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 ~
September 29, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Units 1 and 2 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.55a 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 1 O 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:
Reference:
Examination Category:
Item Number:
==
Description:==
Component Number:
1, 2, &3 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 B-A, B-D, C-B, F-A, R-A 81.12, 83.90, C2.21, C2.22, F1.40, R1.11, R1.20 Limited Examination Coverage 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 1 O 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 1 o 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 1 o CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 1 O 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 1 O CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 1 O 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 1 O CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 1 O 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 Requirements Category/
Outage Material of Diameter/
Operating Exam Angle/
Actual VIII (Summary Description (Figure No.)
Item Examined Construction Thickness Conditions Frequency (MHz) I Coverage Qualified Remarks Number)
(System)'
and Method Number (Pressure I Mode Exam Temperature)
The examination was limited due to Shell Ring o* / 2.25 / Long.
proximity of lhe N17B nozzle. Four IWB-2500-2 indications were found during the 45* T-BF No. 2 Vertical Volumetric B-A 1R14 SA-533 Gr. B N/A / 6-7/16 1045 psig I 45* / 1.0 I Shear 86.9%
Yes scan. The indications were evaluated (600290)
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 SA-508 Cl. 2 The examination was limited due to N2A Inlet *s* Loop IWB-2500-7 B-D (Nozzle) 12 in. ID I 1045 psig I nozzle configuration. Essentially 100%
Nozzle to Volumetric 1R12 6-7/16 in. @
60'/ 3.0 I R. Long.
76.0%
Yes coverage was achieved for inner radius (600700)
Vessel Weld (UT) 63.90 SA-533 Gr. B RPV Shell 535"F examination for this nozzle.
(RPV)
(Shell)
(Enc. 1 Pg. No. 5)
Recirculation SA-508CI. 2 The examination was limited due to N2F Inlet "A" Loop IWB-2500-7 B-D (Nozzle) 12 in. ID/
1045 psig I nozzle configuration. Essentially 100%
Nozzle to Volumetric 1R12 6-7/16 in. @
so*/ 3.0 I R. Long.
76.0o/o Yes coverage was achieved for inner radius (600850)
B3.90 SA-533 Gr. B RPV Shell 535°F examination for this nozzle.
(RPV)
(Shell)
(Enc. 1 Pg. No. 6)
Main Steam SA-508 Cl. 2 The examination was limited due to N3D "D" Loop IWB-2500-7 B-D (Nozzle) 26 in. ID I 1045 psig I nozzle configuration. Essentially 100%
Nozzle to Volumetric 1R12 7-1/4 in. @
60' / 3.0 I R. Long.
75.1%
Yes coverage was achieved for inner radius (601090)
Vessel Weld (UT) 63.90 SA-533Gr. B RPV Shell 535°F examination for this nozzle.
(RPV)
(Shell)
(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 1 O CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 1 O 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 Requirements Category/
Outage Material of Diameter/
Operating Exam Angle/
Actual VIII (Summary Description (Figure No.)
Item Examined Construction Thickness Conditions Frequency (MHz) I Coverage Qualified Remarks Number)
(System)1 (Pressure I Mode and Method Number Temperature)
Exam The examination was limited due to nozzle configuration and proximity of Feedwater SA-508Ci. 2 the N 11 8 nozzle reinforcement. Manual N4D "D" Loop IW8-2500-7 8-D (Nozzle) 12 in. ID I 1045 psig I 60" I 3.0 I Long.
inspection of this component requires Nozzle to Volumetric 1R15 S-7/1Sin.@
87.3%
Yes an inspection interval of 4 years.
(601210)
Vessel Weld (UT) 83.90 SA-533 Gr. 8 APV Shell 535°F 55* I 3.0 I Shear Essentially 100% coverage was (APV)
(Shell) achieved for inner radius examination for this nozzle.
(Enc. 1 Pg. Nos. 19, 20, & 23)
Core Spray SA*508CI. 2 The examination was limited due to N58 "A" Loop IW8-2500-7 8-D (Nozzle) 12 in. ID I 1045 psig I nozzle configuration. Essentially 100%
Nozzle to Volumetric 1R12 S-7/1S in.@
so* / 3.o I R. Long.
77.S%
Yes coverage was achieved for inner radius (601330)
Vessel Weld (UT) 83.90 SA-533 Gr. 8 RPV Shell 535°F examination lor this nozzle.
(RPV)
(Shell)
(Enc. 1 Pg. No. B)
CAD Return SA-508CI. 2 The examination was limited due to N9 (Capped)
IW8-2500-7 8-D (Nozzle) 5-1/8 in. ID I 1045 psig I nozzle configuration. Essentially 100%
(601460)
Nozzle to Volumetric 83.90 1R12 SA-533 Gr. 8 S-7/1S in.@
535°F 60" / 3.0 I R. Long.
80.5%
Yes coverage was achieved for inner radius Vessel Weld (UT)
(Shell)
APV Shell examination for this nozzle.
(APV)
(Enc. 1 Pg. No. 9)
LPCl"D" SA-508CI. 2 The examination was limited due to N178 Loop Nozzle IW8-2500-7 8-D (Nozzle) 12 in. ID I 1045 psig I nozzle configuration. Essentially 100%
to Vessel Volumetric 1A12 S-7/1S in.@
60' / 3.0 I A. Long.
77.S%
Yes coverage was achieved for inner radius (601520)
Weld (UT) 83.90 SA-533Gr. 8 APV Shell 535°F examination for this nozzle.
(RPV)
(Shell)
(Enc. 1 Pg. No. 10)
IWC-2500*4(a)
SA-105 AHR-HXAA*
Nozzle N4 or(b)
C-8 Forging 20 in. OD/
285 psig I so*/ 2.25 /Shear The examination was limited due to N41R Inner Radius Volumetric C2.22 1R15 (Nozzle) 1-1/4 in.@
240°F 79* / 2.25 / Shear 70.0%
No nozzle configuration.
(244801)
(RHR)
(UT)
SA*51S Gr. 70 HX Shell (Enc. 1 Pg. No. 17)
(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 1 O CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 1 O 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 Requirements Category I Outage Material of Diameter/
Operating Exam Angle/
Actual VIII (Summary Description (Figure No.)
Item Examined Construction Thickness Conditions Frequency (MHz) I Coverage Qualified Remarks Number)
(System)'
and Method Number (Pressure/
Mode Exam Temperature)
IWB-2500-8(c) 6" Valve HV-IWB-2500-9 N/A The examination was limited due to AW 138 44-1F040to IWB-2500-10 (Class 3 1R15 SA-312 6 in. NPS/
1045 psig I 45* / 2.25 I Shear 50.0%
Yes single sided access (valve configuration (375231)
Pipe IWB-2500-11 TP316L 0.432 in.
535°F 10* / 2.25 / Shear interference).
(RWCU)
(Enc. 1 Pg. No. 18)
(UT)
IWB-2500-8(c)
Preservice examination due to valve DCA-104-03 12" HV-051-IWB-2500-9 SA-358 45* / 1.5 / Shear replacement. The examination was SW801 1F0508 to IWB-2500-10 R-A 1R12 TP316L 12 in. NPS/
1280 psig /
oo* / 2.0 I Long.
47.8%
Yes limited due to single sided access and (117084)
Pup Piece IWB-2500-11 Rl.11 (0.02% max 0.844 in.
539°F PT long seam area of interest (valve (AHR)
Volumetric Carbon) configuration interference).
(UT)
(Enc. 1 Pg. No. 3)
IWB-2500-8(c)
Preservice examination due to valve DCA-104-01 12" Pup IWB-2500-9 oo* 12.0 I Long.
replacement. The examination was SW1402 Piece to HV-IWB-2500-10 R-A 1R12 SA-376 TP316 12 in. NPS/
1280 psig I 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)
(AHR)
Volumetric PT (valve configuration interference).
(UT)
(Enc. 1 Pg. No. 4)
IWB-2500-8(c) 38" / 2.0 IR. Long.
A site specific mockup and procedure 49* / 2.0 I R. Long.
were required to perform this DCA-318-1 12" Pipe to IWB-2500-9 SA-358 45* / 1.5 / Shear examination. The examination was FW1 Safe End IWB-2500-10 R-A 1R12 TP316L 12 in. NPS I 1045 psig I
- 66. I 2.0 I R. Long.
77.4%
Yes limited due to transducer liftoff at the (602270)
(Az. 135 Deg)
IWB-2500-11 Rl.11 (0.02% max 0.688 in.
535°F 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 1 O CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 1 O 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 Number)
(System)'
(Figure No.)
Item Examined Construction Thickness (Pressure I Mode Coverage Qualified and Method Number Temperature)
Exam 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 1A15 TP316L 12 in. NPS I 1045 psig I 45" I 1.5 I Shear 50.0%
Yes single sided access (valve configuration (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 1A14 TP316L 22 in NPS/
1045 psig I 60" 12.0 I Long.
50.0%
Yes single sided access (sweepolet (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) 2" Pipe to IWB-2500-9 The examination was limited due to AW 118 Elbow IWB-2500-10 A-A 1A12 SA-312 2 in. NPS I 1045 psig I 70" I 2.25 /Shear 50.0%
Yes single sided access (elbow (114250)
(RWCU)
IWB-2500-11 Al.20 TP316L 0.218 in.
535°F 45" / 2.25 /Shear configuration interference).
Volumetric (Enc. 1 Pg. No. 2)
(UT)
IWB-2500-8(c) 20*x20*x20*
IWB-2500-9 SA-358 45" / 1.5 /Shear The examination was limited due to ARB 004 Teeto28" IWB-2500-10 A-A 1A15 TP316L 28 in. NPS I 1045 psig I 60" / 1.5 / Shear 50.0%
Yes single sided access (tee configuration (110150)
Pipe IWB-2500-11 A1.20 (0.02%max 1.285 in.
535°F 70" / 2.0 I R. Long.
interference).
(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 1 O CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 1 O 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 Number)
(System)'
(Figure No.)
Item Examined Construction Thickness (Pressure/
Mode Coverage Qualified and Method Number Temperature)
Exam 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 F-A NIA ASME Section XI, Subsection IWA-SRUP Seismic Visual F1.40 (May NIA N/A N/A NA 0.0%
N/A 2210 could be performed. Draining the (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 SALO Seismic Visual F-A (May N/A N/A NIA NA 0.0%
N/A for review. Additional best effort (760135)
Restraint (VT-3)
F1.40 2012) examinations were performed on the (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 1 O CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 1 O 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 Appendix Exam Exam Operating Exam Angle/
Component ID Weld Requirements Category/
Outage Material of Diameter/
Actual VIII (Summary Description Conditions Frequency (MHz) I Coverage Qualified Remarks (Figure No.)
Item Examined Construction Thickness (Pressure I Mode Number)
(System)'
and Method Number Temperature)
Exam 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 F-A N/A ASME Section XI, Subsection IWA-SRUP Seismic Visual (Decembe N/A N/A N/A NA 0.0%
N/A 2210 could be performed. The RHRSW (760203)
Restraint (VT-3)
Fl.40 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 F-A N/A for review. Additional best effort SALO Seismic Visual (Decembe N/A N/A N/A NA 0.0%
N/A examinations were performed on the (760205)
Restraint (VT-3)
Fl.40 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 1 O 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" IW8-2500-7 SA-508CI. 2 28 in. ID I nozzle configuration. Essentially 100%
N1A Loop Nozzle Volumetric 8-D 2R10 (Nozzle) 6-7/16 in.@
1045 psig I 55° I 1.0 I Shear 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 N2H Inlet "A" Loop IW8-2500-7 8-D (Nozzle) 12 in. ID/
1045 psig I 45" I 1.0 I Shear proximity of N88 nozzle. Essentially Nozzle to Volumetric 2R09 6-7/16 in. @
55" I 1.0 I Shear 80.1%
Yes 100% coverage was achieved for inner (706600)
Vessel Weld (UT) 83.90 SA-533Gr. 8 RPV Shell 535°F so* I 2.0 I Long.
radius examination for this nozzle.
(RPV)
(Shell) 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 N48
- 0* Loop IW8-2500-7 8-D (Nozzle) 12 in. ID/
1045 psig I 45* I 1.0 I Shear nozzle configuration. Essentially 100%
Nozzle to Volumetric 2R10 6-7/16 in.@
55" I 1.0 I Shear 80.3%
Yes coverage was achieved for inner radius (709000)
Vessel Weld (UT) 83.90 SA-533 Gr. 8 RPV Shell 535°f so* I 2.0 I Long.
examination for this nozzle.
(RPV)
(Shell) 70" I 2.0 I Long.
(Enc. 2 Pg. Nos. 27 & 28)
Feedwater The examination was limited due to "D" Loop IW8-2500-7 SA-508CI. 2 12 in. ID I nozzle configuration and the proximity N4D Nozzle to Volumetric 8-D 2R12 (Nozzle) 6-7/16 in.@
1045 psig I 55* I 1.0 I Shear 84.2%
Yes of the N 11 8 nozzle. Essentially 100%
(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 (RPV)
(Shell) examination for this nozzle.
(Enc. 2 Pg. Nos. 34, 35, & 37)
Feedwater SA-508CI. 2 o* I 2.25 I Long.
The examination was limited due to N4E "E" Loop IW8-2500-7 8-D (Nozzle) 12 in. ID I 1045 psig I 45" I 1.0 I Shear nozzle configuration. Essentially 100%
Nozzle to Volumetric 2R10 6-7/16 in.@
55' I 1.0 I Shear 80.3%
Yes coverage was achieved for inner radius (709900)
Vessel Weld (UT) 83.90 SA-533Gr. 8 RPV Shell 535°f so* I 2.0 I Long.
examination for this nozzle.
(RPV)
(Shell) 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 1 O 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)
Feedwater o* I 2.25 / Long.
The examination was limited due to "F' Loop IW8-2500-7 SA-508CI. 2 12 in. ID I 45* / 1.0 I Shear proximity of insulation by the stabilizer N4F Nozzle to Volumetric 8-D 2R09 (Nozzle) 6-7/16 in.@
1045 psig I 55" / 1.0 I Shear 80.1%
Yes brackets. Essentially 100% coverage (710200)
Vessel Weld (UT) 83.90 SA-533Gr. 8 RPV Shell 535"F 60" / 2.0 I Long.
was achieved for inner radius (RPV)
(Shell) 70" I 2.0 I Long.
examination for this nozzle.
(Enc. 2 Pg. Nos. 7, 8, 9, & 37)
Core Spray SA-508CI. 2 The examination was limited due to N58
'A' Loop IW8-2500-7 8-D (Nozzle) 12 in. ID/
1045 psig I 55" / 1.0 I Shear nozzle configuration. Essentially 100%
(710800)
Nozzle to Volumetric 83.90 2R09 SA-533 Gr. 8 6-7/16 in.@
535°F 60" / 3.0 I A. Long.
85.3%
Yes coverage was achieved for inner radius Vessel Weld (UT)
RPV Shell examination for this nozzle.
(RPV)
(Shell)
(Enc. 2 Pg. Nos. 10 & 11)
Jet Pump The examination was limited due to lnstrumentati IW8-2500-7 SA-508 Cl. 2 6 in. OD/
nozzle configuration. Essentially 100%
N88 on 'A" Loop 8-D (Nozzle) 1045 psig I (711300)
Nozzle to Volumetric 83.90 2R10 SA-533 Gr. 8 6-7/16 in.@
535"F 60"/ 3.0 I A. Long.
83.7%
Yes coverage was achieved for inner radius Vessel Weld (UT)
(Shell)
RPV Shell examination for this nozzle.
(RPV)
(Enc. 2 Pg. Nos. 31 & 32)
LPCl"C' SA-508CI. 2 The examination was limited due to N17D Loop Nozzle IW8-2500-7 8-D (Nozzle) 12 in. ID I 1045 psig I 55" / 1.0 I Shear nozzle configuration. Essentially 100%
(712600) to Vessel Volumetric 83.90 2R09 SA-533Gr. 8 6-7/16 in.@
535"F 60" I 3.0 I A. Long.
84.7%
Yes coverage was achieved for inner radius Weld (UT)
RPV Shell examination for this nozzle.
(RPV)
(Shell)
(Enc. 2 Pg. Nos. 2 & 3)
Outlet Nozzle IWC-2500-4(a)
SA-350 LF2 The examination was limited due to 28E-205R N-(N-4) to Shell or(b)
C-8 (Nozzle) 20 in. ID I 285 psig I 45* / 2.25 /Shear nozzle configuration. 91 % coverage Surface and 2R13 1.0 in.@
70" / 2.25 /Shear 53.0%
No 4-1 (362501)
Weld Volumetric C2.21 SA-516 Gr. 70 HXShell 240"F was achieved for MT examination.
(AHR)
(UT)
(Shell)
(Enc. 2 Pg. No. 36)
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 1 O CFR 50.55a Relief Request 13R-23 Proposed Alternative in Accordance with 1 O 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.
DCA-420-1 10" Pipe to IWB-2500-9 SA-358 40" / 2.0 I R. Long.
The examination was limited due to FW1 Safe End IWB-2500-10 A-A 2A09 TP316L 10 in. NPS/
1045 psig I 45* / 1.5 /Shear 72.0%
Yes component configuration.
(023900)
(CS)
IWB-2500-11 A1.11 (0.02% max 0.594 in.
535°F 49* / 2.0 I A. Long.
(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 SW1502 HV IWB-2500-10 A-A 2A09 SA*376 TP316 12 in NPS/
1280 psig/
45* / 1.5 /Shear 50.0%
Yes single sided access (valve configuration (328405) 2F0508 Pup IWB*2500-11 A1.11 0.688 in.
539°F 60" / 2.0 I R. Long.
interference).
Piece Volumetric (Enc. 2 Pg. Nos. 14 & 15)
(AHR)
(UT) 12" Valve IWB-2500-8(c)
DCA-204-3 HV IWB-2500-9 SA-358 a* 14.0 I Long.
The examination was limited due to SW1101 2F0508to IWB-2500-10 A-A 2A09 TP316L 12 in. NPS I 1280 psig I 45* / 1.5 / Shear 50.0%
Yes single sided access (valve configuration (323506)
Pup Piece IWB-2500-11 R1.11 (0.02% max 0.688 in.
539°F 60" / 2.0 I R. Long.
interference).
(AHR)
Volumetric Carbon)
(Enc. 2 Pg. Nos. 12 & 13)
(UT)
IWB-2500-8(c) 38" / 2.0 IR. Long.
IWB-2500-9 SA-358 49* I 2.0 I R. Long.
The examination was limited due to DCA-418-4 12" Pipe to IWB-2500-10 A*A TP316L 12 in. NPS/
1045 psig /
45" / 1.5 /Shear component configuration, 8 degree FW1 Safe End 2R09 45* / 2.0 I R. Long.
78.0"lo Yes (350600)
(AHR)
IWB-2500-11 A1.11 (0.02% max 0.688 in.
535°F 51" / 2.0 I A. Long.
taper between pipe and safe end.
Volumetric Carbon)
(Enc. 2 Pg. Nos. 16 & 17)
(UT) 60" I 2.0 I R. Long.
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 1 O 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)
DCA-419-1 12" Elbow to IWB-2500-9 SA-358 The examination was limited due to FW7 Pipe IWB-2500-10 A-A 2A10 TP316L 12 in. NPS I 1045 psig I 45" / 1.5 / Shear 70.0%
Yes interference from lugs from a pipe (015500)
(CS)
IWB-2500-11 R1.20 (0.02% max 0.688 in.
535"F support.
Volumetric Carbon)
(Enc. 2 Pg. No. 20)
(UT) 26" Valve The examination was limited due to EBB-201-1 HV IWC-2500-7(a)
FW33 2F028C to Volumetric A-A 2A10 SA-106Gr. C 26 in. NPS I 1053 psig I 45" / 2.25 /Shear 75.0%
Yes physical limitations when scanning in (205500) 26" Pipe ID.
(UT)
R1.20 0.928 in.
533°F the axial direction on valve side of weld.
(MS)
(Enc. 2 Pg. No. 21)
GBB-205-2 16" Elbow to IWC-2500-7(a) 45" 15.0 I Shear The examination was limited due to FW8 Valve HV Volumetric A-A 2R10 SA-106 Gr. B 16 in. NPS I 285 psig I 70" I 5.0 I Shear 87.5%
Yes component configuration on (406000) 2F021B (UT)
R1.20 0.375 in.
188"F downstream side of weld.
(AHR)
(Enc. 2 Pg. Nos. 22, 23, & 24)
IWB-2500-8(c)
DCA-201-1 6"x6"x6" Tee IWB-2500-9 SA-312 The examination was limited due to tee FW13 to6" Pipe IWB-2500-10 A-A 2R12 TP316L 6in. NPS/
1045 psig I 45" / 2.25 /Shear 76.9%
Yes configuration.
IWB-2500-11 R1.20 (0.02% max 0.432 in.
535"F 70" I 2.25 / Shear (663300)
(RWCU)
Volumetric Carbon)
(Enc. 2 Pg. No. 33)
(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)
Limerick Generating Station Unit 1 Third Inservice Inspection (ISi) Interval Limited Coverage Non-Destructive Examination (NDE) Coverage Plots Limerick Generating Station Unit 1 Third Inservice Inspection (ISi) Interval Limited Coverage Non-Destructive Examination (NDE) Coverage Plots
I I
Unit 1 Limerick Generating Station Third ISi lnte~al Limited Coverage NOE Coverag,~e....:.P
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Wall Thickness Profile Sheet Site:
Project Limerick Unit L/1Rl2
. I HITACHI I
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LL LIAI System:
RWCU Position o*
90*
180° 1
0.236 NIA NIA 2
0.244 NIA NIA 3
0.245 NIA NIA 4
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270° NIA NIA NIA NIA NIA 3/ll/2008 Dote:
c t ID Number.
RW ll8
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Nominal Dia meter:
2.(1' UPST Component Weld Lengtt 7.11' i
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Report No.:
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3 0.723 0.789 0.720 0.739 I
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0.886 0.871 0.825 0.820 V4L\\J£ i
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Wall Thickness Profile Sheet Site:
Project Limerick l/lRl2 Component ID Number:
DCA-104-03 W801
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l.O" Nominol Diameter:
&Jr Weld Length:
40.25" DC A-ITT'r-'~
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RHR Position o*
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l 0.667 0.668 0.642 2
0.678 0.658 0.640 3
0.730 0725 0.653 4
-* I Unit 1 Limerick Generating Station Third ISi lnt~al Limited Coverage NOE Coverage Plots Wall Thickness Profile Sheet Site:
Project Limerick Ll1R12 Component ID Number:
DCA-104-01 W1402
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[fJ 0.658 Crown Height
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l.O" 0.720 Nominal Diameter:
12.0" E!1e£ UPST Component NIA Weld Length:
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Page,4 of 23 0
Page L.j of 7
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1 6.3° 7.9" so*r so*p I
I Limerick Unit-1 Recirc Inlet N2 Component: N2A (600700) 60° 54 Exam Volume = 8.5 Sq. In.
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.
15.7" 60"T I
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6.3" 7.9" 60"T 60"P I
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Page6 of23 I
I Limerick Unit-1 Recirc Inlet N2 Component: N2F (600850) 60° S4 Exam Volume = 8.5 Sq. In.
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.
15.7" 60"T I
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i Page 7 of 23 6.7' 8.0" so*r so*p I
I Limerick Unit-1 Main Steam N3 Component: N3D (601090) 60° S4 Exam Volume = 10.6 Sq. In.
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.
17.6" 60"T I
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o.o*
I I
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I Page 8 of23 Limerick Unit-1 Core Spray N5 Component: N58 (601330) 60° S4 Exam Volume = 8.5 Sq. In.
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.
15.7" 60"T I
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Page 9 of23 CRD Return N9 Component: N9 (601460) 60° S4 Exam Volume = 8.5 Sq. In.
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.
15.7" 60"T I
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6.3" 7.9" so*r so*p I
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'age\\10 of 23 Limerick Unit-1 LPCIN17 Component: N178 (601520) 60° S4 Exam Volume = 8.5 Sq. In.
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.
15.7" 60"T I
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~
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Limerick Generatina Station Third ISi ln~im Wall Thickness HITACHI Profile Sheet System:
Position I 1
I 2
I 3
I 4
I 5
I LPCI o*
I 90° 0.74" I NIA 0.72" I NIA 0.78 I NIA 1.00 I NIA 1.74" I NIA Joshua Ste/lakis Drawn by:
I I
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Component ID Number:
270' I
NIA Crown Height NIA Crown Width:
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Level:
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Page 11 of 23 I
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ted Coverage NOE Coverage Plots Site:
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602270 System:
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Component ID Number.
OCA-318-l FWl Configuration:
45°shr, ;45°RL1 60°RL
(-) Pipe Weld preps obtained from drawing; VPF#'s 2886-135-00 Flow er of weld build up LKDN - 60.8%
LKUP - 88.4%
LKCW-80.0%
LKCC - 80.0%
Limited Areas Total Procedure Coverage= n.4%
Michael Krueger Drawn by:
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Date: I GE Reviewed By:
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Limerick Generatin raae NDE Coveraae Plots J 1 HITACHI Wall Thickness Profile Sheet Site:
Limerick Unit I
Report No.:
System:
RR Posibon
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90" 1
1.16" 1.20" 2
I i.16" I l.lB" I 3
I 1.32" I 1.46" I 4
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BB!!Q?!!
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22.Cl' l.64" 1.60" Weld Length:
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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.
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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.
Onlt1 Limerick Generating Station Third ISi Interval Limited Coverage NOE Coverage Plots I
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HITACHI I System:
RHR Position o*
90" 180" 1
0.68" NIA NIA 2
0.66" NIA NIA 3
0.72" NIA NIA 4
0.72" NIA NIA 5
NIA NIA NIA t~.B J. Mike Bullen Initials:
Drawn by:
Level:
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Unit 1
_.,Liarnrick Generaling_Station Third ISU~aae NOE Coueiaue Plot<:
1
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HITACHI Indication I Coverage Plot Sheet Site:
Limerick Generating Station Unit Project Li1Rl5 Report Number.:
244801 System:
'.XJ/
Initials:
RHR Component ID Number:
RHR-HXAR-N4/R Configuration:
('VoZ..Z-LF Mark Hilborn Drown by:
N6'2..2.L..£ e £ r£1'.£ Ne. e Po\\/\\IT l.G,...
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Initials:
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Level:
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ited Coverage NOE Coverage Plots Limerick 1 - L1R15 Coverage Plot so* NS T Limerick 1 Feedwater Component: N4D (601210)
Feedwater - N4 Nozzle Proposed Manual UTT-Scan examintion 60" FVT Page 20 of 23
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Unit 1 Exel6ftk""Generating Station Third ISi Interval Limited coverage NOE coverage Plots Nuclear ER-AA-335-016 Revision 7 Page 18 of 18 ATTACHMENT 2 VT-3 Visual Examination NOE Report for Component Supports, Attachments and Interiors of Reactor Vessels p
f aae 1 o 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 THREAD ENGAGEMENT/BOLT ELONGATION/wELOMENT x
6 SPALLEO CONCRETE OR GROUT/ANCHOAS/IMBED x
7 CLEARANCES/TAA VEL STOPS/PINS x
B ENVIRONMENT x
See limitations I obstructions 9
LOCKNUT/PIN/TACKWELO SECURING CAN SETTING x
10 NON-INTEGRAL ATTACHMENT LOOSE/INSUL DAMAGED x
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
~
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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 NOTE:
SHaL N0.5 0
Nl2B SHELL NO. 4 1140 m
SI-ELL NO. 3 0
Nl7C Nl6B SHELL N0.2 N2G 0
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~~llEY a.re I ISSUED FOR lST IT O<<D
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MOC f/lft VESSEL ELEV.
716.25" I
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325'*11.25"
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zqcr-1,5" VESSEL ELEV.
263.5" I 21'-ll.5" 1111 I SITE ELEV.
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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.
S0° FVT I
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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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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.
60° NS T-scan 60° FV T-scan I
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60° FV Exam Volume = 39.2 Sq. In.
Inner 15%T Exam Volume (IRS & 60°T) = 8.5 Sq. In.
60° P-Scan achieved = 6.0 Sq. In.
60° P-Scan achieved = 33.2 Sq. In.
Inner 15% T P-Scan(IRS & 60°P) achieved = 8.5 Sq. In.
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Page 11 of37
GE ENERGY NUCLEAR Sys1em*
RHR Pos1uon a-90" 180' 270" 1
NIA NIA 0.64 NIA NIA NIA 1.25 NIA v
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GE ENERGY NUCLEAR Site: Limerick Weld ID DCA-204-3 SW1101 Drawing:
Xl-DCA-204-1 Lo Location: Top Dead Center o*
Wo Location: Weld Centerline Ind I Angle
% of Indication Len th No Used DAC l1 L Max L2 45*
100 2
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25 26.25 26.5 27.25 Sketch
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.925" 1.4" Metal Path MP1 MP Max
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Thickness:
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1.3" Weld Height:.050" Ax/
UpsU MP2 Circ Dnst Ax DNST Countllrbonl 360"
.--~-* --
.836 Ax DNST ln18nnlltent Root Ga~lry 360"
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Data Report Number:
6 Cal I Data Sheet Number UT-005 Comments:
Exam Start:
1645 Exam End:
1902
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!1 31812007 Date:
Date:
ANll Review:
Date:
Exam mer Leve Page 13 of 37 Page
§ of 7
Unit2 Limerick Generating Station Third ISi lnte'Miieimited Coverage NOE Coverage Plots GE ENERGY NUCLEAR Wall Thickness Profile Sheet Site:
Limerick Project:
L/2R09 System:
~
RHR Pos1uon o<
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180' 270' Component ID Number:
DCA-204-1 SW1502 OJ 12 1
NIA NIA 0.685 NIA Crown Height:
Flush 2
1.3" 3
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Nominal Diameter:
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40.75" FLOW
'lb~
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Date:
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Page 14 of 37 Unit:
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328405 14 I
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Page
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~I GE ENERGY NUCLEAR Weld ID: DCA-204-1 SW1502 Lo Location: Top Dead Center 0° Unit2 Limerick CUTffiiii'b~1~rekiact,WJtr~Bi31~e~f~alr~fi ~~~~Wge Ptots I
Site: Limerick Procedure: GE-PDl-UT-21 Rev. 41 NIA Drawing:
Xl-DCA-204-3 Size: 11::
Thickness:
.810" Wo Location:
Weld Centerline Weld Width: 1.r Weld Height: Flush Upst/
Data Report Number:
Cal I Data Sheet Number YI:!!f1g_
Exam Start:
1620 Exam End:
1804 j Ind No Angle I
% of Indication Len th W Distance Metal Path Used DAC L 1 L Max L 2 W1 W Max W 2 MP 1 MP Max MP 2 Ax/
Circ Dnst I Comments:
1 2
Ske1ch 45*
22 19.5 19.75 21 N/A
.825 1.5 1.025 1.150 45° 22 FLOW
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- Verified vllually during In shop fabrication
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Joev Clairday Examiner
.J-/tJ.(;7 l1 31812001 3~.;;01~/#7 j
Level Date Page 15 of 37 Page
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e GE ENERGY, NUCLEAR S*)1s:
RHR t*'
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Wall Thickness Profile Sheet Component ID Number DCA-418-4 FW1 Crown Height FLUSH Crown Width 1.7" Nominal Diameter 12.0" Weid Length 410" i
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Date 1 Site Limerick Unit g I Report No I Project.
i Li2R09 350600 I
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HITACHI System:
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.390"
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Page 22 of 37
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1§.Q'.'.
Thickness:
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Page 24 of 37
it.2 Limerick Generating Station Third ISi lilhiV~imited Coverage NOE Coverage Plots I
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60D NS T I
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.
SOD FVT I
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T-Scans I
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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 70°T 45°T I
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60° NS T I
Page 31of37 60° FVT I
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60° NS P-Scan achieved = 5.3 Sq. In.
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45° IRS P-Scan achieved = 8.5 Sq. In.
60°P NS I
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Page 32 of 37
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60" FS Bean Vdi..rre = 14.8 Sq. In.
lmer 15%T Bean Vdt..rre (IRS & 60"1) = 3.2 Sq. In 60" P-Scan adliaied = 2.4 Sq. In 60" P-Sca'1 adliaied = 14.6 Sq. In 60"&45" IRS P-Sc:an adlievOO = 3.2 Sq. In 60"&45" N'V I
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Limerick Generating Station Third ISi lnte..Val ited Coverage NOE Coverage Plots Supplemental Report Component: 2BE-205R N-4-1 (362501)
Summary No.: 362501 I 11<< #~
Examiner: Mahoney, Patrick V.
Level:
II Reviewer:
Examiner: NIA I
Level:
NIA 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 = AREA2)
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/.878H2=1% =99%
Scan Coverage with the 70". (45% additional coverage with the 70") TOTAL OF 99%
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.
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 SHE:LL 5A-51G.- GRr/lJ Page 36 of 37
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Report No.:
Page:
I I
t\\.L:i ~ t.. L ~
UT-15-007 3
of 4
Date: ()Cr~./t Date: 4 * 'Z \\- I.OS--
Date: 9/ zi/r S-J 5A-~5D*LF-2
Unit2 Limerick Generating Station Third ISi Interval Limited Coverage NDE Coverage Plots CLOSURE HEAD FLANGE ---,
STUD *76 \\
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- 1 <TYPICAL 76 STUDSI LOCATION
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VESSEL ELEY.
Sct-8.25"
~ *\\!H6.W Hll
~
~
N3A NE '
SITE EL.EV.
0 0
0 325'-11.259 SHELL t<<).5
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~
VESSEL ELEV.
~
51'-U.S-0 0
~1 0 0
SITE a.EV.
318'-2.59 Nl28 Sl£LL NO. 4 N120 Nl2H H12C VESSEL ELH.
537.5" 44*.q.s"
~
~J 0
0 :r 0
0 0
SITE ELEV.
0 0
311'-5" N40 N4E N4f N4A N48 iii N4C SHELL N0.3 tfiB N5A H'J 0 VESSEL ELEV.
AC 400.5*
33'-4.S-
..._,Nl7B SITE ELEV
- 0
'-.../
el 0
'-.../
0
~1
'-.../
0 2qq'-7.5" N168 N17C N160 lf170 N16A m7A N16C Iii SHELL N0.2 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" 0
VESSEL £1.EV.
19'-S.S*
I ~
~..
SITE El.EV.
180 ° 249° 279° 276'-C\\.5"
'IDTE:
SEE Xl-RPV-2 PG. 2 FOR AZIMUTH ANO ELEVt.TlON TABLES.
ELEV. 0* CREF>=266 '3" REACTOR PRESSURE VESSEL Pf PRESENTS AN AREA WHERE SCANNING INTERFERENCES EXIST.
~~
'"1sI DRAWING - RE~T~ BUILDING RPV SCAN LIMJT A Tl~ DRAWit<<i UNlT 2 i~"' catt ISSUED FOR !ST" O<<D mEMI mtU u
'at..,
ow"°
- 1--1£. ~~ INSP. INTERVAL.
MOC ~ ~
~ R'J 8031 Xl-BA-8 PHlLADELPHlA ELECTRIC COMPANY LGS ~ITS l & 2 Nll FOO COOTROCTJ~
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