorded during the surface examination. The indication was acceptable based on IWB-3510.3 of the 2001 Edition with 2003 Addenda of ASME Code, Section Xl. IWB-2500, Table IWB-2500-1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide further assurance of pressure boundary integrity. In addition to the above ASME Code required examinations (i.e., volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through this weld, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications 3.4.5, Page 1 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations "Reactor Coolant System Operational Leakage," provide additional assurance that any leakage would be detected prior to gross failure of the component. The head to flange weld was rigorously inspected by volumetric non-destructive examination (NDE) methods during construction and verified to be free from unacceptable fabrication defects. Based on the coverage and results of the surface, volumetric, and the pressure testing VT-2 examinations performed, this combination of examinations provides a reasonable assurance of quality and safety. Page 2 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Component Affected Unit 1 RPV Shell to Flange Weld Weld Identification Number LCS-1-AF Applicable Code Requirements IWB-2500, Table IWB-2500-1, Examination Category B-A, Item Number B1.30 and Figure IWB-2500-4 Impracticality of Compliance The RPV upper shell plate and flange materials are carbon steel. The plate material is A-533 Grade B, Class 1 and the flange ring is SA-508 Class 2. During the ultrasonic examination of the shell to flange weld, reduced coverage was obtained. The coverage reported represents the aggregate coverage from all scans performed on the weld and adjacent base material. Scanning is limited in both the parallel and transverse directions. The ultrasonic transducers cannot maintain contact due to the curvature of the flange base material in the area of the weld. In order to scan all of the required volume for this weld, the shell to flange joint would need to be redesigned to allow scanning from the flange side of the weld, which is impractical. Justification for Granting Relief Ultrasonic examination of 100 percent of the circumferential length of the shell to flange weld was conducted during the first inspection period of the second 10-year ISI interval using personnel, equipment and procedures qualified in accordance with ASME Code, Section XI, 1989 Edition. There were no recordable indications found during the inspection of this weld. The shell to flange weld has been re-examined in the first period of the third 10-year ISI interval using personnel, equipment and procedures qualified in accordance with ASME Code, Section Xl, 2001 Edition with 2003 Addenda and the applicable requirements of the PDI. No indications were found. IWB-2500, Table IWB-2500-1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide further assurance of pressure boundary integrity. In addition to the above ASME Code required examinations (i.e., volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through this weld, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications 3.4.5, "Reactor Coolant System Operational Leakage," provide additional assurance that any leakage would be detected prior to gross failure of the component. The shell to flange weld was rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the coverage and results of the volumetric and the pressure testing VT-2 examinations performed, this combination of examinations provides a reasonable assurance of quality and safety. Page 3 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Components Affected
- Unit 1 RPV Top Head, Head Meridional Welds Weld Identification Numbers GEL-1009-DM, DP, DR and DT Applicable Code Requirements IWB-2500, Table IWB-2500-1, Examination Category B-A, Item Number B1.22 and Figure IWB-2500-3 Impracticality of Compliance The RPV upper head plate materials are carbon steel. The plate material is A-533 Grade B, Class 1. During the ultrasonic examination of the head meridional welds, reduced coverage was obtained. The coverage reported represents the aggregate coverage from all scans performed on the weld and adjacent base material. Scanning is limited in the parallel and transverse directions due to the presence of 6.5 inch wide, 24 inch long lifting lugs. The lugs are welded to the shell plates directly over these four meridional welds. The ultrasonic transducers cannot physically access the adjacent surfaces of the welds and base metal. In order to scan all of the required volume for these welds, the head and associated lifting lugs would need to be redesigned to allow access to 100 percent of the welds, which is impractical.
Justification for Granting Relief Ultrasonic examination of two of the welds, DM and DP, was conducted during the first inspection period of the second 10-year ISI interval using personnel, equipment and procedures qualified in accordance with ASME Code, Section Xl, 1989 Edition. Ultrasonic examination of the remaining two welds, DR and DT, was conducted during the third inspection period of the second 10-year ISI interval using personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 1989/1995 Edition with 1996 Addenda and the applicable requirements of the PDI. There were no recordable indications found during the inspections of these four welds. Welds DM and DP have been re-examined in the first period of the third 10-year ISI interval using personnel, equipment and procedures qualified in accordance with the ASME Code, Section XI, 2001 Edition with 2003 Addenda and the applicable requirements of the PDI. No indications were recorded. IWB-2500, Table IWB-2500- 1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide further assurance of pressure boundary integrity. In addition to the above ASME Code required examinations (i.e., volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through this weld, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications 3.4.5, "Reactor Coolant System Operational Leakage," provide additional assurance that any leakage would be detected prior to gross failure of the component. The RPV head welds were rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the coverage and results of the volumetric and the pressure testing VT-2 examinations performed, this combination of examinations provides a reasonable assurance of quality and safety. Page 4 of 28
'ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Component Affected Unit 1 RPV Nozzle to Shell Welds Weld Identification Numbers LCS-1-N1 A, N1B, N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, N2K, N3A, N3B, N3C, N3D, N4A, N4B, N4C, N4D, N4E, N4F, N5, N6A, N6B, N6C, N7, N8, N10, N16 and N18 Applicable Code Requirements IWB-2500, Table IWB-2500-1, Examination Category B-D, Item Number B3.90 and Figure IWB-2500-7(b)
Impracticality of Compliance The RPV shell plates and nozzle materials are carbon steel. The plate material is A-533 Grade B, Class 1 and the nozzles are SA-508 Class 2. During the ultrasonic examination of these nozzle to shell welds, reduced coverage was obtained. The coverage reported represents the aggregate coverage from all scans performed on the weld and adjacent base material. Scanning is limited in both the parallel direction and transverse directions. The ultrasonic transducers cannot maintain contact due to the curvature of the nozzle base material in the area of the weld. Scanning from the nozzle forging side of the welds is not possible due to tapered areas in the forgings. In order to scan all of the required volume for this weld, the nozzles would need to be redesigned to allow scanning from the nozzle side of the welds, which is impractical. Justification for Granting Relief during the first and second Ultrasonic examinations of the nozzle to shell welds conducted inspection periods of the second 10-year ISI interval (i.e., seventh, eight, and ninth outages) used personnel, equipment and procedures qualified in accordance with the ASME Code, Section XI, 1989 Edition. Ultrasonic examinations of the nozzle to shell welds conducted during the third inspection period of the second 10-yea r ISI interval (i.e., eleventh outage) used personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 1989/1995 Edition with 1996 Addenda and the applicable requirements of the PDI. Indications were recorded during these examinations as described in the supplemental information. These indications were acceptable to the applicable requirements of Section Xl, and none of the indications required flaw evaluation. Nozzle to shell welds LCS-1-N1A, NIB, N3A, N3B, N3C, and N3D have been re-examined in the first period of the third 10-year ISI interval using personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 2001 Edition with 2003 Addenda and the applicable requirements of the PDI. No indications were recorded. IWB-2500, Table IWB-2500- 1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide further assurance of pressure boundary integrity. In addition to the above ASME Code required examinations (i.e., volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through this weld, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications 3.4.5, "Reactor Coolant System Operational Leakage," provide additional assurance that any leakage would be detected prior to gross failure of the component. The nozzle to shell welds were rigorously inspected by volumetric NDE methods Page 5 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations during construction and verified to be free from unacceptable fabrication defects. Based on the coverage and results of the volumetric and the pressure testing VT-2 examinations performed, this combination of examinations provides a reasonable assurance of quality and safety. Page 6 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Components Affected 0 Unit 1 RPV Bottom Head, RPV Shell to Bottom Head Weld Weld Identification Number GEL-1006-AJ Applicable Code Requirements IWB-2500, Table IWB-2500-1, Examination Category B-A, Item Number B1.21 and Figure IWB-2500-3 Impracticality of Compliance The RPV lower intermediate shell course plate and bottom head assembly materials are carbon steel A-533 Grade B, Class 1. During the ultrasonic examination of the shell course to bottom head weld, reduced coverage was obtained. The coverage reported represents the aggregate coverage from all scans performed of the weld and adjacent base material. No scanning can be performed from the bottom side of the weld due to the presence of the reactor support skirt and the welded pad to which it is attached. Scanning is limited from the top side of the weld in both the parallel and transverse directions for the same reason. The ultrasonic transducers cannot physically contact all of the required areas due to the pad and skirt attachment in the area of the weld. In order to scan all of the required volume for this weld, the RPV support skirt attachment would need to be redesigned to allow complete scanning of the weld, which is impractical. Justification for Granting Relief Ultrasonic examination of the RPV shell to bottom head weld was conducted during the third inspection period of the second 10-year ISI interval using personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 1989/1995 Edition with 1996 Addenda, and the applicable requirements of the PDI. There were no recordable indications found during the inspections of this weld. IWB-2500, Table IWB-2500-1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide further assurance of pressure boundary integrity. In addition to the above ASME Code required examinations (i.e., volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through this weld, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications 3.4.5, "Reactor Coolant System Operational Leakage," provide additional assurance that any leakage would be detected prior to gross failure of the component. The RPV shell to bottom head weld was rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the coverage and results of the surface, volumetric and the pressure testing VT-2 examinations performed, this combination of examinations provides a reasonable assurance of quality and safety. Page 7 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Component Affected Unit 1 RPV Shell Vertical Welds Weld Identification Number LCS-1-BG and BH Applicable Code Requirements IWB-2500, Table IWB-2500-1, Examination Category B-A, Item Number B1i.12 and Figure IWB-2500-2 Impracticality of Compliance The RPV middle shell course is constructed of three plates joined by three vertical welds. The plate material is carbon steel, A-533 Grade B, Class 1. During the ultrasonic examination of two of the vertical welds, LCS-1 -BG and BH, reduced coverage was obtained. The coverage reported represents the aggregate coverage from all scans performed on the welds and adjacent base material. Scanning is limited in both the parallel direction and transverse directions. Vertical weld LCS-1 -BG scanning is limited on both sides as well as above and below the welded pad area surrounding instrument nozzle N12-A. Fabrication details for the instrument nozzle and associated welded pad are shown on drawing E-232-938 (i.e., page 7 of ). The ultrasonic transducers cannot contact the weld or the surrounding base material as the N12-A nozzle pad is welded directly over the vertical weld. 100 percent of the accessible volume was examined including the intersecting portions of circumferential welds LCS-1 -AD and LCS-1 -AC above and below vertical weld LCS-1 -BG. Vertical weld LCS-I -BH scanning is limited on both sides, as well as above and below due to the presence of the LCS-1-N6B nozzle forging. During fabrication, the installation of the nozzle forging proceeded directly through the vertical weld area. The presence of the forging and the associated nozzle to shell weld does not allow contact by ultrasonic transducers of the vertical weld or the surrounding base material. Scanning of the intersecting portions of circumferential welds LCS-1 -AD and LCS-1 -AC above and below respectively, vertical weld LCS-1 -BH was completed with minor interference on the upper right side of the vertical weld due to the presence of welded thermocouple brackets. In order to scan all of the required volume for these two vertical welds, the instrument nozzle, the LCS-1-N6B nozzle forging, and the thermocouple brackets would need to be redesigned and relocated to for allow additional scanning, which is impractical. Justification for Granting Relief Ultrasonic examinations of vertical welds LCS-1-BG and BH were conducted during the first inspection period of the second 10-year ISI interval used personnel, automated equipment and procedures qualified in accordance with the ASME Code, Section Xl, 1989 Edition. At the time of the examinations, some data was collected and recorded electronically from only one side of the vertical welds due to the limitations described. Procedurally, this single sided examination data could not be credited at that time. Later, during the second inspection period, the previously collected data was re-evaluated using the same inspection procedure which was now qualified for single-sided access. This resulted in a small increase in the amount of coverage initially obtained in the first inspection period. Indications were recorded during these examinations that were determined acceptable to the applicable requirements of Section Xl, and Page 8 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations none of the indications required flaw evaluation. IWB-2500, Table IWB-2500- 1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide further assurance of pressure boundary integrity. In addition to the above ASME Code required examinations (i.e., volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through this weld, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications 3.4.5, "Reactor Coolant System Operational Leakage," provide additional assurance that any leakage would be detected prior to gross failure of the component. The RPV shell vertical welds were rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the coverage and results of the volumetric and the pressure testing VT-2 examinations performed, this combination of examinations provides a reasonable assurance of quality and safety. Page 9 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Component Affected Unit 1 RPV Stabilizer Lug Weld Identification Number RPV-SS-1 Applicable Code Requirements Code Case N-509, Table IWB-2500-1, Examination Category B-K, Item Number B10.10 and Figure IWB-2500-15 Impracticality of Compliance There are six RPV stabilizer support bracket attachment lugs equally spaced around the outside circumference of the RPV at the upper intermediate shell course elevation. The attachment lugs and the shell course are constructed of carbon steel, A-533 Grade B, Class 1 material. The attachment lugs are 14 inches wide by 7 inches high, and full penetration welded to the RPV shell. During the ASME Code Case required surface examination of the required attachment weld, RPV-SS-1, reduced coverage was obtained due to other plant structures and components. Accessibility to 100 percent of the examination areas for these welds is limited due to the proximity of the bioshield wall, the stabilizer assembly bar, and vessel insulation. The entire 14 inches of the lower horizontal length of the weld is inaccessible for surface examination due to the biological shield wall and the stabilizer assembly bar. The 14 inches of the top horizontal length and both 7 inch side weld lengths are inaccessible for surface examination without cutting and then repairing the insulation. The surface examination coverage obtained was approximately 66 percent of the entire weld surface. Due to the vessel insulation being panel-type and linked by several small screws which are inaccessible for the subject panels due to the stabilizer bars and brackets, the ability to remove the insulation is not practical due to the tight clearances and potential to damage the fasteners and insulation joints. To provide even limited surfaced examination coverage, the insulation must be cut and then repaired. These activities must be done in an elevated dose rate field. Justification for Granting Relief Accessibility to 100 percent of the examination areas for these welds is limited due to the proximity of the bioshield wall, the stabilizer assembly bar, and vessel insulation. Accessibility was not provided in the original plant design which occurred prior to the issuance of ASME Code, Section XI, ISI requirements. The required surface examination of the vessel stabilizer bracket attachment weld is not possible due to the proximity of the bioshield wall, the stabilizer bar, and vessel insulation. Approximately 66 percent of the required area was examined and no indications were detected. To supplement the reduced coverage, a VT-1 visual examination was performed of essentially 100 percent of the attachment weld and no indications were detected. Additionally, IWB-2500, Table IWB-2500- 1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide further assurance of pressure boundary integrity. In addition to the above ASME Code required examinations (i.e., volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through this weld, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications 3.4.5, "Reactor Coolant System Operational Leakage," provide Page 10 of 28
ATFACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations additional assurance that any leakage would be detected prior to gross failure of the component. The RPV stabilizer support bracket attachment welds were rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the surface examination coverage the pressure testing VT-2 examinations performed and results of the VT-1 visual examination performed, Exelon Generation Company, LLC (EGC) concluded that if significant service-induced degradation would have occurred, there is reasonable assurance that evidence of it would have been detected by the examinations performed. Therefore, the examinations provide a reasonable assurance of quality and safety. For the current third 10-year ISI interval, relief was requested in Relief Request 13R-04, which was granted by the NRC on January 30, 2008 for these examinations. For the third 10-year ISI, alternative examination requirements will be implemented by performing a VT-1 visual examination on the accessible portions of the stabilizer bracket welds, when one of these lugs is scheduled for examination in accordance with the ASME Code, Section Xl. Page 11 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Component Affected Unit 1 Residual Heat Removal Heat Exchanger Welded Attachment Weld Identification Number IRH-HX1B-08A Applicable Code Requirements Code Case N-509, Table IWC-2500-1, Examination Category C-C, Item Number C3.10 and Figure IWC-2500-5 Impracticality of Compliance There are four welded attachments to the 1B Residual Heat Removal (RHR) Heat Exchanger, one in each quadrant of the vertically oriented vessel in the lower middle shell course. The attachment lugs and the shell course are constructed of carbon steel, SA-516 Grade 70, material. Only one of the four lugs at this location is required to be examined. The attachment lugs are constructed of two horizontally oriented plates 26.5 inches apart, full penetration welded to the vessel shell. The upper plate is 28 inches long and 1 inch thick. The lower plate is 30 inches long and 2.50 inches thick. Connecting the two horizontal plates are three equally spaced, vertically oriented gusset plates, each 1 inch thick and 26.5 inches long. The three gussets are vertically full penetration welded to the vessel, and horizontally full penetration welded to the upper and lower horizontal plates. The lower horizontal plate sits atop and is bolted to the upper flange of a structural beam. During the ASME Code Case required surface examination of the attachment weld, reduced coverage was obtained due to the presence of the structural beam. Its location makes the entire 30 inch length of the lower horizontal plate to vessel shell inaccessible for surface examination. The surface examination coverage obtained was approximately 76 percent of the entire attachment weld surface. Due to the design and construction of the attachment and structural beam, removal of the beam is not practical. The beam provides support of the vessel and its removal would require design and installation of alternative temporary supports so the structural integrity of the vessel would not be negatively affected. Removal of the beam and installation of any temporary supports would be done in an elevated dose rate field. Justification for Granting Relief Accessibility to 100 percent of the examination areas for these attachment welds is limited due to the presence of a structural beam. Accessibility was not provided in the original plant design which occurred prior to the issuance of ASME Code, Section Xl, ISI requirements. The required surface examination of the vessel attachment weld is not practical due to the design and construction of the attachment and the structural beam. Approximately 76 percent of the required area was examined and no indications were detected. Additionally, IWC-2500, Table IWC-2500-1, Examination Category C-H Pressure tests and VT-2 visual examinations performed each period provide further assurance of pressure boundary integrity. All of the attachment welds were examined by surface NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the surface examination coverage the pressure testing VT-2 examinations performed, EGC concluded that if significant service-induced degradation would have occurred, there is reasonable assurance that evidence of it Page 12 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations would have been detected by the examinations performed. Therefore the examinations provide a reasonable assurance of quality and safety. Page 13 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Component Affected Unit 1 High Pressure Core Spray Pump, and Low Pressure Core Spray Pump and Residual Heat Removal Pump Welded Attachments Weld Identification Numbers IHP-PU1 -04, ILP-PU-04 and IRH-PU1 C-04 Applicable Code Requirements Code Case N-509, Table IWC-2500-1, Examination Category C-C, Item Number C3.30 and Figure IWC-2500-5 Impracticality of Compliance The High Pressure Core Spray (HPCS), Low Pressure Core Spray (LPCS), and RHR pumps are vertical shaft pumps and are all encased in concrete. The pressure retaining shell portions of the pumps are welded to the bottom of base plates that are bolted to and rest on concrete foundations. The foundations are raised above the floor and the casings extend below floor level into concrete vaults. Each concrete foundation has an opening in one side that allows the suction piping to attach to the pump suction flange just above the floor level. The base plates and the shells are constructed of carbon steel, A-516 Grade 70, material. The base plates are 3.5 inches thick. During the ASME Code Case required surface examination of the attachment weld, reduced coverage was obtained due to the presence of the concrete foundations. The opening in the foundations allow for between 16 and 24 percent of the attachment weld length to be examined. No indications were recorded during these limited examinations. The remaining lengths of the welds are inaccessible as they are beneath and behind the concrete foundations. Due to the design and construction of the attachments and concrete foundations, removal of the pump to perform the ASME Code Case required surface examination is not practical. The foundation provides support to the pump shell and also the pump discharge head and motor. This would necessitate removal of the motor and surrounding interferences in order to lift the pump shell out of the vault and foundation, destruction of the concrete components, or their redesign. All of these activities would be done in an elevated dose rate field. Justification for Granting Relief Accessibility to 100 percent of the examination areas for these attachment welds is limited due to the presence of concrete foundations and vaults. Accessibility was not provided in the original plant design that occurred prior to the issuance of ASME Code, Section Xl, ISI requirements. The required surface examination of the vessel attachment weld is not practical due to the design and construction of the pump and their foundations and vaults. Between 16 and 24 percent of the required area was examined and no indications were detected. Additionally, IWC-2500, Table IWC-2500-1, Examination Category C-H Pressure tests and VT-2 visual examinations performed each period provide further assurance of pressure boundary integrity. The attachment welds were examined by surface NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the surface examination coverage and the pressure testing VT-2 examinations performed, EGC concluded that if significant service-induced degradation would have occurred, there is reasonable assurance that evidence Page 14 of 28
ATrACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations of it would have been detected by the examinations performed. Therefore the examinations provide a reasonable assurance of quality and safety. For the current third 10-year ISI interval, relief was requested in Relief Request 13R-03 and granted by the NRC on January 30, 2008, for these examinations. For the third 10-year ISI interval, an approved alternative examination will be implemented. In the event the subject welds become accessible upon disassembly of any one of the pumps, the welds will be surface examined from the inside surface, or a VT-1 visual examination will be performed for that particular pump group to the maximum extent practicable based on the obstructions and geometric constraints detailed in this relief request. The examination method will be determined based on radiation environment data at the time access is enabled. Additionally, a VT-2 visual examination during system pressure testing per ASME Code, Section XI, Examination Category C-H will be performed once each period by examining the surrounding area (e.g., exposed areas around these components where the pump casing join/merge with the concrete) for evidence of leakage in accordance with ASME Code, Section XI, IWA-5241 (b). Page 15 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Component Affected Unit 1 High Pressure Core Spray Pump, and Low Pressure Core Spray Pump and Residual Heat Removal Pump Casing Welds Weld Identification Numbers IHP-PU1-07A, 07B, 07C, 08A, 08B, 08C, and 09, ILP-PU-07, 08, and 09, and IRH-PU1C-07A, 07B, 07C, 08A, 08B, 08C and 09. Applicable Code Requirements Table IWC-2500-1, Examination Category C-G, Item Number C6.10 and Figure IWC-2500-8 Impracticality of Compliance The HPCS, LPCS, and RHR pumps are vertical shaft pumps and are all encased in concrete. The shells are constructed of carbon steel, A-516 Grade 70, material. The design of the pumps makes the welds inaccessible for inservice inspection. Therefore, it is impractical to perform the surface examination of these welds without destruction of the concrete resulting in unnecessary engineering and installation costs and radiation exposure without a compensating increase in safety. Additionally, due to the design of the subject pumps, access to the affected welds can only be achieved through disassembly of the pump, removal of the pump internals, and the required surface examinations performed from the inside surface of the welds. This effort, in the absence of any other necessary pump maintenance, represents a significant expenditure of man-hours and radiation exposure to plant personnel, without a compensating increase in plant safety. All of these activities would be done in an elevated dose rate field. Justification for Granting Relief Accessibility to the examination areas for these welds is limited due to the presence of concrete foundations and vaults. Accessibility was not provided in the original plant design that occurred prior to the issuance of ASME Code, Section Xl, IS[ requirements. The required surface examination of the welds is impractical to perform without destruction of the concrete resulting in unnecessary engineering and installation costs and radiation exposure without a compensating increase in safety. Additionally, due to the design of the subject pumps, access to the affected welds can only be achieved through disassembly of the pump, removal of the pump internals, and the required surface examinations performed from the inside surface of the welds. This effort, in the absence of any other necessary pump maintenance, represents a significant expenditure of man-hours and radiation exposure to plant personnel, without a compensating increase in plant safety. Additionally, IWC-2500, Table IWC-2500-1, Examination Category C-H, Pressure tests and VT-2 visual examinations performed each period provide further assurance of pressure boundary integrity. For the current third 10-year ISI interval, relief has been requested in Relief Request 13R-03 and granted by the NRC on January 30, 2008, for these examinations. For the third 10-year ISI interval, alternative examination requirements will be implemented. In the event the subject welds become accessible upon disassembly of any one of the pumps, the welds will be surface examined from the inside surface, or a VT-1 visual examination will be performed for that particular pump group to the maximum extent practicable based on the obstructions and geometric constraints detailed in this relief request. The examination method will be determined based on radiation environment data at the time access is enabled. Additionally, a VT-2 visual examination during system pressure testing per ASME Page 16 of 28
A1-ACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations Code, Section Xl, Examination Category C-H will be performed once each period by examining the surrounding area (e.g., exposed areas around these components where the pump casing join/merge with the concrete) for evidence of leakage in accordance with ASME Code, Section X1, IWA-5241 (b). Page 17 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Component Affected Unit 2 RPV Top Head, Head to Flange Weld Weld Identification Number GEL- 1060-AG Applicable Code Requirements IWB-2500, Table IWB-2500-1, Examination Category B-A, Item Number B1.40 and Figure IWB-2500-5 Impracticality of Compliance The RPV upper head plate and flange materials are carbon steel. The plate material is A-533 Grade B, Class 1 and the flange ring is SA-508 Class 2. During the ultrasonic examination of the head to flange weld, reduced coverage was obtained. The coverage reported represent the aggregate coverage from all scans performed on the weld and adjacent base material. Scanning is limited in the parallel direction. The ultrasonic transducers cannot maintain contact due to the curvature of the flange base material in the area of the weld. In order to scan all of the required volume for this weld, the head to flange joint would need to be redesigned to allow scanning from the flange side of the weld, which is impractical. Justification for Granting Relief Ultrasonic examination of approximately 50 percent of the circumferential length of the head to flange weld was conducted during the first inspection period of the second 10-year ISI interval using personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 1989 Edition. Ultrasonic examination of approximately 50 percent of the remaining circumferential length of the head to flange weld was conducted during the third inspection period of the second 10-year ISI interval using personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 1989/1995 Edition with 1996 Addenda, and the applicable requirements of the PDI. A magnetic particle examination of 100 percent of the required surface of the head to flange weld was also completed during the second interval. There were no recordable indications found during the inspections of this weld. IWB-2500, Table IWB-2500- 1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide further assurance of pressure boundary integrity. In addition to the above ASME Code required examinations (i.e., volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through this weld, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications 3.4.5, "Reactor Coolant System Operational Leakage," provide additional assurance that any leakage would be detected prior to gross failure of the component. The head to flange weld was rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the coverage and results of the surface, volumetric and the pressure testing VT-2 examinations performed, this combination of examinations provides a reasonable assurance of quality and safety. Page 18 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited. Examinations ASME Code Component Affected Unit 2 RPV Shell to Flange Weld Weld Identification Number LCS-2-AE Applicable Code Requirements IWB-2500, Table IWB-2500-1, Examination Category B-A, Item Number B1.30 and Figure IWB-2500-4 Impracticality of Compliance The RPV upper shell plate and flange materials are carbon steel. The plate material is A-533 Grade B, Class 1 and the flange ring is SA-508 Class 2. During the ultrasonic examination of the shell to flange weld, reduced coverage was obtained. The coverage reported represents the aggregate coverage from all scans performed on the weld and adjacent base material. Scanning is limited in both the parallel and transverse directions. The ultrasonic transducers cannot maintain contact due to the curvature of the flange base material in the area of the weld. In order to scan all of the required volume for this weld, the shell to flange joint would need to be redesigned to allow scanning from the flange side of the weld, which is impractical. Justification for Granting Relief Ultrasonic examination of approximately 50 percent of the circumferential length of the head to flange weld was conducted during the first inspection period of the second 10-year ISI interval using personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 1989 Edition. Ultrasonic examination of approximately 50 percent of the remaining circumferential length of the head to flange weld was conducted during the third inspection period of the second 10-year ISI interval using personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 1989/1995 Edition with 1996 Addenda, and the applicable requirements of the PDI. There were no recordable indications found during the inspections of this weld. The entire shell to flange weld has been re-examined in the first period of the third 10-year ISI interval using personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 2001 Edition 2003 Addenda and the applicable requirements of the PDI. No indications were recorded during the examination. IWB-2500, Table IWB-2500-1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide further assurance of pressure boundary integrity. In addition to the above ASME Code required examinations (i.e., volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through this weld, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications 3.4.5, "Reactor Coolant System Operational Leakage," provide additional assurance that any leakage would be detected prior to gross failure of the component. The shell to flange weld was rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the coverage and results of the volumetric and the pressure testing VT-2 examinations performed, this combination of examinations provides a reasonable assurance of quality and safety. Page 19 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Component Affected Unit 2 RPV Bottom Head, Head Meridonal Welds Weld Identification Number GEL-1061-DA, DE, DF Applicable Code Requirements IWB-2500, Table IWB-2500-1, Examination Category B-A, Item Number B1.22 and Figure IWB-2500-3 Impracticality of Compliance The RPV bottom head plate materials are carbon steel. The plate material is A-533 Grade B, Class 1. During the ultrasonic examination of the head meridonal welds, reduced coverage was obtained. The coverage reported represent the aggregate coverage from all scans performed on the weld and adjacent base material. No scanning can be performed from the bottom side of the weld due to the presence of the reactor support skirt and the welded pad to which it is attached. Scanning is limited from the top side of the weld in both the parallel and transverse directions for the same reason. The ultrasonic transducers cannot physically contact all of the required due to the pad and skirt attachment in the area of the weld. In order to scan all of the required volume for this weld, the RPV support skirt attachment would need to be redesigned to allow complete scanning of the weld, which is impractical. Justification for Granting Relief Ultrasonic examination of the welds used personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 1989/1995 Edition with 1996 Addenda and the applicable requirements of the PDI. There were no recordable indications found during the inspections of these three welds. All three of these welds have been re-examined in the first period of the third 10-year ISI interval using personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 2001 Edition with 2003 Addenda and the applicable requirements of the PDI. No indications were recorded during the examinations. IWB-2500, Table IWB-2500-1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide further assurance of pressure boundary integrity. In addition to the above ASME Code required examinations (i.e., volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through this weld, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications 3.4.5, "Reactor Coolant System Operational Leakage," provide additional assurance that any leakage would be detected prior to gross failure of the component. The RPV head welds were rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the coverage and results of the volumetric and the pressure testing VT-2 examinations performed, this combination of examinations provides a reasonable assurance of quality and safety. Page 20 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Component Affected Unit 2 RPV Nozzle to Shell Welds Weld Identification Numbers LCS-2-N1A, N1B, N2A, N2B, N2C, N2D, N2E, N2F, N2G, N2H, N2J, N2K, N3A, N3B, N3C, N3D, N4A, N4B, N4C, N4D, N4E, N4F, N5, N6A, N6B, N6C, N7, N8, N10, N16, and N18 Applicable Code Requirements IWB-2500, Table IWB-2500-1, Examination Category B-D, Item Number B3.90 and Figure IWB-2500-7(b) Impracticality of Compliance The RPV shell plates and nozzle materials are carbon steel. The plate material is A-533 Grade B, Class 1 and the nozzles are SA-508 Class 2. During the ultrasonic examination of these nozzle to shell welds, reduced coverage was obtained. The coverage reported represents the aggregate coverage from all scans performed on the weld and adjacent base material. Scanning is limited in both the parallel direction and transverse directions. The ultrasonic transducers cannot maintain contact due to the curvature of the nozzle base material in the area of the weld. Scanning from the nozzle forging side of the welds is not possible due to tapered areas in the forgings. In order to scan all of the required volume for this weld, the nozzles would need to be redesigned to allow scanning from the nozzle side of the welds, which is impractical. Justification for Granting Relief Ultrasonic examinations of the nozzle to shell welds conducted during the first inspection period and portions of the second inspection period of the second 10-year ISI interval (i.e., seventh and eighth outages) used personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 1989 Edition. Ultrasonic examinations of the nozzle to shell welds conducted during portions of the second inspection period of the second 10-year ISI interval (i.e., ninth outage) and the third inspection period of the second 10-year ISI interval (i.e., tenth and eleventh outage) used personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 1989/1995 Edition with 1996 Addenda, and the applicable requirements of the PDI. Indications were recorded during these examinations, which were determined acceptable to the applicable requirements of the ASME Code, Section XI. None of the indications required flaw evaluation. Nozzle to shell welds LCS-2-N1A, N1B, N2C, N3A, N3B, N3C, N3D, N6A, N6C, and N10 have been re-examined in the first period of the third 10-year ISI interval using personnel, equipment and procedures qualified in accordance with the ASME Code, Section Xl, 2001 Edition with 2003 Addenda, and the applicable requirements of the PDI. No indications were recorded. IWB-2500, Table IWB-2500-1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide further assurance of pressure boundary integrity. In addition to the above ASME Code required examinations (i.e., volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through this weld, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications 3.4.5, "Reactor Coolant System Operational Leakage," provide additional assurance that any leakage would be detected prior to gross failure of the Page 21 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations component. The nozzle to shell welds were rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Based'on the coverage and results of the volumetric and the pressure testing VT-2 examinations performed, this combination of examinations provides a reasonable assurance of quality and safety. Page 22 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Component Affected Unit 2 RPV Stabilizer Lug Weld Identification Number RPV-SS-2 Applicable Code Requirements Code Case N-509, Table IWB-2500-1, Examination Category B-K, Item Number B10.10 and Figure IWB-2500-14 Impracticality of Compliance There are six RPV stabilizer support bracket attachment lugs equally spaced around the outside circumference of the RPV at the upper intermediate shell course elevation. The attachment lugs are and the shell course are constructed of carbon steel, A-533 Grade B, Class 1 material. The attachment lugs are 14 wide by 7 inches high, and full penetration welded to the RPV shell. During the ASME Code Case required surface examination of the required attachment weld, RPV-SS-1, reduced coverage was obtained due to other plant structures and components. Accessibility to 100 percent of the examination areas for these welds is limited due to the proximity of the bioshield wall, the stabilizer assembly bar, and vessel insulation. The entire 14 inches of the lower horizontal length of the weld is inaccessible for surface examination due to the biological shield wall and the stabilizer assembly bar. The 14 inches of the top horizontal length and both 7 inch side weld lengths are inaccessible for surface examination without cutting and then repairing the insulation. The surface examination coverage obtained was approximately 52 percent of the entire weld surface. Due to the vessel insulation being panel-type and linked by several small screws which are inaccessible for the subject panels due to the stabilizer bars and brackets, the ability to remove the insulation is not practical due to the tight clearances and potential to damage the fasteners and insulation joints. To provide even limited surfaced examination coverage, the insulation must be cut and then repaired. These activities must be done in an elevated dose rate field. Justification for Granting Relief Accessibility to 100 percent of the examination areas for these welds is limited due to the proximity of the bioshield wall, the stabilizer assembly bar, and vessel insulation. Accessibility was not provided in the original plant design which occurred prior to the issuance of ASME Code, Section Xl, ISI requirements. The required surface examination of the vessel stabilizer bracket attachment weld is not possible due to the proximity of the bioshield wall, the stabilizer bar, and vessel insulation. Approximately 52 percent of the required area was examined and no indications were detected. To supplement the reduced coverage, a VT-1 visual examination was performed of essentially 100 percent of the attachment weld and no indications were detected. Additionally, IWB-2500, Table IWB-2500- 1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide further assurance of pressure boundary integrity. In addition to the above ASME Code required examinations (i.e., volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through this weld, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications 3.4.5, "Reactor Coolant System Operational Leakage," provide Page 23 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations additional assurance that any leakage would be detected prior to gross failure of the component. The RPV stabilizer support bracket attachment welds were rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the surface examination coverage the pressure testing VT-2 examinations performed and results of the VT-1 visual examination performed, EGC concluded that if significant service-induced degradation would have occurred, there is reasonable assurance that evidence of it would have been detected by the examinations performed. Therefore the examinations provide a reasonable assurance of quality and safety. For the current third 10-year ISI interval, relief was requested in Relief Request 13R-04 and granted by the NRC on January 30, 2008, for these examinations. For the third 10-year ISI interval, the approved alternative examination requirements will be implemented by performing a VT-1 visual examination on the accessible portions of the stabilizer bracket welds, when one of these lugs is scheduled for examination in accordance with ASME Code, Section X1. Page 24 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Component Affected Unit 2 Residual Heat Removal Heat Exchanger Welded Attachment Weld Identification Number IRH-HX2B-08D Applicable Code Requirements Code Case N-509, Table IWC-2500-1, Examination Category C-C, Item Number C3.10 and Figure IWC-2500-5 Impracticality of Compliance There are four welded attachments to the 2B RHR heat exchanger, one in each quadrant of the vertically oriented vessel in the lower middle shell course. The attachment lugs and the shell course are constructed of carbon steel, SA-516 Grade 70, material. Only one of the four lugs at this location is required to be examined. The attachment lugs are constructed of two horizontally oriented plates 26.5 inches apart full penetration welded to the vessel shell. The upper plate is 28 inches long and 1 inch thick. The lower plate is 30 inches long and 2.50 inches thick. Connecting the two horizontal plates are three equally spaced, vertically oriented gusset plates each 1 inch thick and 26.5 inches long. The three gussets are vertically full penetration welded to the vessel, and horizontally full penetration welded to the upper and lower horizontal plates. The lower horizontal plate sits atop and is bolted to the upper flange of a structural beam. During the ASME Code Case required surface examination of the attachment weld, reduced coverage was obtained due to the presence of the structural beam. Its location makes the entire 30 inch length of the lower horizontal plate to vessel shell inaccessible for surface examination. The surface examination coverage obtained was approximately 74 percent of the entire attachment weld surface. Due to the design and construction of the attachment and structural beam removal of the beam is not practical. The beam provides support of the vessel and its removal would require design and installation of alternative temporary supports so the structural integrity of the vessel would not be negatively affected. Removal of the beam and installation of any temporary supports would be done in an elevated dose rate field. Justification for Granting Relief Accessibility to 100 percent of the examination areas for these attachment welds is limited due to the presence of a structural beam. Accessibility was not provided in the original plant design which occurred prior to the issuance of ASME Code, Section Xl, ISI requirements. The required surface examination of the vessel attachment weld is not practical due to the design and construction of the attachment and the structural beam. Approximately 74 percent of the required area was examined and one indication was detected. The indication is acceptable based its length of 0.125 inches and Table IWC-3510-03. Additionally, IWC-2500, Table IWC-2500-1, Examination Category C-H Pressure tests and VT-2 visual examinations performed each period provide further assurance of pressure boundary integrity. All of the attachment welds were examined by surface NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the surface examination coverage the pressure testing VT-2 examinations performed, EGC concluded that if significant service-induced degradation would have occurred, there is reasonable assurance that evidence of it Page 25 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations would have been detected by the examinations performed. Therefore the examinations provide a reasonable assurance of quality and safety. Page 26 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations ASME Code Components Affected Unit 2 High Pressure Core Spray Pump, and Low Pressure Core Spray Pump and Residual Heat Removal Pump Casing Welds Weld Identification Numbers IHP-PU2-07A, 07B, 07C, 08A, 08B, 08C, and 09, ILP-PU-07, 08, and 09, and IRH-PU2C-07A, 07B, 07C, 08A, 088, 08C, and 09. Applicable Code Requirements Table IWC-2500-1, Examination Category C-G, Item Number C6.10 and Figure IWC-2500-8 Impracticality of Compliance The HPCS, LPCS, and RHR pumps are vertical shaft pumps and are all encased in concrete. The shells are constructed of carbon steel, A-516 Grade 70, material. The design of the pumps makes the welds inaccessible for inservice inspection. Therefore, it is impractical to perform the surface examination of these welds without destruction of the concrete resulting in unnecessary engineering and installation costs and radiation exposure without a compensating increase in safety. Additionally, due to the design of the subject pumps, access to the affected welds can only be achieved through disassembly of the pump, removal of the pump internals, and the required surface examinations performed from the inside surface of the welds. This effort, in the absence of any other necessary pump maintenance, represents a significant expenditure of man-hours and radiation exposure to plant personnel, without a compensating increase in plant safety. All of these activities would be done in an elevated dose rate field. Justification for GrantinQ Relief Accessibility to the examination areas for these welds is limited due to the presence of concrete foundations and vaults. Accessibility was not provided in the original plant design that occurred prior to the issuance of ASME Code, Section Xl, ISI requirements. The required surface examination of the welds is impractical to perform without destruction of the concrete resulting in unnecessary engineering and installation costs and radiation exposure without a compensating increase in safety. Additionally, due to the design of the subject pumps, access to the affected welds can only be achieved through disassembly of the pump, removal of the pump internals, and the required surface examinations performed from the inside surface of the welds. This effort, in the absence of any other necessary pump maintenance, represents a significant expenditure of man-hours and radiation exposure to plant personnel, without a compensating increase in plant safety. Additionally, IWC-2500, Table IWC-2500-1, Examination Category C-H, pressure tests and VT-2 visual examinations performed each period provide further assurance of pressure boundary integrity. For the current third 10-year ISI interval, relief was requested in Relief Request 13R-03 and granted by the NRC on January 30, 2008, for these examinations. For the third 10-year ISI interval, the following approved alternative examination requirements will be implemented. In the event the subject welds become accessible upon disassembly of any one of the pumps, the welds will be surface examined from the inside surface, or a VT-1 visual examination will be performed for that particular pump group to the maximum extent practicable based on the obstructions and geometric constraints detailed in this relief request. The examination method will be determined based on radiation environment data at the time access is enabled. Additionally, a VT-2 visual examination during system Page 27 of 28
ATTACHMENT 5 Additional Information Describing the Impracticalities Associated with the Limited Examinations pressure testing per ASME Code, Section Xl, Examination Category C-H will be performed once each period by examining the surrounding area (e.g., exposed areas around these components where the pump casing join/merge with the concrete) for evidence of leakage in accordance with ASME Code, Section X1, IWA-5241(b). Page 28 of 28 A'N}}