RS-18-112, End of Interval Relief Request Associated with the Third Ten-Year Inservice Inspection (ISI) Interval: Difference between revisions

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Component Number: 1&2 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 B-A, B-D, C-C, R-A B1.12, B3.90, C3.10, C3.30, R1.20 Limited Examination Coverage See Tables 13R-15.1 and 13R-15.2 for a list of Component IDs 2. Applicable Code Edition and Addenda 3. 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.
Component Number: 1&2 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 B-A, B-D, C-C, R-A B1.12, B3.90, C3.10, C3.30, R1.20 Limited Examination Coverage See Tables 13R-15.1 and 13R-15.2 for a list of Component IDs 2. Applicable Code Edition and Addenda 3. 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.
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. 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 (ML 15226A412) 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
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. 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
: 4. ATTACHMENT 1 OCFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 1 OCFR50.55a(g)(5)(iii)  
: 4. ATTACHMENT 1 OCFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 1 OCFR50.55a(g)(5)(iii)  
--lnservice Inspection Impracticality--
--lnservice Inspection Impracticality--
Line 67: Line 67:
Due to the physical interferences causing these limitations, there are no alternative examination techniques currently available to increase coverage.
Due to the physical interferences causing these limitations, there are no alternative examination techniques currently available to increase coverage.
Duration of Proposed Alternative Relief is requested for the Third ISi Interval for LSCS, Units 1 and 2. Precedents The following similar end of interval impracticality relief requests have been previously authorized by the NRC.
Duration of Proposed Alternative Relief is requested for the Third ISi Interval for LSCS, Units 1 and 2. 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. ML 18192C172)
* 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)
* 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)  
ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5)(iii)  
--lnservice Inspection Impracticality--
--lnservice Inspection Impracticality--
Revision O (Page 4 of 11)
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. ML 15097 A 153)
* 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)
Exam Weld Requirements Component ID Description (Figure No.) (System)'
Exam Weld Requirements Component ID Description (Figure No.) (System)'
and Method N1 Recirc IWB-2500-7 LCS-1-N1A Outlet Nozzle Volumetric to Shell (UT) (RPV) N1 Recirc IWB-2500-7 LCS-1-N1B Outlet Nozzle Volumetric to Shell (UT) (RPV) N3 Main Steam IWB-2500-7 LCS-1-N3A Nozzle to Volumetric Shell (UT) (RPV) N3 Main Steam IWB-2500-7 LCS-1-N3B Nozzle to Volumetric Shell (UT) (RPV) N3 Main Steam IWB-2500-7 LCS-1-N3C Nozzle to Volumetric Shell (UT) (RPV) Note: ATTACHMENT 1 OCFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 1 OCFR50.55a(g)(5)(iii)  
and Method N1 Recirc IWB-2500-7 LCS-1-N1A Outlet Nozzle Volumetric to Shell (UT) (RPV) N1 Recirc IWB-2500-7 LCS-1-N1B Outlet Nozzle Volumetric to Shell (UT) (RPV) N3 Main Steam IWB-2500-7 LCS-1-N3A Nozzle to Volumetric Shell (UT) (RPV) N3 Main Steam IWB-2500-7 LCS-1-N3B Nozzle to Volumetric Shell (UT) (RPV) N3 Main Steam IWB-2500-7 LCS-1-N3C Nozzle to Volumetric Shell (UT) (RPV) Note: ATTACHMENT 1 OCFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 1 OCFR50.55a(g)(5)(iii)  

Revision as of 22:05, 14 June 2019

End of Interval Relief Request Associated with the Third Ten-Year Inservice Inspection (ISI) Interval
ML18267A058
Person / Time
Site: LaSalle  Constellation icon.png
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)
v • d • e


Text

{{#Wiki_filter:Exelon Generation 4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office 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 10 CFR 50.55a

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 1 OCFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5)(iii) --lnservice Inspection Impracticality-- Revision O (Page 1 of 11) 1. ASME Code Component(s) Affected Code Class:

Reference:

Examination Category: Item Number:

Description:

Component Number: 1&2 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 B-A, B-D, C-C, R-A B1.12, B3.90, C3.10, C3.30, R1.20 Limited Examination Coverage See Tables 13R-15.1 and 13R-15.2 for a list of Component IDs 2. Applicable Code Edition and Addenda 3. 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. 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

4. ATTACHMENT 1 OCFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 1 OCFR50.55a(g)(5)(iii)

--lnservice Inspection Impracticality-- 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. Impracticality of Compliance In accordance with 1 OCFR50.55a(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

5. 6. 7. 8. ATTACHMENT 1 OCFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 10CFR50.55a(g)(5)(iii)

--lnservice Inspection Impracticality-- 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. 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). 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. Duration of Proposed Alternative Relief is requested for the Third ISi Interval for LSCS, Units 1 and 2. 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) --lnservice Inspection Impracticality-- 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)

Exam Weld Requirements Component ID Description (Figure No.) (System)' and Method N1 Recirc IWB-2500-7 LCS-1-N1A Outlet Nozzle Volumetric to Shell (UT) (RPV) N1 Recirc IWB-2500-7 LCS-1-N1B Outlet Nozzle Volumetric to Shell (UT) (RPV) N3 Main Steam IWB-2500-7 LCS-1-N3A Nozzle to Volumetric Shell (UT) (RPV) N3 Main Steam IWB-2500-7 LCS-1-N3B Nozzle to Volumetric Shell (UT) (RPV) N3 Main Steam IWB-2500-7 LCS-1-N3C Nozzle to Volumetric Shell (UT) (RPV) Note: ATTACHMENT 1 OCFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 1 OCFR50.55a(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 Exam Normal Category I Outage Material of Diameter/ Operating Exam Ang.le / Actual Item Examined Construction Thickness Conditions Frequency (MHz)/ Coverage Number (Pressure/ Mode Temperature) SA-508 Cl. 2 46" dia / B-D L1R12 (Nozzle) 7-11/16" thk 1025 psig / 55° /1.0 I Shear 82.9% B3.90 SA-533 Gr. B atRPV 550°F so* /3.03 I Long (Shell) Shell SA-508 Cl. 2 46" dia / B-D L1R12 (Nozzle) 7-11/16" thk 1025 psig / 55° /1.0 I Shear 83.6% B3.90 SA-533 Gr. B atRPV 550°F so* /3.03 / Long (Shell) Shell SA-508 Cl. 2 50-3/4" dia / B-D L1R12 (Nozzle) 6-11/16" thk 1025 psig / 55° /1.0 I Shear 83.8% B3.90 SA-533 Gr. B atRPV 550°F so* /3.03 1 RL (Shell) Shell SA-508 Cl. 2 50-3/4" dia / B-D L1R12 (Nozzle) 6-11/16" thk 1025 psig / 55° /1.0 I Shear 83.8% B3.90 SA-533 Gr. B atRPV 550°F so* /3.03 / RL (Shell) Shell SA-508 Cl. 2 50-3/4" dia / B-D L1R12 (Nozzle) 6-11/16" thk 1025 psig / 55° /1.0 I Shear 83.8% B3.90 SA-533 Gr. B atRPV 550°F so* /3.03 / RL (Shell) Shell Appendix VIII Qualified Remarks Exam The examination was limited at Yes 180° due to a 3.25" thermocouple located 2.5" from the weld toe. (Enc. 1 Pg. Nos. 2-6 & 51) The examination was limited due Yes to nozzle configuration. (Enc. 1 Pg. Nos. 7-1 O & 51) The examination was limited due Yes to nozzle configuration. (Enc.1 Pg. Nos. 11-14 & 51) The examination was limited due Yes to nozzle configuration. (Enc. 1 Pg. Nos. 15-18 & 51) The examination was limited due Yes to nozzle configuration. (Enc. 1 Pg. Nos. 19-22 & 51) 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) Exam Weld Component ID Description Requirements (System)1 (Figure No.) and Method N3 Main Steam IW8-2500-7 LCS-1-N3D Nozzle to Volumetric Shell (UT) (RPV) N2 Recirc. IW8-2500-7 LCS-1-N2C Inlet Nozzle Volumetric to Shell (UT) (RPV) N2 Recirc. IW8-2500-7 LCS-1-N2D Inlet Nozzle Volumetric to Shell (RPV) (UT) N16 Core IW8-2500-7 LCS-1-N16 Spray Nozzle* Volumetric to Shell (RPV) (UT) N5 Core IW8-2500-7 LCS-1-N5 Spray Nozzle Volumetric to Shell (RPV) (UT) Note: ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 1 OCFR50.55a(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 Exam Normal Operating Exam Angle/ Category I Outage Material of Diameter/ Conditions Frequency (MHz)/ Actual Item Examined Construction Thickness (Pressure/ Mode Coverage Number Temperature) SA-508 Cl. 2 50-3/4" dia / 8-D (Nozzle) 6-11/16" thk 1025 psig / 55° /1.0 I Shear L1R12 83.8% 83.90 SA-533 Gr. 8 atRPV 550°F so* /3.03 t RL (Shell) Shell SA-508 Cl. 2 30" dia I 8-D L1R13 (Nozzle) 7-11/16" thk 1025 psig / so* /3.03 t RL 85.9% 83.90 SA-533 Gr. 8 atRPV 550°F 55° /1.0 I Shear (Shell) Shell SA-508 Cl. 2 30" dia I 8-D L1R13 (Nozzle) 7-11/16" thk 1025 psig / so* /3.03 / RL 85.9% 83.90 SA-533 Gr. 8 atRPV 550'F 55° /1.0 I Shear (Shell) Shell SA-508 Cl. 2 31-5/16" dia 8-D L1R13 (Nozzle) / 6-11/16" 1025 psig / so* /3.03 / RL 86.3% 83.90 SA-533 Gr. 8 thk atRPV 550'F 55° /1.0 I Shear (Shell) Shell SA-508 Cl. 2 31-5/16" dia 8-D L1R13 (Nozzle) / 6-11/16" 1025 psig / so* /3.03 1 RL 86.3% 83.90 SA-533 Gr. 8 thk atRPV 550'F 55° /1.0 I Shear (Shell) Shell Appendix VIII Remarks Qualified Exam The examination was limited due Yes to nozzle configuration. (Enc. 1 Pg. Nos. 23-26 & 51) The examination was limited due Yes to nozzle configuration. (Enc.1 Pg. Nos. 27-28 & 51) The examination was limited due Yes to nozzle configuration. (Enc. 1 Pg. Nos. 29-30 & 51) The examination was limited due Yes to nozzle configuration. (Enc. 1 Pg. Nos. 31-32 & 51) The examination was limited due Yes to nozzle configuration. (Enc.1 Pg. No. 33-34 & 51) 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) Exam Weld Component ID Description Requirements (System)' (Figure No.) and Method NB LPCI IW8-2500-7 LCS-1-NBA Nozzle to Volumetric Shell (RPV) (UT) NS LPCI IW8-2500-7 LCS-1-N68 Nozzle to Volumetric Shell (RPV) (UT) NB LPCI IW8-2500-7 LCS-1-NBC Nozzle to Volumetric Shell (RPV) (UT) N10 CRD Return IW8-2500-7 LCS-1-N10 Nozzle to Volumetric Shell (UT) (RPV) 18 RHR HX IWC-2500-5 IRH-HX18-Welded 088 Attachment Surface (RHR) (MT) SC3 Long IW8-2500-2 LCS-1-8G Seam@20" Volumetric Az. (UT) (RPV) Note: ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 1 OCFR50.55a(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 Exam Normal Operating Exam Angle/ Category I Outage Material of Diameter/ Conditions Frequency (MHz) / Actual Item Examined Construction Thickness (Pressure/ Mode Coverage Number Temperature) SA-508 Cl. 2 33" dia / 8-D L 1R13 (Nozzle) 6-11/16" thk 1025 psig / 60" /3.03 / RL 83.3% 83.90 SA-533 Gr. 8 atRPV 550°F 55" /1.0 I Shear (Shell) Shell SA-508 Cl. 2 33" dia I 8-D L1R13 (Nozzle) 6-11/16" thk 1025 psig / 60" /3.03 / RL 83.3% 83.90 SA-533 Gr. 8 atRPV 550°F 55" /1.0 I Shear (Shell) Shell SA-508 Cl. 2 33" dia I 8-D L1R13 (Nozzle) 6-11/16" thk 1025 psig / 60" /3.03 / RL 83.3% 83.90 SA-533 Gr. 8 atRPV 550°F 55" /1.0 I Shear (Shell) Shell SA-508 Cl. 2 19-7/16" dia 8-D L1R13 (Nozzle) / 6-11/16" 1025 psig / 60" /3.03 / RL 88.1% 83.90 SA-533 Gr. 8 thk at RPV 550°F 55" /1.0 I Shear (Shell) Shell 124" Length 500 psig / C-C / 1-5/16" C3.10 L1R14 Carbon Steel Shell 4B0°F N/A 81.67% Thickness (Design) 112-3/8" O" I 2.25 / Long 8-A L1R16 SA-533 Gr. 8 Length/ 1025 psig / 45" / 1.0 I Shear 84.3% 81.12 6-3/4" Shell 5so°F 60" / 2.0 I Long Thickness 70" I 2.0 I Long Appendix VIII Remarks Qualified Exam The examination was limited due Yes to nozzle configuration. (Enc. 1 Pg. Nos. 35-36 & 51) The examination was limited due Yes to nozzle configuration. (Enc.1 Pg. Nos. 37-38 & 51) The examination was limited due Yes to nozzle configuration. (Enc. 1 Pg. Nos. 39-40 & 51) The examination was limited due Yes to nozzle configuration. (Enc. 1 Pg. Nos. 41-42 & 51) The examination was limited due No to structural interference. (Enc. 1 Pg. Nos. 43-44) The examination was limited from Yes the OD surface due to the N12-A nozzle. (Enc. 1 Pg. Nos. 45-48) 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) Exam Weld Component ID Description Requirements (System)1 (Figure No.) and Method N7 Top Head IWB-2500-7 LCS-1-N7 Spray Nozzle Volumetric to Shell (RPV) (UT) Note: 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 Exam Normal Operating Exam Angle/ Category/ Outage Material of Diameter/ Conditions Frequency (MHz)/ Actual Item Examined Construction Thickness (Pressure/ Mode Coverage Number Temperature) SA-508 Cl. 2 17" dia / 8-D L1R16 (Nozzle) 3-5/8" thk at 1025 psig / 60° /3.0 I Long 87% 83.90 SA-533 Gr. B Closure 550°F 55° /1.0 I Shear (Shell) Head Appendix VIII Remarks Qualified Exam The examination was limited due Yes to nozzle configuration. (Enc. 1 Pg. Nos. 49-50) 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) Exam Weld Component ID Description Requirements (System)1 (Figure No.) and Method Pump 2E22-C001 IWC-2500-5 HP-PU2-04 Welded Surface Attachment (MT) (HP) 18" Pipe to IWC-2500-7(a) IMS-2044-13 Valve Weld Volumetric (MS) (UT) N10 CRD Return IWB-2500-7 LCS-2-N10 Nozzle to Volumetric Shell (UT) (RPV) N1 Recirc IWB-2500-7 LCS-2-N1A Outlet Nozzle Volumetric to Shell (UT) (RPV) N1 Recirc IWB-2500-7 LCS-2-N1B Outlet Nozzle Volumetric to Shell (UT) (RPV) Note: ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 1 OCFR50.55a(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 Exam Normal Operating Exam Angle/ Category/ Outage Material of Diameter/ Conditions Frequency (MHz)/ Actual Item Examined Construction Thickness (Pressure/ Mode Coverage Number Temperature) C-C 171.5 in. 1325 psig / C3.30 L2R12 A516 Gr70 Length/ 212°F N/A 16.0% 0.75 in. (Design) R-A 18" dia I 1250 psig / 45' I 2.0 I Shear R1.20 L2R12 A106 GrB Sch 80 575°F 70' I 2.0 I Shear 59.8% (Design) SA-508 Cl. 2 20-1/2" dia / 45' / 1.0 I Shear 60' / 2.0 I RL B-D L2R12 (Nozzle) 6-3/16" thk 1025 psig / 70' / 2.0 I RL 71.9% B3.90 SA-533 Gr. B atRPV 550°F 60' /3.03 / Long (Shell) Shell* 55' /3.03 / Shear SA-508 Cl. 2 49-9/16" dia 45' / 1.0 I Shear B-D L2R12 (Nozzle) / 6-3/16" thk 1025 psig / 60' I 2.0 I RL 71.6% B3.90 SA-533 Gr. B atRPV 550°F 70' / 2.0 I RL (Shell) Shell SA-508 Cl. 2 49-9/16" dia 45' / 1.0 I Shear B-D L2R12 (Nozzle) I 6-3/16" th k 1025 psig / 60' I 2.0 I RL 71.6% B3.90 SA-533 Gr. B atRPV 550°F 70' I 2.0 I RL (Shell) Shell Appendix VIII Remarks Qualified Exam The examination was limited due to No the permanent pump stand. (Enc. 2 Pg. Nos. 2-3) The examination was limited due to Yes component configuration. (Enc. 2 Pg. Nos. 4-5) The automated examination was limited due to insulation interference and the mechanical Yes limit of the scanner arm. Manual examination was limited due to nozzle configuration. IEnc. 2 Pa. Nos. 6-12 & 451 The automated examination was Yes limited due to nozzle configuration. (Enc. 2 Pg. Nos. 13-15 & 45) The automated examination was Yes limited due to nozzle configuration. (Enc. 2 Pg. Nos. 16-18 & 45) 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) Exam Weld Component ID Description Requirements (System)' (Figure No.) and Method N2 Recirc. IW8-2500-7 LCS-2-N2C Inlet Nozzle Volumetric to Shell (RPV) (UT) N3 Main Steam IW8-2500-7 LCS-2-N3A Nozzle to Volumetric Shell (UT) (RPV) N3 Main Steam IW8-2500-7 LCS-2-N38 Nozzle to Volumetric Shell (UT) (RPV) N3 Main Steam IW8-2500-7 LCS-2-N3C Nozzle to Volumetric Shell (UT) (RPV) N3 Main Steam IW8-2500-7 LCS-2-N3D Nozzle to Volumetric Shell (UT) (RPV) N6 LPCI IW8-2500-7 LCS-2-N6A Nozzle to Volumetric Shell (RPV) (UT) Note: ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 1 OCFR50.55a(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 Exam Normal Operating Exam Angle/ Category/ Outage Material of Diameter/ Conditions Frequency (MHz)/ Actual Item Examined Construction Thickness (Pressure/ Mode Coverage Number Temperature) SA-508 Cl. 2 33-7/8" dia / 45° / 1.0 I Shear 8-D L2R12 (Nozzle) 6-3/16" thk 1025 psig / 60° 12.0 I RL 70.5% 83.90 SA-533 Gr. 8 atRPV 550°F (Shell) Shell 70° 12.0 I RL SA-508 Cl. 2 48-7/8" dia I 8-D L2R12 (Nozzle) 7" thk at 1025 psig / 55° /1.0 I Shear 83.3% 83.90 SA-533 Gr. 8 RPV Shell 550°F so* /3.03 I Long (Shell) SA-508 Cl. 2 48-7/8" dia / 8-D L2R12 (Nozzle) 7" thk at 1025 psig / 55° /1.0 I Shear 83.3% 83.90 SA-533 Gr. 8 RPV Shell 550°F so* /3.03 I Long (Shell) SA-508 Cl. 2 48-7/8" dia / 45° / 1.0 I Shear 8-D L2R12 (Nozzle) 7" thk at 1025 psig / 60° 12.0 I RL 74.1% 83.90 SA-533 Gr. 8 RPV Shell 550°F 70° 12.0 I RL (Shell) SA-508 Cl. 2 48-7/8" dia / 45° / 1.0 I Shear 8-D L2R12 (Nozzle) 7" thk at 1025 psig / 60° 12.0 I RL 74.1% 83.90 SA-533 Gr. 8 RPV Shell 550°F 70° /2.0/ RL (Shell) SA-508 Cl. 2 33-7r8 dia t 45° / 1.0 I Shear 8-D L2R12 (Nozzle) 6-3/16" thk 1025 psig / 60° 12.0 I RL 71.2% 83.90 SA-533 Gr. 8 atRPV 550°F (Shell) Shell 70° /2.0 I RL Appendix VIII Remarks Qualified Exam The examination was limited due to Yes nozzle configuration. (Enc. 2 Pg. Nos. 19-21 & 45) The examination was limited due to Yes nozzle configuration. (Enc. 2 Pg. No. 22 & 45) The examination was limited due to Yes nozzle configuration. (Enc. 2 Pg. No. 23 & 45) The examination was limited due to Yes nozzle configuration. (Enc. 2 Pg. Nos. 24-26 & 45) The examination was limited due to Yes nozzle configuration. (Enc. 2 Pg. Nos. 27-29 & 45) The examination was limited due to Yes nozzle configuration. (Enc. 2 Pg. Nos. 30-32 & 45) 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) Exam Weld Component ID Description Requirements (System)' (Figure No.) and Method NB LPCI IWB-2500-7 LCS-2-N6C Nozzle to Volumetric Shell (RPV) (UT) N6 LPCI IWB-2500-7 LCS-2-N6B Nozzle to Volumetric Shell (RPV) (UT) 16" Ring IWB-2500-8(c) Header-to IWB-2500-9, IRR-2001-03 Sweep-0-Let 10, & 11 Weld Volumetric (RR) (UT) 16" Ring IWB-2500-8(c) Header-to IWB-2500-9, IRR-2001-04 Sweep-0-Let 10, & 11 Weld Volumetric (RR) (UT) Note: ATTACHMENT 10CFR50.55a Relief Request 13R-15 Proposed Alternative in Accordance with 1 OCFR50.55a(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 Exam Normal Operating Exam Angle/ Category I Outage Material of Diameter/ Conditions Frequency (MHz) / Actual Item Examined Construction Thickness (Pressure/ Mode Coverage Number Temperature) SA-508 Cl. 2 33-7/8 dia / 45' / 1.0 I Shear B-D L2R12 (Nozzle) 6-3/16" thk 1025 psig / 60' I 2.0 I RL 71.2% B3.90 SA-533 Gr. B atRPV 550'F (Shell) Shell 70' / 2.0 I RL SA-508 Cl. 2 33-7/8" dia / B-D L2R14 (Nozzle) 6-3/16" thk 1025 psig / 60' / 3.03 / Long 59.8% B3.90 SA-533 Gr. B 550'F 55' / 1.0 I Shear (Shell) at RPV shell R-A 48" Length/ 1025 psig / 45' I 2.25 I Shear L2R14 SA-358 Gr 304 60' I 2.25 I Shear 86.0% R1.20 0.758" thk 550'F 60' / 2.0 I Long R-A 48" Length/ 1025 psig / 45' / 2.25 I Shear L2R14 SA-358 Gr 304 60' / 2.25 I Shear 85.3% R1.20 0.758" thk 550'F 60' 12.0 I Long Appendix VIII Remarks Qualified Exam The examination was limited due to Yes nozzle configuration. (Enc. 2 Pg. Nos. 33-35 & 45) The examination was limited due to Yes nozzle configuration. (Enc. 2 Pg. Nos. 36-38 & 45) The examination was limited due to Yes component configuration. (Enc. 2 Pg. Nos. 39-41) The examination was limited due to Yes component configuration. (Enc. 2 Pg. Nos. 42-44) 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 0

  • I Report Noa HITACHI EXAMINATION

SUMMARY

SHEET L1Rl2-013 Site: LaSalle Component ID: LCS-1-NlA Outage: L1Rl2 N-SH System: RECIRC ASME Cat.: B-D ASME Item 83.90 Aug Req N/A Exams I Doto Sheet Col Sheet Procedure Calibration Block I Exam /Oper. Cert Level Dote Performed 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. 0 Compared to Report #96-152. 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 Sum~e following data sheets have been reviewed and accep~wing personnel: RWP: 8330 . . :;/;2/c!fr-~ . if/ft Dose: 149 mr. ared By: () Level: Date: Utility Review: , 'J) ate: f2v.2_,_d_

7..:_;i-J-o:?

ANII Review: Dote: Page 1 of 10 ---Page 2 of 51 "U Ill cc CD u.) 0 -01 ....,. r !lJ en ro C :::J ' I\:) 0 0 OJ 0 i I I Component ID: LCS-j-N1A I !

  • GE Energy-Nuclear Reactor Pressure Vessel Coverag~ Calculation Sheet I I i LaSalle Unit-1, 2008 N 1 Recirc Outlet Nozzle! to Shell L1R12 I CODE CROSS-SECTIONAL AREA i TOTAL CODE COVERAGE i Weld Length = 360. Required Exam !Percent Exam Volume= 72.6 Area Sq. In. Area Scanned '1of Area Weld Length 60° T-Scan (S4) A 10.6 10.6 114.6% 360 60° T-Scan (S6) A 62 55.8 i 76.9% 360 IRS P-Scan (S4) A* 10.6 10.6 114.6% 360 60° P-Scan (S6) A 62 44.4 : 61.2% 360 I 60° T-Scan (S4) I 60° T-Scan (S6) i I IRS P-Scan (S4) I 60° P-Scan (S6) I I 60° T-Scan (S4\ ' 60° T-Scan {S6) I IRS P-Scan (S4} I 60° P-Scan (S6) I I 60° T-Scan (S4} i 60° T-Scan (S6) ! IRS P-Scan (S4) i 60° P-Scan (S6) I % Total Composite Coverage=

I Comments: I I I 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 Percent 7.3% 38.4% 7.3% 30.6% 83.6% Rev. 0 9!23'05 r 0 (/) C ::J ;:::;: ....,. -l :::J" a. en ::J ~m < ::J Ill C') ro' -* Ul ~-CD CD c.. :-7 0 0 < CD -, Ill co CD z 0 m ;a CD "Cl 0 ;:i Ul Enclosure 1: LCS Unit 1 Third ISi Interval Limited Coverage NOE Reports Manual RPV Nozzle Exam Plan 0 Plant and Unit ID: LaSalle Unit-1 Component: LCS-1-NlA Outage: LlR12 Cal. Block: 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 ~Ill ~~1:: 1-28-08 z-t/-c,J: i.*\-cnJ tarr'iincd Bv: Prcnared Bv: Date: Re~iew~d Bv: Date: Date:, v (J t_1.1212-¢13 (o .st(() Page 4 of 51 ""CJ Dl cc CD CJ'I 0 -CJ'I ...... <t. I I I I I I l I I I I I I I I ----1 ... ) i ~asa11;e 1 N 1 Nozile -Recirculation Outlet ! ComponentilD: LCS-1-N1A 60° S4 & IRS Exam Volume= 10.6 Sq. In 60° S6 Exam Volume= 62.0 Sq. In. I 60° S4 T-Scan Exam Volume= 10.6 Sq. In 60° S6 T-Scarl Exam Volume= 55.8 Sq. ln. i IRS P-Scan qam Volume= 10.6 Sq. In 60° S6 P-Scan Exam Volume = 44.4 Sq. In. l 60°P-Scan I 60° T-Scan I 0 r 0 (/) C :J ;::;: ...... -i ::r a (/) :J m-m < :J ~(") C: ~-CD CD 0.. 0 0 < CD .., Dl ca CD z 0 m :::0 CD "C 0 ;::::i en "U !ll cc CD 0) 0 -(]1 ('.. ...Jo. ' i'i::i "' 1 \),) D() R 0 ----I I I I I I I I ' 0 LaSall~ 1 N 1 Noz~le -Recirculation Outlet I Component ID: LCS-1-N1A I 60° T-Scan proposed scan coverage ' I

  • 60° P-Scan pr0posed scan coverage Scan limits sh6wn at 90° Az. I 0 r 0 (J) C ::, ;:::;: ...Jo. --l ::,-a. en ::, ro m < ::, Q.. C: ~-CD CD a. 0 0 < CD i.i3 co CD z 0 m ;o CD "C 0 ;:i. en

"'U Ill cc CD -...J 0 -CJ1 ...... I\) 0 0 OJ 0 Component ID: LCS-1-N1 B ** GE Erre,gy-Nur:Jear Reactdr Pressure Vessel Coverag~ Calculation Sheet I I LaSalle Unit-1, 2008 N1 Recirc Outlet Nozzle to Shell Weld Length = Exam Volume= 60° 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) 60° P-Scan (S6) 60° 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) 60° P-Scan (S6) 360. 72.6 A A A* A L 1 R12 , I CODE CROSS-SECTIONAL AREA I Required Exam Area Sq. In. 10.6 62 10.6 62 Area Scanned 10.6 55.8 10.6 44.4 I Percent i of Area 14.6% ' 76.9% i 14.6% i 61.2% I I I TOTAL CODE COVERAGE Weld Length 360 360 360 360 1% Total Composite Coverage = I Comments: i I l ! 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. '. (J))' \ r Percent 7.3% 38.4% 7.3% 30.6% 83.6% Ae-1. 0 9/23/05 r () (f) C :J ;:;: ...... :J co m < :J !!!. Q. C. 3 C ft ro 0.. :-7 (') 0 < CD ru cc CD z 0 m ::0 CD "C 0 ;:i. en Enclosure 1: LCS Unit t Third ISi Interval Limited Coverage NOE Reports Manual RPV Nozzle Exam Plan 0 Plant and Unit ID: LaSalle Unit-1 Component: LCS-1-NlB Outage: L1Rl2 Cal. Block: 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" >vJ.<;;J~_,Jdod' 1-28-08 '-. U~ z:-11-l>o

  • tt~d Bv: 2*1-c)8' Prenared Bv: Date: Date: Examlned Bv: Date: lu<viewelVBv:

Date: (~) Page 8 of 51 ""'O Dl cc CD co 0 ->. r**., l_) ct I I I I I I I I I ----1 t I l:asade 1 N 1 Nozzle -Recirculation Outlet ' ComponentjlD: LCS-1-N1B ! 60° S4 & IRS .Exam Volume= 10.6 Sq. In 60° S6 Exam Volume= 62.0 Sq. In. 60° S4 T-Scarn Exam Volume= 10.6 Sq. In 60° S6 T-Scarii Exam Volume= 55.8 Sq. In. I IRS P-Scan Exam Volume= 10.6 Sq. In 60° S6 P-Scam Exam Volume = 44.4 Sq. In. 60"P-Scan I 60° T-Scan I *O* \ ; r () (J) C :::::, ;::;: -->. :::::, ~m <:::::, Q. C. g 3 C ro Cl. :-7 0 0 < CD .., Dl cc CD z 0 m ;:o CD "O 0 ::i. (/) ""CJ Ol cc CD ....>. 0 0 -(J'1 ....>. ---0 I I LaSallie 1 I ' N1 Nozzle -Recirculation Outlet Component ID: LCS-1-N1 B I 60° T-Scan proposed scan coverage i 60° P-Scan proposed scan coverage Scan limits shbwn at 90° Az.. I 0 r () (/) C :J ;:::;: ....>. :J CD m < :J Q_ C: g ~-CD CD a. 0 0 < CD -, Ol cc CD z 0 m ::u CD "O 0 ;::i. en "U D) cc CD 0 -C1l ....,. r ll) en !!:!. co C ::, ¥ ...... l'v 0 0 (X) r,;a I 0 Component ID: LCS-1-N3A -GE Energy-Nuclear Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit-1, 2008 N3 Main Steam Nozzle to Shell L1R12 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume= 56.3 Area Sq. In. Are;1 Scanned of Area Weld Length 60° T-Scan S4) A 8.2 8.2 14.6% 360 60°T-Scan S6) A 48.1 43.3 76.9% 360 IRS P-Scan S4) A" 8.2 8.2 14.6% 360 60° P-Scan (S6) A 48.1 34.7 61.6% 360 60°T-Scan 1 S4) ao* T-Scan 1 S6) IRS P-Scan S4) 60° P-Scan (S6) 60° T-Scan (S4l 60° T -Scan S6) IRS P-Scan S4) 60° P-Scan (S6) 60° T-Scan S4) 60° T-Scan S6l IRS P-Scan S4) 60° P-Scan (S6) % Total Composite Coverage= Comments: A* -Single side access. 100% credit of the achieved Supplement 4 T -scan volume claimed iaw. 1 OCFR50.55a. Note* Rounding methods may affect calculated values. Weld length in degrees. Percent 7.3% 38.5% 7.3% 30.8% 83.8% Rev. 0 9123/US r () Cl) C ::J ;:;: ....,. -i :::r a: en ::J CD m < ::J D) C"> ~o -* C/l ~-!:; CD CD Cl. 0 0 < CD ru cc CD z 0 m ;:o CD "C 0 ra-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 CW ICCW 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 &: 1.-~~! XIA d-:ilolov 1-28-08 R~iewe&Bv: "t-\-Ofi Prenared Bv: Date: Date:

  • IR,lviewed M Date: --Page 12 of 51

"'U D) cc (l) ....>. w 0 -(J1 ....>. () I I I I I I ----1 LaSalle 1 N3 Nozzle -Main Steam Component ID: LCS-1-N3A 60° S4 & IRS Exam Volume = 8.2 Sq. In 60° S6 Exam Volume ;:: 48.1 Sq. In. 60° S4 T-Scan Exam Volume = 8.2 Sq. In 60° S6 T-Scan Exam Volume = 43.3 Sq. In. IRS P-Scan Exam Volume = 8.2 Sq. In (By modeling) 60° S6 P-Scan Exam Volume = 34.7 Sq. In. 60" P-Sean I 0 60" T-Sc:an I <..!. C) ' \,. r 0 (J) C -l :J ;:::;: ....>. -, ::::; -, C. U) :J ..+ (l) m < :J Q. re -* en 3 C: -*-, mro a. 0 0 < (l) -, D) cc (l) z 0 m ::0 (l) "'O 0 ;:::i. en ""O Ill co CD ....>. 0 -01 ....>. I ------0 LaSalle 1 N3 Nozzle -Main Steam Component ID: LCS-1-N3A 60° T-Scan proposed scan coverage 60° P-Scan proposed scan coverage Scan limits shown at 90° Az.. () . . r 0 en C ::::::i ;:.: ....>. ::::::i CD m < ::::::i Ill Q. C: ~-!:; CD CD 0. :-7 0 0 < CD ru co CD z 0 m ::u CD "Cl 0 "U D) co CD -->. CJ1 0 -CJ1 -->. I\) 0 0 (X) () --. O< () 0 Component ID: LCS-1-N3B " ... .. fl:GE,~'.Nuctear .. Reactor Pressure Vessel '* Coverage Calculation Sheet LaSalle Unit-1, 2008 N3 Main Steam Nozzle to Shell L1R12 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume= 56.3 Area Sq. In. Area Scanned of Area Weld Length 60° T-Scan (S4 A 8.2 8.2 14.6% 360 60° T-Scan (S6 A 48.1 43.3 76.9% 360 IRS P-Scan S4 A* 8.2 8.2 14.6% 360 60° P-Scan (S6) A 48.1 34.7 61.6% 360 60° T-Scan S4 60° T-Scan (S6 IRS P-Scan S4 60° P-Scan (S6) 60°T-Scan I S4 60°T-Scan 1 S6 IRS P-Scan S4, 60° P-Scan (S6) 60° T-Scan S4 60° T-Scan S6 IRS P-Scan S4) 60° P-Scan (S6) % Total Composite Coverage= Comments: A* -Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed iaw. 1 OCFR50.55a. Note -Rounding methods may affect calculated values. Weld length in degrees. Percent 7.3% 38.5% 7.3% 30.8% 83.8% Rev. O !!l23I05 r () (J) C :J ;:::;: -->. --l ::r a: CJ) :J CD m < :J Q. C. g ~-!:; CD CD 0.. :-7 0 0 <* CD ru cc CD z 0 m :::0 CD "C 0 ;:::i. (J) 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 ~~0W?+t1if ~-,jc 1 ~)./1;;,/()1r 1-28-08 Z-b-o~ pr .. nared Bv: Date: Rev:-e-;;;- Bv: Date: Date:

  • Reviewed-~:

Date: LHW2-?JIC. Page 16 of 51 "U ll) co CD ->. -...J 0 ....... (J1 ->. Iii CJ) !!!. iii I I I I I I -----l 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. 60° S4 T-Scan Exam Volume = 8.2 Sq. In 60° S6 T-Scan Exam Volume = 43.3 Sq. In. IRS P-Scan Exam Volume = 8.2 Sq. In (By modeling) 60" S6 P-Scan Exam Volume = 34.7 Sq. In. 60" P-&:an I 0 60"T.sa.n I Iii'"\ u <:') '* r-r () (J) C ::::J ,3 ;:;: \s. ->. I -; N ::r .., Cl!. a. -en -1 ::::J -CD m .., < ::::J ll) Q. rO -* en 3 C -*.., CD CD a. :-7 () 0 < CD .., ll) cc CD z 0 m ::0 CD ""C 0 ;:i.. en "U Dl cc CD ....>. co 0 -01 ....>. r-")'1:3 N , (>'I I I I I / ===4~--==--1--tt~ ::_:--1 --, 0 LaSalle 1 N3 Nozzle -Main Steam Component ID: LCS-1-N3B 60° T-Scan proposed scan coverage 60° P-Scan proposed scan coverage Scan limits shown at 90° Az. r 0 (/) C :::J ;::;: ....>. :::J ~m < :::J Dl Q. C 5l 3 r::: co 0. :-:" 0 0 < CD ..... Dl cc CD z 0 m ::0 CD "O 0 ;:::i. (/) "U Dl co CD ..... c.o 0 -CJ'1 ..... to 0 0 CX> 0

  • ComponenQ LCS-1-N3C

-GE Energy* Nuclear Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit-1, 2008 N3 Main Steam Nozzle to Shell L1R12 CODE CROSS-SECTIONAL AREA TOT AL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume= 56.3 Area Sq. In. Area Scanned of Area Weld Length soc T-Scan S4) A 8.2 8.2 14.S% .360 soc T-Scan S6) A 48.1 43.3 76.9% 360 IRS P-Scan S4} A* 8.2 8.2 14.6% 360 S0° P-Scan (S6) A 48.1 34.7 61.6°k 360 60° T-Scan S4) soc T-Scan S6) IRS P-Scan S4l 60° P-Scan (S6) 60° 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} 60° P-Scan (S6) % Total Composite Coverage= 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. Percent 7.3% 38.5% 7.3% 30.8% 83.8% Rev.a 9'23/05 r 0 (f) C ::, ;:::;: ..... -, ::,-a. (f) ::, CD m <::, Dl (1 ;:: 0 -* en ;!_ Si CD CD a. :-:' 0 0 < CD i.i3 (Q CD z 0 m :;o CD "C 0 @" 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-N3C Outage: L1R12 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% T NN PLATE 0"-8.0" +/-55°-75° CW/CCW Limitations: None. 0 Previous Results: Review on site. Comments: None. Cf ltt~ 5-v ~-{) .,c/,cJe 1-28-08 ~~~7j*al.' 2g: .... -Z-/~-41 Prenared Bv: Date: Rci~ed Bv: Date: Examined Bv: Date: IR .. Liewed Bil\ Date: ........ -1 ........ ~ilr-r.**"*ctJ LI f2.t1..-aH, of-/0 Page 20 of 51 "'U D) cc CD N ...... 0 -CJ'1 ...... -.j 0 c--ri::) ..-.\ I 'Q. --....l I I I I I I ----I 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. 60° S4 T-Scan Exam Volume = 43.3 Sq. In 60° S6 T-Scan Exam Volume= 55.8 Sq. In. IRS P-Scan Exam Volume = 8.2 Sq. In (By modeling} 60° S6 P-Scan Exam Volume= 34.7 Sq. In. 60" P-Saln I 60" T-5can I r () Cf) C ::, ;:::;: ...... ::, CD m <::, Q.. C: g ~-CD CD a. 0 0 < CD m cc CD z 0 m :;o CD "C 0 @" "U Ill cc CD N N 0 -CJ1 -->. oO -0 r--:e N I "Q. -'-....1 <t I -----'-1-0 LaSalle 1 N3 Nozzle -Main Steam Component ID: LCS-1-N3C 60° T-Scan proposed scan coverage 60° P-Scan proposed scan coverage Scan limits shown at 90° Az.. 6:'\ r 0 CJ) C ::I ;:::;: -->. --l :!. a.. CJ) 3. m < ::I Ill " ~a -* (/1 3 f:; ;:;: CD CD ....,, c.. .. 0 0 < CD ...... Ill cc CD z 0 m :::0 CD "O 0 ;:::i (/1 "'U D> ca CD N w 0 -en ....>. 0 CD \'-' I\\ 1 .......

  • 0 Component ID: LCS-1-N3D e Reactor Pressure Vessel Coverage Calculation Sheet GE Energy -Nuclear LaSalle Unit-1, 2008 N3 Main Steam Nozzle to Shell L1R12 CODE CROSS-SECTIONAL AREA TOT AL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume= 56.3 Area Sq. In. Area Scanned of Area Weld Length 60°T-Scan S4 A 8.2 8.2 14.6% 360 60°T-Scan I S6 A 48.1 43.3 76.9% 360 IRS P-Scan S4 A* 8.2 8.2 14.6% 360 60° P-Scan (SS) A 48.1 34.7 61.S% 360 so* T-Scan £S4l so* T-Scan css) IRS P-Scan S4 60° P-Scan (S6) so 0 T-Scan <S4, so* T-Scan SSJ IRS P-Scan (S4 so* P-scan (S6) S0°T-Scan S4 so* T-Scan SS IRS P-Scan 1 S4 60° P-Scan (SS) % Total Composite Coverage=

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. Percent 7.3% 38.5% 7.3% 30.8% 83.8% Rev. 0 9123/05 r () (f) C ::, ;:::.: ....>. ::, co m < ::, Q. C: 3 C ~m C. :-:" () 0 < CD i:i3 cc CD z 0 m ;;o CD "C 0 it r\ 0

  • Enclosure 1: LCS Unit 1 Third ISi Interval Limited Coverage NDE Reports Manual RPV Nozzle Exam Plan 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. Previous Results: Review on site. Comments: None. CJ-frl.r ~~"L-\-09 A J s n5 ../'d

  • It/ ?"fr 1-28-08 '2-/tJ-8 Prenared Bv: Date: Re~ Bv: Date: Examined Bv: Date: l --n.eviewefNif...:..

/l Date: /'rl.J.lk!.A.. "JS 'Z.. \~ .c:,e, Page 24 of 51 "U !l) cc CD "' ('.. 01 0 " n -01 ' ...>. I l I I I I I ---~ --.j 0 "1--0 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. 60° S4 T-Scan Exam Volume= 43.3 Sq. In 60° S6 T-Scan Exam Volume= 55.8 Sq. In. IRS P-Scan Exam Volume = 8.2 Sq_ In (By modeling) 60° S6 P-Scan Exam Volume = 34.7 Sq. In. eo* P-Scan 6ll"T-S0an I I :::\ IE") V r 0 (/) C ::i ;:::.: ...>. ::i mm < ::i ~() C: ~-!:; CD CD 0. :-7" 0 0 < CD ru co CD z 0 m ;o CD "C 0 "U D) ca <D N 0) 0 ...... -(J'I ->. °" -Cr. I I I I / --===4,,-~--::--~ ==---/ I --J 0 LaSalle 1 N3 Nozzle -Main Steam Component ID: LCS-1-N3D 60° T-Scan proposed scan coverage 60° P-Scan proposed scan coverage Scan limits shown at 90° Az. () r 0 (f) C :::::, ;::;.: ->. --l ::r a: (f) :::::, cii m <:::::, !!?.. Q. cg ~-cii <D a. :-7 0 0 < <D .., D) ca CD z 0 m ::0 <D "C 0 :::i Cl) -0 Dl co CD N --.J 0 -(J'I ..... i;;-cn e. ii" C ::s ;; -,--;;o -c.> z [ CD h '{' -z N 0 cc CD en a .....

  • 0 ' , fl Reactor Pressure Vessel Coverage HITACHI Calculation Sheet LaSalle Unit-1 Weld LCS-1-N2C 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= 73 60" T-Scan IS4 Radial) A 10.6 10.6 14.5% 360 7.3% 60"T-Scan IS6 Radial) A 62.5 55.8 76.3% 360 382% 55° P-Scon IS4 LKCW) A 10.6 10.6 14.5% 360 3.6% 55° P-Scan (S4 LKCC) A 10.6 10.6 14.5% 360 3.6% 60° P-Scon 156 CW/CCWI A 62.5 48.6 66.5% 360 33.2% % Total Composite Coverage = 85.9% Comments:

NN -NoZZ1e to Vessel Inner l5%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, S6-Supplement 6 volume. Weld length in degrees

  • Rev.1 YZl/O'l r () Cl) C :::J ;:::;: ..... -, :::; a: ci.i :::J CD < m Dl :::J _o rO -* en 3 C: -*-, CD CD 0. ..... () 0 < CD ii3 cc CD z 0 m :::0 CD "C 0 1t C) ""O z 0 Dl !l ca CD (II I\) r (') 00 C/) 0 I .... -+, I c.n z N ->. (') -+-----I I I I I I I "'O I m cc I (II I O> 1 0 I -"-4 ----1 0
  • LaSalle 1 N2 Nozzle -Recirculation Inlet 60° S6 Exam Volume = 62.5 Sq. In Inner 15%T Exam Volume (60°T & IRS)= 10.6 Sq. In 60° S6 T-Scan achieved = 55.8 Sq. In 60° S4 T-Scan achieved = 10.6 Sq. In 60° S6 P-Scan achieved = 48.6 Sq. In Inner 15%T P-Scan achieved=

10.6 Sq. In (By modeling) 6.3" 60°T/P NS 9.6" 60°P 18.1" 60°T r 0 (/) C ::::l ;:::;: ->. -; ::r a: (/) ::::l ~m < ::::l Q. C: £ ~-CD CD a. :-7 0 0 < CD ru cc CD z 0 m ;o CD "C 0 "U Ill cc CD i') (0 0 -CJ"I ....>. m en !a. S" C .... r-.... ::0 .... c., z I r-I .... I z II,) 0 l G) en 9. .... ;,' ( * -HITACHI I Weld Length= 360 Exam Volume= 73 60° T-Scan IS4 Radial) A 60° T-Scon (S6 Radial) A 55° P-Scan (S4 LKCW) A 55° P-Scan [S4 LKCCI A 60° P-Scan (56 ON/CONJ A \fJI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit-1 Weld LCS-1-N2D CODE CROSS*SECTIONAL AREA TOTAL CODE COVERAGE Required Exam Percent Area sq.In. Area Scanned of Area Weld Length 10.6 10.6 14.5% 360 62.5 55.8 76.3% 360 10.6 10.6 14.5% 360 10.6 10.6 14.5% 360 62.5 48.6 66.5% 360 % Total Composite Coverage= Comments: NN -Nozzle to Vessel Inner 15%T circumferential scans A-Scanned.area 360°. Scanning restricted due to the nozzle configuration Percent 7.3% 38.2% 3.6% 3.6% 33.2% 85.9% Note -Rounding methods may affect calculated values. S4-Supplement 4 underdad volume. 56-Supplement 6 volume. Weld length in degr~ * ~.1JJl3/0'. r () (J) C ::I ;::::;: ....>. -I ::J" -, c.. (J) ::I ro < m Ill ::I -C') re -* en 3 C: -* -, ID CD c.. ....>. () CD tu cc CD z 0 m :::0 CD "C 0 "'U ru co (D (.,.) 0 0 ...... CJ1 ->. r Ill Cl) !!!. m C S! r :u c:.> z [ (I) r-(') Cf> I z I\) 0 ""O Ill IC (I) C) 0 -"'

  • I I ~--' T/P't_ I -+-I I I I l I I I I I I I ----1 0 {) ' LaSalle 1 N2 Nozzle -Recirculation Inlet Component ID: LCS-1-N2D 60° S6 Exam Volume = 62.5 Sq. In Inner 15%T Exam Volume (60°T & IRS)= 10.6 Sq. In 60° S6 T-Scan achieved=

55.8 Sq. In 60° S4 T-Scan achieved= 10.6 Sq. In 60° S6 P-Scan achieved = 48.6 Sq. In Inner 15% T P-Scan achieved = 10.6 Sq. In (By modeling) 6.3" 60°T/P NS 9.6 11 60°P 18.1" 60°T r 0 (J) C :::J ;:;: ->. -I ::r a u.i :::J CD m < :::J Q. C: g ~-CD ro 0. :-7 0 0 < (D ii3 cc (D z 0 m :::a (D "C 0 "'U D) cc CD (.,.) ->. 0 -0, ->. * -HITACHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit-1 Weld LCS-1-N16 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= 56 60° T-Scon (S4 Radial) A 8.2 8.2 14.6% 360 7.3% 60" T-Scan (56 Radial! A 47.8 43.4 77.5% 360 38.8% 55° P-Scon (S4 LKCWl .A 8.2 8.2 14.6% 360 3.7% 55° P-Scan !54 LKCCI A 8.2 8.2 14.6% 360 3.7% 6D° P-Scon 156 ON/CONJ A 47.8 36.9 65.9% 360 32.9% % Total Composite Coverage= 86.3% 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

  • Rov.13/nlal r 0 (/) C :J ;:::;: ->. --l ::r a: (/) :J CD m < :J Q. cg ~-CD CD 0. :-7 0 0 < CD ru cc CD z 0 m ::0 CD "O 0

"'U z ti) cc CD CD (.,) r "' (') 0 en I -...... CJ'I I z ->. ...... 0) * <t T-Scans I T I I I + I I I I I ---~ 0 LaSalle 1 N16 Nozzle Component ID: LCS-1-N16 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 60° S6 P-Scan achieved= 36.9 Sq. In Inner 15% T P-Scan achieved = 8.2 Sq. In 5.8" 60°T/P 8.0" 60°P 15.9" 60°T I 11;\ V r 0 CJ) C :::J ;:::;: ->. :::J CD m < :::J ti) (') ~o -* en ~-CD CD a. :"':' 0 0 < CD .., ti) cc CD z 0 m ::0 CD "O 0 @'

  • -Reactor Pressure Vessel Coverage r. HITACHI I Calculation Sheet LaSalle Unit-1 Weld LCS-1-NS 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% 60° T-Scon (56 Radial) A 47.8 43.4 77.5% 360 38.8% "'U z D) (C [ CD Cl) 55° P-SCon 154 LKCW) A 8.2 8.2 14.6% 360 3.7% 55° P-Scon 154 LKCCI A 8.2 8.2 14.6% 360 3.7% 60° P-Scan IS6 CW/CONJ A 47.8 36.9 65.9% 360 32.996 u.) r-u.) 0 0 ! ...... z (J'1 (11 ->. % Total Composite Coverage=

86.3% 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 underclod volume, 56-Supplement 6 volume. Weld length in degrees

  • Rev. l 3/23/09 r 0 (f) C ::i ;:::;: ->. (f) ::i CD m < ::i D) C') ~o -* en ~-CD CD C. 0 0 < CD o3 (C CD z 0 m ;o CD "C 0 ra-

""O D) ca CD (.,J .i:,.. 0 -en ....>. r ...... ;:c ...... w z 0 !;j_ CD r (') en I ...... I z en * <t T-Scans I T I I I + I I I I I -----1 0 0 LaSalle 1 N5 Nozzle -Core Spray Component ID: LCS-1-N5 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 60° S6 P-Scan achieved = 36.9 Sq. In Inner 15% T P-Scan achieved = 8.2 Sq. In 5.8" 60°T/P 8.0" 60°P 15.9" 60°T I r 0 (J) C :J ;:;: ....>. --l :J" a. (J) :J ~m < :J D) 0 ~a -* (/) ~-CD CD a. :-7 () 0 < CD .., D) ca CD z 0 m :::0 CD "O 0 "'U D) (C CD u.) 01 0 >. * -Reactor Pressure Vessel Coverage f~j HITACHI Calculation Sheet LaSalle Unit-1 Weld LCS-1-N6A 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-Scan 154 Radial) A 9.6 9.6 14.5% 360 7.2% 60° r-scan !S6 Radiall A 56.8 50.2 75.6% 360 37.8% 55° P-Scan 154 LKCWl A 9.6 9.6 14.5% 360 3.6% 55° P-Scan IS4 LKCCI A 9.6 9.6 14.5% 360 3.6% 60° P-Scon IS6 cw,ccw1 A 56.8 41.2 62.0% 360 31.0% % Total Composite Coverage= 83.3% 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

  • Rev. 1 3/73100 r 0 (J) C ::i ;:;.: ->. -j ::r a: (J) ::i ..+ CD m < ::i ~o C: ~-!:; CD CD c.. :-7 0 0 < CD @ (C CD z 0 m ;;o CD "O 0 "U fl) cc CD w 0) 0 -CJ'1 ->. .... ::0 .... c.> z 0 CD r-n en I .... . z 0) > 1J m (C CD 0) 0 -'""' I r-I I I ---0 0 LaSalle 1 N6 Nozzle -LPCI 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 60" S6 T-Scan achieved = 50.2 Sq. In 60° S4 T-Scan achieved=

9.6 Sq. In 60° S6 P-Scan achieved = 41.2 Sq. In Inner 15%T P-Scan achieved= 9.6 Sq. In {By modeling) 6.7" 8.6" 60°T/P NS 60°P I I I I I 15.9" 60°T -----l r 0 (/) C :::l ;:;: ->. :::l CD m < :::l fl) Q. !:: ~. !=; CD CD Q. :-7 0 0 < CD ..., fl) cc CD z 0 m ;:u CD "C 0 ;::::i. en ""O Dl cc CD (.,J -...J 0 -(J'1 ....>. z [ .. z en (D * -HITACHJ Weld Length= 360 Exam Volume= 66 60° T-Scon (S4 Radial) A 60° T-Scon IS6 Radial) A 55" P-Scan tS4 LKCWI A 55" P-Scon IS4 LKCCI A 60° P-Scan 156 ON/CONJ A A y Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit-1 Weld_LCS-1-N6S CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Required E>cam Percent Area sq.in. Area Scanned of Area Weld Length 9.6 9.6 14.5% 360 56.8 50;2 75.6% 360 9.6 9.6 14.5% 360 9.6 9.6 14;5% 360 56.8 41.2 62.0% 360 % Total Composite Coverage= Comments: NN -Nozzle to Vessel Inner 15%T circumferential scans A -Scanned area 360". Scanning restricted due to the nozzle configuration Percent 7_2% 37.8% 3.6% 3.6% 31.0% 83.3% Note -Rounding methods may affect calcufated values. S4-Supplement 4 underclad volume, S6-Suppfement 6 volume. Wefd length in degrees * . R<Y. l 3/Zl/O! r 0 (/) C ::J ;:.: ....>. ::J CD m < ::J Q. c~ ~-CD CD 0. 0 0 < CD m co CD z 0 m :::a CD 'O 0 ""U Ql cc CD (,.) 00 0 -CJ'l ...... r Dl (/l 21.. 1D C: ::::, .... r .... :::0 .... c.l z c6" r (") C/) I .... I z O> a, * <t T/P I I r-r I I 0 LaSalle 1 N6 Nozzle -LPCI 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 60° S6 T-Scan achieved= 50.2 Sq. In 60° S4 T-Scan achieved = 9.6 Sq. In 60° S6 P-Scan achieved = 41.2 Sq. In Inner 15% T P-Scan achieved = 9.6 Sq. In (By modeling) 6.7" 8.6" 60°T/P NS 60°P I I I I I ----~ 15.9" 60°T r () (J) C :::i ;:::;: ...... :::i CD m < :::i Ql C') C. ~-CD CD a. :-7 () 0 < CD -, Ql cc CD z 0 m ::0 CD "O 0 ""O D> ca CD u.) (0 0 -CJ'1 ..... * -Reactor Pressure Vessel Coverage . HITACHI Calculation Sheet LaSalle Unit-1 Weld LCS-1-N6C 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 A 9.6 9.6 14.5% 360 3.6% 55* P-Scon 154 LKCC) A 9.6 9.6 14.5% 360 3.6% 60" P-Scon 156 CW/CCW) A 56.8 41.2 62.0% 360 31.0% % Total Composite Coverage= 83.3% 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~

  • Rev. 1 l/23/0S r 0 (f) C :J ;::::;: ..... :J CD m < :J Q. C: ~-!:; CD CD 0. 0 0 < CD -, D> ca CD z 0 m ::u CD "O 0

"'U Ill cc CD 0 0 -CJ1 ....>. r Ql en m C ::, ...... r ..... :;o ..... c.> z 0 !;t <D r () 'fl ...... I z C) () -0 Ql IC <D C) 0 -....., r-I I I ---0 LaSalle 1 N6 Nozzle -LPCI Component ID: LCS-1-N6C 60° S6 Exam Volume= 56.8 Sq. In Inner 15% T Exam Volume (60°T & IRS)= 9.6 Sq. In 60° S6 T-Scan achieved= 50.2 Sq. In 60° 54 T-Scan achieved= 9.6 Sq. In 60° S6 P-Scan achieved = 41.2 Sq. In Inner 15%T P-Scan achieved= 9.6 Sq. In (By modeling) 6.7" 8.6" 60°T/P NS 60°P I I I I I 15.9" 60°T -----l r 0 (f) C :::J ;:;: ....>. -I :::J" a. 00 :::J CD m < :::J Ill Q. C: ~-CD CD c.. :-7° () 0 < CD -, Ill cc CD z 0 m ;a CD "O 0 ...... r -:;a ...... w ""CJ z Ill ca CD r-0 ....,. en 0 I .... -I CJl z .... ....,. 0

  • a Reactor Pressure Vessel Coverage I HITACHI Calculation Sheet LaSalle Unit-1 Weld LCS-1-NlO 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% 55° P-Scon (S4 LKCWl A 8.2 8.2 14.5% 360 3.6% 55° P-Scon (S4 LKCC) A 8.2 8.2 14.5% 360 3.6% 60° P-Scon 156 CW/CONJ A 48.2 39.5 70.0% 360 35.0% % Total Composite Coverage=

88.1% 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
  • 111!,.l 3/Z!/O'J r 0 (f) C ::, ;::;: ....,. ::, CD m < ::, Q. cg ~-CD CD C. :-7 0 0 < CD iil cc CD z 0 m :::a CD "O 0 ;:i. en r Ill en et CD C ,. $: .... !::: :::c .... (.,) "U z ru 0 co l:j CD CD r I\.) C') en 0 I -.... CJ'l z <t -->. .... 0 T/P I T I '1J I Ill I Ul ID + m 0 -'I ---l I I I I ---~ 0 LaSalle 1 N10 Nozzle -CRD Return Component ID: LCS-1-N10 60° S6 Exam Volume = 48.2 Sq. In Inner 15% T Exam Volume (60°T & IRS) = 8.2 Sq. In 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 Inner 15%T P-Scan achieved= 8.2 Sq. In (By modeling) 5.8" 60°T/P NS 9.4" 6Qop 15.8" 60°T r 0 (/) C ::J ;::::;: -->. ::J CD m < ::J !:I:!.(") C. ~-!=; CD CD 0. :-7 0 0 < CD ru co CD z 0 m :::0 CD 'C 0 @" co co 0 I co r-x I +/- O::'. ci -C Q) C 0 Cl.. E 0 0 Enclosure 1: LCS Unit 1 Third ISi Interval Limited Coverage NOE Reports ,._. \ \ \ Page 43 of 51 f--_ ' '"O OJ (Q CD .i,,. .i,,. 0 -01 ...... 5,tJf/0 ' I C ~-Torr-I C '.,.) B r 0 (J) C ::J ;::..: ...... (j) ::J m-m < ::J Q. C: g ~-CD CD Cl. :-7 0 0 < CD ..... OJ (Q CD z 0 m ;:o CD "O 0 ;::::i. (/) "'O Ql cc CD .i:,. CJ1 0 -CJ1 ...... en !!!. or C 'J co a, "' e e e HITACHI LaSa l le Unit 1 L CS-1-BG W e l d Shell 3 CW I ~'T--Scan I I 45'T-Scan L _______ _ 1 8.5" Co ve r age Pl o t 70"T-&an P-Scans Scanner Mo ti on Left S i de Scans I ----~ I I I : I ----{ I I _ _____ _J ~1*6..1$" HonM'lllla.d T*Q..3125'" -5.5" Coverage Plot for L eft S i de Scans L aSa ll e U nit-1 W e l d BG 10* Exam Volume= 8.5 Sq. In. 45' Exam Volume= 39.5 Sq. In. 60' Exam Volume = 8.3 Sq. In. 70" T-Scan ach i eved = 8.5 Sq. I n. 45' T-Scan achieved= 39.5 Sq. In. 60' T-Scan achieved = 8.3 Sq. I n. 7 0' P-Scan acl1 i eved = 8.5 Sq. In. 45' P-Scan ach i eved = 39.5 Sq. In. 60' P-Scan acl1 i eved = 8.3 Sq. I n. Shell 3 CCW r 0 (/) C :::J ;:;: ...... -, ::; --, c.. (/) :::J m-m < :::J Q.. C: g ~-CD CD c.. ...... 0 0 < CD --, Ql cc CD z 0 m :::0 CD "O 0 ;::i. CJ) "U ru co CD .i:,. 0) 0 -CJ1 ....,. e ~-HITACHI a, u, <ii C LaSa ll e Un it-1 Weld BG 70" Exam Volume = 8.5 Sq. In. 45" Exam Volume = 39.5 Sq. In. 60" Exam Volume = 8.3 Sq. In. 70" T-Scan ach i eved = 8.5 Sq. In. 45' T-Scan achieved= 39.5 Sq. In. 60" T -Scan achieved= 8.3 Sq. In. 70' P-Scan achieved = 8.5 Sq. I n. 45: P-Scan achieved= 39.5 Sq. In. 60 P-Scan achieved = 8.3 Sq. I n. Shell 3 CW e LaSalle U n i t 1 LCS-1-BG We l d Coverage Plot <t. P-5cans T/P-Scans 1 1o*r-scan I L ____ I ----I I I I I I I I I I I I I I r-------. L_________ S canner Motion 6.25" Right Side Scans ~T*4.1S" Hamnlll Old

  • il.3125"'

Coverage Plot for Right S i de Scans 45'T-Sca n ' ________ _J -18.5" r 0 (/) C :::i ;:::;: ....,. -i -=,--, a. (/) :::i m m -, < :::i ru (") C 0 (J) 3 C -, CD a. ....,. 0 0 < CD -, ru co CD Sl1e U3 CCW z 0 m :::0 CD "O 0 ;:::i.. (J) Enclosure 1: LCS Un i t 1 Third ISi Interval Lim i ted Coverage NOE Reports ""'O (1) s l9 co I .-I I c.n -~ M +-' C (1) 0 c.n 0 _J -::c -e :c +-' 0 a.. (1) 0) 0 L.. (1) > 0 u 0 <( e LaSalle Unit 1 -RF016 <( I N r-i 8 z 8 N 8 Page 47 of 51 -l.{) N N ..::::,-1") i 8 u <( Ul Q) ..c u .... 0 a. C 0 *.;::; 0 C .E 0 X Q) f-=> "O Q) +-' 0 E 0 .... ::i <I: Page 12 0115 "'U ll) cc CD CX) 0 ->. * ., en !!!. i5" C ::, "" . ::u .,, 0 en 1 Cl) 0 0 e HITACHI SP2000 RPV Examination Coverage 1 ca/cu/ation Sheet LaSalle Unit 1 / L1R16 I LCS-1-BG I CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 109.38 Required Exam Percent Exam Volume = 56.3 Area Sq. in. Area Scanned of Area Weld Length 70° T-Scan [S6 NS) A 8.5 8.5 15.1% 92.3 45° T-Scan {56 FV) A 39.5 39.5 70.2% 92.3 60° T-Scan ON (S4) A 8.3 8.3 14.7% 92.3 60° T-Scan CC (S4) A 8.3 8.3 14.7% 92.3 70° P-Scan [S6 NS] A 8.5 8.5 15.1% 92.3 45° P-Scon [S6 FVJ A 39.5 39.5 70.2% 92.3 60° P-Scon UP [S4) A 8.3 8.3 14.7% 92.3 60° P-Scon ON {S4J A 8.3 8.3 14.7% 92.3 70° T-Scon {S6 NS! I 45° T-Scan IS6 FVl I 60° T-Scan ON (541 I so* T-Scon cc IS4l I 70° P-Scon [S6 NS] 45° P-Scon (S6 FVJ I 60° P-Scon UP {S4] i 60° P-Scon ON {54] I I 70° T-Scan {S6 NS) I 45° T-Scan (S6 FV) I I 60° T-Scan ON IS4l . 60° T-Scan CC [S4l I 70° P-Scon [S6 NSl I 45° P-Scan (56 FV) I I 60° P-Scon UP (54) I so* P-Scan ON 154) I % Total Composite Coverage= I Comments: A-Automated Scanning was limited due to the proximity of the Nl2-A nozzle i I I I Note -Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in inches. 0 Percent 6.4% 29.6% 3.1% 3.1% 6.4% 29.6% 3.1% 3.1% 84.3% Rell.O 5/Zl/15 r 0 Cl) C :J ;:::;: -->. :J ~m < :J ll) Q. C. vi ~-CD CD 0. :-7 0 0 < CD -, ll) ca CD z 0 m ;:a CD -0 0 ;::::i. en _,.,.,..,__ Enclosure 1: LCS Unit 1 Third ISi Interval Limited Coverage NOE Reports HITACHI / / Component ID: LCS-1-N? LaSalle Unit-1 Scan Plan U7ftJ1S LaSalle Unit-1 2016 Page 49 of 51 (, 6/). & Pag~~ "J..{t,/lr,. ""U Dl ca CD CJ1 0 0 -CJ1 ....>. SSEnmr~Y...un.* 1~a~ SI £ua~-.o:n

  • 2.0:5q In .S~~tO>"aQ;i,a*.;hito..c:1*1Q9S::;i n 5'~'°"'<9rJga~*U1Sq ti... N7TopSide Component ID: LCS-1-N7 ) i LaSalle Unit-1 Scan Pian I ! I ' I I I I I I I I I I I I I I ' J. I I LaSalle Unil-1 2016 N7 Bottom Side Top Head N7 Nozzle SB E.<.lirn.1ct11

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"'U ID cc CD 01 ....>. 0 -01 ....>. D C B ._) 6\3l l-fr)-;S[ ELEV. 745.25" ill V. 723.JS" SHELL R*NG 5 El[V. 589.0" Sl--..£.U RmG 4 EL[V 3<2 2:, S:IELl RING 2 [LEV. 229.SB" sc* ,.5 SfiELL RING I 8 270' BS BF 8 112-J $ N2-H ELEV. tl9-B 121.05* r:: '125' 210* 1eo* iso* us* BR m~-C Nl~-3 .. 9 + llJ BE M EB AJ ,\2 8 © 8 8 N2-G tl2-f N2-E 1l2-D ,$ g~* I 1C'\ VA27 HJ-,. AE SS-2 BK Al! B,l. Al ""(+/-) 8 N2-C ll2-B ss-; D BO 8 N2-A 119-A AA .., L I 9" 1 330' 31S' 270' A318 113-D ss;-e 0 5H-Bf i llC A6 GJ e t12-K Nl-A' r------------*- UQZZL[ LOC.JillOt;S NOZlll A 211.IU I K Elf.:VATIOtl lli.!1E5.:. 1 -A!.~ *1.1[Yi'S ARE lOKl'JC AT \l~SSEL me,., OU TSOE 2 -A-S£ns.oo !QOHl.!l(ATJO~-,S INSERVICE INSPECTION ';{?V WELD & SEi-iSOR L.A.YOL!: D C A r 0 CJ) C :J ;:;: ....>. -, ::r -, a. en :J .-+ CD m < :J Q. C: 0 en 3 C: -, ;:::;: CD CD a. ....>. 0 0 < CD -, ID ca CD z 0 m :::0 CD "O 0 ;:::i. en 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

  • I Report No.: HITACHI EXAMINATION

SUMMARY

SHEET L2Rl2*029 e Site: LaSalle Component ID: HP-PU2-04 Outage: L2R12 PL-PUMP System: HP ASME Cat.: C-C ASME Item C3.30 Aug Req N/A Exoms I Doto Sheet I Col Sheet I Procedure I Calibration Block I Exam/Oper. Cert Level I Date Performed 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~ l*Ulf1 l'j~ 1-Zb*C.'{ Dose: l mr. Prepared By: Level: Dote: Utility Review: Dote: /)_vi,~ 1~J..1-crr ANII Review: Dote: Page 1 of 1,.,.4---0 Page 2 of 45 0 Enclosure 2: LCS Unit 2 Third ISi Interval Limited Coverage NOE Reports Component ID: HP-PU2-04 .AREA t X..AM / ,v E .f) .2 7, o _!J;* 6c./. {., '{ 3.IL/1(.,, -:. I 7/. 5 Lb!SfL... -f.d;.J(_ 1_,.."7, 0 t~'A>>1 I Obi) U:'}1~ ft G';o4M1A/~: 2 1,o/(71.r )((DO~ = I bt;; Page 3 of 45 L. :2 f?( 2.-02 '1 µ ?-'4)4 z.-o4 (-\qroq 1--lP 5-<.t-S~ p L Jo ?Lt M,P . "U !l) cc CD .i:,. 0 -.i:,. c.n ii I HITACHI r System: Position l 2 3 4 5 O' 90" .90 NIA I .88 I NIA I l.10 I NIA I NIA NIA I NIA NIA Alida Hutton Drown by: 180" 270' NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA PIPE .\ ~,. ll.~ Levet Date: 11 Wall Thickness Profile Sheet I Component ID Number. /MS-2044-:13 Crown Height .15" Crown Width: l.3" Nominal Diameter: l8.0" Weld Length: 57.5" PL~w' <i. , ,,,,. ,_,,,4, /*Ut1 r, V ~t Dote: Site: LaSalle Project L2R12 --*** rn rn Ef2£ UPST Component Unit ' Report No~ l I l2R12-047 [ID I rn @] Valve DNST Component FLOW .. ,,._..__, ___ J..-:z-01 I Dote: I Page r 0 C/) C :::J ;:::;: N -l ::J" a cr.i :::J ro m < :::J ~(") re -* en 3 C -*-, CD CD a. N 0 0 < CD -, !l) cc CD z 0 m :::0 CD "C 0 "'U Dl ca CD u, 0 -u, e e Comments: HITACHI Weld Length= Exam Area= D.843 Upstream Scan I Downstream Scan I CW Scan I CCWScan I Weld Length= 360. Exam Volume= o. NIA I NIA NIA I NIA NIA I NIA NIA I NIA 0 Pipe Weld Coverage Calculation Sheet LaSalle Unit 2 / L2R12 I MS-2044-13 Spring / 2009 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Required Area Scanned Area Total Required Total Scanned %Coverage Area Area 0.843 0.697 0.843 0.477 3.373 2.02 59.8% 0.843 0.422 0.843 0.422 % Total Composite Coverage= 59.8% CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Required Exam Area Scanned of Area Weld Length Percent Area Sq. In. Manual Manual Manual Manual NIA NIA NIA NIA NIA NIA N/A NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA N/A L2R12*047 PageS.._of5~ r 0 Cl) C :::J ;:;: (J) :::J cii m < :::J Dl Q. C: ;!_ !:; ,.-,. CD [!':' 0 0 < CD .., Dl cc CD z 0 m ::a CD "C 0 ;:::i. en Enclosure 2: LCS Unit 2 Third ISi Interval Limited Coverage NOE Reports e I HITACHI Examination Summary Sheet Report No.: L2R12*081 Site: LaSalle Unit 2 Component ID: LCS-2-NlO 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 O reference 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.~ -n:r:. 2.j'lo'i --4 'Iii" Prepared By: Level: Dote: ="J;i~ Date: 2/.5 / D-2._ ANIJ Reviewed BY: Date: e LaSalle Unit 2, l2Rt2, 2009 Page 1 of 15 Page 6 of 45 "'U Ill co CD -.,J 0 -.i:,.. CJ1 n u e I HITACHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 2 / L2R12 LCS-2-N10 (Noz-RPV) 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% IRS P-Scan CS4 UC1 A 8.5 7.8 13.2% 360 6.6% 45° P-Scan (S6 FV A 39 16.4 27.7% 360 13.9% 70° P-8can S6 NS A 11.6 2.5 4.2% 360 2.1% 60°T-Scan S4UC 45° T*Scan S6FV 70"T-Scan S6NS IRSP-Scan S4UC 45* P-Scan S6FV 70° P-8can S6NS ao 0 T-Scan S4UC 45°T-scan S6FV 70° T-Scan S6NS IRSP-8can S4UC 45° P-Scan S6FV 70° P-8can S6NS % Total Composite Coverage= 54.1% 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 Rov.O IIIZ3IOS r 0 (J) C ::, ;:;: ::, CD m <::, Ill (") ~a -* en 3 C -* -, CD CD a. !':' 0 0 < CD -, Ill co CD z 0 m :::0 CD "C 0 ;:i. en "'U Ql cc CD co 0 -CJ1 e 0 ' . e fl I HITACHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 2 / L2R12 LCS-2-N10 (Noz-RPV) Spring / 2009 CODECROSS-SECTIONALAREA TOTAL CODE COVERAGE Percent Weld Length= 360. Required Exam Area Scanned of Area Weld Length Percent Exam Volume= 59.1 Area SQ. In. Manual Manual Manual Manual 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% so* T-Scan S6NS A 11.6 2.5 4.2% 360 2.1% 60" P-Scan S4UC A 8.5 0.7 1.2% 360 0.6% 60° P-Scan S6t-v A 39 10.3 17.4% 360 8.7% 60" P-Scan 56NS A 11.6 2.5 4.2% 360 2.1% so* T-Scan CS4 uc 60° T-Scan (56 FV so* T-Scan tS6 NS 60° P-Scan (S4 UC) so* P-Scan css FV) 60° P-Scan (56 NS) so* T-Scan 1 S4UC so* T-Scan 56FV 60°T-Scan S6NS 60" P-Scan 1 S4UC so* P-Scan SSl'V 60" P-Scan S6NS % 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. r 0 en C :::, ;:::;: I\.) -, ::r a CJ) :::, co m <:::, Q. rO -* en 3 C: -*-, -CD !'? () 0 < CD -, Ql cc CD z 0 m ;;o CD "O 0 1J D) (Q CD CD 0 -.i,.. (]1 "II .. CD .. "' !al. UI I { I 1-----1 I I 0 LaSalle Unit-2 LCS-2-N10 10* Exam Volume = 11 .6 Sq. In, 45* Exam Volume = 39.0 Sq. In. Inner 15%T Exam Volume (IRS & 60"T) = 8.5 Sq. In. 70' T-Scan achieved = 3.7 Sq. In. 45° T -Scan achieved = 25.0 Sq. In. 60' T -Scan achieved = 8.5 Sq. In. Automated T -Scan llmited due to Jhe medlanlcal llmll of the scanner arm 60"T I r 0 Cl) C ::, ;:;: I\) --l ::; .... C. Cl), ::, co m <::, !!!. Q_ rO -* CJ) 3 C -* .... ..... CD I\) 0 0 < CD a (Q CD z 0 m :::0 CD "C 0 ;:::i. CJ)

"U [I) cc CD ....>. 0 0 -.i,. 01 0 LaSalle Unit-2 LCS-2-N10 70" Exam Volume = 11.6 Sq. In. 45" Exam Volume = 39.0 Sq. In. Inner 15% T Exam Volume (IRS & 60'T) = 8.5 Sq. In. 70" P-Scan achieved = 2.5 Sq. In

  • 45' P-Scan achieve<!

16.4 Sq. In. IRS P-Scan achieved

7.8 Sq. In. By ModeUng) Automated P-Scan llmlted due to lhe mechanical limit of the scanner arm IRS P-Scan I r () en C ::::J ;:;: en ::::J ro m < ::::J Q. ro -* C/l 3 C: -* -, ..+ CD !':' () 0 < CD -, [I) cc CD z 0 m ;:a CD "C 0 ;:i C/l 0 ,.. a, er, .. i' C "' !" i;; r () !" (fJ "' 0 C 0 <D :::J ;:::;: N -; :::J'" -, a. LaSalle Unit-2 (fJ LCS-2-N10

J ""O .-+ CD m D) < co :::J CD D) Q. ->. 60' NS Exam Volume= 11.6 Sq. In. r 0 ->. 60' FV Exam Volume = 39.0 Sq. In. ~r en Inner 15%T Exam.Volume (IRS & 60"T) = 8.5 Sq. In. C 0 -, ;:::;: CD -CD .i,,.. 60' NS T-Scan achieved = 2.5 Sq. In . a. N en 60' FV T-Scan achieved = 5.0 Sq. In. 0 60° T-Scan achievoo = 0 Sq. In. 0 < CD -, D) co CD 2.0 Supplemental manual exam area z 6 T 0 TNS m ::::0 CD -----1 "C 0 I ;:i. "D I en m OJ I .. 0 I a I (ft ----1 0 lo g, iii' C :, ;:;: !" i;; r ;c 0 _.; N CJ) 0 C 0 "' ::, ;::::;: I\.) --l :::::r .., c.. LaSalle Unit-2 en LCS-2-N10
, "1J r+ CD m ru .., cc < ::, CD ru Q. ...... 60" NS Exam Volume= 11.6 Sq. In. r 0 I\.) 60" FV Exam Volume = 39.0 Sq. In. ~i" (/) Inner 15%T Exam Volume (IRS & 60"T) = 8.5 Sq. In. C: 0 .., -r+ CD .J:>,. 60' NS P-5can achieved=

2.5 Sq. In . ~!':' CJ'I 60' FV P-5can achieved= 10.3 Sq. In. 0 IRS P-Scan achieved= .7 Sq. In. By Modeling) 0 < CD .., ru cc CD IRSP-5can Supplemental manual exam area z 'r. 60PFV 0 60PNS m I ;o CD ----1 -c 0 I ;::i 1 I (/) .. I -I -2. I -----1 a, "'U Dl co CD --" u.) 0 -.i:,.. 01 e ., u, ., ;if C ::, = e I HITACHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 21 L2R12 LCS-2-N1A Recirculation Outlet (Naz-Shell) Spring / 2009 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% 10°T-Scan S6NS A 12.7 6.3 10.4% 360 5.2% IRS P-Scan1 S4UC> A* 8.5 8.5 14.1% 360 7.0% 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%. so* r-scan S4UCl 0 0 45° T-Scan S6t-VJ 0 0 70° T-Scan S6NS 0 0 IRSP-Scan S4UC 0 0 45° P-5can S6 t-V 0 0 70° P~can ;:,o fill) 0 0 so 0 T-Scan S4UC 0 0. 45°T-Scan S6FV 0 0 70°T-Scan S6NS 0 0 IRSP-Scan S4UC 0 0 45° P-5can S6i-v 0 0 10* P-Scan ;:,o NO 0 0 % Total Composite Coverage = 71.6% 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. Rev.081ZW5 r 0 (J) C :J ;:::;: :J ro m < :J ~C') ro -* en 3 C: -*-, ..... CD !'? 0 0 < CD ii3 cc CD z 0 m ;a CD "O 0 "'U !l) cc CD 0 I I I I I ----l LaSalle U nit-2 LCS-2-N1 Component ID: LCS-2-N1A 70° Exam Volume = 12.7 Sq. In. 45° Exam Volume = 39.2 Sq. In. Inner 15%T Exam Volume (IRS & 60°n = 8.5 Sq. In. 70° T -Scan achieved = 6.3 Sq. In. 45° T -Scan achieved = 34.6 Sq. In. 60° T-Scan achieved = 8.5 Sq. In. 70"T 45°T 60°T I I r 0 CJ) C :::, ;:;: I\.) -I ::r a en :::, ro m <:::, !l) (") ~o -* en 3 C -* -, ..+ CD [ !'? 0 0 < CD -, !l) cc CD z 0 m ;a CD "C 0 ;:i. en "'U Ill cc CD ....,. 01 0 -01 "' 2. a> I I I 1-----1 I I I I J---0 LaSalle Unit-2 LCS-2-N1 Component ID: LCS-2-N1A 70° Exam Volume= 12.7 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. 45° P-Scan achieved = 24.1 Sq. In. IRS Scan achieved (By Modeling) = 8.5 Sq. In. 70°T 45°T I l I I I ----1 I I r 0 CJ) C ::::, ;:;: I\.) -l ::r a: CJ) ::::, ro m <::::, Q. re -* en 3 C: -*-, r+ CD ~!':' () 0 < CD -, Ill co CD z 0 m :::0 CD "C 0 @" -a Dl ca CD ...... O') 0 -01 ... a. a> fl I HITACHI Weld Length= 360. rl. y Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 2 I L2R12 LCS-2-N1B Recirculation Outlet (Noz-Shell) Spring / 2009 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Required Exam Area Scanned of Area Weld Length Percent Exam Volume= 60A AreaSq.ln. Automated Automated Automated Automated 60"T-5can S4UC A 8.5 8.5 14.1% 360 7.0% 45°T-5c:an S6 F\I A 39.2 34.6 57.3% 360 28.6% 70° T-Scan S6NS A 12.7 6.3 10.4% 360 5.2% IRSP-Scan, S4UC) A" 8.5 8.5 14.1% 360 7.0% 45° P-scan S6FV A 39.2 24.1 39.9% 360 20.0% 70° P-scan :S6Nl:i A 12.7 4.5 1.sv11, 360 3.7% 60°T-Scan S4UC 0 0 45° T-Scan S6FV 0 0 70"T-Scan, S6NS 0 0. IRSP-Scan, S4UCl 0 0 45° P-Scan, S6FV 0 0 70" P-scan :ss Nl:i) D 0 so* T-Scan S4UC 0 0 45°T-Scan S6FV 0 0 70° T-5can S6NS 0 0 IRSP-5can S4UC1 0 0 45° P-Scan 56 F\I 0 0 70° P-5can 0 0 % Total Composite Coverage = 71.6% Comments: A -Automated scanning was not restricted . 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. R ... o Bl'ZW! r 0 (f) C :J ;:::;: -; ::::; a en :J ro m < :J !!!. Q.. ro -* en 3 C: -* -, r+ CD [!':) 0 0 < CD -, Dl ca CD z 0 m :;u CD "C 0 ;::::i. en "U Ol cc CD ->. --.J 0 -.J:>. 01 0 I I I I I ---~ LaSalle Unit-2 LCS-2-N1 Component ID: LCS-2-N1 B 70° Exam Volume= 12.7 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 = 6.3 Sq. In. 45° T-Scan achieved = 34.6 Sq. In. 60° T-Scan achieved = 8.5 Sq. In. 70°T 45°T 60°T I I 'W r 0 (f) C ::J ;:::;: ::J ro m < ::J Ol (") ;:: 0 -* (J) 3 C: -*..., ..+ CD ~!':' 0 0 < CD ..., Ol cc CD z 0 m ;:o CD "O 0 ;:l,. (J) 0 r CII en CII ii' C ii-!" LaSalle Unit-2 i:; r :n 0 LCS-2-N1 (J) "' 0 C 0 "' :::J Component ID: LCS-2-N1 B ;:;.: I\.) 70° Exam Volume= 12.7 Sq. In. -i ::; 45° Exam Volume = 39.2 Sq. In. ..., Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. 0. (J) 70° P-Scan achieved = 4.5 Sq. In. 45° P-Scan achieved = 24.1 Sq. In. :::J ,-,. ""U IRS Scan achieved (By Modeling) = 8.5 Sq. In. CD m !l) < :::J co CD Q. ....>. rO 0:, -* en 3 C 0 -*..., ,-,. CD -~!':' (.J'I 0 0 < CD ..., !l) I co CD I 70°T 45°T z ! I I 0 m I-----:::0 I I CD "'C I I 0 I I ;::::i en I I I I ... !al. 1--------! "' "lJ D) cc CD ...... (0 0 -.j:>.. (]1 w a "' 0 81 Hl"mCHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 2/ L2R12 LCS-2-N2C (Noz-RPV) Spring / 2009 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% 70° T-Scan CS6 NS) A 11.4 5.8 9.8% 360 4.9% IRS P-8can CS4 UCl A* 8.5 8.5 14.4% 360 7.2% 45" P-8can lS6 FVI A 39.2 22.5 38.1% 360 19.0% 10* P-Scan (S6 N~) A 11.4 4.5 7.6% 360 3.81{; 60"T-Scan S4UC 0 0 45°T-Scan S6FV 0 0 10* T-Scan, S6NS 0 0 IRS P-Scan S4UC 0 0 45° P-Scan S6 t-V 0 0 10* P-Scan ::sr.NS 0 0 60°T-Scan, S4UC1 0 0 45° T-Scan S6 F\i 0 0 10° T-Scan S6NS 0 0 IRSP-Scan S4UC 0 0 45° P-Scan S6FV 0 0 70° P-Scan l:>~N::i 0 0 % Total Composite Coverage= 70.5% Comments: A -Automated scanning was not restricted ~* -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. e Rov,0812311)5 r 0 (/) C ::i ;::::.: (/) ::i ~m < ::i !!!. Q. ro -* C/l 3 C: -* -, CD CD a. !'? 0 0 < CD ru cc CD z 0 m ;o CD "C 0 @" 0 ,.. a, en .. = ., C: :, ;;; LaSalle Unit-2 -"' ,.. "' r 3! 0 _ .. LCS-2-N2 (J) N 0 C 0 <O ::::, Component ID: LCS-2-N2C

I\.) 70° Exam Volume = 11.4 Sq. In. -l
r 45° Exam Volume = 39.2 Sq. In. "'"1 0.. Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In. ci.i 70° T -Scan achieved = 5.8 Sq. In. :::i "U ...... Ill 45° T-Scan achieved=

33.5 Sq. In. mm cc 60° T-Scan achieved = 6.8 Sq. In. <::::, CD ~(") I\.) rO 0 -* en 3 C: 0 -* "'"1 -...... CD .i:,. !':' 01 0 Umltedarea 0 due to N9. < CD "'"1 70°T 45"T 60°T 60°T Ill ca I I I ' CD z 0 m :::0 CD "'C 0 ;::i. en .... g_ 00 "U !l) co CD N ...,. 0 -.I),. 01 "' !l. 0, I I f------1 I I I I I----<t 17.25" 0 LaSalle Unit-2 LCS-2-N2 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. 70° P-Scan achieved = 4.5 Sq. In. 45° P-Scan achieved = 22.5 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model) 70"P45"P I I I I I ----I I I r 0 CJ) C ::, ;:::.: (J) ::, mm <::, Q. rO -* CJ) 3 r::: -* -, -CD ~!':' 0 0 < CD @ cc CD z 0 m ;o CD "'Cl 0 ra- "'U D) cc CD N N 0 -01 0 e Reactor Pressure Vessel HITACHI Coverage Calculation Sheet . LaSalle Unit 2 / L2R12 LCS-2-N3A Spring 2009 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 50.1 47.8 65.0% 360 32.5% 60° T *Scan (S6 NS A 12.8 5.9 8.0% 360 4.0% IRS P-Scan S4 UC) A 10.6 10.6 14.4% 360 7.2% 60° P-Scan S6 FV) A 50.1 42 57.1% 360 28.6o/o 60° P-scan (S6 NS) A 12.8 5.5 7.5% 360 3.7% 60° T-Scan (S4 UC> 60° T-Scan (S6 FV 60° T-Scan 1S6 NS IRS P-Scan S4UC so* P-Scan S6FV 50° P-scan (56 NS) 60° T-Scan CS4 UC) 60° T-Scan (S6 FV 60° T-Scan S6 NS IRS P-Scan (S4 UC> 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. r 0 CJ) C :::i ;:;: :::i ro m < :::i D) (') i= 0 -* CJ) ,.... CD ~!':' 0 0 < CD .., D) cc CD z 0 m ;:o CD "'C 0 "'U ru cc (l) I'.) w 0 -.i:,. CJ1 "Dr ~N i: ?'\::I l 0 C}.) 0 e Reactor Pressure Vessel HITACHI Coverage Calculation Sheet LaSalle Unit 2 / L2R 12 LCS-2-N38 Spring 2009 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360. Required Exam Area Scanned of Area Weld Length Exam Volume= 73.5 Area Sq. In. Manual Manual Manual 60° T-Scan lS4 UC) A 10.6 10.6 14.4% 360 60° T-Scan S6FV A 50.1 47.8 65.0% 360 60°T-Scan S6NS A 12.8 5.9 8.0% 360 IRS P-Scan, S4UC1 A 10.6 10.6 14.4% 360 60° P-Scan S6FV A 50.1 42 57.1% 360 60° P-Scan (S6 N~) A 12.8 5.5 7.5% 360 60° T-Scan lS4 UC) 60° T-Scan S6 FV) 60° T-Scan S6 NS) IRS P-Scan S4 UC 60° P-Scan S6 FV) 60° P-Scan (S6 NS) ' 60° T-Scan S4 UC 60° T-Scan (S6 FV) 60° T-Scan S6 NS IRS P-Scan S4 UC 60° P-Scan lS6 FV) 60° P-Scan (S6 NS) % Total Composite Coverage= Comments: A -Manual exam was restricted due to the nozzle configuration. Percent Manual 7.2% 32.5% 4.0% 7.2% 28.6% 3.7% 83.3% w Rev.a 912:WS Note -Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in inches or degrees. r 0 (f) C :J ;::;: :J ..... m < :J Q.. rO -* en 3 C: -* -, ..... (l) !'? 0 0 < (l) iu cc (l) z 0 m ::0 (l) "Cl 0 "U D> cc CD I\) ..i:,.. 0 -..i:,.. en i s' = !" i;:; .!'> g m l w a "" e 81 HITACHI Weld Length= 360. Exam Volume= 73.5 60°T-Scan S4UC A 45° T-Scan SSF\J A 70"T-8can S6NS A IRS P-5can S4UC A* 45° P-5can S6FV A 70" P-SCSn S6NS A so* T-Scan S4UC 45" T-Scan S6 F\J 10* T-Scan S6NS IRSP-Scan 1 S4UC 45° PaScan (SS FV 70° P-scan (S6 NS 60°T-Scan 1 S4UC 45°T-5can S6FVl 70"T-Scan S6NS IRSP-Scan 1 S4UC 45* P.Scan (S6 FVl 70" P-5can (SS NS) n y Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 2 / L2R12 LCS-2-N3C (Noz-RPV) Spring / 2009 CODE CROSS-SECTIONAL ARl:A TOTAL CODE COVERAGE Percent Required Exam Area Scanned of Area Weld Length Percent Area Sq.In. Automated Automated Automated Automated 10.6 10.6 14.4% 360 7.2% 50.1 42.7 58.1% 360 29.0% 12.8 5.8 7.9% 360 3.9% 10.6 10.6 14.4% 360 7.2% 50.1 33.7 45.9% 360 22.9% 12.8 5.6 7.6% 360 3.8% 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 % Total Composite Coverage= 74.1% Comments: A-Automated scaMlng was restricted due to nozzle configuration Note -Rounding methods may affect calculated values. UC-Undercfad, FV-Full volume, NS-Near Surface. Weld lenath in dearees. -Rov,O~ r 0 Cl) C :::J ;:::;: I\) -i ::,-a Cl) :::J mm < :::J (') ro -* en 3 C -* -, CD CD a. !':' 0 0 < CD -, D> cc CD z 0 m :::0 CD "C 0 ra- ""U Ol cc CD "' CJ1 0 -CJ1 t. 24.75" 0 I I I I I I -----i LaSalle Unit-2 LCS-2-N3 Component ID: LCS-2-N3C 70° Exam Volume= 12.8 Sq. In. 45° Exam Volume = 50.1 Sq. In. Inner 15% T Exam Volume (IRS & 60°T) = 10.6 Sq. In. 70° T-Scan achieved = 5.8 Sq. In. 45° T-Scan achieved= 42.7 Sq. In. 60° T-Scan achieved = 10.6 Sq. In. 45°T I 60°T I 0 ' . r 0 en C ::I ;:::;: "' -i :, a. (/) ::I m-m < ::I Q.. C: ~-!:; ,.... CD !'? 0 0 < CD -, Ol cc CD z 0 m ;;o CD "O 0 @" "'U Ill cc Cl) N 0) 0 -.i:,... CJ1 l .. "' 2. ()0 P-Scans It 24.75" I f------1 I I I I I i---0 LaSalle Unit-2 LCS-2-N3 Component ID: LCS-2-N3C 70° Exam Volume = 12.8 Sq. In. 45° Exam Volume = 50.1 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 10.6 Sq. In. 70° P-Scan achieved = 5.6 Sq. In. 45° P-Scan achieved= 33.7 Sq. In. IRS scan achieved (By Modeling}= 10.6 Sq. In. 70°P 45°P I I I I I I ------1 I I r 0 en C :::::J ;:::;: (J) :::::J ~m < :::::J Q. rO -* en 3 C: -*-, ...... Cl) ~!':' () 0 < Cl) @ ca Cl) z 0 m :::0 Cl) "C 0 ra- "'U D) cc CD N --.J 0 -.r:,.. CJ1 j = .!" i;; .!" g ... i (,> g, <D e e I HITACHI Weld Length= 360, Exam Volume= 73.5 60° T-Scan S4UC A 45° T-Scan S6FV A 70°T-5can S6NS A IRS P-Scan S4UC A* 45° P-5can S6FV A 10* t"~can ::st!NQi A 60°T-Scan S4UC 45° T-Scan S6FV 70° T-Scan S6NS IRS P-5can1 S4UC 45° P-Scan S6FV 10* P-Scan S6NS 60' T-5can S4UC 45° T-Scan S6FV 70°T-5can S6NS IRS P-5can (S4 UC 45° P-Sc:an CS6 FV 70° P-~ 1::;a NS V Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 2 / L2R12 LCS-2-N3D (Noz-RPV) , Spring / 2009 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Required Exam Area Scanned of Area Weld Length Percent Area Sa.In, Automated Automated Automated Automa1Bd 10.6 10.6 14.4% 360 7.2% 50.1 42.7 58.1% 360 29.0% 12.8 5.8 7.9% 360 3.9% 10.6 10.6 14.4% 360 7.2% 50.1 33.7 45.9% 360 22.9% 12.8 5.6 7.6'Yo 360 3.8"/o 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 % Total Composite Coverage= 74.1% Comments: A -Automated scanning was restricted due to nozzle configuration Note -Rounding methods may affect calculated values. UC-Underclad, FV-Futl volume, NS-Near Surface. Weld lenath in degrees. -Rff.OW23111! r () Cl) C ::, ;:::;: N -l :, a: ci5 ::, ro m <::, ~(") rO -* en 3 C cil a. N () .. 0 c5 .., D) ca CD z 0 m :::0 CD "O 0 @" 0 i; "' ., ii C :, ::;; i;; LaSalle Unit-2 r ;o _;;; () ., Cl) 0 0 LCS-2-N3 C ro ::, ;::;: Component ID: LCS-2-N3D "' -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. (f) 70° T-Scan achieved = 5.8 Sq. In. ::, ""CJ ..... Dl 45° T-Scan achieved= 42.7 Sq. In. !!l m ca 60° T-Scan achieved= 10.6 Sq. In. <::, CD Q. "' rO co -* (/) 0 3 C -*...., -CD CD .i:,. (.Jl a. !':' () 0 < CD ...., Dl ca CD 45°T 60°T z I I 0 m :::u CD "C 0 ;:I,. (/) 1 ... 2. QI "'U Q) cc CD N (0 0 -.i:,.. 01 P-Scans 1------1 I I I I I i----I <t 24.75" I 0 LaSalle Unit-2 LCS-2-N3 Component ID: LCS-2-N3D 70° Exam Volume= 12.8 Sq. In. 45° Exam Volume = 50.1 Sq. In. Inner 15%T Exam Volume (IRS & 60°T) = 10.6 Sq. In. 70° P-Scan achieved = 5.6 Sq. In. 45° P-Scan achieved= 33.7 Sq. In. IRS scan achieved (By Modeling) = 10.6 Sq. In. 70°P 45°P I I r 0 (J) C :::J ;:::;: N -I ::r a en :::J co m < :::J Q) (") ~o -* CJ) 3 C -* -, ..... CD !'? 0 0 < CD -, Q) cc CD z 0 m ::u CD "O 0 (I) Enclosure 2: LCS Unit 2 Third ISi Interval Limited Coverage NOE Reports e HITACHI Examination Summary Sheet Report No.: L2R12-089 Site: LaSalle Unit 2 Component ID: LCS-2-N6A 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 o reference 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 These e><ominotions were performed under Work Order: 1011137 This summary and the following data sheets hove been reviewed and accepted by the following personnel: Level: *{"L~(dl Dote: [81 No Change 0Chonge -;J..-/-c>9 9.__ _______________________ ---'A-'-N"'-II_Rev_lewed~~Bv:.._. ________ .::;.Do~t""e: ___ _, Page 30 of 45 "'U Ill cc CD (,J ...... 0 -01 0 I I I I I -----1 LaSalle Unit-2 LCS-2-N6 Component ID: LCS-2-N6A 70° Exam Volume = 11.4 Sq. In. 45° Exam Volume = 39.2 Sq. In. (D . , 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. 70°T 45°T 60°T r 0 (J) C ::::i ;::::;: ::::i cii m < ::::i Q_ rO -* en 3 C: -* -, r+ CD [!':' 0 0 < CD -, Ill cc CD z 0 m ::0 CD -c 0 "'U Ill cc CD u.) I\J 0 -.i,.. CJ1 "' a a, I I .<t 17.25" 1-----1 I I I I f----0 70°P LaSalle Unit-2 LCS-2-N6 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. 70° Exam Volume = 4.8 Sq. In. 45° Exam Volume = 23.1 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model) I ~scp I I I I I ----j r 0 en C :J ;:::.: I\J -I ::; a. 00 :J ro m < :J Q. ro -* en 3 C: -*-, ..+ CD ~!':' 0 0 < CD -, Ill cc CD z 0 m :::0 CD -c 0 ;:i. en "U ti) cc CD (,,) (,,) 0 -.i::,. 0, e e Comments: HITACHI Weld Length= 360. Exam Volume

  • 59.1 60°T-Scan1 S4UC A 45° T-Scan S6FV A 10°T-Scan S6NS A IRS P-Scan1 S4UCI A* 45° P-Scan S6FV A 70° P-Scan ::;o NS A so* T-Scan S4UC 45° T-Scan S6FV 70°T-Scan 1 S6NS IRS P-8can S4UC1 45° P-8can S6Fv: 70° P-5can S6NS so 0 T-scan S4UC 45°T-8can S6FV 70° T-Scan 1 S6NS IRS P-Scan S4UC1 45° P-8can! S6FV 70° P~can (S6 NS n y Reactor Pressure Vessel Coverage Calculation Sheet LaSalle Unit 2 / L2R12 Lcs:.2-N6C LPCI (Noz-Shell)

Spring / 2009 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Required Exam Area Scanned of Area Weld Length Percent Area Sa.In. Automated Automated Automated Automated 8.5 8.5 14.4% 360 7.2% 39.2 33.5 56.7% 360 28.3% 11.4 5.8 9.8% 360 4.9% 8.5 8.5 14;4% 360 7;2% 39.2 23.1 39.1% 360 19.5% 11.4 4.8 IS.1'1o 360 4.1'1o 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D D 0 0 0 0 0 0 0 0 % Total Composite Coverage= 71.2% 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. Rw.o~ r 0 (/) C ::::, ;:;: I\.) -f :,-a (/) ::::, co m <::::, !!!. Q. re -* CJ) 3 C -*-, ,..... CD ~!':' 0 0 < CD -, ti) cc CD z 0 m ::0 CD "O 0

"'U Dl cc CD w .i:,. 0 -.i:,. CJ1 ... 5?. a, 0 I I I I I ----1 LaSalle Unit-2 LCS-2-N6 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. 70° T-Scan achieved = 5.8 Sq. In. 45° T-Scan achieved = 33.5 Sq. In. 60° T-Scan achieved = 8.5 Sq. In. 70°T 45°T 60°T r 0 en C :J ;:;: :J co m < :J Q. re -* en 3 C: -*..., .-+ CD [~ 0 0 < CD m cc CD z 0 m ;:u CD "C 0 "'U Dl . cc CD (.,J CJ1 0 -.J:>. CJ1 "' 2, CD <t I 17.25" I f-----1 I I I I 1----0 I I I I I ----, LaSalle Unit-2 LCS-2-N6 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. 70° Exam Volume = 4.8 Sq. In. 45° Exam Volume = 23.1 Sq. In. IRS P-Scan achieved = 8.5 Sq. In. (By model} r 0 CJ) C ::::J ;:::;: N -I ::; a (/) ::::J r+ mm < ::::J Q.. rO -* en 3 C -* -, r+ CD [!':) 0 0 < CD -, Dl ca CD z 0 m :::0 CD "'C 0 @" ""CJ OJ (Q CD w 0) 0 -.i,.. CJ1 GE Hitachi 4 5* N 6C e 315° 1 35° Vessel Elevation 7 93'-3.75" N6B I N 6 A V essel Elevation 780'-9" Vesse l Map -O u tside View o f Shell Ring Assembly " 2 P a ge.....f.._01 G,c.._ r 0 (J) C ::::, ;:;.: N -l ::; -, Q. (J) ::::, m-m <::::, ~(") ro -* (/l 3 C -*-, CD CD Q. N 0 0 < CD -, OJ co CD z 0 m :::0 CD "C 0 ::i. (/l ""CJ D> ca CD w -.J 0 -CJ1

  • GE Hitachi LaSalle Unit 2 L2R14 LPCIN68 Nozzle to Shell Weld Cross Section @ 0° & 180° 60° 54 Exam Area =9.1 Sq. In. 60° S6 Exam Area = 59.0 Sq In. 15.6" 60°T 60° S4 T-Scan Achieved = 9.2 Sq. In. 60° S6 T-Scan Achieved=

43.5 Sq. In. 60° S4 P-Scan Achieved = 4.6 Sq. In. 60° S6 P-Scan Achieved = 24.2 Sq. In. Page~of r 0 CJ) C ::::, ;::;: ::::, ro m <::::, ~(') rO -* en 3 C: ;:::;: ro ~!':' 0 0 < CD .., D> ca CD z 0 m :::0 CD "O 0 @" -u D) cc CD w CX) 0 -CJ1 e HITACHI Reactor Pressure Vessel Coverage Calculation Sheet LaSalle L2R14 N6B Nozzle to Shell Weld Spring 2013 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 so* T-Scan CS4 UCl A 9.1 9.1 13.4% 109.6 6.7% so* T-Scan css t-V) A 59.0 43.5 63.9% 109.6 31.9% 0.0 0 -so* P-Scan (S4 UCl A 9.1 4.6 6.8% 109.6 3.4% so* P-Sean css FV> A 59.0 24.2 35.5% 109.6 17.8% --so* T-Scan CS4 UC) 60°T-Scan(S6t-V) so* P-Scan (S4 UCl so* P-Scan (S6 FV> so* T-Scan CS4 UC> 60° T-Scan (S6 FV) so* P-Sean {S4 UC) 60° P-Scan (S6 FV) % Total Composite Coverage= 59.8% 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. e R ... o Sl23ID5 r () (J) C :J ;:::;: (f) :J ,-+ CD m < :J Q. rO -* en 3 C: -*..., .-CD ~!':' () 0 < CD ru cc CD z 0 m ::0 CD "CJ 0 I ~~ITACHI --1 Wall Thickness -.--i Site: LaSalle Unit l Report No; ll Profile Sheet Project: !2Rl4 3rd lnterval{g!J.d Period .. ---** ~-.--~-*~ I System: Bl! I PY 4 I I ! I Component 10 Number: IRR-2001-03 Posioon I ()" I *90" I 180" I 270' [ID III rn [!] [fil l I NIA l.197' NIA NIA Crown Height: 2 I NIA 1.667' NIA NIA Crown Width: 1..2" 3 I NIA I 1.556" I NIA I NIA I Ringer Header \ii Sweep-o-let UPST Component: ONST Component Nominol Diameter: 16.(1' 4 I NIA I u63" I NIA I NIA NIA NIA NIA Weld Length: 48.0" ! FLOW* s 0.880 -u !l) co CD (,J I <t. co 0 -01 I ,;5* I lfS* ~l.OJ!Jt.. t:=. lt!i~w::a~ C_ Drownby: ---, !! 2/20/201J j _.!)_~ ~~h_ 1:JJ:!117 Level: Dote: I GE Reviewed By: :~-= Level: Dote: ----I *------.. ---------------

Page z_or8J r 0 Cl) C ::, ;::::;: I'.) -I ::,-a: en ::, CD m <::, ~(") re -* en 3 C: -*-, CD CD C. I'.) o** 0 < CD ru co CD z 0 m ::a CD "C 0

-0 !ll cc CD 0 0 -a, e ------------Site: Unit: Re port No:

  • HITACHI. ~, -~---~ .. ~.=-=-=.-=-=~-~--

j I Profile Sheet Project: LaSalle /.2Rl4 3rd Interval/2nd Period System: Position O' 90" 1 l.lD" NIA 2 l27fY' NIA 3 I l.350" NIA " I 5 I f~-. '-~ t~: __ _ NIA NIA NIA NIA David Hancock Drown by. RR --r--Component ID Number. 180' 27fJ> -NIA NIA Crown Height NIA NIA Crown Width: NIA NIA Nominol Diameter:

NIA NIA NIA NIA Weld Length: IRR-2001--03 FLUSH l.2" 16.11' fl!!!! \ \ m 12 Ring Header UPST Component Cf. r---~, t' : :y ~-r----!! mo120~ I _J , 'x:S:P ./ zfu/r_) Level: Dote: I GERe>A~~-Levet Dote: ___i_ _____________________ _ t I]] FLOW* 4 SweeP:9::let DNST Component

=

Poge 3 of e -----------------. -----r 0 (f) C ::I ;::;: N -I ::I" a: en ::I CD m < ::I ~C') ro -* en 3 C -*-, CD CD C. !'? 0 0 < CD ru co CD z 0 m ::a CD "O 0 "U D) cc CD .i:,.. ....>. 0 -.i:,.. 0, ATTQMENT7 Coverage Summary Form LaSalle Unit: _0_2_ Date: 02/20/2013 REPORT NUMBER: L2R14-026 omponent/ EPN: _IR_R_-2_0_0_1_-0_3 ________________________ System: Page ER-~-010 Revision 4 4 of 8 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. 48.0" Len th Circumference 18:1 Measured D Calculated 0.D. Diameter x Pi Number of Angles Utilized lal Upstream O & 180 (AU1) See Comments Percent% Coverage Obtained :--,:86% (Upstream + Dnstream, etc.) / # of Scans 15.2 TV (L) x 1.os 0/'ll x~ (T) 0.0 R 0.0 (L) X __!!:Q_ 0/'J) X 0.0 (T} ial Downstream o & 180 {AD1) 14.4 TV ~(L)x~r,N) x~(T) 14.4 R 29.0 (L) x 0N) x~ (T) lal Upstream 90 & 270 (AU2) 15.4 TV ~(L)x 1.05 0/'I) X ...QI!_ (T} 0.0 R _0_.0_(L) X ___Q&_ 0N) X _!!:.9_ (T) *a1 Downstream 90 & 270 (AD2) 11.2 TV ~(L)x 1.20 0/'I) x~(T) 0.0 R _0_.0_(L) X 0.0 0N) X 0.0 (T) Circ Facing Clockwise (CW) __!QQ_ % Coverage No restrictions to circumferential scanning Circ Facing Counter Clockwise (CCW) __!QQ_ % Coverage No restrictions to clrcumferential scanning otal examination all axial scans 100% Axial Upstream 43.8% Axial Dnstream 15.2 (AU1) +_1_5.4_ (AU2) = 30.6 (TV) -14.4 (AD1) + 11.2 (AD2) = 25.6 (TV) -0.0 (A) = 30.6 (A) / 30.6 14.4 (R) = ---1.!+/-._ (A} / 25.6 (TV) X 100 = _ (TV) X 100 = __ 43'""".8'--- 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 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 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: r 0 (J) C :J ;::;: :J ..+ m < :J C) C: g ~-..+ CD 8. !':' 0 0 < CD .., D) cc CD z 0 m ::0 CD "C 0 ;:i. CJ) "'U Q) co CD .i,. N 0 -C1I ** _J __ Wall Thickness HITACHI Profile Sheet ~-**~---~~~-+---System: RR Component ID Number: IRR-2001-04 Position o* 90* 180° 270° 1 0.85 NIA NIA NIA Crown Height: FLUSH 2 0.84" NIA NIA NIA Crown Width: 1.0" 3 1.03" NIA NIA NIA Nominal Diameter: 16.0 4 1.20 NIA NIA NIA 5 NIA NIA NIA NIA Weld Length: 48.0 FLOW 1£b .. :..H.:..., ~. Z/2onoD ~"2F,1"> --~ih.fb Lois: Drown by: Level: Dote: GE Revie~~~---= Level: Dote: Site: Unit: Project: 3rd Interval/2nd Period OJ 2 Ring Header UPST Component: 0° = DSR of dnst elbow SWEEP 0-L.E;T Report No.: LZR14*027 SweeP::5tlet DNST Component: Page l of 0 r 0 (/) C ;:J ;:::;: ;:J ro m < ;:J Q. C: ~-..+ CD !'? 0 0 < CD ..... Q) cc CD z 0 m :::u CD "C 0 @' "'tJ Ill cc CD .i:,.. w 0 -.i:,.. CJl e

  • HITACHI System: RR Position o* go* 1ao* 270° NIA 0.87' NIA NIA 2 NIA 0.87' NIA NIA 3 NIA 1.0" NIA NIA 4 NIA NIA NIA NIA 5 NIA NIA NIA NIA Wall Thickness Profile Sheet Component JD Number: IRR-2001-04 Crown Height: FLUSH Crown Width: 1.0" Nominol Diometer:

16.0 Weld Length: 48.0 !---,-----~-,-~ Site: Project: Ring Header UPST Component: 0° = OSR of dnst elbow \ r--\-1 \ / Unit: 3rd Interval/2nd Period / / I I Report No.: L2Rl4-027 Sweep-a-let DNST Component:

..s..

v FLOW IRR-2.00I.-OL\ 'Ji=~=W/=---Pa-~J-c:k.~Ma-ho=ne=y--/1 ~2/2-0/2_0_13=* =--,j= j*,--* )-~-=*-=~--;w,-, -"2--2**-, .-,;,-=~~~

  • Drawn by: Level: Dote: -level: Dote: --------*-*--*---------------------------------'

Poge of 6 r () Cl) C ::, ;::::;: ::, co m < ::, Q. rO -* C/l 3 C -* -, ,.... CD ~!':' () 0 < CD iil cc CD z 0 m :::0 CD "C 0 "U Dl ca CD 0 -CJ1 LaSalle Unit: 02 -------ATTDMENT7 Coverage Summary Form Date: 02/20/2013 REPORT NUMBER: L2R14-027 omponent / EPN: _IR_R_-_2_00_1_-04 ___________________________ System: Page ER-A.Lis-010 Revision 4 4 of 8 ---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 Number of Angles Utilized See Comments Percent% Coverage Obtained fo'eslji:; (Upstream + Dnstream, etc.) / # of Scans ial Upstream o & 180 (AU1) 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) ial Downstream O & 180 (AD1) 8.9 TV 19.0 {L) X 1.03" r,t,/) X 0.45 (T) 0.0 ial Upstream 90 & 270 (AU2) 11.0 TV 29.0 {L) X 1.05 {)N) X 0.36 (T) 0.0 ial Downstream 90 & 270 (AD2) _ry_ TV 29.0 {L) X 1.0 r,t,/) X 0.39 (T) 11.3 Circ Facing Clockwise (CW) % Coverage No restrictions to circumferential scanning Circ Facing Counter Clockwise (CCW) % Coverage No restrictions to circumferential scanning otal examination all axial scans R R R 100% Axial Upstream 44.1 % Axial Dnstream _6_.3_(AU1) +_1_1_;.0_ {AU2) = 17.3 (TV) ---..c.Bc.c..9_ (AD1) + 11.3 (AD2) = 20.2 (TV) -0.0 {L) X 0.0 {)N) X 0.0 (T) 0.0 (L) X 0.0 ry,/) X 0.0 (T) 29.0 (L) X 1.0 ry,/) X 0.39 (T) 0.0 (R) = 17.3 (A) / 17.3 11.3 (R) = 8.9 (A) / 20.2 (TV) X 100 = _ (TV) X 100 = __ 44_.1 __ 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 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 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 r 0 (/) C ::, ;:;: I\.) -j ::,-a. ci5 ::, ~m <::, Q. rO -* en 3 C: -*.., CD CD 0. !':' 0 0 < CD .., Dl cc CD z 0 m ::0 CD "'C 0 ;:i. en "'U D) ca CD 01 0 ,~, D I l ~V. ::;t f~!(~(*, ru,..::.; 5.EA.. ;:u;._;;,:f (!£'\I 11~h-l:,!l*-,~~-i ~,r i;..-.7t~* !~*~ t..C* : }~,.-! 1,:,-. *~*~*; -~*----. -------I ' fd'< ..... .r::,-$;U: o:-',f'.,f.~1.. lt11f~ NA'.I 757'-ni* II I I I *,1 ... 0 ---~ 0 I f I I --ti' Ht%i'"I w. I E-iJ I I ~,;i I 1:.:. I o,;-CJ I &i* I c,.J [ o.~ I l,ul tr., I 11 *r Ni *1.""' I at !1~*~:..1,,11~;1* 11~~* 11~ li~J* lr:,.1* I ,::.:r i~r h:.: I 1:.a:-1,~J* 1 t'!J""i ns 1 -I --I -l!:'1 I~ I~ I~ I: I~ I~ I" I~ I: I: I: I~ I: I I I I E::t;**-... * .. *-T **-. '/I: !tit -*-1,:-16;" **?*' .,;.;c 1 .. c.u. 1.11,:11;

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