ML17275A202
| ML17275A202 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/29/2017 |
| From: | Jim Barstow Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17275A202 (76) | |
Text
Exelon Generation ~ 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.55a September 29, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 NRG Docket Nos. 50-352 and 50-353
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)(S)(iii), Exelon Generation Company, LLC (Exelon), 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 January 31, 2017, for the Limerick Generating Station, Units 1 and 2. The third ten-year ISi interval complied with the ASME Boiler and Pressure Vessel Code,Section XI, 2001 Edition with 2003 Addenda.
There are no regulatory commitments in this letter.
Exelon requests approval of this relief request by September 29, 2018.
If you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.
Respectfully, Jam Barstow Direc or - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Attachment:
- 1) Relief Request 13R-23 cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, LGS USNRC Project Manager, LGS R. R. Janati, Pennsylvania Bureau of Radiation Protection
ATTACHMENT 1 10 CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
-lnservice Inspection Impracticality--
Revision o (Page 1 of 14)
- 1. ASME Code Component(s) Affected Code Class: 1, 2, &3
Reference:
IWB-2500, Table IWB-2500-1, IWC-2500, Table IWC-2500-1, IWF-2500, Table IWF-2500-1, ASME Code Case N-460 ASME Code Case N-578-1, Table 1 Examination Category: B-A, B-D, C-B, F-A, R-A Item Number: 81 .12, 83.90, C2.21, C2.22, F1 .40, R1 .11, R1 .20
Description:
Limited Examination Coverage Component Number: See Tables l3R-23.1 and l3R-23.2 for a list of Component IDs
2. Applicable Code Edition and Addenda
The Limerick Generating Station (LGS), Units 1 and 2 third interval lnservice Inspection (ISi) program was based on the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel (B&PV) Code,Section XI, 2001 Edition through the 2003 Addenda.
LGS, 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 10 CFR 50.55a 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 l3R-23.1 and l3R-23.2 identify if the examinations were performed in accordance with the requirements of ASME,Section XI, Appendix VIII.
- 3. Applicable Code Requirements The extent of examination requirement for Examination Category B-A, Item Number 81 .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 83.90, per Table IWB-2500-1, requires a volumetric examination of all nozzle-to-vessel welds. During the third interval, LGS, Units 1 and 2 was approved to use ASME Code Case N-702 in a Safety Evaluation Report (SER) dated September 9, 2010 (ML102390467) for Relief Request 13R-14. Also, as allowed by ASME Code Case N-613-1, LGS, Units 1 and 2 performed a volumetric examination using a reduced examination volume (A-B-C-D-E-F-G-H) of Figures 1, 2, and 3 of the Code Case in lieu of the previous examination volumes of ASME Section XI, Figures IWB-2500-7(a), (b),
and (c).
The extent of examination requirement for Examination Category C-B, Item Number C2.21, per Table IWC-2500-1, requires a volumetric and surface examination of the nozzle-to-shell weld. Note 4 in Table IWC-2500-1 states, in the case of multiple vessels of similar design, size, and service (such as steam generators, heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels.
ATTACHMENT 1 10 CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 1o CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality-Revision O (Page 2 of 14)
The extent of examination requirement for Examination Category C-B, Item Number C2.22, per Table IWC-2500-1, requires a volumetric examination of the nozzle inside radius section. Note 4 in Table IWC-2500-1 states, in the case of multiple vessels of similar design, size, and service (such as steam generators, heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels.
The extent of examination requirement tor Examination Category F-A, Item Number F1 .40, per Table IWF-2500-1, requires a VT-3 visual examination of 100% of the supports. Note 3 in Table IWF-2500-1 states, tor multiple components other than piping, within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
The extent of examination requirement for Examination Category R-A, Item Number R1 .11 and 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. Relief Request 13R-02 was submitted, and was approved by the NRC in a SER dated March 11, 2008 (ML080500584) 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 includes several Class 3 and Non-Class welds that fall within the BER Augmented Inspection Program. One of the RI-ISi components included in this relief is an ISi Class 3 weld. The item number tor this component in Table 13R-23.1 is listed as N/A since there is no equivalent ASME Section XI item number tor Class 3 piping welds.
LGS, Units 1 and 2 adopted ASME Code Case N-460 ("Alternative Examination Coverage tor Class 1 and Class 2 Welds,Section XI, Division 1"), which defines "essentially 100%" as greater than 90% coverage of the examination volume or surface area, as applicable. The 90% minimum coverage was applied to all surface and volumetric examinations required by ASME Section XI.
- 4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested on the basis that conformance with these ASME Section XI Code requirements is impractical as conformance would require extensive structural modifications to the component or surrounding structure.
Due to the original design of these components, it is not feasible to effectively perform the examinations to the extent required for welds, nozzle inside radius sections, and supports, greater than 90% of the volume and/or area. Therefore, relief is requested on the basis that the ASME Section XI Code requirements to examine these components are impractical due to physical obstructions, plant location, and/or component geometry.
LGS, Units 1 and 2 is unable to satisfy the ASME Section XI Code requirements to perform a visual or volumetric examination of these components due to the physical component configuration, interference from permanent plant equipment, single-sided access, etc. LGS, Units 1 and 2 would incur significant engineering, material, and installation costs to perform such modifications without a compensating increase in the level of quality and safety.
ATTACHMENT 1 1o CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 3 of 14)
Component supports, Examination Category F-A, Item Number F1 .40, for the Emergency Service Water (ESW) and Residual Heat Removal Service Water (RHRSW) system pumps were included in this relief. Per Note 3 in Table IWF-2500-1, " ... only one of the multiple components are required to be examined." Of the four ESW and four RHRSW pumps, the requirement would be to examine two supports, one upper and one lower support, for an ESW pump and a RHRSW pump. A qualified VT-3 visual examination could not be performed due to the clarity of the water within the pump bays and the buildup of scale around the supports. It is possible to drain the pump bays, but this would place both units into a 72-hour shutdown LCO. LGS, Units 1 and 2 have not attempted to use the sluice gates for this examination because the actions to drain and refill the pump pits cannot be completed within the 72-hour LCO. A best effort inspection was performed during maintenance activities, which are listed in the tables below and the visual inspections are detailed in Enclosure 1.
NOE summary sheets were not completed for all of the inspections performed since a qualified VT-3 was not performed. One representative NOE summary sheet, for these pump supports, is provided in Enclosure 1.
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 coverage. This determination was made based on comparison of configurations, delta core damage frequency (CDF) values, the systems involved, and inspection history. During outages, when situations were identified where coverage was an issue, LGS, Units 1 and 2 personnel reviewed the systems for alternatives.
Tables l3R-23.1 and 13R-23.2 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.
Required surface exams were performed in addition to the required volumetric examinations for Examination Category C-8, C2.21 welds with greater than 90%
coverage. No unacceptable indications were detected during these exams.
Based on the above explanation, LGS, Units 1 and 2 request relief to perform examinations without achieving coverage when required coverage is impractical.
- 5. Burden Caused by Compliance Compliance with the applicable ASME Section XI Code volumetric examination requirements can only be accomplished by redesigning and refabricating the subject and/or surrounding components. For the Examination Category F-A, Item Number F1 .40 components, compliance with the applicable ASME Section XI Code visual examination requirements can only be accomplished by shutting down both units and
ATTACHMENT 1 10 CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 4 of 14) installing the sluice gate and draining the pump pits. Based on this, the ASME Section XI Code requirements are deemed impractical in accordance with 10 CFR 50.55a(g)(5)(iii).
- 6. Proposed Alternative and Basis for Use LGS, Units 1 and 2 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-23.1 and l3R-23.2. Due to the physical interferences causing these limitations, there are no alternative examination techniques currently available to increase coverage.
- 7. Duration of Proposed Alternative Relief is requested for the third ten-year ISi interval for LGS, Units 1 and 2.
- 8. Precedents A similar relief request was approved for the Oyster Creek Nuclear Generating Station in an NRG Safety Evaluation Report dated May 1, 2015 (ML15097A153).
ATTACHMENT 1 10 CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 5 of 14)
Table 13R-23.1 Limerick Generating Station, Unit 1 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Component ID Weld Operating Exam Angle/
Requirements Category/ Outage Material of Diameter/ Actual VIII (Summary Description Conditions Frequency (MHz) I Remarks (Figure No.) Item Examined Construction Thickness Coverage Qualified Number) (System)' (Pressure I Mode and Method Number Exam Temperature)
The examination was limited due to proximity of lhe N17B nozzle. Four Shell Ring IWB-2500-2 o* / 2.25 / Long. indications were found during the 45* T-BF No. 2 Vertical B-A N/A / 6-7/16 1045 psig I 45* / 1.0 I Shear Volumetric 1R14 SA-533 Gr. B 86.9% Yes scan. The indications were evaluated (600290) Seam Weld (UT)
B1 .12 in. 535"F so* I 2.0 I Long. and determined acceptable per ASME (RPV) 70' / 2.0 I Long.
Section XI.
(Enc. 1 Pg. Nos. 14, 15, & 23)
Recirculation The examination was limited due to SA-508 Cl. 2 Inlet *s* Loop IWB-2500-7 12 in. ID I nozzle configuration. Essentially 100%
N2A B-D (Nozzle) 1045 psig I Nozzle to Volumetric 1R12 6-7/16 in. @ 60'/ 3.0 I R. Long. 76.0% Yes coverage was achieved for inner radius (600700) 63.90 SA-533 Gr. B 535"F Vessel Weld (UT) RPV Shell examination for this nozzle.
(Shell)
(RPV) (Enc. 1 Pg. No. 5)
Recirculation The examination was limited due to SA-508CI. 2 Inlet "A" Loop IWB-2500-7 12 in. ID/ nozzle configuration. Essentially 100%
N2F B-D (Nozzle) 1045 psig I (600850)
Nozzle to Volumetric B3.90 1R12 SA-533 Gr. B 6-7/16 in. @
535°F so*/ 3.0 I R. Long. 76.0o/o Yes coverage was achieved for inner radius Vessel Weld (UT) RPV Shell examination for this nozzle.
(Shell)
(RPV) (Enc. 1 Pg. No. 6)
Main Steam The examination was limited due to SA-508 Cl. 2 "D" Loop IWB-2500-7 26 in. ID I nozzle configuration. Essentially 100%
N3D B-D (Nozzle) 1045 psig I Nozzle to Volumetric 1R12 7-1/4 in. @ 60' / 3.0 I R. Long. 75.1% Yes coverage was achieved for inner radius (601090) 63.90 SA-533Gr. B 535°F Vessel Weld (UT) RPV Shell examination for this nozzle.
(Shell)
(RPV) (Enc. 1 Pg. No. 7)
Note:
- 1. The following systems and their abbreviations are listed here: Core Spray (CS), Emergency Service Water (ESW), Main Stearn (MS), Residual Heat Removal (RHR), Residual Heat Removal Service Water (RHRSW), Reactor Water Cleanup (RWCU),
Reactor Pressure Vessel (RPV), and Reactor Recirculation (RR)
ATTACHMENT 1 10 CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 6 of 14)
Table 13R-23.1 Limerick Generating Station, Unit 1 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Component ID Weld Operating Exam Angle/
Requirements Category/ Outage Material of Diameter/ Actual VIII (Summary Description Conditions Frequency (MHz) I Remarks (Figure No.) Item Examined Construction Thickness Coverage Qualified Number) (System)1 (Pressure I Mode and Method Number Exam Temperature)
The examination was limited due to nozzle configuration and proximity of Feedwater the N 11 8 nozzle reinforcement. Manual SA-508Ci. 2 "D" Loop IW8-2500-7 12 in. ID I inspection of this component requires N4D 8-D (Nozzle) 1045 psig I 60" I 3.0 I Long.
Nozzle to Volumetric 1R15 S-7/1Sin.@ 87 .3% Yes an inspection interval of 4 years.
(601210) 83.90 SA-533 Gr. 8 535°F 55* I 3.0 I Shear Vessel Weld (UT) APV Shell Essentially 100% coverage was (Shell)
(APV) achieved for inner radius examination for this nozzle.
(Enc. 1 Pg. Nos. 19, 20, & 23)
Core Spray The examination was limited due to SA*508CI. 2 "A" Loop IW8-2500-7 12 in. ID I nozzle configuration. Essentially 100%
N58 8-D (Nozzle) 1045 psig I Nozzle to Volumetric 1R12 S-7/1S in.@ so* / 3.o I R. Long. 77.S% Yes coverage was achieved for inner radius (601330) 83.90 SA-533 Gr. 8 535°F Vessel Weld (UT) RPV Shell examination lor this nozzle.
(Shell)
(RPV) (Enc. 1 Pg. No. B)
CAD Return The examination was limited due to SA-508CI. 2 (Capped) IW8-2500-7 5-1/8 in. ID I nozzle configuration. Essentially 100%
N9 8-D (Nozzle) 1045 psig I Nozzle to Volumetric 1R12 S-7/1S in.@ 60" / 3.0 I R. Long. 80.5% Yes coverage was achieved for inner radius (601460) 83.90 SA-533 Gr. 8 535°F Vessel Weld (UT) APV Shell examination for this nozzle.
(Shell)
(APV) (Enc. 1 Pg. No. 9)
LPCl"D" The examination was limited due to SA-508CI. 2 Loop Nozzle IW8-2500-7 12 in. ID I nozzle configuration. Essentially 100%
N178 8-D (Nozzle) 1045 psig I to Vessel Volumetric 1A12 S-7/1S in.@ 60' / 3.0 I A. Long. 77.S% Yes coverage was achieved for inner radius (601520) 83.90 SA-533Gr. 8 535°F Weld (UT) APV Shell examination for this nozzle.
(Shell)
(RPV) (Enc. 1 Pg. No. 10)
SA-105 IWC-2500*4(a)
AHR-HXAA* Nozzle N4 Forging 20 in. OD/ The examination was limited due to or(b) C-8 285 psig I so*/ 2.25 /Shear N41R Inner Radius 1R15 (Nozzle) 1-1/4 in.@ 70.0% No nozzle configuration.
Volumetric C2.22 240°F 79* / 2.25 / Shear (244801) (RHR) SA*51S Gr. 70 HX Shell (Enc. 1 Pg. No. 17)
(UT)
(Shell)
Note:
- 1. The following systems and their abbreviations are listed here: Core Spray (CS), Emergency Service Water (ESW), Main Steam (MS), Residual Heat Removal (RHR), Residual Heat Removal Service Water (RHRSW), Reactor Water Cleanup (RWCU),
Reactor Pressure Vessel (RPV), and Reactor Recirculation (RR)
ATTACHMENT 1 10 CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality-Revision O (Page 7 of 14)
Table 13R-23.1 Limerick Generating Station, Unit 1 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Component ID Weld Operating Exam Angle/
Requirements Category I Outage Material of Diameter/ Actual VIII Remarks (Summary Description Conditions Frequency (MHz) I (Figure No.) Item Examined Construction Thickness Coverage Qualified Number) (System)' (Pressure/ Mode and Method Number Exam Temperature)
IWB-2500-8(c) 6" Valve HV- IWB-2500-9 The examination was limited due to N/A 45* / 2.25 I Shear AW 138 44-1F040to IWB-2500-10 SA-312 6 in. NPS/ 1045 psig I single sided access (valve configuration (Class 3 1R15 50.0% Yes (375231) Pipe IWB-2500-11 TP316L 0.432 in. 535°F 10* / 2.25 / Shear interference).
BER weld) (Enc. 1 Pg. No. 18)
IWB-2500-8(c) Preservice examination due to valve 12" HV-051- IWB-2500-9 SA-358 replacement. The examination was DCA-104-03 45* / 1.5 / Shear 1F0508 to IWB-2500-10 R-A TP316L 12 in. NPS/ 1280 psig / limited due to single sided access and SW801 Pup Piece IWB-2500-11 Rl .11 1R12 (0.02% max 0.844 in. 539°F oo* / 2.0 I Long. 47.8% Yes long seam area of interest (valve (117084) PT (AHR) Volumetric Carbon) configuration interference).
(UT) (Enc. 1 Pg. No. 3)
IWB-2500-8(c)
Preservice examination due to valve 12" Pup IWB-2500-9 DCA-104-01 Piece to HV- IWB-2500-10 R-A 12 in. NPS/ 1280 psig I oo* 12.0 I Long. replacement. The examination was SW1402 1R12 SA-376 TP316 45* / 1.5 /Shear 50.0% Yes limited due to single sided access 051-1F0508 IWB-2500-11 Rl.11 0.688 539°F (117106) PT (valve configuration interference).
(AHR) Volumetric (Enc. 1 Pg. No. 4)
(UT) 38" / 2.0 IR. Long. A site specific mockup and procedure IWB-2500-8(c) 49* / 2.0 I R. Long. were required to perform this 12" Pipe to IWB-2500-9 SA-358 DCA-318-1 45* / 1.5 / Shear examination. The examination was Safe End IWB-2500-10 R-A TP316L 12 in. NPS I 1045 psig I FW1 1R12 66. I 2.0 I R. Long. 77.4% Yes limited due to transducer liftoff at the (Az. 135 Deg) IWB-2500-11 Rl .11 (0.02% max 0.688 in. 535°F (602270) 51 * / 2.0 I R. Long. upstream weld toe and areas of the (AHR) Volumetric Carbon) 45* / 2.0 IR. Long. weld build up.
(UT) 60" 12.0 IR. Long. (Enc. 1 Pg. Nos. 11 & 12)
Note:
- 1. The following systems and their abbreviations are listed here: Core Spray (CS), Emergency Service Water (ESW), Main Steam (MS), Residual Heat Removal (RHR), Residual Heat Removal Service Water (RHRSW), Reactor Water Cleanup (RWCU),
Reactor Pressure Vessel (RPV), and Reactor Recirculation (RR)
ATTACHMENT 1 10 CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality-Revision O (Page 8 of 14)
Table 13R-23.1 Limerick Generating Station, Unit 1 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Component ID Weld Operating Exam Angle/
Requirements Category/ Outage Material of Diameter/ Actual VIII (Summary Description Conditions Frequency (MHz) I Remarks (Figure No.) Item Examined Construction Thickness Coverage Qualified Number) (System)' (Pressure I Mode and Method Number Exam Temperature)
IWB-2500-8(c) 12" Valve 51- IWB-2500-9 SA-358 The examination was limited due to RHB 003 1F065B to IWB-2500-10 A-A TP316L 12 in. NPS I 1045 psig I 45" I 1.5 I Shear single sided access (valve configuration 1A15 50.0% Yes (116790) Pipe IWB-2500-11 Al.11 (0.02% max 0.688 in. 535°F 60" I 2.0 I A. Long. interference).
(AHR) Volumetric Carbon) (Enc. 1 Pg. No. 16)
(UT)
IWB-2500-8(c) 22" Pipe to IWB-2500-9 SA-358 The examination was limited due to RAB028 22*x12* IWB-2500-10 R-A TP316L 22 in NPS/ 1045 psig I 60" 12.0 I Long. single sided access (sweepolet 1A14 50.0% Yes (110640) Sweep-o-let IWB-2500-11 A1.20 (0.02% max 1.009 in. 535°F 45" / 1.51 Shear configuration interference).
(RR) Volumetric Carbon) (Enc. 1 Pg. No. 13)
(UT)
IWB-2500-8(c)
IWB-2500-9 The examination was limited due to 2" Pipe to AW 118 IWB-2500-10 A-A SA-312 2 in. NPS I 1045 psig I 70" I 2.25 /Shear single sided access (elbow Elbow 1A12 50.0% Yes (114250) IWB-2500-11 Al.20 TP316L 0.218 in. 535°F 45" / 2.25 /Shear configuration interference).
(RWCU)
Volumetric (Enc. 1 Pg. No. 2)
(UT)
IWB-2500-8(c) 20*x20*x20* IWB-2500-9 SA-358 The examination was limited due to 45" / 1.5 /Shear ARB 004 Teeto28" IWB-2500-10 A-A TP316L 28 in. NPS I 1045 psig I single sided access (tee configuration 1A15 60" / 1.5 / Shear 50.0% Yes (110150) Pipe IWB-2500-11 A1 .20 (0.02%max 1.285 in. 535°F interference).
70 " / 2.0 I R. Long.
(RR) Volumetric Carbon) (Enc. 1 Pg. No. 21)
(UT)
Note:
- 1. The following systems and their abbreviations are listed here: Core Spray (CS), Emergency Service Water (ESW), Main Steam (MS), Residual Heat Removal (RHR), Residual Heat Removal Service Water (RHRSW), Reactor Water Cleanup (RWCU),
Reactor Pressure Vessel (RPV), and Reactor Recirculation (RR)
ATTACHMENT 1 10 CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision 0 (Page 9 of 14)
Table 13R-23.1 Limerick Generating Station, Unit 1 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Component ID Weld Operating Exam Angle/
Requirements Category/ Outage Material of Diameter/ Actual VIII (Summary Description Conditions Frequency (MHz) I Remarks (Figure No.) Item Examined Construction Thickness Coverage Qualified Number) (System)' (Pressure/ Mode and Method Number Exam Temperature)
Examinations of the D ESW pump upper and lower seismic restraints were limited due to spray pond water clarity.
Water clarity could not be improved such that a qualified VT-3 examination D ESW Pump in accordance with the requirements of OD-P548- Lower IWF-1300-1 NIA ASME Section XI, Subsection IWA-F-A SRUP Seismic Visual (May NIA N/A N/A NA 0.0% N/A 2210 could be performed. Draining the F1 .40 (760133) Restraint (VT-3) 2012) ESW pump wetwell would place both (ESW) LGS Units 1 and 2 in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO.
The examination would require draining of the ESW pump wetwell, cleaning the seismic restraints, performance of a qualified VT-3 examination, and refilling the wetwell within the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> window; therefore, this exam was not attempted. Best effort examinations of the D ESW pump upper and lower seismic restraints were performed using a camera and no signs of structural damage were identified. A representative examination datasheet is D ESW Pump included and representative OD-P548- Lower IWF-1300-1 N/A examination videos are available onsite F-A for review. Additional best effort SALO Seismic Visual (May N/A N/A NIA NA 0.0% N/A F1.40 examinations were performed on the (760135) Restraint (VT-3) 2012)
(ESW) upper and lower seismic restraints for the B ESW (June 2013) and C ESW (Dec. 2014) pumps, with no signs of structural damage identified.
Examination is only required on one of the pumps in the group, so the examinations for only one pump are listed in this table. (Enc. 1 Pg. No. 22)
Note:
- 1. The following systems and their abbreviations are listed here: Core Spray (CS), Emergency Service Water (ESW), Main Steam (MS), Residual Heat Removal (RHR), Residual Heat Removal Service Water (RHRSW), Reactor Water Cleanup (RWCU),
Reactor Pressure Vessel (RPV), and Reactor Recirculation (RR)
ATTACHMENT 1 10 CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 10 of 14)
Table 13R-23.1 Limerick Generating Station, Unit 1 List of Components with Limited Examination Coverage Normal Exam Exam Appendix Component ID Weld Operating Exam Angle/
Requirements Category/ Outage Material of Diameter/ Actual VIII (Summary Description Conditions Frequency (MHz) I Remarks (Figure No.) Item Examined Construction Thickness Coverage Qualified Number) (System)' (Pressure I Mode and Method Number Exam Temperature)
Examinations of the A RHRSW pump upper and lower seismic restraints were limited due to spray pond water clarity.
No actions could be taken to improve spray pond water clarity such that a qualified VT-3 examination in ARHRSW accordance with the requirements of OA-P506- Pump Upper IWF-1300-1 N/A ASME Section XI, Subsection IWA-F-A SRUP Seismic Visual (Decembe N/A N/A N/A NA 0.0% N/A 2210 could be performed. The RHRSW Fl.40 (760203) Restraint (VT-3) r 2011) pump wetwell can be drained, however (RHRSW) this places both LGS Unit 1 and 2 in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO. The work required to completely drain the RHRSW pump wetwell, clean the seismic restraints, and perform a qualified VT-3 examination cannot be completed within the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> window and was not attempted. Best effort examinations of the A RHRSW pump upper and lower seismic restraints were performed using a camera and no signs of structural damage were identified. A representative examination datasheet is included and representative ARHRSW examination videos are available onsite OA-P506- Pump Lower IWF-1300-1 N/A for review. Additional best effort F-A SALO Seismic Visual (Decembe N/A N/A N/A NA 0.0% N/A examinations were performed on the (760205) Fl.40 Restraint (VT-3) r2011) upper and lower seismic restraints for (RHRSW) the B RHRSW (Aug. 2014) and C RHRSW (Mar. 2013) pumps, with no signs of structural damage identified.
Examination is only required on one of the pumps in the group, so the examinations for only one pump are listed in this table. (Enc. 1 Pg. No. 22)
Note:
- 1. The following systems and their abbreviations are listed here: Core Spray (CS), Emergency Service Water (ESW), Main Steam (MS), Residual Heat Removal (RHR), Residual Heat Removal Service Water (RHRSW), Reactor Water Cleanup (RWCU),
Reactor Pressure Vessel (RPV), and Reactor Recirculation (RR)
ATTACHMENT 1 10 CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
-lnservice Inspection Impracticality--
Revision O (Page 11 of 14)
Table 13R-23.2 Limerick Generating Station, Unit 2 List of Components with Limited Examination Coverage Component ID Weld Exam Exam Outage Material of Diameter/ Normal Exam Angle/ Actual Appendix Remarks (Summary Description Requirements Category I Examined Construction Thickness Operating Frequency I Mode Coverage VIII Number) (System)' (Figure No.) Item Conditions Qualified and Method Number (Pressure I Exam Temperature)
Recirculation The examination was limited due to Outlet"A" SA-508CI. 2 IW8-2500-7 28 in. ID I nozzle configuration. Essentially 100%
N1A Loop Nozzle 8-D (Nozzle) 1045 psig I 55° I 1.0 I Shear Volumetric 2R10 6-7/16 in.@ 83.5% Yes coverage was achieved for inner radius (703900) to Vessel (UT) 83.90 SA-533 Gr. 8 RPV Shell 535°f so* I 3.0 I A. Long. examination for this nozzle.
Weld (Shell)
(Enc. 2 Pg. Nos. 25 & 26)
(RPV)
Recirculation SA-508CI. 2 o* I 2.25 I Long. The examination was limited due to Inlet "A" Loop IW8-2500-7 12 in. ID/ 45" I 1.0 I Shear proximity of N88 nozzle. Essentially N2H 8-D (Nozzle) 1045 psig I Nozzle to Volumetric 2R09 6-7/16 in. @ 55" I 1.0 I Shear 80.1% Yes 100% coverage was achieved for inner (706600) 83.90 SA-533Gr. 8 535°F Vessel Weld (UT)
(Shell)
RPV Shell so* I 2.0 I Long. radius examination for this nozzle.
(RPV) 70" I 2.0 I Long. (Enc. 2 Pg. Nos. 4, 5, 6, & 37)
Feedwater SA-508CI. 2 o* I 2.25 I Long. The examination was limited due to
- 0* Loop IW8-2500-7 12 in. ID/ 45* I 1.0 I Shear nozzle configuration. Essentially 100%
N48 8-D (Nozzle) 1045 psig I Nozzle to Volumetric 2R10 6-7/16 in.@ 55" I 1.0 I Shear 80.3% Yes coverage was achieved for inner radius (709000) 83.90 SA-533 Gr. 8 535°f Vessel Weld (UT)
(Shell)
RPV Shell so* I 2.0 I Long. examination for this nozzle.
(RPV) 70" I 2.0 I Long. (Enc. 2 Pg. Nos. 27 & 28)
The examination was limited due to Feedwater SA-508CI. 2 nozzle configuration and the proximity "D" Loop IW8-2500-7 12 in. ID I N4D 8-D (Nozzle) 1045 psig I 55* I 1.0 I Shear of the N 11 8 nozzle. Essentially 100%
Nozzle to Volumetric 2R12 6-7/16 in.@ 84.2% Yes (709600)
Vessel Weld (UT) 83.90 SA-533Gr. 8 RPV Shell 535°f so* I 3.0 I Long. coverage was achieved for inner radius (Shell) examination for this nozzle.
(RPV)
(Enc. 2 Pg. Nos. 34, 35, & 37)
Feedwater SA-508CI. 2 o* I 2.25 I Long. The examination was limited due to "E" Loop IW8-2500-7 12 in. ID I 45" I 1.0 I Shear nozzle configuration. Essentially 100%
N4E 8-D (Nozzle) 1045 psig I Nozzle to Volumetric 2R10 6-7/16 in.@ 55' I 1.0 I Shear 80.3% Yes coverage was achieved for inner radius (709900) 83.90 SA-533Gr. 8 535°f Vessel Weld (UT)
(Shell)
RPV Shell so* I 2.0 I Long. examination for this nozzle.
(RPV) 70' I 2.0 I Long. (Enc. 2 Pg. Nos. 29 & 30)
Note:
- 1. The following systems and their abbreviations are listed here: Core Spray (CS), Emergency Service Water (ESW), Main Steam (MS), Residual Heat Removal (RHR), Residual Heat Removal Service Water (RHRSW), Reactor Water Cleanup (RWCU),
Reactor Pressure Vessel (RPV), and Reactor Recirculation (RR)
ATTACHMENT 1 10 CFR 50.SSa Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O
{Page 12 of 14)
Table 13R-23.2 Limerick Generating Station, Unit 2 List of Components with Limited Examination Coverage Component ID Weld Exam Exam Outage Material of Diameter/ Normal Exam Angle/ Actual Appendix Remarks (Summary Description Requirements Category/ Examined Construction Thickness Operating Frequency I Mode Coverage VIII Number) (System)' (Figure No.) Item Conditions Qualified and Method Number (Pressure I Exam Temperature)
The examination was limited due to Feedwater SA-508CI. 2 o* I 2.25 / Long. proximity of insulation by the stabilizer "F' Loop IW8-2500-7 12 in. ID I 45* / 1.0 I Shear N4F 8-D (Nozzle) 1045 psig I brackets. Essentially 100% coverage Nozzle to Volumetric 2R09 6-7/16 in.@ 55" / 1.0 I Shear 80.1% Yes (710200) 83.90 SA-533Gr. 8 535"F was achieved for inner radius Vessel Weld (UT) RPV Shell 60" / 2.0 I Long.
(Shell) examination for this nozzle.
(RPV) 70" I 2.0 I Long.
(Enc. 2 Pg. Nos. 7, 8, 9, & 37)
Core Spray The examination was limited due to SA-508CI. 2
'A' Loop IW8-2500-7 12 in. ID/ nozzle configuration. Essentially 100%
N58 8-D (Nozzle) 1045 psig I 55" / 1.0 I Shear Nozzle to Volumetric 2R09 6-7/16 in.@ 85.3% Yes coverage was achieved for inner radius (710800) 83.90 SA-533 Gr. 8 535°F 60" / 3.0 I A. Long.
Vessel Weld (UT) RPV Shell examination for this nozzle.
(Shell)
(RPV) (Enc. 2 Pg. Nos. 10 & 11)
Jet Pump The examination was limited due to lnstrumentati SA-508 Cl. 2 IW8-2500-7 6 in. OD/ nozzle configuration. Essentially 100%
N88 on 'A" Loop 8-D (Nozzle) 1045 psig I Volumetric 2R10 6-7/16 in.@ 60"/ 3.0 I A. Long. 83.7% Yes coverage was achieved for inner radius (711300) Nozzle to 83.90 SA-533 Gr. 8 535"F (UT) RPV Shell examination for this nozzle.
Vessel Weld (Shell)
(Enc. 2 Pg. Nos. 31 & 32)
(RPV)
LPCl"C' The examination was limited due to SA-508CI. 2 Loop Nozzle IW8-2500-7 12 in. ID I nozzle configuration. Essentially 100%
N17D 8-D (Nozzle) 1045 psig I 55" / 1.0 I Shear to Vessel Volumetric 2R09 6-7/16 in.@ 84.7% Yes coverage was achieved for inner radius (712600) 83.90 SA-533Gr. 8 535"F 60" I 3.0 I A. Long.
Weld (UT) RPV Shell examination for this nozzle.
(Shell)
(RPV) (Enc. 2 Pg. Nos. 2 & 3)
IWC-2500-4(a)
Outlet Nozzle SA-350 LF2 The examination was limited due to or(b) 20 in. ID I 45* / 2.25 /Shear 28E-205R N- (N-4) to Shell C-8 (Nozzle) 285 psig I nozzle configuration. 91 % coverage Surface and 2R13 1.0 in.@ 70" / 2.25 /Shear 53.0% No 4-1 (362501) Weld C2.21 SA-516 Gr. 70 240"F was achieved for MT examination.
Volumetric HXShell (AHR) (Shell) (Enc. 2 Pg. No. 36)
(UT)
Note:
- 1. The following systems and their abbreviations are listed here: Core Spray (CS), Emergency Service Water (ESW), Main Steam (MS), Residual Heat Removal (RHR), Residual Heat Removal Service Water (RHRSW), Reactor Water Cleanup (RWCU),
Reactor Pressure Vessel (RPV), and Reactor Recirculation (RR)
ATTACHMENT 1 10 CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
-lnservice Inspection Impracticality--
Revision O (Page 13 of 14)
Table 13R-23.2 Limerick Generating Station, Unit 2 List of Components with Limited Examination Coverage Component ID Weld Exam Exam Outage Material of Diameter/ Normal Exam Angle/ Actual Appendix Remarks (Summary Description Requirements Category/ Examined Construction Thickness Operating Frequency I Mode Coverage VIII Number) (System)' (Figure No.) Item Conditions Qualified and Method Number (Pressure/ Exam Temperature)
IWB-2500-8(c) 38" / 2.0 I R. Long.
IWB-2500-9 SA-358 40" / 2.0 I R. Long.
DCA-420-1 10" Pipe to The examination was limited due to IWB-2500-10 A-A TP316L 10 in. NPS/ 1045 psig I 45* / 1.5 /Shear FW1 Safe End 2A09 72.0% Yes component configuration.
IWB-2500-11 A1 .11 (0.02% max 0.594 in. 535°F 49* / 2.0 I A. Long.
(023900) (CS) (Enc. 2 Pg. Nos. 18 & 19)
Volumetric Carbon) 55" I 2.0 I R. Long.
(UT) 60" / 2.0 I Shear 12" Pipe to IWB-2500-8(c)
DCA-204-1 Check Valve IWB-2500-9 o* I 4.0 I Long. The examination was limited due to HV IWB-2500-10 A-A 12 in NPS/ 1280 psig/ 45* / 1.5 /Shear single sided access (valve configuration SW1502 2A09 SA*376 TP316 50.0% Yes 2F0508 Pup IWB*2500-11 A1 .11 0.688 in. 539°F 60" / 2.0 I R. Long. interference).
(328405)
Piece Volumetric (Enc. 2 Pg. Nos. 14 & 15)
(AHR) (UT)
IWB-2500-8(c) 12" Valve IWB-2500-9 SA-358 The examination was limited due to DCA-204-3 HV IWB-2500-10 A-A TP316L 12 in. NPS I 1280 psig I a* 14.0 I Long.
single sided access (valve configuration SW1101 2F0508to 2A09 45* / 1.5 / Shear 50.0% Yes IWB-2500-11 R1 .11 (0.02% max 0.688 in. 539°F interference).
(323506) Pup Piece 60" / 2.0 I R. Long.
Volumetric Carbon) (Enc. 2 Pg. Nos. 12 & 13)
(AHR)
(UT) 38" / 2.0 IR. Long.
IWB-2500-8(c) 49* I 2.0 I R. Long.
IWB-2500-9 SA-358 The examination was limited due to DCA-418-4 12" Pipe to 45" / 1.5 /Shear IWB-2500-10 A*A TP316L 12 in. NPS/ 1045 psig / component configuration, 8 degree FW1 Safe End 2R09 45* / 2.0 I R. Long. 78.0"lo Yes IWB-2500-11 A1 .11 (0.02% max 0.688 in. 535°F taper between pipe and safe end.
(350600) (AHR) 51" / 2.0 I A. Long.
Volumetric Carbon) (Enc. 2 Pg. Nos. 16 & 17) 60" I 2.0 I R. Long.
(UT) 66" I 2.0 I R. Long.
Note:
- 1. The following systems and their abbreviations are listed here: Core Spray (CS), Emergency Service Water (ESW), Main Steam (MS), Residual Heat Removal (RHR), Residual Heat Removal Service Water (RHRSW), Reactor Water Cleanup (RWCU),
Reactor Pressure Vessel (RPV), and Reactor Recirculation (RR)
ATTACHMENT 1 10 CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
-lnservice Inspection Impracticality--
Revision O (Page 14 of 14)
Table 13R-23.2 Limerick Generating Station, Unit 2 List of Components with Limited Examination Coverage Component ID Weld Exam Exam Outage Material of Diameter/ Normal Exam Angle/ Actual Appendix Remarks (Summary Description Requirements Category/ Examined Construction Thickness Operating Frequency I Mode Coverage VIII Number) (System)' (Figure No.) Item Conditions Qualified and Method Number (Pressure I Exam Temperature)
IWB-2500-8(c)
IWB-2500-9 SA-358 The examination was limited due to DCA-419-1 12" Elbow to IWB-2500-10 A-A TP316L 12 in. NPS I 1045 psig I interference from lugs from a pipe FW7 Pipe 2A10 45" / 1.5 / Shear 70.0% Yes IWB-2500-11 R1 .20 (0.02% max 0.688 in. 535"F support.
(015500) (CS)
Volumetric Carbon) (Enc. 2 Pg. No. 20)
(UT) 26" Valve The examination was limited due to EBB-201-1 HV IWC-2500-7(a)
A-A 26 in. NPS I 1053 psig I physical limitations when scanning in FW33 2F028C to Volumetric 2A10 SA-106Gr. C 45" / 2.25 /Shear 75.0% Yes R1.20 0.928 in. 533°F the axial direction on valve side of weld.
(205500) 26" Pipe ID. (UT)
(Enc. 2 Pg. No. 21)
(MS) 16" Elbow to The examination was limited due to GBB-205-2 IWC-2500-7(a) 45" 15.0 I Shear Valve HV A-A 16 in. NPS I 285 psig I component configuration on FW8 Volumetric 2R10 SA-106 Gr. B 70" I 5.0 I Shear 87.5% Yes 2F021B R1.20 0.375 in. 188"F downstream side of weld.
(406000) (UT)
(AHR) (Enc. 2 Pg. Nos. 22, 23, & 24)
IWB-2500-8(c)
IWB-2500-9 SA-312 DCA-201-1 6"x6"x6" Tee The examination was limited due to tee IWB-2500-10 A-A TP316L 6in. NPS/ 1045 psig I 45" / 2.25 /Shear FW13 to6" Pipe 2R12 76.9% Yes configuration.
IWB-2500-11 R1 .20 (0.02% max 0.432 in. 535"F 70" I 2.25 / Shear (663300) (RWCU) (Enc. 2 Pg. No. 33)
Volumetric Carbon)
(UT)
Note:
- 1. The following systems and their abbreviations are listed here: Core Spray (CS), Emergency Service Water (ESW), Main Steam (MS), Residual Heat Removal (RHR), Residual Heat Removal Service Water (RHRSW), Reactor Water Cleanup (RWCU),
Reactor Pressure Vessel (RPV), and Reactor Recirculation (RR)
Enclosure 1 Limerick Generating Station Unit 1 Third Inservice Inspection (ISi) Interval Limited Coverage Non-Destructive Examination (NDE) Coverage Plots
Enclosure 1 Limerick Generating Station Unit 1 Third Inservice Inspection (ISi) Interval Limited Coverage Non-Destructive Examination (NDE) Coverage Plots
Unit 1
.I Limerick Generating Station Third ISi lnte~al Limited Coverage NOE Coverag,~e....:.P....:.lo~t,,,,s_ _ _ __
Wall Thickness Site: Limerick Unit l I Report No.:
HITACHI Profile Sheet Project L/1Rl2 ll4250
- - I ti GE_ LL . LIAI ,_
System:
Position o* 90*
RWCU 180° 270° c t ID Number. RW ll8 DJ
~12 rn
~
- 4 41 ~
1 0.236 NIA NIA NIA Crown Heigl t FLUSH 2 0.244 NIA NIA NIA I CrownWidtl Not Measurable f!R! Elbow 3 0.245 NIA NIA NIA UPST Component DNST Component Nominal Dia meter: 2.(1' 4 NIA NIA NIA NIA Weld Lengtt 7.11' I
lls LISj ,,~*s_ .i L_1
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Unit 1 Limerick Generating Station Third ISi Interval L~d Coverage NOE Coverag~Plo~ __
~-~~~- -~- ,--
Wall Thickness Site: Limerick Unit ~ Report No.:
HITACHI Profile Sheet Project l/lRl2 117084
~
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System: RHR I
Position o* 90" 180" 210*
Component ID Number: DCA-104-03 W801 w
[)) 121 141 ~
1 NIA NIA NIA NIA Crown Height FLUSH I I I 2 NIA NIA NIA NIA I Crown Width:
-l.O" Valve I
E?lR£ 3 0.723 0.789 0.720 0.739 I UPST Component DNST Component I Nominol Diameter: &Jr I 4 0.742 0.693 0.688 0.625 I
I Weld Length: 40.25" I
i 5 0.886 0.871 0.825 0.820 DC A- ITT'r-'~ 5WBo FLOW.,
4: PaPE V4L\J£ FLow
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Unit 1 Limerick Generating Station Third ISi lnt~al Limited Coverage NOE Coverage Plots Wall Thickness Site: Limerick Unit !. Report No.:
HITACHI Profile Sheet Project Ll1R12 117106
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~ 4 System: RHR Component ID Number: DCA-104-01 W1402 Position o* 90" 180' 270' ((]
l 0.667 0.668 0.642 0.658 OJ [fJ I f41 ~
I Crown Height ~
2 0.678 0.658 0.640 0.642 Crown Width: l.O" 3 0.730 0725 0.653 0.720 E!1e£ ~
UPST Component DNST Component Nominal Diameter: 12.0" 4 NIA NIA NIA NIA Weld Length: 40.375" 5 NIA NIA NIA NIA FLOW_.
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I Page L.j of 7 L_
0 Page,4 of 23
Unit 1 Limerick Generating Station Third ISi Interval Limited Coverage NOE Coverage Plots r-
~r Limerick Unit-1 O"
""c
~
Recirc Inlet N2
~' Component: N2A (600700) 0 60° 54 Exam Volume = 8.5 Sq. In.
0 60° S6 Exam Volume =51.5 Sq. In.
°'
60° S4 IRS-Scan LKCW achieved = 8.5 Sq. In.
=
60° S4 IRS-Scan LKCCW achieved 8.5 Sq. In.
60° 56 P-Scan achieved= 31.8 Sq. In.
=
60° S4 T-Scan achieved 8.5 Sq. In.
60° S6 T-Scan achieved = 42.4 Sq. In.
I
<t o.o* 6.3° 7.9" 15.7" I so*r so*p 60"T I I I I
I I
I I
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1 ff-'4-Jif. *~
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=
)ate T Norn. 6.4375" L1J<=--z.::;d' Page,5 of 23
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Unit 1 Limerick Generating Station Third ISi Interval Limited Coverage NOE Coverage Plots
~
r
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...er CD Limerick Unit-1
"'c
- J Recirc Inlet N2 7...... Component: N2F (600850) 0 0
~
60° S4 Exam Volume =8.5 Sq. In.
co so* SS Exam Volume = 51.5 Sq. In.
S0° S4 IRS-Scan LKCW achieved = 8.5 Sq. In.
50° S4 IRS-Scan LKCCW achieved = 8.5 Sq. In.
50° SS P-Scan achieved= 31.8 Sq. In.
50° S4 T-Scan achieved = 8.5 Sq. In.
so 0 SS T-Scan achieved = 42.4 Sq. In.
6.3" 7.9" 15.7" 60"T 60"P 60"T I I I I
I I
I I
---~
-r~:p~
Lcvelar 3/1'6 /zoolf Radial Plate T Norn. =6.4375"
=
Clac(~m. 0.1875" Page6 of23
Unit 1 r
3*
Limerick Generating Station Third ISi Interval Limited Coverage NOE Coverage Plots Limerick Unit-1 CD ff
'7'"
c
- I Main Steam N3
~
.... Component: N3D (601090)
N 0 60° S4 Exam Volume = 10.6 Sq. In.
0 (X) 60° S6 Exam Volume = 64.4 Sq. In.
60° S4 IRS-Scan LKCW achieved= 10.6 Sq. In.
60° 54 IRS-Scan LKCCW achieved= 10.6 Sq. In.
60° S6 P-Scan achieved = 38.1 Sq. In.
60° 54 T-Scan achieved = 10.6 Sq. In.
60° S6 T-Scan achieved= 53.4 Sq. In.
~
I
<t 0.0" 6.7' 8.0" 17.6" I so*r so*p 60"T I
I I I r----
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t.c=-ve-l 1lr 3 ;is-/a Radii ~te T Norn.= 7.25" Page 7 of 23
=
Clad \.-.n6m. 0.1875"
Unit 1 Limerick Generating Station Third ISi Interval Limited Coverage NOE Coverage Plots r
~f (I) Limerick Unit-1 ff
- it" c
- i Core Spray N5
...... Component: N58 (601330) r-l 0
0
=
60° S4 Exam Volume 8.5 Sq. In.
co 60° S6 Exam Volume = 50.3 Sq. In.
60° S4 IRS-Scan LKCW achieved = 8.5 Sq. In.
60° S4 IRS-Scan LKCCW achieved = 8.5 Sq. In.
60° S6 P-Scan achieved = 31.8 Sq. In.
60° S4 T-Scan achieved= 8.5 Sq. In.
60° S6 T-Scan achieved= 42.4 Sq. In.
~
ct.
o.o* 6.3" 7.9" 15.7" 60"T 60"P 60"T I I I I
I I
I I
I
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=
Radial Plate T Norn. 6.4375" LCV&.. 7Jr f .3/14)2 () cJ?
Clad r"'m. = 0.1875" Page 8 of23
Unit 1 Limerick Generating Station Third ISi Interval Limited Coverage NOE Coverage Plots r
~~r m
- l.
' * -~
- Limerick Unit-n A"
c
- J CRD Return N9
~ Component: N9 (601460)
~
0 60° S4 Exam Volume = 8.5 Sq. In.
0 OJ 60° S6 Exam Volume = 50.3 Sq. In.
=
60° S4 IRS-Scan LKCW achieved 8.5 Sq. In.
60° S4 IRS-Scan LKCCW achieved = 8.5 Sq. In.
60° S6 P-Scan achieved = 35.3 Sq. In.
60° S4 T-Scan achieved= 8.5 Sq. In.
60° S6 T-Scan achieved= 42.4 Sq. In.
ct
~
I 6.3" 7.9" 15.7" I 60"T 60"P 60"T I I I I I
I I
I I
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L1JcCilL / 3)18'/<!.oog Radi te T Norn. = 6.4375" Page 9 of23 Clad am. = 0.1875"
Unit 1 Limerick Generating Station Third ISi lnterv.aLLimited Coverage NOE Coverage Plots r
3*
....CD Limerick Unit-1 c:r
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c::::J LPCIN17
~
...... Component: N178 (601520)
N 0 60° S4 Exam Volume =8.5 Sq. In.
0 co 60° 56 Exam Volume =50.3 Sq. In.
60° S4 IRS-Scan LKCW achieved = 8.5 Sq. In.
60° S4 IRS-Scan LKCCW achieved = 8.5 Sq. In.
60° S6 P-Scan achieved= 31.8 Sq. In.
60° S4 T-Scan achieved= 8.5 Sq. In.
60° 56 T-Scan achieved = 42.4 Sq. In.
~
<t I 6.3" 7.9" 15.7" I so*r so*p 60"T I I I I
1---
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I I
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=
te T Norn. 6.4375" 'age\ 10 of 23 om. =0.1875"
- HITACHI Limerick Generatina Station Third ISi ln~im ted Coverage NOE Coverage Plots Wall Thickness Profile Sheet Site:
Project Limerick Li1Rl2 Unit
!l --u Report No.:
602270
~
~ 4 System: LPCI I Component ID Number: DCA-318-1 FW1 Position I o* I 90° I 180" I 270' I I [1]
1 I 0.74" I NIA I NIA NIA Crown Height FLUSH rn rn I
[!] [fil 2 I 0.72" I NIA I NIA NIA Crown Width: 1.6"
-PIPE 3 I 0.78 I NIA I NIA I NIA I Nominal Diameter: 10.0" I UPST Component: \ii SAFE END DNST Component 4 I 1.00 I NIA NIA NIA Weld Length: 41.25" 5 I 1.74" I NIA NIA NIA I FLOW ..
{.,{fl~
wcU> '/DC Joshua Ste/lakis 11-L 311012008 /'r I' ~/ /~ __::zzz:- -'----=-- j' I l~*O Drawn by: Level: Date: Level: Date: Date:
Page f of 17 Page 11 of 23
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WJ I Plot Sheet Project L11R12 602270 I -- ~----------------~-----------4 System: LPC/ Component ID Number. OCA-318-l FWl Configuration: PIPE to SAFE END Flow 51°RL, 66°RL er of weld build up 45°shr, ;45°RL 1 60°RL
(+)Safe End
(-) Pipe Limited Areas LKDN - 60.8%
Weld preps obtained from drawing; LKUP - 88.4%
LKCW- 80.0%
VPF#'s 2886-135-00 LKCC - 80.0%
Total Procedure Coverage= n.4%
Michael Krueger Drawn by:
Level:
wgoos 1 .)i{fHt Date: I GE Reviewed By:
~ Level:"14 *b,fot~a\_Q Date: :Reviewed By: ~~~18 vu.... I Page ~ of 17 I
Page 12 of 23
Limerick Generatin raae NDE Coveraae Plots
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Wall Thickness Profile Sheet Site:
Project Limerick Li1R14 Unit
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Posibon ()" 90" 180" 270" I
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3 I 1.32" I 1.46" I 1.48" I l.52" I Nominal Diameter. 22.Cl'
!!l2!l UPST Component Sweepo/et DNST Component 4 I l.28" 1.44. l.64" 1.60" Weld Length: filM!..'
5 I l.38" l.52 l.76" l.72" FLOW_.
FLOW' PIP£ .SUEEPOLC:\
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".J"'II:_ Jason Jennings Drawn by 11 Level:
212512012 1~,:PT Z-.49-1~4-LN Dote: GE Reviewed By Level: Date~ ~y Review:
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Page ~ of _a Page 13 of 23
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Limerick Unit-2 Weld LGS-1-BF Component: BF (600290) 70° Exam Volume = 8.6 Sq. In.
45° Exam Volume= 37.6 Sq. In.
60° Exam Volume = 8.0 Sq. In.
70° T-Scan achieved= 8.6 Sq. In.
45° T-Scan achieved= 37.6 Sq. In.
60" T-Scan achieved = 8.0 Sq. In.
70° P-Scan achieved = 8.6 Sq. In.
45° P-Scan achieved = 37 .6 Sq. In.
60° P-Scan achieved = 8.0 Sq. In.
70"T P-Scans TIP-Scans 45°T I I
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Onlt1 Limerick Generating Station Third ISi Interval Limited Coverage NOE Coverage Plots i
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~ Limerick Unit-1 Weld LGS-1-BF Component: BF (600290) 70° Exam Volume = 8.6 Sq. In.
45° Exam Volume = 37 .6 Sq. In.
60° Exam Volume = 8.0 Sq. In.
70° T-Scan achieved= 8.6 Sq. In.
45° T-Scan achieved= 37.6 Sq. In.
60° T-Scan achieved= 8.0 Sq. In.
70° P-Scan achieved = 8.6 Sq. In.
45° P-Scan achieved= 37.6 Sq. In.
60° P-Scan achieved = 8.0 Sq. In.
TIP-Scans P-Scans 70°T 45°T I I I I 60"T I
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Uni(1 U
- HITACHI I Wall Thickness '-'I /
Limerick..Generating..St~tion_T.bi[dJSJJnterJal Umltecftoverage NDFCoverage Plots Site: umertckGeneratlnqStation unit ! J ReportNo.:
i I Profile Sheet I J Project ~ _I_ ll6790 I
~.5" rn~ ~.5" I RHR I
II System:
Compon nt ID Number:
RHBD03 Position o* 90" 180" 270" ~
OJ fI] ; [4J ~
1 0.68" NIA NIA NIA Crowr Height Flush 2 0.66" NIA NIA NIA i
Crown Width: 1.2" I 3 0.72" NIA NIA NIA I ElM Valve UPST Component DNST Component Norn in I Diameter: 12.0" 4 0.72" NIA NIA NIA I~.~~~~~~__,._/"' I '*~~~~~~---'
5 NIA NIA NIA NIA Weld I ength: 37.7' I L Fl.._OVV ...- I p, ?f. FL()W
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A~ew: Date:
Page J of 2 Page 16 of 23
Unit 1
- - - - - - - - - - - -....---- _.,Liarnrick Generaling_Station Third ISU~aae NOE Coueiaue Plot<: 1 {
Indication I Coverage Site: Limerick Generating Station Unit ! Report Number.:
- HITACHI Plot Sheet Project Li1Rl5 244801 System: RHR Component ID Number: RHR-HXAR-N4/R Configuration: ~ to Plate
('VoZ..Z-LF PL,ATE N6'2..2.L..£ e £ r£1'.£ Ne. e A R...£A 80° f
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Mark Hilborn Drown by:
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Valve f1ll£ 3 I 0.52" I NIA I NIA I NIA I Nominal Diameter: 6.0" UPST Component DNST Component 4 I 0.44" I NIA NIA NIA I o.44" I NIA NIA NIA Weld Length:
-21.0" 5
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Page 18 of 23
u it 1 0 Limerick Generating Station Third ISi l e Limited Coverage NOE Coverage Plots
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ited Coverage NOE Coverage Plots
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Page21of23
Unit 1 Exel6ftk""Generating Station Third ISi Interval Limited coverage NOE coverage Plots ER-AA-335-016 Revision 7 Nuclear Page 18 of 18 ATTACHMENT 2 VT-3 Visual Examination NOE Report for Component Supports, Attachments and Interiors of Reactor Vessels p aae 1 of 1 STATION: limerick I UNIT: 0 I DATE: 05-14-12 I REPORT NO: NA
'SYSTEM: 11 I COMP. NO.: OD-P548-SAUP I OD-P548-SRLO I WO. NO.: C0235899-43 VT-3 X I LIMITED VT-3 n I DIRECT n I REMOTE x I SNUBBER S/N: NA DRAWING($): 8031-M-12-19-98A I REV.: G DESIGN C.S.: NA I DESIGN H.S. NA AIDS: I FLASHLIGHT DI MIRROR D I TESTCARD XI OTHER: Everest Ca-Zoom 6.2 PTZ140 ATTRIBUTE RI NRI 10 EXPLANATIONS/ COMMENTS 1 CRACK/LINEAR/ROUNDED/PITTING/SEVERED x 2 ARC STRIKEs/wELO SPATTER/SCORING/ROUGHNESS x 3 EAOSION/CORROSIONlwEARIGOUGING/SCRAPING x 4 DEFOAMED/BENT/LOOSEIDETACHEO/MISSING PARTS x 5
6 7
THREAD ENGAGEMENT/BOLT ELONGATION/wELOMENT SPALLEO CONCRETE OR GROUT/ANCHOAS/IMBED CLEARANCES/TAA VEL STOPS/PINS x
x x
B ENVIRONMENT x See limitations I obstructions 9
10 LOCKNUT/PIN/TACKWELO SECURING CAN SETTING - x x
NON-INTEGRAL ATTACHMENT LOOSE/INSUL DAMAGED 11 SPAINGs/ROLLERs/BEAAINGS x 12 FLUID LEVEL/FLUID LEAKs/wEEPAGE/INDICATOR STUD x 14 OTHER x 15
- SUPPORT SETTING WITHIN TOLERANCE OF DESIGN INCHES NA I LBS. NA
- THESE ITEMS NEED NOT BE EVALUATED WHEN EXAM PERFORMED IS A STATION APPLICABLE LIMITED VT*3.
RESULTS: =
Al RECORDABLE INDICATION NRI =NO RECORDABLE INDICATION =
10 INFO ONLY COMMENTS: A remote VT-3 examination was performed on the subject commponets following removal of the
- o* ESW pump. Upper support Sum No. 760133 lower support Sum No. 760135 There was no evidence of structural deformation, missing, detached or loosened items. There was no evidence of cracked or fractured parts, or bolting.
DOCUMENTATION OF LIMITATIONS/OBSTRUCTIONS Due to the poor visibility underwater and the presence of scale build up and corrosion product on the submerged comoonents, an ASME Section XI Vf *3 examination can not be credited for these comoonents.
ISi Interval: I Third I ISi Period: J Second EXAMINER: Karl Fisher k'ae~
~
LEVEL: Ill DATE: 05*14-12 Further Evaluation Required: x Yes D No Additional Actions:
Reference:
IA# 01298712 (Action Reauest, Work Order, Issue Renort, etc. initiated for Corrective Action)
REVIEWER: DATE:
ANll: DATE:
Page_1_of _1_
Page 22 of 23
Unit 1 Limerick Generating Station Third ISi Interval Limited Coverage NDE Coverage Plots CLOSURE SM "l CTYPICAL 76 STUOSI HEAD FLANGE Hll.E LOCATION VESSEL ELEV.
- rE-716.25" I Sf!'* B.25" 0 ~
N30 N3A N:ll SITE ELEV.
325'*11.25" SHaL N0.5 0 0 :z:
m 623.5" YESSEL ELEV.
s1*-u.s*
SITE ElEV.
0 Nl2B SHELL NO. 4 0
Hl2D ~1 0 "1ZA 0
Nl2C
- £ m
318'* 2.5" VESSEL aEV.
AD 537.5" 44*-q.5" SITE ELEV.
0N4E 0N4F
~r~* 0N4A 0 0 JU'-5" 1140 m 0H58 0N5A N4B ii N4C SI-ELL NO. 3 If! 0 VESSEL ELEV.
33'*4.5" II:, "88.5
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288'-2.5" VESSEL ELEY.
Uf-6.5" I~ ~ SITE ELEV.
276'*4t5" 180 ° 188 ° IHSIDE VIFlt NOTE:
SEE Xl*RPY-1 PG. 2 FOR AZIMUTH AND B..EVATION TABLES. ELEV. e* CREFJ:266'J*
REACTOR PRESSURE VESSEL JSI mAVlt<<i - REACTOR BUll.OING RPY SCAN LIMITATI~ DRAWING
~n 1
~~llEY
'a.re° IISSUED REPRES£NTS AN AREA 'lt'HERE SCANNifl<<i FOR lST IT O<<D
.~ *i&. tlf INSP. INTERVAL. MOC IOI 1111 DllG lllD INTEAFERENCES EXIST.
f/lft 8031 Xl-BA .. 6
-- PHILADELPHIA ELECTRIC CMANY LGS UNITS 1 & 2 Page 23 of 23 tllT FOR Ol6TRUCTlm. PAGE J OF 1
Enclosure 2 Limerick Generating Station Unit 2 Third Inservice Inspection (ISi) Interval Limited Coverage Non-Destructive Examination (NDE) Coverage Plots
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S0° NS Exam Volume = 11.2 Sq. In.
S0° FV Exam Volume = 39.2 Sq. In.
Inner 15%T Exam Volume (IRS & S0°T) = 8.5 Sq. In.
so 0 NS T-Scan achieved= S.2 Sq. In.
S0° FV T-Scan achieved= 38.3 Sq. In.
Inner 15%T-Scan achieved (IRS & S0°n = 8.5 Sq. In.
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60° FS Exam Volume = 39.2 Sq. In.
Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In.
60° P-Scan achieved = 5.1 Sq. In.
60° P-Scan achieved= 33.2 Sq. In.
Inner 15%T (IRS & 60°P) achieved= 8.5 Sq. In.
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=
45° Exam Volume 39.3 Sq. In Inner 15%T Exam Volume (60°T & IRS) = 8.5 Sq. In 70° T-Scan achieved = 6.1 Sq. In 45° T-Scan achieved= 34.8 Sq. In 60° T Scan achieved = 8.5 Sq. In T-Scans 70°T 45°T 60°T I I I
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Unit 2 Limerick Generating Station Third ISi lnterVatlimited Coverage NDE Coverage Plots r
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=
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=
70° P-Scan achieved 5.2 Sq. In
=
45° P-Scan achieved 32.9 Sq. In Inner 15%T Scan achieved= 8.5 Sq. In I P-Scans 70°P 45°P I
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=
70° T-Scan achieved 6.1 Sq. In
=
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=
45° T-Scan achieved 34.8 Sq. In
=
60° T Scan achieved 8.5 Sq. In T-Scans 70°T 45"T 60°T
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=
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=
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=
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=
60° NS Exam Volume 11.2 Sq. In.
60° FV Exam Volume = 39 .2 Sq. In.
Inner 15%T Exam Volume (IRS & S0°T) = 8.5 Sq. In.
60° NS T-Scan achieved= 6.2 Sq. In.
60° FV T-Scan achieved = 38.3 Sq. In.
Inner 15%T-Scan achieved (IRS & S0°T) =8.5 Sq. In.
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=
60° P-Scan achieved 6.0 Sq. In.
=
60° P-Scan achieved 33.2 Sq. In.
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Unit2 Limerick Generating Station Third ISi lnte~"1lmited Coverage NOE Coverage Plots
- GE ENERGY NUCLEAR Sys1em* RHR Pos1uon a- 90" 180' 270" 1 NIA NIA NIA NIA 2 NIA NIA NIA NIA 3 NIA NIA 0.78 NIA 4 NIA NIA 0.64 NIA
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Unit2 CUTfFcii~~reii\WU\'Wl'f~~ea~atrati Nfii~~Wge Ptots e GE ENERGY NUCLEAR umerick Site: Limerick Procedure: GE-PDl-UT-2 I Ver. 4 I NIA I Data Report Number:
Cal I Data Sheet Number 6
UT-005 Weld ID DCA-204-3 SW1101 Drawing: Xl-DCA-204-1 Size: tr. Thickness: . 780" Exam Start: 1645 Lo Location: Top Dead Center o* Wo Location: Weld Centerline Weld Width: 1.3" Weld Height: .050" Exam End: 1902 Ind No I Angle Used
% of DAC l1 Indication Len th L Max L2 W1 W Distance WMax W2 MP1 Metal Path MP Max MP2 Ax/
Circ UpsU Dnst Comments:
45* 100 2 45* 25 26.25 26.5 27.25 1.1" .925" 1.4" .695 .777 .836 Ax Ax DNST Countllrbonl 360"
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DNST ln18nnlltent Root Ga~lry 360" Sketch FLOW
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Exam mer Leve Date:
Page 13 of 37 Page § of 7
Unit2 Limerick Generating Station Third ISi lnte'Miieimited Coverage NOE Coverage Plots Wall Thickness Profile Sheet Site: Limerick Unit: ~ Report No.:
- GE ENERGY NUCLEAR Project: L/2R09 328405 System:
Pos1uon o< go=
RHR 180' 270' Component ID Number: DCA-204-1 SW1502
~
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Nominal Diameter: 12.0" 4 NIA NIA NIA NIA Weld Length: 40.75" 5 NIA NIA NIA NIA FLOW--
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Page § of 7 Page 14 of 37
Unit2 CUTffiiii'b~1~rekiact,WJtr~Bi3 1~e~f~alr~fi ~~~~Wge Ptots Data Report Number:
~i
~I GE ENERGY NUCLEAR Limerick I
Cal I Data Sheet Number YI:!!f1g_
Site: Limerick Procedure: GE-PDl-UT-21 Rev. 41 NIA Weld ID: DCA-204-1 SW1502 Drawing: Xl-DCA-204-3 Size: 11:: Thickness: .810" Exam Start: 1620 Lo Location: Top Dead Center 0° Wo Location: Weld Centerline Weld Width: 1.r Weld Height: Flush Exam End: 1804 j Ind No Angle Used I% of DAC L1 Indication Len th L Max L2 W1 W Distance W Max W2 MP 1 Metal Path MP Max MP 2 Ax/
Circ Upst/
Dnst I Comments:
1 45* 22 19.5 19.75 21 N/A .825 1.5 1.025 1.150 Ax UPST Root Ge~
2 45° 22 lntennltt&nt Root Geometry 360"
- Verified vllually during In shop fabrication Ske1ch FLOW
~
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Examiner
~
Joev Clairday l1 Level
.J-/tJ.(;7 31812001 3~.;;01~/#7 Page ~ of 7 j
Date Page 15 of 37
Unit2 Limerick Generating-Station Third ISi lnterval'timited *. :__------------r-- ---
I Coverage NOE Covera_ge Plots e GE ENERGY, NUCLEAR Wall Thickness 1 Site Limerick Unit g I Report No Profile Sheet I Project. Li2R09 350600
__: 45"--
i
~--~
I S*) s:
1 RHR Component ID Number DCA-418-4 FW1 I t*' *~ . o* 90' 180' 270*
i OJ \rJJ tl.J:. CjJ [fil I I
0.722 NIA NIA NIA Crown Height FLUSH
- 0.813 NIA NIA NIA I \ i I Crown Width 1.7" PIPE \
- SAFE END c---
~/ \
3 0.903 NIA NIA NIA 1JPST vrnpon,;,nt II Nominal Diameter 12.0" - - ) I /_ 01131 ' <*OTIP*CMI
~ 0.878 NIA NIA NIA Weid Length 410" 1 '*
....5ftf'e.. c~.1 ft?E:-
i fn~J Ar <-Pc 3-23 cf71 ~ :z::r_1 Mortin Crane Drawn by
!1 Levei
- / " ., I~ * - """'
Date Date !i AN!J Revi~{~ Date I
I i
=====---=--"'---- ~-'
- _ _ _ __ _. , - L _ Pa 2 a f 17 Page 16 of 37
Unit2
- Limerick-Generating Station -Third ISi lnte..Valll:imited Coverage NOE Coverage Plots r---- Wall Thickness I~ Stte Limerick Unit ?. Report No Wt GE ENERGY, NUCLEAR Profile Sheet Project. Li2R09 350600 I I I - - -- -
I RHR I I ~ ~ ~ ;
Pos, t~o ... o* 90* 180" 270" Component ID Number DCA-418-4 FW1 I i--l flJ ------l I J 0.722 NIA NIA NIA OJ [I] GJ [fil I
~ 0.878 NIA NIA NIA 5 1.47 NIA NIA NIA Flow Interface noted
~ 45°shr, ~ 0 RL, 60°RL 45"shr, 45°RL, 60°RL 51 °RL, 66°RL
<t - - r...
- ~
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DCA-418-4 FW1 (N170)
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Procedural Exam Volume Martm Crane Drown by 11 Level
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Unit2
, - -timerick-Generating Station-Third ISi lnterV&f~mited Coverage NDE Coverage Plots -,
Ir------
- I I
m,
- WollThickness- - : Site Limerick Uni ?. Report No
~* GE ENERGY, NUCLEA Profile Sheet Ii ___ l__ J
--1 Project _u2_Ro_9 023900 _____
?o* ~10; o* 90" cs
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Component ID Number OCA-420-l FWl
~ ~- -; 4 15.. *I
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' Crown Height. FLUSH I. 0.655 NIA NIA NIA Crown Width ~
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0.705 0.723 NIA NIA NIA NIA NIA NIA Nominal OJOmeter 10.0" eJff.
UPST Cornpon.:ont
\!; SAFE END DNST Ccrnpon.ent
~~-~----~---~
Weld Length 35.0" NIA NIA NIA NIA
--- --*- -~ - -- - * ~ ~00~ I P1 PE. F_LOW . .__ . ._ SAfE. e.~o
~
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Martin Crane 11 -;r7 1-21-01 .
Drew~ by Le*;el Dote Level ~Dote , AN ll Review Dote I Pa ~ of 15
- Page1 8o f37 - -------------- - - - -- *-
Unit2 s~ation-Third*ISI Int~ imited Coverage.NDE_C_o_y!llilge Plots
.-----1-imericl<.Generaun*g I - - - - - - - - - - -.- - - -
GE ENERGY, NUCLEA 1 Woll Thickness - 1 I
Site Limerick Unit ?. Report No I Profile Sheet I Project- ~ 023900
~- - ,-41 ~*~ :I
~
System cs .J corn po nent ID Number DCA-420-1 FW1 Posit.on o* gc* iao* 270*
~ I :
-- OJ r2 41 12]
1 0.645 NIA NIA NIA Crov. n Height ruilli
~ 0.655 NIA NIA NIA Crow n Width 1.25" PIPE \ . / SAFE END 3 0.705 NIA NIA NIA 1 UPST Cornpc.ne-n\ I/ OMST (.)mp*:ini:nl Norn nal Diameter 10.0" I *1 I
~ NIA NIA NIA NIA Weld Length ~ I FLOW~ J Flow er 45°shr, 60°shr 45°shr, 60°shr
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40°RL. 45°shr. 55°RL, 60°shr 40°RL, 45°shr, 55°RL. 60°shr DCA 420-1 FW 1 (NSB)
[-------]
Procedural Exam Volume Martin Crane Drawn by 11 Level
£,, ¥, -~~~-£ Level.
2 1'n.C-Dote 7~ ~23 o-:J~ $J7il I
- Review Dote ANll Review Date
~-~-- ------
! _l Pa ~ of 15 _j Page 19 of 37
Unit 2 Limerick Generating- station Third ISi In al*l:imited Goverage-NgE Goverage-P-lots__ - -
I -* .. - - - -
HITACHI Wall T~ickness Profile Sheet 1s,,,
Proiect
~
Li2R10 Unit.: l I
I Report No.:
015500 i
~
~ ~
System: cc Component ID Number: DCA-419-1 FW7 Pos111on o* 90° 11:10° no* [}]
OJ f2l '
f4l ~
1 NIA NIA NIA NIA Crown Height Flush 2 .70 NIA NIA NIA Crown Width: .8" Elbow .ei2£ j .73 NIA NIA NIA DNST Component UPST Component Nominal Diameter* gQ_ I
~
~
.70 NIA NIA NIA NIA NIA NIA NIA Weld Length: 40.0 I /
FLOW--
- - - - ~- . - - - -- - -* - -
Ct I "'15" ELBOW PIPE'
/ /Jli (
l ~~~~~Dat;'/v/2'°9 1 ~~;,,
Lee Moore II 41412009 i
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Page 20 of 37
- ~ ~
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Limerick Profile Sheet Site:
Proiect
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component ID Number: EBB-201-1 FW33 Pos1tion o* 90" 180" no* [}]
1 NIA NIA NIA NIA Crown Height ~
OJ f21 I rn @]
2 1.43 NIA NIA NIA Crown Width. 1:1:
UPST Component ONST Component Nominal Diameter: ~
4 1.11 NIA NIA NIA Weld Length: 82.5 5 1.15 NIA NIA NIA FLOW_.
~
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t
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VALVE I
Level1! : 4/3/2009
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Lee Moore f/11{ Drown by Dote:
Page 3 of 4 Page 21of37
- - -*--- ,--- ~ 1- -
Limerick GeneratiniJ.Station-Third ISi I I
Wall Tnickness Site: Limerick Urnl l HITACHI Profile Sheet Proiect ~ I I
~
~
R 4 System: 051 Component ID Number* GBB-20~2 FWB Pos1t1on o* go* 180" no* QJ 1 .397' .361" .390" .390"
--- OJ f2l . f4l ~
own Heighl £fi!£1 2 .365" .314" ..364" ..360" own Width. :lJr.
3 .475" .417' .47fJ' .460" ~ Valve UPST Component ONST Component ominol Diameter: 1§.Q.
4 NIA NIA NIA NIA eld length: ~** I ... ~ I s NIA NIA NIA NIA Oo ~~~~-------~~--}-~
'i0cj ,-
I bOc - - r
- ) 70(J
. ~~/.../£:.
-'1" J . Mike Bullen 11 4/5/2009
~"-h.~A Zir- fl/7/00~f
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J2. Poge '-/ of b Page 22 of 37
-*~- - m1tecrcoveragErNDE-C---overege*Plots
- - -timerick Generating-Station :rhirdJSL '
I I Wall Ttiickness I Site: Limerick Unit: l HITACHI Profile Sheet I Project 1dl!llil I I
~
~
~ 4 System- Qg Component ID Number: GBB-205-2 FWB Position o* 90* 1110* 210* l}1
[!] 41 ~
1 .397" NIA NIA NIA Crown Height &!.!h 2 .365" NIA NIA NIA Crown Width: .7'1' Elbow ~
~ .47!;;' NIA NIA NIA UPST Component: DNST Component:
Nom1nol D1ometer: 16.0 **
4 NIA NIA NIA NIA weld Length: ~**
Ax U? I u(/'fc f\X .DN IOO"t o.
e,, ~c. '-"P i\X:i b 10°/S C1RC Dr-J 50%
3'50%
o.J 35ot "t'.: 8 7. 5 7o AcM'ccveP 87.5/o Cor>C: C~v'L~AG-E I
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= l:lntt*2 Weld ID:
&1 HITACHI GBB-105-l FWB Site:
-timerick-G'enerating-Station-Third.lSUiit~~iffi!ecfCoverage*NDE-eoverage*Plots----,-
Limerick Drawing:
Ultrasonic Examina&m'lndication Report Xl-GBB-205-l
_ Procedure: GfH-POl-UT-l/ 6 / 08 _14 Size: 1§.Q'.'. Thickness: Q:lli:
) I Doto Report Number:
_= - _ J.Col/ Dalo Sheet Number:
Exam Start-
~
0311
.Q:Q2l LO LOCO!IOn TDC Wo Locol1on: Weld Center Line Weld Width: :lJ!:. Weld Height :9£. Exam End: 0334 I I Ind Angle %of I 1ndica11on Length WD1stonce Metal Poth AA./Clfc Upst/ j No 1 I used 70 DAC I 141 .
Ll I L Max I L 2
.so I . .
WI I WMox I W 2 I 1.15 I . . MP l I MP Mox I MP 2 I l.JS I . AA Dnst UPST 1 Comments.
- ot>seivec1 10 Root Geomettv above ond below recordable levels mtermrttent 360°.
Sketch 7t"/S i I
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Examiner Mike Bullen 11 Level:
~~~~~,f~~ t!*i~ if/P I
Page
~
of
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Page 24 of 37
it.2 Limerick Generating Station Third ISi lilhiV~imited Coverage NOE Coverage Plots Limerick 1 5"i1~ 11s vn.)rr z
~
RECIRCULATION OUTLET Li( 3{ <009 Component: N1A (703900}
=
60D NS Exam Volume 11.2 Sq. In.
=
60D FV Exam Volume 39.2 Sq. In.
Inner 15%T Exam Volume (IRS & 60DT) =8.5 Sq. In.
=
SOD NS T-Scan achieved 5.S Sq. In.
SOD FV T-Scan achieved= 37.7 Sq. In.
Inner 15%T-Scan achieved (IRS & 60DT) = 8.5 Sq. In.
T-scans 60D NS T SOD FVT 1II I I II I
I 703 900 I
I II I
I {'11 A I I
~--- ----1
/)
- 1 Limerick Generating Station Third ISi 16ie..Val\imited Coverage NOE Coverage Plots u,.;1T Z Limerick 1 5it~E. ;t.s
~
RECIRCULATION OUTLET t//7/loo'j Component: N1A (703900) 60° NS Exam Volume = 12.0 Sq. In 60° FV Exam Volume = 39.3 Sq. In Inner 15%T Exam Volume (45°P & IRS)= 8.5 Sq. In 60° NS P-Scan achieved= 5.2 Sq. In
=
60° FV P-Scan achieved 32.9 Sq. In Inner 15%T P-Scan achieved = 8.5 Sq. In 60°P 60°P I I I I
~---
1 I I I I I 7DJ9oO I I I p.)1R
f I',
nit2 Limerick Generating Station Third ISlilnterv lil,Limited Coverage NOE Coverage Plots r
~3"
!!l
,..ff
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Limerick 2 Feedwater Component: N48 (709000) 70° Exam Volume = 12.0 Sq. In 45° Exam Volume = 39.3 Sq. In Inner 15%T Exam Volume (60°T & IRS)= 8.5 Sq. In 70° T-Scan achieved= 6.1 Sq. In 45° T-Scan achieved = 34.8 Sq. In 60° T Scan achieved = 8.5 Sq. In T-Scans 70°T 45°T 60°T I I I
_ _ _ _ _ _j 1:/7' 7 7 I
I I
I
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QI \ / /i I!\ I
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Page 27 of 37
it 2 Limerick Generating Station Third ISi Jhhlrv~Limited Coverage NOE Coverage Plots gf Ill
- I.
~
~
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Limerick 2 Feedwater Component: N4B (709000) 70D Exam Volume = 12.0 Sq. In
=
45D Exam Volume 39.3 Sq. In Inner 15%T Exam Volume (45°P & IRS) =8.5 Sq. In 70° P-Scan achieved = 5.2 Sq. In
=
45° P-Scan achieved 32.9 Sq. In Inner 15%T Scan achieved= 8.5 Sq. In 70°P 45°P I
I I
I tJl I
2.
CJ) I I
Page 28 of 37
Limerick 2 Feedwater Component: N4E (709900) 70° Exam Volume= 12.0 Sq. In 45° Exam Volume = 39.3 Sq. In Inner 15%T Exam Volume (60°T & IRS)= 8.5 Sq. In 70° T-Scan achieved = 6.1 Sq. In 45° T-Scan achieved = 34.8 Sq. In 60° T Scan achieved = 8.5 Sq. In T-Scans 70°T 45°T 60°T I I I
I I
I I
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r---- ----..,I
1:t't 2 Limerick Generating Station Third ISi (~~Limited Coverage NOE Coverage Plots Limerick 2 Feedwater Component: N4E (709900) 70° Exam Volume = 12.0 Sq. In 45° Exam Volume = 39.3 Sq. In Inner 15%T Exam Volume (45°P & IRS)= 8.5 Sq. In 70° P-Scan achieved = 5.2 Sq. In 45° P-Scan achieved = 32.9 Sq. In Inner 15%T Scan achieved = 8.5 Sq. In 70°P 45°P I P-snns I
I IL ___ _
I I I I I I I I I I I I I
1
F Limerick Generating Station Third ISi lltte~imited Coverage NOE Coverage Plots Limerick Unit-2 Jet Pump Inst.
Component: NBB (711300) 60° NS Exam Volume= 12.2 Sq. In.
=
60° FV Exam Volume 39.2 Sq. In.
Inner 15%T Exam Volume {IRS & 60°T} =8.5 Sq. In.
60° NS T-Scan achieved= 5.7 Sq. In.
60° FV T-Scan achieved= 37.8 Sq. In.
Inner 15%T Scan achieved {IRS & 60°T) = 8.5 Sq. In.
60° NS T 60° FVT I I I
I I I ~11 I I I I 3/31 /zo:>?
~--- ----t
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/ /)1'7 AtfJZZ. ~ fl) 8 B Page 31of37
(\
Limerick Unit-2 Jet Pump Inst.
Component: N8B (711300) 60° NS Exam Volume= 12.2 Sq. In.
60° FV Exam Volume = 39.2 Sq. In.
Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In.
=
60° NS P-Scan achieved 5.3 Sq. In.
60° FV P-Scan achieved = 34.5 Sq. In.
45° IRS P-Scan achieved = 8.5 Sq. In.
I P-Scans I 60°P NS 60°P FV I I I
1----
1 I
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---~
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.J Unit2, Limerick Generating Station Third ISi lntElrval limited Coverage NOE Coverage Plots HITACHI Wall Thickness V I Site: Limerick Generating Station Unit ?. Report No; Profile Sheet Project Li2Rl2 663300
~
~ ~
System: RWCU Component ID Number. DCA-201-1 FWl3 Position ()" 90* l!IO" 270" [))
l NIA NIA NIA 0.64u III m I 141 ~
Crown Height Flush 2 NIA NIA NIA 0.48" Crown Width: o.asu J NIA NIA NIA 0.49" Tee !21?!
UPST Component DNST Component Nominal Diameter: 6.0U 4 NIA NIA NIA 0.4lu Weld Length: 21.0U 5 NIA NIA NIA o.4r FLOW--
r.cie R.ow . ,P/r'£
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qoo C.*"IC 70° '!So
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Page 33 of 37
u "t2 Limerick Generating Station Third ISi lntial L,imited Coverage NOE Coverage Plots HITACHI Weld N4D {Nozzle to Vessel Weld)
~-l K>
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\
\ Feedv\ater
\ Component: N4D (709600)
"O
- 0
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0
\
,,'\ 00' NS Bean VdLJTe = 3.5 Sq. In 00' FV Exan VdITTe = 14.8 Sq. In lrre-15%T Bean VdlJTe (IRS & 001) =3.2 Sq. In
- i.
z I
!='
0
--.I 00' NS T-&al a:hevOO =2.8 Sq. In
<O Ol 00' FVT-&al a::lieved = 14.8 Sq. In lrre-15%T-&al CK:hevEd (IRS & 001) =3.2 Sq. 111 0
0 z
0 !
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Coverage T Scans Page 34 of 37
Unit-,
Limerick Generating Station Third ISi lnte fval Limited Coverage NOE Coverage Plots Weld N4D {Nozzle to Vessel Weld}
3 c~ HITACHI
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\ Component: N40 (709600)
- 0
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\""*" *,. 00° NS Bean Vdt..rre = 3.5 Sq. In.
60" FS Bean Vdi..rre = 14.8 Sq. In.
lmer 15%T Bean Vdt..rre (IRS & 60"1) = 3.2 Sq. In
- i.
z 60" P-Scan adliaied = 2.4 Sq. In
- ,"1
!=' 60" P-Sca'1 adliaied = 14.6 Sq. In
-..J 0
<O 60"&45" IRS P-Sc:an adlievOO = 3.2 Sq. In O>
0 0
z.:..
Cl z
0 I
\
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co Coverage P-Scans Page 35 of 37
Limerick Generating Station Third ISi lnte..Val ited Coverage NOE Coverage Plots Supplemental Report Report No.: UT-15-007 Component: 2BE-205R N-4-1 (362501)
Page: 3 of 4 Summary No.: 362501 11<< #~I ()Cr~ ./t I
Examiner: Mahoney, Patrick V. Level: II Reviewer: Date:
Examiner: NIA Level: NIA Date: 4 * 'Z \- I .OS--
Other: NIA Level: NIA Date: 9/zi/rS-As per procedural requirements, 2BE-20SR N-4-1 was examined in 4 directions utilizing ii 45" & 70" Shear wave.
The 70" shear wave was utilized to increase the axial inspection of the far side of the weld.
All calculations are based on (height x width)/total volume of area. Triangle volume is ((HxW)/2)
WELD EXAM VOLUME: .39"X2.25H=.878" 2 (H x W = AREA 2 )
Axlal Scan Direction 1 was performed from the shell side looking into the weld with flow, on the l" leg.
Scan Coverage: (.39"xl")+{(.39"x.4")/2)=.47" 2/.878""=S3% Coverilge Scan l with the 45".
The 70" achieved and additional 46% coverage (limitation was (.25Hx.1)/2=.012S"2/.878H 2 =1% =99%
Scan Coverage with the 70". (45% additional coverage with the 70") TOTAL OF 99%
I Axial Scan Direction 2 Wils achieved from the shell side looking into the weld with flow, by utilizing the bounce on the 2nd leg with the 45". (No coverage credit was taken for the 2** leg of the 70")
=
Scan Coverage: (.39"Kl.4")+((.39"x.4H)/2)=.63# 2 /.878"2 TOTAL OF 72%
Circumferential Scans 3&4 were in the Clockwise & Counter Clockwise Directions.
I Scan Coverage: (.39"x.4")+((.39"x.15")/2)=.185" 2/.878" 2= TOTAL OF 21%
TOTAL COMBINED COVERAGES:
Axial Scans 99%+72%+21%+21%= 213/4= TOTAL COVERAGE OF 53%
LJ5D t\.L:i ~ t.. L ~
J 5A-~5D*LF-2 SHE:LL 5A-51G.- GRr/lJ
_\
/
Page 36 of 37
Unit2 Limerick Generating Station Third ISi Interval Limited Coverage NDE Coverage Plots CLOSURE STUD *76 \ I~ *1 <TYPICAL 76 STUDSI HEAD FLANGE ---, uni r' LOCATION
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Sct-8.25"
- ~ *\!H6.W
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~
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VESSEL ELEV.
51'-U.S-SITE a.EV.
0 Nl28 Sl£LL NO. 4 0
N120 ~1 0 Nl2H 0
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537.5" 44*.q.s"
- r SITE ELEV.
~
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33'-4.S-AC 400.5*
SITE ELEV*
..._,Nl7B 2qq'-7.5"
~1
'-.../ '-.../ '-.../ 0 0 0 0 N168 SHELL N0.2 N17C el N160 lf170 N16A m7A N16C Iii I VESSEL ELEV.
263.5" Zl'-ll.5.
N2G H2H N2J N2K N2A ~c N20 112£ SITE ELEV.
0 Q.N88 ~ 0 0 cto~ 0 288'-2.5" VESSEL £1.EV.
0 19'-S.S*
I ~ ~ .. SITE El.EV.
276'-C\.5" 180 ° 249° 279°
'IDTE:
SEE Xl -RPV- 2 PG. 2 FOR AZIMUTH ANO ELEVt.TlON TABLES. ELEV. 0* CREF>=266 '3" REACTOR PRESSURE VESSEL '"1sI DRAWING - RE~T~ BUILDING RPV SCAN LIMJT ATl~ DRAWit<<i PfPRESENTS AN AREA WHERE SCANNING UNlT 2 INTERFERENCES EXIST. i~"' catt ISSUED FOR !ST" mEMI u 'at.., ow"°
- 1--1£. ~~ INSP. INTERVAL. MOC ~ ~ ~ R'J 8031 O<<D mtU Xl-BA-8 PHlLADELPHlA ELECTRIC COMPANY LGS ~ITS l& 2 Nll FOO COOTROCTJ~ Pt<< I OF I
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