RS-18-112, End of Interval Relief Request Associated with the Third Ten-Year Inservice Inspection (ISI) Interval
| ML18267A058 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/19/2018 |
| From: | Gullott D Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-18-112 | |
| Download: ML18267A058 (109) | |
Text
{{#Wiki_filter:4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 657 2000 Office 10 CFR 50.55a RS-18-112 September 19, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
End of Interval Relief Request Associated with the Third Ten-Year lnservice Inspection (ISi) Interval In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(5)(iii), Exelon Generation Company, LLC (EGC), is requesting relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components." This relief request applies to the third ten-year lnservice Inspection (ISi) interval, which concluded on September 30, 2017, for the LaSalle County Station (LSCS), Units 1 and 2. The third ten-year ISi interval complied with the ASME Boiler and Pressure Vessel Code, Section XI, 2001 Edition with the 2003 Addenda. There are no regulatory commitments contained within this letter. EGC requests approval of this relief request by September 19, 2019. Should you have any questions concerning this letter, please contact Ms. Rebecca L. Steinman at (630) 657-2831. David Gullett Manager - Licensing Exelon Generation Company, LLC
Attachment:
10 CFR 50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii) - lnservice Inspection Impracticality
U.S. NRC September 19, 2018 Page 2 cc: USNRC Region Ill, Regional Administrator USNRC Senior Resident Inspector, LSCS USNRC Project Manager, LSCS Illinois Emergency Management Agency - Division of Nuclear Safety
ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5)(iii)
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Revision O (Page 1 of 11)
- 1. ASME Code Component(s) Affected Code Class: 1&2
Reference:
IWB-2500, Table IWB-2500-1, IWC-2500, Table IWC-2500-1, ASME Code Case N-460, ASME Code Case N-578-1, Table 1, ASME Code Case N-702 Examination Category: B-A, B-D, C-C, R-A Item Number: B1.12, B3.90, C3.10, C3.30, R1.20
Description:
Limited Examination Coverage Component Number: See Tables 13R-15.1 and 13R-15.2 for a list of Component IDs
2. Applicable Code Edition and Addenda
The Third 10-Year Interval of the LaSalle County Station (LSCS), Units 1 and 2 lnservice Inspection (ISi) Program was based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," 2001 Edition with the 2003 Addenda. LSCS, Units 1 and 2 maintains the responsibility to ensure exams were performed in accordance with the requirements of ASME, Section XI, Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," as amended and mandated by 10CFR50.55a and as modified by the Performance Demonstration Initiative (POI) Program description. In the case of limited examinations, efforts were made to obtain additional examination coverage. Tables 13R-15.1 and 13R-15.2 identify whether each listed examination was performed in accordance with the requirements of ASME, Section XI, Appendix VIII or not.
- 3. Applicable Code Requirements The extent of examination requirement for Examination Category B-A, Item Number B1 .12, per Table IWB-2500-1, requires a volumetric examination of essentially 100% of the weld length.
The extent of examination requirement for Examination Category B-D, Item Number B3.90, per Table IWB-2500-1, requires a volumetric examination of all nozzle-to-vessel welds. During the third interval, LSCS, Units 1 and 2 was approved to use ASME Code Case N-702 by the Nuclear Regulatory Commission (NRC) through a Safety Evaluation (SE) dated October 30, 2015 (ML15226A412) associated with the submittal of Relief Request 13R-14. During the Third ISi Interval, no recordable indications were identified during examination and no plant-specific operating experience related to degradation were
ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5)(iii)
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Revision O (Page 2 of 11) identified for the Examination Category B-D components listed in Tables 13R-15.1 or 13R-15.2. The extent of examination requirement for Examination Category C-C, Item Numbers C3.10 and C3.30, per Table IWC-2500-1, requires a surface examination of the welded attachments for pressure vessels and pumps. Note 2 in Table IWC-2500-1 states, the extent of the examination includes essentially 100% of the length of the attachment weld at each attachment subject to examination. The extent of examination requirement for Examination Category R-A, Item Number R1.20, per Table 1 of ASME Code Case N-578-1, requires a volumetric examination of essentially 100% of the length of the Risk Informed lnservice Inspection (RI-ISi) weld. (Note: Relief Request 13R-01 was submitted and was approved by the NRC through an SE dated April 29, 2008 (ML080940215) in order to utilize EPRI Topical Report (TR) 112657 Rev. B-A, as supplemented by ASME Code Case N-578-1). The RI-ISi program scope includes welds in the Break Exclusion Region (BER) piping, also referred to as the High Energy Line Break (HELB) region, which may include several Class 3 and Non-Class welds that fall within the BER Augmented Inspection Program. None of the RI-ISi piping welds included in this relief are within the scope of the BER Program. LSCS, Units 1 and 2 adopted ASME Code Case N-460 ("Alternative Examination Coverage for Class 1 and Class 2 Welds, Section XI, Division 1"), which defines "essentially 100%" as greater than 90% coverage of the examination volume or surface area, as applicable. The 90% minimum coverage was applied to all surface and volumetric examinations required by ASME Section XI.
- 4. Impracticality of Compliance In accordance with 10CFR50.55a(g)(5)(iii), relief is requested on the basis that conformance with these code requirements is impractical since conformance would require extensive structural modifications to the component or surrounding structure.
Due to the original design of these components, LSCS is unable to satisfy the ASME Section XI Code requirements to perform to the extent required for welds and welded attachments (greater than 90% of the volume or area) a surface or volumetric examination due to the physical component configuration, interference from permanent plant equipment, single-sided access, etc. LSCS would incur significant engineering, material, and installation costs to perform such modifications without a compensating increase in the level of quality and safety. Therefore, relief is requested on the basis that the ASME Section XI Code requirements to examine these components are impractical. During outages, when situations were identified where coverage was an issue, LSCS
- personnel reviewed the systems for alternatives. For the RI-ISi weld population, Examination Category R-A welds, submitted in this relief request, a case by case review was performed to determine whether additional or alternative welds could have been examined to supplement the reduced volumetric coverage examination. It was determined that there were no other welds to select that would have resulted in better
ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5)(iii)
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Revision O (Page 3 of 11) coverage. This determination was made based on comparison of configurations, delta core damage frequency (CDF) values, the systems involved, and inspection history. Tables 13R-15.1 and 13R-15.2 provide a summary of the examination limitations for each component for which relief is requested. The tables also indicate the outage the component was examined, the coverage percentage obtained for each component, and other pertinent design information. These tables are the cumulative lists of the limited ASME Section XI examinations performed during the Third ISi Interval. Enclosures 1 and 2 provide coverage plots which were extracted from the non-destructive examination (NOE) summary sheets that detail the examination limitations. Based on the above explanation, LSCS, Units 1 and 2 request relief to perform examinations without achieving ASME Section XI Code compliance coverage when the required coverage is impractical.
- 5. Burden Caused by Compliance Compliance with the applicable ASME Section XI Code volumetric or surface examination requirements can only be accomplished by redesigning and refabricating the subject and/or surrounding components. Based on this, the ASME Section XI Code requirements are deemed impractical in accordance with 10CFR50.55a(g)(5)(iii).
- 6. Proposed Alternative and Basis for Use LSCS has performed the ASME Section XI Code required examinations to the maximum extent practical (Code Coverage), or best effort, which are documented in Tables 13R-15.1 and 13R-15.2. Due to the physical interferences causing these limitations, there are no alternative examination techniques currently available to increase coverage.
- 7. Duration of Proposed Alternative Relief is requested for the Third ISi Interval for LSCS, Units 1 and 2.
- 8. Precedents The following similar end of interval impracticality relief requests have been previously authorized by the NRC.
- Relief Request 13R-23 was authorized for Limerick Generating Station, Units 1 and 2 by NRC SE dated August 7, 2018 (ADAMS Accession No. ML18192C172)
- Relief Requests LMT-R01, LMT-C02, and LMT-C03 were authorized for Surry Power Station Unit 2 by NRC SE dated February 17, 2017 (ADAMS Accession No.
16365A 118)
ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5)(iii)
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Revision O (Page 4 of 11)
- Relief Request R-44 and R-45 were authorized for Oyster Creek Nuclear Generating Station by NRC SE dated May 1, 2015 (ADAMS Accession No. ML15097A153)
ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 5 of 11) Table 13R-15.1 LaSalle County Station, Unit 1 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Weld Operating Exam Ang.le / Requirements Category I Outage Material of Diameter/ Actual VIII Component ID Description Conditions Frequency (MHz)/ Remarks (Figure No.) Item Examined Construction Thickness Coverage Qualified (System)' (Pressure/ Mode and Method Number Exam Temperature) N1 Recirc SA-508 Cl. 2 46" dia / The examination was limited at IWB-2500-7 Outlet Nozzle B-D (Nozzle) 7-11/16" thk 1025 psig / 55° /1.0 I Shear 180° due to a 3.25" thermocouple LCS-1-N1A Volumetric L1R12 82.9% Yes to Shell (UT) B3.90 SA-533 Gr. B atRPV 550°F so* /3.03 I Long located 2.5" from the weld toe. (RPV) (Shell) Shell (Enc. 1 Pg. Nos. 2-6 & 51) N1 Recirc SA-508 Cl. 2 46" dia / IWB-2500-7 The examination was limited due Outlet Nozzle B-D (Nozzle) 7-11/16" thk 1025 psig / 55° /1.0 I Shear LCS-1-N1B Volumetric L1R12 83.6% Yes to nozzle configuration. to Shell (UT) B3.90 SA-533 Gr. B atRPV 550°F so* /3.03 / Long (Enc. 1 Pg. Nos. 7-1 O& 51) (RPV) (Shell) Shell N3 Main SA-508 Cl. 2 50-3/4" dia / Steam IWB-2500-7 The examination was limited due B-D (Nozzle) 6-11/16" thk 1025 psig / 55° /1.0 I Shear LCS-1-N3A Nozzle to Volumetric L1R12 83.8% Yes to nozzle configuration. Shell (UT) B3.90 SA-533 Gr. B atRPV 550°F so* /3.03 1 RL (Enc.1 Pg. Nos. 11-14 & 51) (Shell) Shell (RPV) N3 Main SA-508 Cl. 2 50-3/4" dia / Steam IWB-2500-7 The examination was limited due B-D (Nozzle) 6-11/16" thk 1025 psig / 55° /1.0 I Shear LCS-1-N3B Nozzle to Volumetric L1R12 83.8% Yes to nozzle configuration. Shell (UT) B3.90 SA-533 Gr. B atRPV 550°F so* /3.03 / RL (Enc. 1 Pg. Nos. 15-18 & 51) (Shell) Shell (RPV) N3 Main SA-508 Cl. 2 50-3/4" dia / Steam IWB-2500-7 The examination was limited due B-D (Nozzle) 6-11/16" thk 1025 psig / 55° /1.0 I Shear LCS-1-N3C Nozzle to Volumetric L1R12 83.8% Yes to nozzle configuration. Shell (UT) B3.90 SA-533 Gr. B atRPV 550°F so* /3.03 / RL (Enc. 1 Pg. Nos. 19-22 & 51) (Shell) Shell (RPV) Note:
- 1. The following systems and their abbreviations are listed here: High Pressure Core Spray (HP), Main Steam (MS), Residual Heat Removal (RHR), Reactor Recirculation (RR), and Reactor Pressure Vessel (RPV)
ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5){iii)
--1 nservice Inspection Im practicality--
Revision 0 (Page 6 of 11) Table 13R-15.1 LaSalle County Station, Unit 1 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Weld Operating Exam Angle/ Requirements Category I Outage Material of Diameter/ Actual VIII Component ID Description Conditions Frequency (MHz)/ Remarks (Figure No.) Item Examined Construction Thickness Coverage Qualified (System)1 (Pressure/ Mode and Method Number Exam Temperature) N3 Main SA-508 Cl. 2 50-3/4" dia / Steam IW8-2500-7 The examination was limited due 8-D (Nozzle) 6-11/16" thk 1025 psig / 55° /1.0 I Shear LCS-1-N3D Nozzle to Volumetric L1R12 83.8% Yes to nozzle configuration. Shell (UT) 83.90 SA-533 Gr. 8 atRPV 550°F so* /3.03 t RL (Enc. 1 Pg. Nos. 23-26 & 51) (Shell) Shell (RPV) N2 Recirc. SA-508 Cl. 2 30" dia I IW8-2500-7 The examination was limited due LCS-1-N2C Inlet Nozzle Volumetric 8-D L1R13 (Nozzle) 7-11/16" thk 1025 psig / so* /3.03 t RL 85.9% Yes to nozzle configuration. to Shell 83.90 SA-533 Gr. 8 atRPV 550°F 55° /1.0 I Shear (UT) (Enc.1 Pg. Nos. 27-28 & 51) (RPV) (Shell) Shell N2 Recirc. SA-508 Cl. 2 30" dia I IW8-2500-7 The examination was limited due LCS-1-N2D Inlet Nozzle Volumetric 8-D L1R13 (Nozzle) 7-11/16" thk 1025 psig / so* /3.03 / RL 85.9% Yes to nozzle configuration. to Shell 83.90 SA-533 Gr. 8 atRPV 550'F 55° /1.0 I Shear (UT) (Enc. 1 Pg. Nos. 29-30 & 51) (RPV) (Shell) Shell N16 Core SA-508 Cl. 2 31-5/16" dia IW8-2500-7 The examination was limited due LCS-1-N16 Spray Nozzle* Volumetric 8-D L1R13 (Nozzle) / 6-11/16" 1025 psig / so* /3.03 / RL 86.3% Yes to nozzle configuration. to Shell 83.90 SA-533 Gr. 8 thk atRPV 550'F 55° /1.0 I Shear (UT) (Enc. 1 Pg. Nos. 31-32 & 51) (RPV) (Shell) Shell N5 Core SA-508 Cl. 2 31-5/16" dia IW8-2500-7 The examination was limited due LCS-1-N5 Spray Nozzle Volumetric 8-D L1R13 (Nozzle) / 6-11/16" 1025 psig / so* /3.03 1 RL 86.3% Yes to nozzle configuration. to Shell 83.90 SA-533 Gr. 8 thk atRPV 550'F 55° /1.0 I Shear (UT) (Enc.1 Pg. No. 33-34 & 51) (RPV) (Shell) Shell Note:
- 1. The following systems and their abbreviations are listed here: High Pressure Core Spray (HP), Main Steam (MS), Residual Heat Removal (RHR), Reactor Recirculation (RR), and Reactor Pressure Vessel (RPV)
ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5){iii)
--lnservice Inspection Impracticality--
Revision 0 (Page 7 of 11) Table 13R-15.1 LaSalle County Station, Unit 1 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Weld Operating Exam Angle/ Requirements Category I Outage Material of Diameter/ Actual VIII Component ID Description Conditions Frequency (MHz) / Remarks (Figure No.) Item Examined Construction Thickness Coverage Qualified (System)' (Pressure/ Mode and Method Number Exam Temperature) NB LPCI SA-508 Cl. 2 33" dia / IW8-2500-7 The examination was limited due Nozzle to 8-D (Nozzle) 6-11/16" thk 1025 psig / 60" /3.03 / RL LCS-1-NBA Volumetric L 1R13 83.3% Yes to nozzle configuration. Shell 83.90 SA-533 Gr. 8 atRPV 550°F 55" /1.0 I Shear (RPV) (UT) (Enc. 1 Pg. Nos. 35-36 & 51) (Shell) Shell NS LPCI SA-508 Cl. 2 33" dia I IW8-2500-7 The examination was limited due Nozzle to 8-D (Nozzle) 6-11/16" thk 1025 psig / 60" /3.03 / RL LCS-1-N68 Volumetric L1R13 83.3% Yes to nozzle configuration. Shell 83.90 SA-533 Gr. 8 atRPV 550°F 55" /1.0 I Shear (UT) (Enc.1 Pg. Nos. 37-38 & 51) (RPV) (Shell) Shell NB LPCI SA-508 Cl. 2 33" dia I IW8-2500-7 The examination was limited due Nozzle to 8-D (Nozzle) 6-11/16" thk 1025 psig / 60" /3.03 / RL LCS-1-NBC Volumetric L1R13 83.3% Yes to nozzle configuration. Shell 83.90 SA-533 Gr. 8 atRPV 550°F 55" /1.0 I Shear (UT) (Enc. 1 Pg. Nos. 39-40 & 51) (RPV) (Shell) Shell N10 CRD SA-508 Cl. 2 19-7/16" dia Return IW8-2500-7 The examination was limited due 8-D (Nozzle) / 6-11/16" 1025 psig / 60" /3.03 / RL LCS-1-N10 Nozzle to Volumetric L1R13 88.1% Yes to nozzle configuration. 83.90 SA-533 Gr. 8 thk at RPV 550°F 55" /1.0 I Shear Shell (UT) (Enc. 1 Pg. Nos. 41-42 & 51) (Shell) Shell (RPV) 18 RHR HX 124" Length IWC-2500-5 500 psig / The examination was limited due IRH-HX18- Welded C-C / 1-5/16" Surface L1R14 Carbon Steel 4B0°F N/A 81.67% No to structural interference. 088 Attachment C3.10 Shell (RHR) (MT) (Design) (Enc. 1 Pg. Nos. 43-44) Thickness SC3 Long 112-3/8" O" I 2.25 / Long The examination was limited from IW8-2500-2 Seam@20" 8-A Length/ 1025 psig / 45" / 1.0 I Shear the OD surface due to the N12-A LCS-1-8G Volumetric L1R16 SA-533 Gr. 8 84.3% Yes Az. 81.12 6-3/4" Shell 5so°F 60" / 2.0 I Long nozzle. (UT) (RPV) Thickness 70" I 2.0 I Long (Enc. 1 Pg. Nos. 45-48) Note:
- 1. The following systems and their abbreviations are listed here: High Pressure Core Spray (HP), Main Steam (MS), Residual Heat Removal (RHR), Reactor Recirculation (RR), and Reactor Pressure Vessel (RPV)
ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision 0 (Page 8 of 11) Table 13R-15.1 LaSalle County Station, Unit 1 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Weld Operating Exam Angle/ Requirements Category/ Outage Material of Diameter/ Actual VIII Component ID Description Conditions Frequency (MHz)/ Remarks (Figure No.) Item Examined Construction Thickness Coverage Qualified (System)1 (Pressure/ Mode and Method Number Exam Temperature) N7 Top Head SA-508 Cl. 2 17" dia / IWB-2500-7 The examination was limited due Spray Nozzle 8-D (Nozzle) 3-5/8" thk at 1025 psig / 60° /3.0 I Long LCS-1-N7 Volumetric L1R16 87% Yes to nozzle configuration. to Shell 83.90 SA-533 Gr. B Closure 550°F 55° /1.0 I Shear (UT) (Enc. 1 Pg. Nos. 49-50) (RPV) (Shell) Head Note:
- 1. The following systems and their abbreviations are listed here: High Pressure Core Spray (HP), Main Steam (MS), Residual Heat Removal (RHR), Reactor Recirculation (RR), and Reactor Pressure Vessel (RPV)
ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision 0 (Page 9 of 11) Table 13R-15.2 LaSalle County Station, Unit 2 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Weld Operating Exam Angle/ Requirements Category/ Outage Material of Diameter/ Actual VIII Component ID Description Conditions Frequency (MHz)/ Remarks (Figure No.) Item Examined Construction Thickness Coverage Qualified (System)1 (Pressure/ Mode and Method Number Exam Temperature) Pump 2E22-C001 IWC-2500-5 171.5 in. 1325 psig / The examination was limited due to C-C the permanent pump stand. HP-PU2-04 Welded Surface L2R12 A516 Gr70 Length/ 212°F N/A 16.0% No C3.30 Attachment (MT) 0.75 in. (Design) (Enc. 2 Pg. Nos. 2-3) (HP) 18" Pipe to IWC-2500-7(a) 1250 psig / The examination was limited due to R-A 18" dia I 45' I 2.0 I Shear IMS-2044-13 Valve Weld Volumetric L2R12 A106 GrB 575°F 59.8% Yes component configuration. R1.20 Sch 80 70' I 2.0 I Shear (MS) (UT) (Design) (Enc. 2 Pg. Nos. 4-5) The automated examination was N10 CRD 45' / 1.0 I Shear limited due to insulation SA-508 Cl. 2 20-1/2" dia / Return IWB-2500-7 60' / 2.0 I RL interference and the mechanical B-D (Nozzle) 6-3/16" thk 1025 psig / LCS-2-N10 Nozzle to Volumetric L2R12 70' / 2.0 I RL 71.9% Yes limit of the scanner arm. Manual B3.90 SA-533 Gr. B atRPV 550°F Shell (UT) 60' /3.03 / Long examination was limited due to (Shell) Shell* (RPV) 55' /3.03 / Shear nozzle configuration. IEnc. 2 Pa. Nos. 6-12 & 451 N1 Recirc SA-508 Cl. 2 49-9/16" dia IWB-2500-7 45' / 1.0 I Shear The automated examination was Outlet Nozzle B-D (Nozzle) / 6-3/16" thk 1025 psig / LCS-2-N1A Volumetric L2R12 60' I 2.0 I RL 71.6% Yes limited due to nozzle configuration. to Shell B3.90 SA-533 Gr. B atRPV 550°F (UT) 70' / 2.0 I RL (Enc. 2 Pg. Nos. 13-15 & 45) (RPV) (Shell) Shell N1 Recirc SA-508 Cl. 2 49-9/16" dia IWB-2500-7 45' / 1.0 I Shear The automated examination was Outlet Nozzle B-D (Nozzle) I 6-3/16" th k 1025 psig / LCS-2-N1B Volumetric L2R12 60' I 2.0 I RL 71.6% Yes limited due to nozzle configuration. to Shell B3.90 SA-533 Gr. B atRPV 550°F (UT) 70' I 2.0 I RL (Enc. 2 Pg. Nos. 16-18 & 45) (RPV) (Shell) Shell Note:
- 1. The following systems and their abbreviations are listed here: High Pressure Core Spray (HP), Main Steam (MS), Residual Heat Removal (RHR), Reactor Recirculation (RR), and Reactor Pressure Vessel (RPV)
ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 10 of 11) Table 13R-15.2 LaSalle County Station, Unit 2 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Weld Operating Exam Angle/ Requirements Category/ Outage Material of Diameter/ Actual VIII Component ID Description Conditions Frequency (MHz)/ Remarks (Figure No.) Item Examined Construction Thickness Coverage Qualified (System)' (Pressure/ Mode and Method Number Exam Temperature) N2 Recirc. SA-508 Cl. 2 33-7/8" dia / IW8-2500-7 45° / 1.0 I Shear The examination was limited due to Inlet Nozzle 8-D (Nozzle) 6-3/16" thk 1025 psig / LCS-2-N2C Volumetric L2R12 60° 12.0 I RL 70.5% Yes nozzle configuration. to Shell 83.90 SA-533 Gr. 8 atRPV 550°F (UT) 70° 12.0 I RL (Enc. 2 Pg. Nos. 19-21 & 45) (RPV) (Shell) Shell N3 Main SA-508 Cl. 2 Steam IW8-2500-7 48-7/8" dia I The examination was limited due to 8-D (Nozzle) 1025 psig / 55° /1.0 I Shear LCS-2-N3A Nozzle to Volumetric L2R12 7" thk at 83.3% Yes nozzle configuration. Shell (UT) 83.90 SA-533 Gr. 8 RPV Shell 550°F so* /3.03 I Long (Enc. 2 Pg. No. 22 & 45) (Shell) (RPV) N3 Main SA-508 Cl. 2 Steam IW8-2500-7 48-7/8" dia / The examination was limited due to 8-D (Nozzle) 1025 psig / 55° /1.0 I Shear LCS-2-N38 Nozzle to Volumetric L2R12 7" thk at 83.3% Yes nozzle configuration. Shell (UT) 83.90 SA-533 Gr. 8 RPV Shell 550°F so* /3.03 I Long (Enc. 2 Pg. No. 23 & 45) (Shell) (RPV) N3 Main SA-508 Cl. 2 Steam IW8-2500-7 48-7/8" dia / 45° / 1.0 I Shear The examination was limited due to 8-D (Nozzle) 1025 psig / LCS-2-N3C Nozzle to Volumetric L2R12 7" thk at 60° 12.0 I RL 74.1% Yes nozzle configuration. 83.90 SA-533 Gr. 8 550°F Shell (UT) RPV Shell 70° 12.0 I RL (Enc. 2 Pg. Nos. 24-26 & 45) (Shell) (RPV) N3 Main SA-508 Cl. 2 Steam IW8-2500-7 48-7/8" dia / 45° / 1.0 I Shear The examination was limited due to 8-D (Nozzle) 1025 psig / LCS-2-N3D Nozzle to Volumetric L2R12 7" thk at 60° 12.0 I RL 74.1% Yes nozzle configuration. 83.90 SA-533 Gr. 8 550°F Shell (UT) RPV Shell 70° /2.0/ RL (Enc. 2 Pg. Nos. 27-29 & 45) (Shell) (RPV) N6 LPCI SA-508 Cl. 2 33-7r8 dia t IW8-2500-7 45° / 1.0 I Shear The examination was limited due to Nozzle to 8-D (Nozzle) 6-3/16" thk 1025 psig / LCS-2-N6A Volumetric L2R12 60° 12.0 I RL 71.2% Yes nozzle configuration. Shell 83.90 SA-533 Gr. 8 atRPV 550°F (UT) 70° /2.0 I RL (Enc. 2 Pg. Nos. 30-32 & 45) (RPV) (Shell) Shell Note:
- 1. The following systems and their abbreviations are listed here: High Pressure Core Spray (HP), Main Steam (MS), Residual Heat Removal (RHR), Reactor Recirculation (RR), and Reactor Pressure Vessel (RPV)
ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 11 of 11) Table 13R-15.2 LaSalle County Station, Unit 2 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Weld Operating Exam Angle/ Requirements Category I Outage Material of Diameter/ Actual VIII Component ID Description Conditions Frequency (MHz) / Remarks (Figure No.) Item Examined Construction Thickness Coverage Qualified (System)' (Pressure/ Mode and Method Number Exam Temperature) NB LPCI SA-508 Cl. 2 33-7/8 dia / Nozzle to IWB-2500-7 45' / 1.0 I Shear The examination was limited due to B-D (Nozzle) 6-3/16" thk 1025 psig / LCS-2-N6C Volumetric L2R12 60' I 2.0 I RL 71.2% Yes nozzle configuration. Shell B3.90 SA-533 Gr. B atRPV 550'F (UT) 70' / 2.0 I RL (Enc. 2 Pg. Nos. 33-35 & 45) (RPV) (Shell) Shell N6 LPCI SA-508 Cl. 2 IWB-2500-7 33-7/8" dia / The examination was limited due to Nozzle to B-D (Nozzle) 1025 psig / 60' / 3.03 / Long LCS-2-N6B Volumetric L2R14 6-3/16" thk 59.8% Yes nozzle configuration. Shell B3.90 SA-533 Gr. B 550'F 55' / 1.0 I Shear (UT) at RPV shell (Enc. 2 Pg. Nos. 36-38 & 45) (RPV) (Shell) 16" Ring IWB-2500-8(c) Header-to IWB-2500-9, 45' I 2.25 I Shear The examination was limited due to R-A 48" Length/ 1025 psig / IRR-2001-03 Sweep-0-Let 10, & 11 L2R14 SA-358 Gr 304 60' I 2.25 I Shear 86.0% Yes component configuration. R1.20 0.758" thk 550'F Weld Volumetric 60' / 2.0 I Long (Enc. 2 Pg. Nos. 39-41) (RR) (UT) 16" Ring IWB-2500-8(c) Header-to IWB-2500-9, 45' / 2.25 I Shear The examination was limited due to R-A 48" Length/ 1025 psig / IRR-2001-04 Sweep-0-Let 10, & 11 L2R14 SA-358 Gr 304 60' / 2.25 I Shear 85.3% Yes component configuration. R1.20 0.758" thk 550'F Weld Volumetric 60' 12.0 I Long (Enc. 2 Pg. Nos. 42-44) (RR) (UT) Note:
- 1. The following systems and their abbreviations are listed here: High Pressure Core Spray (HP), Main Steam (MS), Residual Heat Removal (RHR), Reactor Recirculation (RR), and Reactor Pressure Vessel (RPV)
Enclosure 1 LaSalle County Generating Station Unit 1 Third lnservice Inspection (ISi) Interval Limited Coverage Non-Destructive Examination (NOE) Reports
Enclosure 1: LCS Unit 1 Third ISi Interval Limited Coverage NOE Reports Report Noa HITACHI EXAMINATION
SUMMARY
SHEET L1Rl2-013 I 0 Site: Outage: LaSalle Component ID: LCS-1-NlA N-SH L1Rl2 System: RECIRC ASME Cat.: B-D ASME Item 83.90 Aug Req N/A Exams Doto Sheet Col Sheet Procedure Calibration Block Exam /Oper. Cert Level Dote Performed I I Personnel 60° Long D-036 NIA GE-UT-300 Ver/Rev 10 01-92-07 Troy Huhe II 2/11/2008 60° Long D-035 N/A GE-UT -300 Ver/Rev 10 CAL-IIW-028 Troy Huhe II 2/11/2008 55° Shear D-037 N/A GE*UT-311 Ver/Rev 15 01-92-07 Troy Huhe II 2/11/2007 Examination Results: During the manual ultrasonic examination of the above referenced component. no recordable indications were detected utilizing o 55° shear wo'J search unit and o 60° refracted longitudinal wove search unit. This examination is acceptable per the requirements of ASME Section 2001 Edition. 2003 Addenda. 82.9% of the examination volume was examined** 83.6% from Coverage Calculation Sheet IPoge 5 of 101 less .66% from previously recorded thermocouple. Compared to Report #96-152. 0 Previous examination results supplied by customer for review of ISi Program documents? ~ Yes D Change These examinations were performed under Work Order: NIA D No ~No Change This S u m ~ e following data sheets have been reviewed and a c c e p ~ w i n g personnel: RWP: 8330
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CODE CROSS-SECTIONAL AREA i TOTAL CODE COVERAGE
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Exam Volume= 72.6 Area Sq. In. Area Scanned '1of Area Weld Length 360 7.3% en 60° T-Scan (S4) A 10.6 10.6 114.6% 60° T-Scan (S6) i 76.9% 360 38.4% ::J A 62 55.8 "U IRS P-Scan (S4) A* 10.6 10.6 114.6% 360 7.3% ~m Ill 60° P-Scan (S6) A : 61.2% 360 30.6%
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% Total Composite Coverage= 83.6%
I Rev. 0 9!23'05 Comments: I II 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
Enclosure 1: LCS Unit 1 Third ISi Interval Limited Coverage NOE Reports Manual RPV Nozzle Exam Plan 0 Plant and Unit ID: Outage: LaSalle Unit-1 LlR12 Component: Cal. Block: LCS-1-NlA 01-92-07 Procedures: Examination: GE-UT-300 Sizing: GE-UT-304 Examination (N/V): GE-UT-311 Sizing: GE-UT-309 Extents: Examiner: Analyst: Examine 360°. See attached drawing for limits. NIA NIA 60°RL Full Volume T-scan 60°RL Full Volume P-scan CWICCW 60°RL Near Surface T-scan 60°RL Near Surface P-scan CW/CCW 55° Inner 15%T NN PLATE 0"-9.0" +/-50°-70° CW/CCW Limitations:
.~--------- -*-----**- -- ------***-------* .. --------~-~------------------- ~one.
CJ Previous Results: Review on site. Comments: None. Cf frl.r (J Prcnared Bv: 1-28-08 Date: A~~ Re~iew~d Bv: i.*\-cnJ Date:
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tarr'iincd Bv: Date:, v t_1.1212- ¢13 (o .st(() Page 4 of 51
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CODE CROSS-SECTIONAL AREA I TOTAL CODE COVERAGE Weld Length = 360. Required Exam I Percent Exam Volume= 72.6 Area Sq. In. Area Scanned i of Area Weld Length Percent 60° T-Scan (S4) A 10.6 10.6 14.6% 360 7.3% 60° T-Scan (S6) A 62 55.8 ' 76.9% 360 38.4% :J "'U IRS P-Scan (S4) A* 10.6 10.6 i 14.6% 360 7.3% co m Ill cc 60° P-Scan {S6) A 62 44.4 i 61.2% 360 30.6%
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~ A* - Single side access, 100% credit of the achieved Supplement 4 T-scan volume claim~d iaw. 10CFR50.55a.
~ Note - Rounding methods may affect calculated values. Weld length in degrees. '.
Enclosure 1: LCS Unit t Third ISi Interval Limited Coverage NOE Reports Manual RPV Nozzle Exam Plan 0 Plant and Unit ID: Outage: LaSalle Unit-1 L1Rl2 Component: Cal. Block: LCS-1-NlB 01-92-07 Procedures: Examination: GE-UT-300 Sizing: GE-UT-304 Examination (N/V): GE-UT-311 Sizing: GE-UT-309 Extents: Examiner: Analyst: Examine 360°. See attached drawing for limits. N/A NIA 60°RL Full Volume T-scan 60°RL Full Volume P-scan CW/CCW 60°RL Near Surface T-scan 60°RL Near Surface P-scan CW/CCW 55° Inner 15%T NN PLATE 0"-9.0" +/-50°-70° CW/CCW Limitations:
*----~~--------*--- * -None. -- * *-- --*------**-------------------* -----*-- - *-* * - - - - - - - - - -
0 Previous Results: Review on site. Comments: None. Ct-/11" 1-28-08
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Page 8 of 51
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60° S4 T-Scarn Exam Volume= 10.6 Sq. In r 60° S6 T-Scarii Exam Volume= 55.8 Sq. In. () (J) I IRS P-Scan Exam Volume= 10.6 Sq. In C 60° S6 P-Scam Exam Volume = 44.4 Sq. In. ;::;: ct :::::,
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Rev. 0 9123/US 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.
Enclosure 1: LCS Unit 1 Third ISi Interval Limited Coverage NOE Reports Manual RPV Nozzle Exam Plan Plant and Unit ID: LaSalle Unit-1 Component: LCS-l-N3A Outage: LIR12 Cal. Block: 01-91-03 Procedures: Exa*mination: GE-UT-300 Sizing: GE-UT-304 Examination (NN): GE-UT-311 Sizing: GE-UT-309 Extents: Examiner: Analyst: Examine 360°. See attached drawing for limits. NIA NIA 60°RL Full Volume T-scan 60°RL Full Volume P-scan CWICCW 60°RL Near Surface T-scan 60°RL Near Surface P-scan CWICCW 55° Inner 15%T NN PLATE 0"-8.0" +/-55°-75° CWICCW Limitations: None. 0 Previous Results: Review on site. Comments: None. Cf /11-r
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Page 12 of 51
LaSalle 1 ~ N3 Nozzle - Main Steam C) Component ID: LCS-1-N3A ' 60° S4 & IRS Exam Volume = 8.2 Sq. In \,. 60° S6 Exam Volume ;:: 48.1 Sq. In.
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() Rev. O !!l23I05 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.
Enclosure 1: LCS Unit 1 Third ISi Interval Limited Coverage NOE Reports Manual RPV Nozzle Exam Plan Plant and Unit ID: LaSalle Unit-1 Component: LCS-1-N3B Outage: L1Rl2 Cal. Block: 01-91-03 Procedures: Examination: GE-UT-300 Sizing: GE-UT-304 Examination (N/V): GE-UT-311 Sizing: GE-UT-309 Extents: Examiner: Analyst: Examine 360°. See attached drawing for limits. NIA NIA 60°RL Full Volume T-scan 60°RL Full Volume P-scan CWICCW 60°RL Near Surface T-scan 60°RL Near Surface P-scan CWICCW 55° Inner 15%TNN PLATE 0"-8.0" +/-55°-75° CW/CCW Limitations: None. 0 Previous Results: Review on site. Comments: None. C/-111.r 1-28-08
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Iii CJ) iii LaSalle 1 N3 Nozzle - Main Steam <:') Component ID: LCS-1-N38 60° S4 .& IRS Exam Volume = 8.2 Sq. In 60° S6 Exam Volume = 48.1 Sq. In. r- r () (J) 60° S4 T-Scan Exam Volume = 8.2 Sq. In 60° S6 T-Scan Exam Volume = 43.3 Sq. In. C
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Enclosure 1: LCS Unit 1 Third ISi Interval Limited Coverage NOE Reports Manual RPV Nozzle Exam Plan
- Plant and Unit ID:
Outage: Procedures: Examination: LaSalle Unit-1 L1R12 GE-UT-300 Component: Cal. Block: Sizing: LCS-1-N3C 01-91-03 GE-UT-304 Examination (N/V): GE-UT-311 Sizing: GE-UT-309 Extents: Examiner: Analyst: Examine 360°. See attached drawing for limits. NIA NIA 60°RL Full Volume T-scan 60°RL Full Volume P-scan CW/CCW 60°RL Near Surface T-scan 60°RL Near Surface P-scan CW/CCW 55° Inner 15%T NN PLATE 0"-8.0" +/-55°-75° CW/CCW Limitations: None. 0 Previous Results: Review on site. Comments: None. Cf ltt~ 1-28-08 Prenared Bv: Date:
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0 LaSalle 1 N3 Nozzle - Main Steam Component ID: LCS-1-N3C 60° S4 & IRS Exam Volume = 8.2 Sq. In 60° S6 Exam Volume = 48.1 Sq. In. r () 60° S4 T-Scan Exam Volume = 43.3 Sq. In Cf) 60° S6 T-Scan Exam Volume= 55.8 Sq. In. C IRS P-Scan Exam Volume = 8.2 Sq. In (By modeling} ;:::;: 60° S6 P-Scan Exam Volume= 34.7 Sq. In. ......
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% Total Composite Coverage= 83.8%
Rev. 0 9123/05 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.
Enclosure 1: LCS Unit 1 Third ISi Interval Limited Coverage NDE Reports Manual RPV Nozzle Exam Plan r\ Plant and Unit ID: LaSalle Unit- I Component: LCS-l-N3D ~ Outage: LIRI2 Cal. Block: 01-91-03 Procedures: Examination: GE-UT-300 Sizing: GE-UT-304 Examination (N/V): GE-UT-311 Sizing: GE-UT-309 Extents: Examiner: Analyst: Examine 360°. See attached drawing for limits. NIA NIA 60°RL Full Volume T-scan 60°RL Full Volume P-scan CW/CCW 60°RL Near Surface T-scan 60°RL Near Surface P-scan CW/CCW 55° Inner 15%TNN PLATE 0"-8.0" +/-55°-75° CW/CCW Limitations: None. 0 Previous Results: Review on site. Comments: None. CJ-frl.r
~ sn5 1-28-08
~~"L-\-09 ~ '2-/tJ-8 A J It/
../'d * ?"fr Prenared Bv: Date: R e ~ Bv: Date: Examined Bv: Date: l --n.eviewefNif...:.. /l Date:
/'rl.J.lk!.A.. "JS 'Z.. \~ .c:,e, Page 24 of 51
IE") 0 V LaSalle 1 N3 Nozzle - Main Steam Component ID: LCS-1-N3D 60° S4 & IRS Exam Volume = 8.2 Sq_ In 60° S6 Exam Volume = 48.1 Sq. In. r 0 60° S4 T-Scan Exam Volume= 43.3 Sq. In (/) 60° S6 T-Scan Exam Volume= 55.8 Sq. In. C
- i IRS P-Scan Exam Volume = 8.2 Sq_ In (By modeling) ;:::.:
60° S6 P-Scan Exam Volume = 34.7 Sq. In. mm
- i "U
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- s fl i~~ HITACHI Reactor Pressure Vessel Coverage Calculation Sheet
,- LaSalle Unit-1
;;o c.>
Weld LCS-1-N2C r () Cl) C
- J CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE ;:::;:
Required E>Cam Percent -, Weld Length= 360 Area sq. in. Area Scanned of Area Weld Length Percent :::; Exam Volume= 60" T-Scan IS4 Radial) 73 A 10.6 10.6 14.5% 360 7.3% a: ci.i 60"T-Scan IS6 Radial) A 62.5 55.8 76.3% 360 382% 55° P-Scon IS4 LKCW) 14.5% 3.6% :::J
-0 z A 10.6 10.6 360 CD Dl co
[ CD 55° P-Scan (S4 LKCC) 60° P-Scon 156 CW/CCWI A A 10.6 62.5 10.6 48.6 14.5% 66.5% 360 360 3.6% 33.2% Dl _o m
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% Total Composite Coverage = 85.9% "C 0
Rev.1 YZl/O'l Comments: NN - NoZZ1e to Vessel Inner l5%T circumferential scans 1t
~ A - Scanned area 360°. Scanning restricted due to the nozzle configuration cc CD en a
Note - Rounding methods may affect calculated values. S4-Supplement 4 underclad volume, S6-Supplement 6 volume. Weld length in degrees
C) 0 LaSalle 1 N2 Nozzle - Recirculation Inlet r 0 (/) C
- l 60° S6 Exam Volume = 62.5 Sq. In ->.
Inner 15%T Exam Volume (60°T & IRS)= 10.6 Sq. In -;
- r 60° S6 T-Scan achieved = 55.8 Sq. In a:
(/) 60° S4 T-Scan achieved = 10.6 Sq. In
- l z0
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!l 60° S6 P-Scan achieved = 48.6 Sq. In ~m
< ::::l ca CD (II r
Inner 15%T P-Scan achieved= 10.6 Sq. In (By modeling) ~ Q. I\) 00 (') C: £
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- I CODE CROSS*SECTIONAL AREA TOTAL CODE COVERAGE ;::::;:
Required Exam Percent
-I Weld Length= 360 Area sq.In. Area Scanned of Area Weld Length Percent ::J" Exam Volume= 73 c..
60° T-Scan IS4 Radial) A 10.6 10.6 14.5% 360 7.3% (J) 60° T-Scon (S6 Radial) A 62.5 55.8 76.3% 360 38.2% 55° P-Scan (S4 LKCW) A 10.6 10.6 14.5% 360 3.6% ::I "U z ro Ill cc CD i') Ir-55° P-Scan [S4 LKCCI 60° P-Scan (56 ON/CONJ A A 10.6 62.5 10.6 48.6 14.5% 66.5% 360 360 3.6% 33.2% Ill re m
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% Total Composite Coverage= 85.9% "C 0
~.1JJl3/0'.
Comments: NN - Nozzle to Vessel Inner 15%T circumferential scans ~ A- Scanned.area 360°. Scanning restricted due to the nozzle configuration l G) en 9. Note - Rounding methods may affect calculated values. S4-Supplement 4 underdad volume. 56-Supplement 6 volume. Weld length in degr~
r Ill Cl)
- 0 {)
m C LaSalle 1 S!
~
r
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- u N2 Nozzle - Recirculation Inlet r
~ 0 c:.> (J)
Component ID: LCS-1-N2D C
- J 60° S6 Exam Volume = 62.5 Sq. In ->.
Inner 15%T Exam Volume (60°T & IRS)= 10.6 Sq. In -I
- r 60° S6 T-Scan achieved= 55.8 Sq. In a
u.i 60° S4 T-Scan achieved= 10.6 Sq. In
- J
"'U z CD m ru [ 60° S6 P-Scan achieved = 48.6 Sq. In < :::J co (D (I) Inner 15%T P-Scan achieved = 10.6 Sq. In (By modeling) ~ Q.
(.,.) 0 r-(') C: g 0 Cf> ~- ~
...... ~
I CD ro CJ1 z I\) 6.3" 9.6 11 18.1" 0. :-7 0 0 T/P't_ 60°T/P NS 60°P 60°T 0 (D I I ii3 cc I (D z
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HITACHI Reactor Pressure Vessel Coverage LaSalle Unit-1 Weld LCS-1-N16 Calculation Sheet r 0 (/) C
- J CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE ->.
Required Exam Percent --l Weld Length= 360 Area sq.In. Area Scanned of Area Weld Length Percent ::r Exam Volume= 56 14.6% a: 60° T-Scon (S4 Radial) A 8.2 8.2 360 7.3% (/) 60" T-Scan (56 Radial! A 47.8 43.4 77.5% 360 38.8%
- J 55° P-Scon (S4 LKCWl .A 8.2 8.2 14.6% 360 3.7%
"'U 55° P-Scan !54 LKCCI 8.2 CD m D) cc 6D° P-Scon 156 ON/CONJ A
A 8.2 47.8 36.9 14.6% 65.9% 360 360 3.7% 32.9%
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% Total Composite Coverage= 86.3% "O 0
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Rov.13/nlal Comments: NN - Nozzle to Vessel Inner 15%T circumferential scans A - Scanned area 360°. Scanning restricted due to the nozzle configuration Note - Rounding methods may affect calculated values. S4-Supplement 4 underclad volume, 56-Supplement 6 volume. Weld length in degrees
- 0 11;\
V LaSalle 1 r N16 Nozzle 0 CJ) C Component ID: LCS-1-N16 :::J 60° S6 Exam Volume = 47.8 Sq. In Inner 15%T Exam Volume (60°T & IRS)= 8.2 Sq. In 60° S6 T-Scan achieved= 43.4 Sq. In 60° S4 T-Scan achieved= 8.2 Sq. In :::J
"'U z CD m ti) cc ~ <
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(') CD CD 60° S6 P-Scan achieved= 36.9 Sq. In ~o (.,) r -* en Inner 15%T P-Scan achieved = 8.2 Sq. In - ~- ~ (') 0 en I CD CD I CJ'I z...... a. :"':'
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I HITACHI
~ Calculation Sheet LaSalle Unit-1 Weld LCS-1-NS r 0
(f) C
- i CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE ->.
Required Exam Percent Weld Length = 360 Area sq. In. Area Scanned of Area Weld Length Percent EMam Volume= S6 60° T-Scon (54 Rodioll A 8.2 8.2 14.6% 360 7.3% (f) 60° T-Scon (56 Radial) A 47.8 43.4 77.5% 360 38.8%
- i 55° P-SCon 154 LKCW) A 8.2 8.2 14.6% 360 3.7%
"'U z CD m D)
(C [ 55° P-Scon 154 LKCCI 60° P-Scan IS6 CW/CONJ A A 8.2 47.8 8.2 36.9 14.6% 65.9% 360 360 3.7% 32.996
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% Total Composite Coverage= 86.3% "C 0
Rev. l 3/23/09 Comments: NN -Nozzle to Vessel Inner 15%T circumferential scans ra-A- Scanned area 360°. Scanning restricted due to the nozzle configuration Note - Rounding methods may affect calculated values. 54-Supplement 4 underclod volume, 56-Supplement 6 volume. Weld length in degrees
- 0 0 LaSalle 1 r
...... r
;:c w
N5 Nozzle - Core Spray 0 (J) C Component ID: LCS-1-N5 :J 60° S6 Exam Volume = 47.8 Sq. In --l
- J" Inner 15%T Exam Volume (60°T & IRS)= 8.2 Sq. In a.
60° S6 T-Scan achieved = 43.4 Sq. In (J) 60° S4 T-Scan achieved = 8.2 Sq. In :J
""O z0 ~m D) ca < :J CD !;j_ 60° S6 P-Scan achieved = 36.9 Sq. In D) 0
(.,J CD r
~a Inner 15%T P-Scan achieved = 8.2 Sq. In (/)
.i:,.. 0 (') en ~- ~ I CD CD en I a. :-7 ....>. zen () 0
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CD T-Scans 60°T/P 60°P 60°T D) ca I CD z 0 I m T I I I
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- i CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE ->.
Required Exam Percent -j Weld Length = 360 Area sq.In. Area Scanned of Area Weld Length Percent ::r Exam Volume= 66 a: 60° T-Scan 154 Radial) A 9.6 9.6 14.5% 360 7.2% (J) 60° r-scan !S6 Radiall A 56.8 50.2 75.6% 360 37.8%
- i 55° P-Scan 154 LKCWl A 9.6 9.6 14.5% 360 3.6% ..+
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(C 55° P-Scan IS4 LKCCI 60° P-Scon IS6 cw,ccw1 A A 9.6 56.8 9.6 41.2 14.5% 62.0% 360 360 3.6% 31.0%
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% Total Composite Coverage= 83.3% "O 0
Rev. 1 3/73100
~
Comments: NN - Nozzle to Vessel Inner 15%T circumferential scans A- Scanned area 360°. Scanning restricted due to the nozzle configuration Note - Rounding methods may affect calculated values. S4-Supp!ement 4 underclad volume, S6-Supplement 6 volume. Weld length in degrees
0 0
....r-
....c.>
- 0 LaSalle 1 0 r
(/) N6 Nozzle - LPCI C
- l Component ID: LCS-1-N6A 60° S6 Exam Volume = 56.8 Sq. In Inner 15%T Exam Volume {60°T & IRS) = 9.6 Sq. In
- l z 60" S6 T-Scan achieved = 50.2 Sq. In "U CD m fl) cc CD 0
~
60° S4 T-Scan achieved= 9.6 Sq. In < Q. fl)
- l CD w r- !:: ~
nen - 60° S6 P-Scan achieved = 41.2 Sq. In 0)
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0 CJ'1 ->. z I 0) Inner 15%T P-Scan achieved= 9.6 Sq. In {By modeling) CD Q. CD
- -7
> 0 0
6.7" 8.6" 15.9" < CD 60°T/P NS 60°P 60°T fl) cc CD z 0 r-I m
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Reactor Pressure Vessel Coverage HITACHJ Calculation Sheet LaSalle Unit-1 Weld_LCS-1-N6S r 0 (/) C
- J CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE ....>.
Required E>cam Percent Weld Length= 360 Area sq.in. Area Scanned of Area Weld Length Percent Exam Volume= 66 60° T-Scon (S4 Radial) A 9.6 9.6 14.5% 360 7_2% 60° T-Scon IS6 Radial) A 56.8 50;2 75.6% 360 37.8%
- J 55" P-Scan tS4 LKCWI A 9.6 9.6 14.5% 360 3.6%
""O z CD m Dl
[ 55" P-Scon IS4 LKCCI A 9.6 9.6 14;5% 360 3.6% cc CD . 60° P-Scan 156 ON/CONJ A 56.8 41.2 62.0% 360 31.0% ~ Q.
- J
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% Total Composite Coverage= 83.3% 'O 0
~
R<Y. l 3/Zl/O! Comments: NN - Nozzle to Vessel Inner 15%T circumferential scans A - Scanned area 360". Scanning restricted due to the nozzle configuration Note - Rounding methods may affect calcufated values. S4-Supplement 4 underclad volume, S6-Suppfement 6 volume. Wefd length in degrees
r Dl (/l
- 0 21..
1D C:
....~
....r
- 0 LaSalle 1 r
() c.l (J) N6 Nozzle - LPCI C
- i Component ID: LCS-1-N6B ......
60° S6 Exam Volume = 56.8 Sq. In Inner 15%T Exam Volume (60°T & IRS) = 9.6 Sq. In
- i z 60° S6 T-Scan achieved= 50.2 Sq. In
""U CD m Ql cc CD
~ 60° S4 T-Scan achieved = 9.6 Sq. In <
Ql
- i C')
c6" (,.) r C. ~ - 60° S6 P-Scan achieved = 41.2 Sq. In 00 (") 0 C/)
.... ~- ~
I I Inner 15%T P-Scan achieved = 9.6 Sq. In (By modeling) CD CD CJ'l ...... zO> a. :-7 a, ()
<t 6.7" 8.6" 15.9" 0 CD T/P 60°T/P NS 60°P 60°T Ql cc CD I z 0
r- m I
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. HITACHI Reactor Pressure Vessel Coverage LaSalle Unit-1 Weld LCS-1-N6C Calculation Sheet r
0 (f) C
- J CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE ;::::;:
Required Exam Percent Weld Length = 360 Area sq.In. Area Scanned of Area Weld Length Percent Exam Volume= 66 60" T-Scon 154 Rodioll A 9.6 9.6 14.5% 360 7.2% 60" T-Scon (56 Rodfall A 56.8 50.2 75.6% 360 37.8% 55° P-Scon 154 LKCWJ 9.6 9.6 14.5% 3.6% :J A 360
""O 55* P-Scon 154 LKCC) A 9.6 9.6 14.5% 360 3.6% CD m D>
ca 60" P-Scon 156 CW/CCW) A 56.8 41.2 62.0% 360 31.0% <
~ Q.
- J CD u.)
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% Total Composite Coverage= 83.3% "O 0
Rev. 1 l/23/0S Comments: NN - Nozzle to Vessel Inner 15%1 circumferential scans ~ A- Scanned area 360°. Scanning restricted due to the nozzle configuration Note - Rounding methods may affect calculated values. 54-Supplement 4 underclod volume. 56-Supplemerit 6 volume. Weld length in degree~
0 r Ql en
~
m C
~
r
- o LaSalle 1 r 0
(f) c.> N6 Nozzle - LPCI C
- J Component ID: LCS-1-N6C
-I
- J" 60° S6 Exam Volume= 56.8 Sq. In a.
Inner 15%T Exam Volume (60°T & IRS)= 9.6 Sq. In 00
- J z 60° S6 T-Scan achieved= 50.2 Sq. In
"'U CD m Ill cc 0
!;t 60° 54 T-Scan achieved= 9.6 Sq. In <
Ill Q.
- J CD <D
~ r C: ~
() 0 60° S6 P-Scan achieved = 41.2 Sq. In ~- ~ 0 'fl
...... CD CD CJ1 z I Inner 15%T P-Scan achieved= 9.6 Sq. In (By modeling) c.. :-7°
....>. C) () () 0 6.7" 8.6" 15.9" < CD 60°T/P NS 60°P 60°T Ill cc CD z 0 r-m
--- ;a CD I "O 0
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a~ I HITACHI Reactor Pressure Vessel Coverage Calculation Sheet
...... LaSalle Unit-1 r
- a w
Weld LCS-1-NlO r 0 (f) C CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE ....,. Requi,ed Exam Percent Weld Length = 360 Area sq.in. Area scanned of Area Weld Length Percent EJcam Volume= 56.4 60° T-Scon (S4 Redial) A 8.2 8.2 14.5% 360 7.3% 60"T-Scan (S6 Rodiall A 48.2 43.5 77.1% 360 38.6% z 55° P-Scon (S4 LKCWl A 8.2 8.2 14.5% 360 3.6%
""CJ CD m Ill ca CD
~
~
55° P-Scon (S4 LKCC) 60° P-Scon 156 CW/CONJ A A 8.2 48.2 8.2 39.5 14.5% 70.0% 360 360 3.6% 35.0% <
~ Q. ~
r- cg
....,. 0 en 0 ....
I I
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....,. ....z 0
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% Total Composite Coverage= 88.1% "O 0
111!,.l 3/Z!/O'J ;:i. en Comments: NN
- Nozzle to Vessel Inner 15%T circumferential scans A - Scanned area 360°. Scanning restricted due to the nozzle configuration Note - Rounding methods may affect calculated values. 54-Supplement 4 underdad volume. 56-Supplement 6 volume. Weld length in degrees
0 r Ill LaSalle 1 en et CD C N10 Nozzle - CRD Return
....$: Component ID: LCS-1-N10
!::: r
....:::c
(.,) 0 (/) 60° S6 Exam Volume = 48.2 Sq. In C Inner 15%T Exam Volume (60°T & IRS) = 8.2 Sq. In ::J 60° S6 T-Scan achieved= 43.5 Sq. In 60° S4 T-Scan achieved= 8.2 Sq. In 60° S6 P-Scan achieved= 39.5 Sq. In ::J "U z Inner 15%T P-Scan achieved= 8.2 Sq. In (By modeling) CD m ru co CD 0 l:j CD
< ::J
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Page 43 of 51
r 0 (J) C
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en or e HITACHI LaSa lle Unit 1 LCS- 1-BG Weld Coverage Plot C
~
LaSalle Unit-1 Weld BG 10* Exam Volume= 8.5 Sq. In. r 45' Exam Volume= 39.5 Sq. In. 0 (/) 60' Exam Volume = 8.3 Sq. In. C 70" T-Scan achieved = 8.5 Sq. In. :::J 45' T-Scan achieved= 39.5 Sq. In. ;:;: 60' T-Scan achieved = 8.3 Sq. In. ...... 70' P-Scan acl1ieved = 8.5 Sq. In. 45' P-Scan achieved = 39.5 Sq. In. --, 60' P-Scan acl1ieved = 8.3 Sq. In. c.. (/)
- J
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< :::J m
cc CD ~ Q..
.i:,.
CJ1 C: g - ~- ~ I 70"T-&an P-Scans 0 45'T-Scan
~'T--Scan CD CD CJ1
...... I I I -- --~ c.. ...... 0 I I 0 I : I CD Ql cc CD Shell 3 CW - - - -{ Shell 3 CCW z 0 m I I
- 0 CD L __ __ __ __ Scanner Motion _ _____ _J "O 0
;::i.
Left Side Scans -5.5" CJ) 18.5"
~1*6..1$"
'J co HonM'lllla.d T*Q..3125'"
a,
"' Coverage Plot for Left Side Scans
e e
~- HITACHI LaSalle Unit 1 LCS-1-BG Weld a,
u,
~
Coverage Plot
<ii C
~
LaSalle Unit-1 Weld BG 70" Exam Volume = 8.5 Sq. In. r 45" Exam Volume = 39.5 Sq. In. 0 (/) 60" Exam Volume = 8.3 Sq. In. C 70" T-Scan achieved = 8.5 Sq. In. :::i 45' T-Scan achieved= 39.5 Sq. In. ;:::;: 60" T-Scan achieved= 8.3 Sq. In. ....,. 70' P-Scan achieved = 8.5 Sq. In. -i
-=,-
45: P-Scan achieved= 39.5 Sq. In . -, 60 P-Scan achieved = 8.3 Sq. In. a. (/)
- i "U
ru m
-, m co <
ru (") :::i CD
.i:,. C (J) 0
- 0) <t.
- 3 -, P-5cans T/P-Scans11o* r-scan C 0 45' T-Scan
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________ _J' "O L_________ Scanner Motion 0
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6.25" Right Side Scans -18.5" (J)
~ T* 4.1S" Hamnlll Old
- il.3125"'
Coverage Plot for Right Side Scans
Enclosure 1: LCS Un it 1 Third ISi Interval Limited Coverage NOE Reports
-l.{)
N N 1")
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e -:c e LaSalle Unit 1 - RF016 Page 12 0115 Page 47 of 51
0 0 0 en i5" C e HITACHI SP2000 RPV Examination Coverage ca/cu/ation Sheet LaSalle Unit 1 / L1R16 I 1
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0 en CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE r Weld Length = 109.38 Required Exam Percent 0 Cl) Exam Volume = 56.3 Area Sq. in. Area Scanned of Area Weld Length Percent C 70° T-Scan [S6 NS) A 8.5 8.5 15.1% 92.3 6.4% :J 45° T-Scan {56 FV) A 39.5 39.5 70.2% 92.3 29.6% -->. 60° T-Scan ON (S4) A 8.3 8.3 14.7% 92.3 3.1% 60° T-Scan CC (S4) A 8.3 8.3 14.7% 92.3 3.1% 70° P-Scan [S6 NS] A 8.5 8.5 15.1% 92.3 6.4% 45° P-Scon [S6 FVJ A 39.5 39.5 70.2% 92.3 29.6% 60° P-Scon UP [S4) A 8.3 8.3 14.7% 92.3 3.1%
- J 60° P-Scon ON {S4J A 8.3 8.3 14.7% 92.3 3.1%
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% Total Composite Coverage= 84.3%
1 Cl) I Comments: A- Automated Scanning was limited due to the proximity of the Nl2-A nozzle iI I I Note - Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in inches. Rell.O 5/Zl/15
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Enclosure 2 LaSalle County Generating Station Unit 2 Third lnservice Inspection (ISi) Interval Limited Coverage Non-Destructive Examination (NDE) Reports
Enclosure 2: LCS Unit 2 Third ISi Interval Limited Coverage NOE Reports Report No.: HITACHI EXAMINATION
SUMMARY
SHEET L2Rl2*029 I e Site: Outage: LaSalle L2R12 Component ID: HP-PU2-04 PL-PUMP System: HP ASME Cat.: C-C ASME Item C3.30 Aug Req N/A Exoms I I Doto Sheet Col Sheet I Procedure Calibration Block Exam/Oper. Cert Level I Date Performed I I Personnel MT I MT-004 I NIA I GE-MT-100 Ver/Rev 8 I NIA I Jamil Wolden 11-L I 1/19/2009 Examination Results: During the magnetic particle examination of the obove referenced weld. no recordable indications were detected. Examination was limited due to permanent purrip stand. 16% of the required examination volume was examined. This examination meets the requirements of ASME Section XI, 2001 Edition. 2003 Addenda. No previous data was available for review. 0 Examination results were compared to Doto Report N/A from: NIA D Change These examinations were performed under Work Order: 01011137-01 ONo Change This Summary and the following data sheets hove been reviewed ond accepted by the following personnel: Ju)-5t~ Prepared By:
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ii I r HITACHI 11 Wall Thickness Profile Sheet Site: Project LaSalle L2R12 Unit
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System: ~ I Component ID Number. /MS-2044-:13 Position O' 90" 180" 270' [ID l .90 NIA NIA NIA Crown Height .15" rn rn I rn r 0 C/) 2 I .88 I NIA NIA NIA C Crown Width: l.3" :::J Ef2£ Valve ;:::;: 3 I l.10 I NIA NIA NIA UPST Component DNST Component N Nominal Diameter: l8.0" -l I NIA NIA ::J" 4 NIA NIA Weld Length: 57.5" a 5 I NIA NIA NIA NIA FLOW.. cr.i
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e 0 e HITACHI Pipe Weld Coverage Calculation Sheet LaSalle Unit 2 / L2R12 r IMS-2044-13 0 Cl) Spring / 2009 C
- J CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Total Required Total Scanned Weld Length= Required Area Scanned Area %Coverage Area Area Exam Area= D.843 Upstream Scan I 0.843 0.697 (J)
Downstream Scan I 0.843 0.477
- J 3.373 2.02 59.8%
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Enclosure 2: LCS Unit 2 Third ISi Interval Limited Coverage NOE Reports eI Site: HITACHI LaSalle Unit 2 Examination Summary Sheet Component ID: LCS-2-NlO Report No.: L2R12*081 Outage: L2R12 Configuration: Nozz-Shell / NV IRS System: CRD ASMECat B-D ASMEltem: B3.90 Aug. Requirements: NIA Exams Colibrotion SheeUs~ Colibrotion Bloclc Exominotion NOE Level: Performed: Procedure: Personnel: Dote: Tl APC-005 thru 008 01-92-01 GE-UT-716 Vl Jonothon Guillote LVII 01-26-09 Pl APC-001 thru 004 CAL-IIW2-067 GE-UT-718 VO Grohom McNabb LVII 01-27-09 NV APC-017 thru 020 TP 0-073, 0-074 01-92-01 GE-UT*300 VlO Joncithon Guillote LVII 01-28-09 NN 0-069 CAL-IIW2-067 GE-UT-311 VlS Comments: Ultrasonic exominotion results were occeptoble to the requirements of ASME B&PV Code Section XI. 2001 Edition with the 2003 Addenda os modified by the POI progrom description and the Federol Register, Port II, Nuclear Regulatory commission, 10 CFR Port 50 for Cotegory 8-0 Reactor Pressure Vessel (RPV) Nozzle-to-Vessel Weld Automated transverse ond parollel scans. were performed in accordance with procedure GE-UT-716, Vl, using 45° Shear wave, 60° RI.. and 70° RL search units, supplemental 0° L-Wave scans were also performed. Automated 55° Shear Inner Radius Nozzle to Vessel examinations were performed in accordance with procedure GE-UT-718 VO, ORR No. 07-07 and 08-15 and volidoted by modeling: Reference, "The General Electric LaSalle 2 Nozzle Modeling Document". Automated UT scanning wos performed from the vessel OD surface and wos restricted due to the nozzle configuration and the mechanical limit of the scanner arm. Manual exams were performed to supplement the automated exominotions. Manuel examinations were performed in accordance with GE-UT-300 VlO and GE*UT-311 VlS. The SP 2000 OD automated UT system Oreference is located ot TDC of nozzle. For SP 2000 automated colibrotions refer to report l2Rl2-094. No relevant indications were recorded. Previous examination doto was reviewed, with no changes noted. Automated and Manual UT Composite Coverage= 71.9%. The examination results were compared with data report LCS*2*Nl0 from 1996 outogewith 181 No Change These examinations were performed under Work Order. 1011137 0Chonge This summary and the following data sheets hove been reviewed and accepted by the following personnel: Jk-C.~Prepared By:
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Level: 2.j'lo'i Dote: 4="J;i~ ~ 'Iii" ~ Date:
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ANIJ Reviewed BY: Date: e LaSalle Unit 2, l2Rt2, 2009 Page 1 of 15 Page 6 of 45
nu e eI HITACHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 2 / L2R12 r 0 (J) LCS-2-N10 (Noz-RPV) C Spring / 2009 ::, CODE CROSS-SECTIONAL AREJI TOTAL CODE COVERAGE Percent Weld Length= 360. Required Exam Area Scanned of Area Weld Length Pereent Exam Volume= 59.1 Area Sq.In. Automated Automated Automated Automated so* T-scan cS4 uc1 A 8.5 8.5 14.4% 360 7.2% 45° T-8ca.n(S6 FV A 39 25 42.3% 360 21.2% ::, 70° T-5can CS6 NS A 11.6 3.7 6.3% 360 3.1% CD m
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Ill 45° P-Scan (S6 FV A 39 16.4 27.7% 360 13.9% CD 70° P-8can S6 NS A 11.6 2.5 4.2% 360 2.1% ~a
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% Total Composite Coverage= 54.1%
Rov.O IIIZ3IOS Comments: A - Automated scanning was restricted due to insulation interference and the mechanical limit of the scanner arm.. Manual exams were performed to supplement the automated exams. Note* Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, Ns-Near Surface. Weld lenoth in degrees.
e 0 . e fl I HITACHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 2 / L2R12 r 0 LCS-2-N10 (Noz-RPV) en C Spring / 2009 :::, I\.) CODECROSS-SECTIONALAREA TOTAL CODE COVERAGE -, Percent ::r Weld Length= Exam Volume= 360. 59.1 Required Exam Area Scanned Area SQ. In. Manual of Area Manual Weld Length Manual Percent Manual a CJ) 60° T-Scan CS4 UCl A 8.5 0 0.0% 360 0.0% so* T-Scan S6 FV A 39 5 8.5% 360 4.2% :::,
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cc ~ Q. CD 60° P-Scan S6t-v A 39 10.3 17.4% 360 8.7% rO co 60" P-Scan 56NS A 11.6 2.5 4.2% 360 2.1%
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% Total Composite Coverage= 17.8%
RoY. 0 Sl2MJ! Comments: A - Supplemental manual exam due to insulation interference and mechanical limit of scanner ann Note
- Rounding methods may affect calculated values. UC-Underclad, FV-FuD volume, NS-Near Surface. Weld lenath in inches or degrees.
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eI HITACHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 21 L2R12 r 0 (J) LCS-2-N1A Recirculation Outlet (Naz-Shell) C Spring / 2009 :J CODECROS~ECTIONALAREA TOTAL CODE COVERAGE PeRent Weld Length= 360. Required Exam Area Scanned of Area Wald Length PeRent Exam Volume= &OA Am Sq.In. Automated Automated Automated Automatad so 0 T-Scan S4UC A 8.5 8.5 14.1% 360 7.0% 45° T*Scan S61-v A 39.2 34.6 57.3% 360 28.6% :J
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A 12.7 6.3 10.4% 360 360 5.2% 7.0% ro< :Jm co A* 8.5 8.5 14.1% CD ~C') 45° P-Scan S6FV A 39.2 24.1 .39.9% 360 20.0%
--" 70° P-Scan ::,o N;:; A 12.7 4.5 7.5% 360 3.7%. ro
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% Total Composite Coverage = 71.6%
Rev.081ZW5 Comments: A - Automated scanning was not restricted. A* - Single side access. 50% credit of the achieved Supplement 4 T-scan volume claimed. Note - RoundinQ methods mav affect calculated values. UC-Underdad. FV-Full volume, NS-Near Surface. Weld length in degrees.
0 LaSalle Unit-2 r 0 CJ) LCS-2-N1 C Component ID: LCS-2-N1A ;:;: I\.) 70° Exam Volume = 12.7 Sq. In. -I
- r 45° Exam Volume = 39.2 Sq. In.
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yrl. fl I HITACHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 2 I L2R12 r 0 (f) LCS-2-N1B Recirculation Outlet (Noz-Shell) C Spring / 2009 :J
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CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE -; Percent ::::; Weld Length= 360. Exam Volume= 60A Required Exam AreaSq.ln. Area Scanned Automated of Area Automated Weld Length Automated Percent Automated a 60"T-5can S4UC A 8.5 8.5 14.1% 360 7.0% en 45°T-5c:an S6 F\I A 39.2 34.6 57.3% 360 28.6% :J
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A A" 12.7 6.3 10.4% 360 5.2% ro
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...... 70° P-scan :S6Nl:i A 12.7 4.5 1.sv11, 360 3.7% ro
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% Total Composite Coverage = 71.6%
R... o Bl'ZW!
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a. a> A" - Singfe side access, 50% credit of the achieved Supplement 4 T-scan volume claimed. Note - Roundina methods mav affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld lenath in dearees.
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45° Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 70" T-Scan achieved = 6.3 Sq. In. 45° T-Scan achieved = 34.6 Sq. In. ::J "U 60° T-Scan achieved = 8.5 Sq. In. ro m Ol cc < Ol (")
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0 e 81 Hl"mCHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 2/ L2R12 r 0 (/) LCS-2-N2C (Noz-RPV) C Spring / 2009 ::i CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length= 380. Required Exam Area Scanned ofArea Weld Length Percent Exam Volume= 59.1 Area Sa.In. Automated Automated Automated Automated (/) so* T-Scan S4 uc1 A 8.5 8.5 14.4% 360 7.2% 45° T-Scan lS6 FVI A 39.2 33.5 56.7% 360 28.3% ::i "lJ 70° T-Scan CS6 NS) A 11.4 5.8 9.8% 360 4.9% ~m D) cc IRS P-8can CS4 UCl A* 8.5 8.5 14.4% 360 7.2% < ::i CD 45" P-8can lS6 FVI A 39.2 22.5 38.1% 360 19.0%
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...... 10* P-Scan (S6 N~) A 11.4 4.5 7.6% 360 3.81{;
ro
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0 60"T-Scan S4UC 0 0 CD CD .j:>.. a. !'? (]1 45°T-Scan S6FV 0 0 10* T-Scan, S6NS 0 0 0 0 IRS P-Scan S4UC 0 0 < CD 45° P-Scan S6 t-V 10* P-Scan ::sr.NS 0 0 0 0 ru cc CD 60°T-Scan, S4UC1 0 0 z 0 45° T-Scan S6 F\i 0 0 m 10° T-Scan S6NS 0 0 ;o IRSP-Scan S4UC 0 0 CD "C 45° P-Scan S6FV 0 0 0 70° P-Scan l:>~N::i 0 0 @"
% Total Composite Coverage= 70.5%
Rov,0812311)5 w Comments: A- Automated scanning was not restricted a
~* -Single side access, 50% credit of the achieved Supplement 4 T-scan volume claimed. '
Note - Rounding methods may affect calculated values. UC-Underclad, FV-Fun volume, NS-Near Surface. Weld lenath in dearees.
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-l 70° Exam Volume = 11.4 Sq. In. ::r 45° Exam Volume = 39.2 Sq. In.
"'"1 0..
Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. ci.i
- i 70° T -Scan achieved = 5.8 Sq. In. ......
"U Ill cc 45° T-Scan achieved= 33.5 Sq. In. mm CD 60° T-Scan achieved = 6.8 Sq. In. ~(")
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0 LaSalle Unit-2 r 0 LCS-2-N2 CJ) C Component ID: LCS-2-N2C 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. (J) 70° P-Scan achieved = 4.5 Sq. In.
"U !l) 45° P-Scan achieved = 22.5 Sq. In. mm co IRS P-Scan achieved = 8.5 Sq. In. (By model)
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0 e HITACHI Reactor Pressure Vessel Coverage Calculation Sheet
.LaSalle Unit 2 / L2R12 r 0
LCS-2-N3A CJ) C Spring 2009 :::i CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld length = 360. Required Exam Area Scanned of Area Weld length Percent Exam Volume= 73.5 Area Sq.In. Manual Manual Manual Manual 60° T-Scan (S4 UC) A 10.6 10.6 14.4% 360 7.2% 60° T-Scan (S6 FV) A 47.8 65.0% 360 :::i 50.1 32.5%
"'U 60° T *Scan (S6 NS A 12.8 5.9 8.0% 360 4.0% ro m D) cc IRS P-Scan S4 UC) A 10.6 10.6 14.4% 360 7.2%
D)
- i
(') CD N 60° P-Scan S6 FV) A 50.1 42 57.1% 360 28.6o/o i= 0
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N 60° P-scan (S6 NS) A 12.8 5.5 7.5% 360 3.7% 0 ~-~
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~ 01 60° T-Scan (S4 UC> ~!':' 60° T-Scan (S6 FV 0 0 60° T-Scan 1S6 NS < IRS P-Scan S4UC .., CD D) so* P-Scan S6FV cc CD 50° P-scan (56 NS) z 0 60° T-Scan CS4 UC) m 60° T-Scan (S6 FV ;:o CD 60° T-Scan S6 NS "'C IRS P-Scan (S4 UC> 0 so* P-Scan CS6 FV ~ 60° P-Scan (S6 NS)
% TotaJ Composite Coverage= 83.3%
Rev. 0 9/23/05 Comments: A
- Manual exam was restricted due to the nozzle configuration.
Note - Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in inches or degrees.
~
0 w e HITACHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 2 / L2R 12 r 0 LCS-2-N38 (f) Spring 2009 C
- J CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume= 73.5 Area Sq. In. Manual Manual Manual Manual 60° T-Scan lS4 UC) A 10.6 10.6 14.4% 360 7.2%
"'U 60° T-Scan S6FV A 50.1 47.8 65.0% 360 32.5% .....
- J ru 60°T-Scan S6NS A 12.8 5.9 8.0% 360 4.0% ~ m cc IRS P-Scan, S4UC1 A 10.6 10.6 14.4% 360 7.2% < :J (l) ~ Q..
I'.) 60° P-Scan S6FV A 50.1 42 57.1% 360 28.6% rO w 60° P-Scan (S6 N~) A 12.8 7.5% -* en 5.5 360 3.7% 3 C: 0 -* (l) .i:,. CJ1 60° T-Scan lS4 UC) ~ !'? 60° T-Scan S6 FV) 0 0 60° T-Scan S6 NS) < (l) IRS P-Scan S4 UC 60° P-Scan S6 FV) iu cc (l) 60° P-Scan (S6 NS) z "Dr 0
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60° P-Scan (S6 NS)
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0 % Total Composite Coverage= C}.) 83.3%
~
Rev.a 912:WS
~ ~ Comments: A - Manual exam was restricted due to the nozzle configuration.
Note - Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in inches or degrees.
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=
81 HITACHI Reactor Pressure Vessel Coverage Calculation Sheet i;:; r
~ LaSalle Unit 2 / L2R12 0
.!'> Cl) g LCS-2-N3C (Noz-RPV) m C
Spring / 2009 :::J I\) CODE CROSS-SECTIONAL ARl:A TOTAL CODE COVERAGE -i Percent ::,- Weld Length= 360. Exam Volume= 73.5 Required Exam Area Sq.In. Area Scanned Automated of Area Automated Weld Length Automated Percent Automated a Cl) 60°T-Scan S4UC A 10.6 10.6 14.4% 360 7.2% 45° T-Scan SSF\J A 50.1 42.7 58.1% 360 29.0% :::J "U D> 70"T-8can S6NS A A* 12.8 5.8 7.9% 360 3.9% mm
< :::J cc IRS P-5can S4UC 10.6 10.6 14.4% 360 7.2%
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CD 45° P-5can S6FV A 50.1 33.7 45.9% 360 22.9% I\) 70" P-SCSn S6NS A 12.8 5.6 7.6% 360 3.8% ro
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% Total Composite Coverage= 74.1%
l w Comments: A- Automated scaMlng was restricted due to nozzle configuration Rov,O~ a Note - Rounding methods may affect calculated values. UC-Undercfad, FV-Full volume, NS-Near Surface. Weld lenath in dearees.
0 0. r LaSalle Unit-2 0 en C LCS-2-N3 ::I Component ID: LCS-2-N3C "'-i 70° Exam Volume= 12.8 Sq. In. 45° Exam Volume = 50.1 Sq. In. a. Inner 15%T Exam Volume (IRS & 60°T) = 10.6 Sq. In. (/)
- I 70° T-Scan achieved = 5.8 Sq. In.
""U Ol 45° T-Scan achieved= 42.7 Sq. In. m-
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0 r LaSalle Unit-2 0 en C LCS-2-N3 :::::J Component ID: LCS-2-N3C 70° Exam Volume = 12.8 Sq. In. 45° Exam Volume = 50.1 Sq. In. (J) Inner 15%T Exam Volume (IRS & 60°T) = 10.6 Sq. In.
- J
"'U 70° P-Scan achieved = 5.6 Sq. In.
Ill 45° P-Scan achieved= 33.7 Sq. In. ~m cc IRS scan achieved (By Modeling}= 10.6 Sq. In. < :::::J Cl) ~ Q. N rO
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~
V Reactor Pressure Vessel Coverage Calculation Sheet
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~ LaSalle Unit 2 / L2R12 r
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LCS-2-N3D (Noz-RPV)
...g Spring / 2009 C
N CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE
-l Percent :,
Weld Length= Exam Volume= 360, 73.5 Required Exam Area Sa.In, Area Scanned Automated of Area Automated Weld Length Automated Percent Automa1Bd a: 60° T-Scan S4UC A 10.6 10.6 14.4% 360 7.2% ci5 45° T-Scan S6FV A 50.1 42.7 58.1% 360 29.0% ::,
"'U D) 70°T-5can IRS P-Scan S6NS S4UC A
A* 12.8 10.6 5.8 10.6 7.9% 14.4% 360 360 3.9% 7.2% ro<::,m cc ~(") CD 45° P-5can S6FV A 50.1 33.7 45.9% 360 22.9% N 10* t"~can ::st!NQi A 12.8 5.6 7.6'Yo 360 3.8"/o rO
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% Total Composite Coverage= 74.1%
i (,> Comments: A -Automated scanning was restricted due to nozzle configuration Rff.OW23111! g,
<D Note - Rounding methods may affect calculated values. UC-Underclad, FV-Futl volume, NS-Near Surface. Weld lenath in degrees.
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-I 70" Exam Volume= 12.8 Sq. In. ....,
a. 45" Exam Volume = 50.1 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 10.6 Sq. In. (f)
""CJ 70° T-Scan achieved = 5.8 Sq. In. .....
Dl 45° T-Scan achieved= 42.7 Sq. In. !!l<::,m ca 60° T-Scan achieved= 10.6 Sq. In. ~ Q. CD rO
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0 r LaSalle Unit-2 0 (J) C LCS-2-N3 :::J N Component ID: LCS-2-N3D -I
- r 70° Exam Volume= 12.8 Sq. In.
45° Exam Volume = 50.1 Sq. In. a Inner 15%T Exam Volume (IRS & 60°T) = 10.6 Sq. In. en
- J 70° P-Scan achieved = 5.6 Sq. In.
"'U 45° P-Scan achieved= 33.7 Sq. In. co m Q) cc CD IRS scan achieved (By Modeling) = 10.6 Sq. In. < Q)
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Enclosure 2: LCS Unit 2 Third ISi Interval Limited Coverage NOE Reports (I) e Site: HITACHI LaSalle Unit 2 Examination Summary Sheet Component ID: LCS-2-N6A Report No.: L2R12-089 Outage: L2R12 Configuration: Nozz-Shell / NV IRS System: LPCI ASMECat 8-D ASMEltem: B3.90 Aug. Requirements: NIA Exams Calibrotion Sheetlsl: Calibration Block: Examination NOE Level: Performed: Procedure: Personnel: Dote: TL APC-005 thru 008 01-92-01 GE-UT-716 Vl Jonathon Guillote LVII 01-24-09 Pl APC-001 thru 004 CAL-IIW2-067 GE-UT-718 VO Graham McNabb LVII NV APC-009 thru 012 Comments: Ultrosonic ei<aminotion results were acceptable to the requirements of ASME B&PV Code Section XI, 2001 Edition with the 2003 Addenda os modified by the POI program description and the Federal Register, Port II, Nuclear Regulatory Commission, 10 CFR Port 50 for Category B-D Reactor Pressure Vessel IRPVI Nozzle-to-Vessel Weld. Automated tronsverse and parallel scans were performed in accordance with procedure GE-UT-716, Vl, using 45° Shear wave, 60° RL, and 70° RL search units, supplemental 0° L-Wove scans were also performed. Automated 60" Shear Inner Radius Nozzle to Vessel e><aminotions were performed in accordance with procedure GE-UT-718 VO, DRR No. 07-07 and 08-15 and validated by modeling; Reference, "The General Electric LaSalle 2 Nozzle Modeling Document". Automated UT scanning was performed from the vessel OD surface and was restricted due to the nozzle configuration. The SP 2000 OD automated UT system oreference is located ot TDC of nozzle. For SP 2000 automated calibrations refer to report L2R12-094. No relevant indications were recorded. Previous e><amination data was reviewed, with no changes noted. Automated UT Composite Coverage= 71.2%. The e><omlnotion results were compared with data report LCS-2-N6A from 2000 outage with [81 No Change These e><ominotions were performed under Work Order: 1011137 0Chonge This summary and the following data sheets hove been reviewed and accepted by the following personnel:
*{"L~(dl Level: Dote:
- ~ ;J..-/-c>9 9._________________________---'A-'-N"'-II_Rev_lewed~~Bv:.._._ _ _ _ _ _ _ _.::;.Do~t""e:_ _ __, Page 30 of 45
0 (D. r LaSalle Unit-2 0 (J) C LCS-2-N6 ::::i Component ID: LCS-2-N6A 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.
- i
"'U cii m 70° T-Scan achieved = 5.8 Sq. In.
Ill cc CD 45° T-Scan achieved = 33.5 Sq. In. <
~ Q_
- i
(,J 60° T-Scan achieved = 8.5 Sq. In. rO ...... -* en -0
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0 r LaSalle Unit-2 0 en C LCS-2-N6 :J I\J Component ID: LCS-2-N6A -I 70° Exam Volume = 11.4 Sq. In. a. 45° Exam Volume = 39.2 Sq. In. 00 Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In.
- J
"'U 70° Exam Volume = 4.8 Sq. In. ro m Ill cc 45° Exam Volume = 23.1 Sq. In.
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- J CD u.) IRS P-Scan achieved = 8.5 Sq. In. (By model) ro
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ny e e HITACHI Reactor Pressure Vessel Coverage Calculation Sheet r LaSalle Unit 2 / L2R12 0 (/) Lcs:.2-N6C LPCI (Noz-Shell) C Spring / 2009 ::::, I\.) CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE -f Percent :,- Weld Length= Exam Volume
- 360.
59.1 Required Exam Area Sa.In. Area Scanned Automated of Area Automated Weld Length Automated Percent Automated a (/) 60°T-Scan1 S4UC A 8.5 8.5 14.4% 360 7.2% 45° T-Scan S6FV A 39.2 33.5 56.7% 360 28.3% ::::,
"U ti) 10°T-Scan S6NS A 11.4 5.8 9.8% 360 4.9% co m
cc IRS P-Scan1 S4UCI A* 8.5 8.5 14;4% 360 7;2%
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CD 45° P-Scan S6FV A 39.2 23.1 39.1% 360 19.5% (,,) 70° P-Scan ::;o NS A 11.4 4.8 IS.1'1o 360 4.1'1o re
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% Total Composite Coverage= 71.2%
Rw.o~ Comments: A - Automated scanning was not restricted. Note
- Rounding methods may affect calculated values. UC-Underclad, FV-FuD volume, Ns-Near Surface. Weld lenath in deorees.
0 r LaSalle Unit-2 0 en C LCS-2-N6 :J Component ID: LCS-2-N6C 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.
- J
"'U 70° T-Scan achieved = 5.8 Sq. In. co m Dl cc 45° T-Scan achieved = 33.5 Sq. In.
~ Q.
- J CD w 60° T-Scan achieved = 8.5 Sq. In. re
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0 r LaSalle Unit-2 0 CJ) C LCS-2-N6 ::::J N Component ID: LCS-2-N6C -I 70° Exam Volume = 11.4 Sq. In. 45° Exam Volume = 39.2 Sq. In. a (/) Inner 15%T Exam Volume (IRS & 60°T} = 8.5 Sq. In.
- J r+
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cc 70° Exam Volume = 4.8 Sq. In. mm
< ::::J CD 45° Exam Volume = 23.1 Sq. In. ~ Q..
(.,J IRS P-Scan achieved = 8.5 Sq. In. (By model} rO
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e GE Hitachi r 0 (J) C 315° ::::, 135° ;:;.: N 45* Vessel Elevation 793'-3.75" -l Q. (J) N6C N6B I N6A
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CJ1 0 Cross Section @ 0° & 180° 0 CD 60° 54 Exam Area =9.1 Sq. In. D> ca LaSalle Unit 2 60° S6 Exam Area = 59.0 Sq In. CD z L2R14 0 m 60° S4 T-Scan Achieved = 9.2 Sq. In. LPCIN68 60° S6 T-Scan Achieved= 43.5 Sq. In. :::0 CD "O Nozzle to Shell Weld 0 60° S4 P-Scan Achieved = 4.6 Sq. In. 60° S6 P-Scan Achieved = 24.2 Sq. In. Page~of ~
e e HITACHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle L2R14 r () (J) N6B Nozzle to Shell Weld C Spring 2013 :J CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 109.6 Required Exam Area Scanned of Area Weld Length Percent Exam Volume= 68.1 Area Sq. In. Manual Manual Manual Manual (f) so* T-Scan CS4 UCl A 9.1 9.1 13.4% 109.6 6.7%
- J so* T-Scan css t-V) A 59.0 43.5 63.9% 109.6 31.9% ,-+
-u CD m D) 0.0 0 - < :J cc so* P-Scan (S4 UCl A 9.1 4.6 6.8% 109.6 3.4% ~ Q. CD w so* P-Sean css FV> A 59.0 24.2 35.5% 109.6 17.8% rO
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- 0 CD so* P-Sean {S4 UC) "CJ 0
60° P-Scan (S6 FV) ~
% Total Composite Coverage= 59.8%
R... o Sl23ID5 Comments: Weld length based upon Arc .dimension at C/L of Weld. A* - Single side access, 500Ai credit of the achieved Supplement 4 T-scan volume claimed. Note - Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in inches or degrees.
I I
~~ITACHI 1
ll I Wall Thickness Profile Sheet
- - - * * ~- . - - ~ - * ~
- Site:
Project: LaSalle
!2Rl4 Unit l 3rd lnterval{g!J.d Period
~
~
.- -i Report No; System:
Posioon l I I ()" I *90" Bl! I 180" NIA I 270' NIA II Component 10 Number: IRR-2001-03 I PY III rn [ID [!] 4 [fil r NIA l.197' Crown Height: ~ 0 Cl) 2 I NIA 1.667' NIA NIA C Crown Width: 1..2" ::, Sweep-o-let ;::::;: 3 I NIA I 1.556" I NIA I NIA I Nominol Diameter: 16.(1' Ringer Header UPST Component: \ii ONST Component I'.)
-I I NIA I I NIA I NIA 4 u63" Weld Length: 48.0" a:
s NIA 0.880 NIA NIA
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~ 4 System: RR Component ID Number. IRR-2001--03 Position O' 90" 180' 27fJ> I))
1 l.lD" NIA NIA NIA m 12 ~ r Crown Height FLUSH 0 (f) 2 l27fY' NIA NIA NIA C Crown Width: l.2" ::I Ring Header SweeP:9::let ;::;: 3 I l.350" NIA NIA NIA N UPST Component DNST Component Nominol Diameter: 16.11' -I
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ATTQMENT7 ER-~-010 Coverage Summary Form Revision 4 LaSalle Unit: _0_2_ Date: 02/20/2013 REPORT NUMBER: L2R14-026 Page 4 of 8 omponent/ EPN: _IR_R_-2_0_0_1_-0_3_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ System: Reactor Recirc onfiguration: Ring Header (Pipe) to Sweep-0-Let Diameter: 16" Thickness: 1.2" Descri tion of Restricted/ Limitation: Limitation due to confi uration at o and 180 De rees caused b the crotch area of the swee a.let. r 0 48.0" Len th Circumference 18:1 Measured D Calculated 0.D. Diameter x Pi (J) Number of Angles Utilized See Comments Percent% Coverage Obtained :--,:86% (Upstream + Dnstream, etc.) / # of Scans C
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0 0 Circ Facing Counter Clockwise (CCW) .., CD D) __!QQ_ % Coverage No restrictions to clrcumferential scanning cc CD otal examination all axial scans z 0 100% Axial Upstream 15.2 (AU1) +_1_5.4_ (AU2) = 30.6 (TV) - 0.0 (A) = 30.6 (A) / 30.6 (TV) X 100 = _ _;1~00"--- m 43.8% Axial Dnstream 14.4 (AD1) + 11.2 (AD2) = 25.6 (TV) - 14.4 (R) = ---1.!+/-._ (A} / 25.6 (TV) X 100 = __ 43'""".8'--- ::0 CD "C ommenls: Examination was performed utilizing a 45 and 60 shear for axial coverage and 45 shear for circumferential coverage. Based on the coverage plots, the 45 shear did not 0 dd any additional axial coverage and therefore was not utilized for this calculation. Limitation was due to the configuration and caused single sided access for the axial ;:i. CJ) xamination only. Dual coverage was obtained from 7.25" CW to 16.75" CW (9.5") and 31.25" CW to 40.75"CW (9.5'). Due to the change in OD configuration separate calculations ere performed to determine the total volume using page 2 for the dimensions to calculate for the volume with dual sided coverage and page 3 for the dimensions for single sided olume. II:
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ATTDMENT7 ER-A.Lis-010 Coverage Summary Form Revision 4 LaSalle Unit: 02 Date: 02/20/2013 REPORT NUMBER: L2R14-027 Page 4 of 8 omponent / EPN: _IR_R_-_2_00_1_-04 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ System: Reactor Recirc Configuration: Ring Header (Pipe) to Sweep-0-Let Diameter: 16" Thickness: _1_._0_"_ _ _ _ _ _ _ __ Descri tion of Restricted / Limitation: Limitation due to confi uration at 90 and 270 De rees caused b the crotch area of the swee o-let. Circumference 18:1 Measured D Calculated O.D. Diameter x Pi r 0 Number of Angles Utilized See Comments Percent% Coverage Obtained fo'eslji:; (Upstream + Dnstream, etc.) / # of Scans (/) C ial Upstream o & 180 (AU1) ;:;: I\.) 6.3 TV 19.0 {L) X 1.0 r,t,/) x 0.33 (T) 0.0 R 0.0 (L) x 0.0 ()N) x 0.0 (T) -j ial Downstream O & 180 (AD1) a. 8.9 TV 19.0 {L) X 1.03" r,t,/) X 0.45 (T) 0.0 R 0.0 {L) X 0.0 {)N) X 0.0 (T) ci5 ial Upstream 90 & 270 (AU2) ::,
"U Dl 11.0 TV 29.0 {L) X 1.05 {)N) X 0.36 (T) 0.0 R 0.0 (L) X 0.0 ry,/) X 0.0 (T) ~m ca CD ~ Q.
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- 0 44.1 % Axial Dnstream --..c.Bc.c..9_ (AD1) + 11.3 (AD2) = 20.2 (TV) - 11.3 (R) = 8.9 (A) / 20.2 (TV) X 100 = __ 44_.1_ _ CD
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Comments: Examination was performed utilizing a 45 and 60 shear for axial coverage and 45 shear for circumferential coverage. Based on the coverage plots, the 45 shear did not ;:i. dd any additional axial coverage and therefore was not utilized for this calculation. Limitation was due to the configuration and caused single sided access for the axial en examination only. Dual coverage was obtained from 19.25" CW to 28.75" CW (9.5") and 43.25" CW to 4.75"CW (9.5"). Due to the change in OD configuration separate calculations ere performed to determine the total volume using page 2 for the dimensions to calculate for the volume with dual sided coverage and page 3 for the dimensions for single sided olume. Date: 03-01. 1
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