ML19267A024
| ML19267A024 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/24/2019 |
| From: | David Gudger Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NMP2-2708 | |
| Download: ML19267A024 (63) | |
Text
{{#Wiki_filter:Exelon Generation ~. 200 Exelon Way Kennett Squa re, PA 19348 www.exeloncorp.com 10 CFR 50.55a NMP2-19-2708 September 24, 2019 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRC Docket No. 50-410
Subject:
End of Interval Relief Request Associated with the Third Ten-Year lnservice Inspection (ISi) Interval In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(5)(iii), Exelon Generation Company, LLC (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 October 5, 2018, for the Nine Mile Point Nuclear Station, Unit 2. The third ten-year ISi interval complied with the ASME Boiler and Pressure Vessel Code, Section XI, 2004 Edition with no Addenda. There are no regulatory commitments in this letter. Exelon requests approval of this relief request by September 24, 2020. If you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510. Respectfully, Jc-.__ j y- j,__ J Y"-- David T. Gudger Acting Director - Licensing Exelon Generation Company, LLC Attachments: 1) Relief Request 21Sl-014
- 2) Nine Mile Point Nuclear Station Unit 2 Third lnservice Inspection Interval Limited Coverage Non-Destructive Examination Reports
End of Interval Relief Request Associated with the Third Ten-Year lnservice Inspection (ISi) Interval September 24, 2019 Page2 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, NMP Project Manager USNRC, NMP A. L. Peterson, NYSERDA
Attachment 1 Relief Request 2181-014
ATTACHMENT 1 10 CFR 50.55a Relief Request 21$1-014 in Accordance with 10 CFR 50.55a(g)(5)(iii)
-lnservice Inspection Impracticality--
Revision O (Page 1 of 12)
- 1. ASME Code Component(s) Affected Code Class: 1&2
Reference:
IWB-2500, Table IWB-2500-1, IWC-2500, Table IWC-2500-1, ASME Code Case N-460, ASME Code Case N-578-1, Table 1, ASME Code Case N-716, Table 1. Examination Category: 8-A, 8-0, C-A, R-A Item Number: 81.40, 814.10, C1.10, R1.11, R1.16, R1.20
Description:
Limited Examination Coverage Component Number: See Table 21Sl-014.1 for a list of Component ID's
2. Applicable Code Edition and Addenda
The third 10-year interval of the Nine Mile Point Nuclear Station, Unit 2 lnservice Inspection (ISi) Program was based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," 2004 Edition with No Addenda. The Nine Mile Point Nuclear Station, Unit 2 maintains the responsibility to ensure examinations 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. Table 21Sl-014.1 identifies whether each listed best effort examination was performed in accordance with the requirements of ASME Section XI, Appendix VIII.
- 3. Applicable Code Requirements The extent of examination requirement for Examination Category 8-A, Item Number 81 .40, per Table IWB-2500-1, requires a volumetric and surface examination for the closure head-to-flange weld of essentially 100% of the weld length.
The extent of examination requirement for Examination Category B-0, Item Number 814.10, per Table IWB-2500-1, requires a volumetric or surface examination of the pipe-to-pipe welds and pipe-to-flange-welds in Control Rod Drive (CRD) housings. The extent of examination requirement for Examination Category C-A, Item Number C1.10, per Table IWC-2500-1, requires a volumetric examination for the flange-to-shell weld of essentially 100% of the weld length. The RI-ISi Program in accordance with ASME Code Case N-578-1 was implemented at the beginning of the third ISi interval through the middle of the second period per Relief Request 21Sl-007, which included outages N2R12 and N2R13. Relief Request 21Sl-007 (ML080250410) was submitted and then was approved by the NRC in a Safety Evaluation Report dated December 1, 2008 (ML083190494) in order to utilize EPRI Topical Report (TR) 112657, Rev. 8-A, as supplemented by ASME Code Case N-578-1.
ATTACHMENT 1 10 CFR 50.55a Relief Request 2181-014 in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 2 of 12) The RI-ISi Program was updated to comply with ASME Code Case N-716 per Relief Request 21Sl-011 (ML12306A088). This Code Case was implemented during the middle of the second period of the third ISi interval, which included outages N2R14, N2R15, and N2R16. Relief Request 21Sl-011 was approved in a Safety Evaluation Report dated October 24, 2013 (ML13290A172). The extent of examination requirement for Examination Category R-A, Item Numbers R1 .11 and R1 .16, per Table 1 of ASME Code Case N-578-1 and Table 1 of ASME Code Case N-716, requires a volumetric examination of essentially 100% of the length of the Risk Informed lnservice Inspection (RI-ISi) weld. Nine Mile Point Nuclear Station, Unit 2 adopted ASME Code Case N-460 ("Alternative Examination Coverage for Class 1 and Class 2 Welds, Section XI, Division 1"), which defines "essentially 100%" as greater than 90% coverage of the examination volume or surface area, as applicable. The 90% minimum coverage was applied to all surface and volumetric examinations required by ASME Section XI.
- 4. Impracticality of Compliance In accordance with 10 CFR 50.55a{g){5)(iii}, relief is requested on the basis that conformance with these ASME Section XI requirements is impractical since conformance would require extensive structural modifications to the component or surrounding structure.
Due to the original design of these components, Nine Mile Point Nuclear Station, Unit 2 is unable to satisfy the ASME Section XI requirements to perform a surface or volumetric examination to the extent required for welds and welded attachments (greater than 90% of the volume or area) due to physical component configuration, interference from permanent plant equipment, single-sided access, etc. Nine Mile Point Nuclear Station, Unit 2 would incur significant engineering, material, and installation costs to perform such modifications without a compensating increase in the level of quality and safety. Therefore, relief is requested on the basis that the ASME Section XI requirements to examine these components are impractical. During outages, when situations were identified where coverage was an issue, Nine Mile Point Nuclear Station, Unit 2 personnel reviewed the systems for alternatives. For the RI-ISi weld population, Examination Category R-A welds, submitted in this relief request, a case by case review was performed to determine whether additional or alternative welds could have been examined to supplement the reduced volumetric coverage examination. It was determined that there were no other welds to select that would have resulted in better coverage. This determination was made based on comparison of configurations, delta core damage frequency (GDF) values, the systems involved, and inspection history. Table 21Sl-014.1 provides 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
ATTACHMENT 1 10 CFR 50.55a Relief Request 2151-014 in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 3 of 12) design information. This table is the cumulative list of the limited ASME Section XI examinations performed during the third ISi interval. Attachment 2 provides coverage plots which were extracted from the non-destructive examination (NOE) summary sheets that detail the examination limitations. Based on the above explanation, Nine Mile Point Nuclear Station, Unit 2 requests relief to perform examinations without achieving ASME Section XI compliance coverage when the required coverage is impractical.
- 5. Burden Caused by Compliance Compliance with the applicable ASME Section XI volumetric and surface examination requirements can only be accomplished by redesigning and refabricating the subject and/or surrounding components. Based on this, the ASME Section XI requirements are deemed impractical in accordance with 10 CFR 50.55a{g){5)(iii).
- 6. Proposed Alternative and Basis for Use Nine Mile Point Nuclear Station, Unit 2 has performed the ASME Section XI required examinations to the maximum extent practical (Code Coverage), or best effort, which are documented in Table 21Sl-014.1. Due to the physical interferences causing these limitations, there are no alternative examination techniques currently available to increase coverage. There were no cases in any of the listed examination where the component's outside diameter surface features (i.e., weld crowns, weld shrinkage, surface roughness, etc.) could have been conditioned to obtain the required coverage without major modification to the components.
Periodic system pressure tests that include VT-2 visual examinations will continue to be performed in accordance with ASME Section XI, Examination Category B-P, for Class 1 pressure retaining welds and components during each refueling outage, and Examination Category C-H for Class 2 pressure retaining welds and components each inspection period of Table IWB-2500-1 and Table IWC-2500-1, as well as, any applicable system pressure testing augmented examination programs. The absence of any observed leakage provides additional assurance that the structural integrity of the subject components will be maintained throughout the remainder of the interval. As a minimum, all components received the required volumetric or surface examinations and will continue to be conducted to the maximum extent practical due to limited or lack of access as required by the ASME Section XI ISi Program, the RI-ISi Program, or other applicable augmented examination programs such as the Nine Mile Point Nuclear Station, Unit 2 IGSCC Program.
- 7. Duration of Proposed Alternative Relief is requested for the third ISi interval for Nine Mile Point Nuclear Station, Unit 2.
ATTACHMENT 1 10 CFR 50.55a Relief Request 21SIM014 in Accordance with 10 CFR 50.55a(g)(5)(iii) MMlnservice Inspection lmpracticalityMM Revision O (Page 4 of 12)
- 8. Precedents The following similar end of interval impracticality relief requests have been previously authorized by the NRC:
- Watts Bar Nuclear Plant, Unit 1 second ISi interval Relief Request 1-ISl-21 was authorized per NRC Safety Evaluation Report dated April 12, 2019 (ADAMS Accession No. ML19071A009).
- Limerick Generating Station, Units 1 and 2 third ISi interval Relief Request 13R-23 was authorized per NRC Safety Evaluation Report dated August 7, 2018 (ADAMS Accession No. ML18192C172).
- Surry Power Station Unit 2 fourth ISi interval Relief Requests related to limited coverage examinations in the fourth 10-year ISi interval were authorized per NRC Safety Evaluation Report dated February 17, 2017 (ADAMS Accession No. ML16365A118).
ATTACHMENT 1 10 CFR 50.55a Relief Request 2151-014 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 5 of 12) Table 2151-014.1 Nine Mile Point Nuclear Station, Unit 2 List of Components with Limited Examination Coverage Class/ Normal Exam Appendix Weld Exam Diameter/ Operating Exam Angle/ Requirements Outage Material of Actual VIII Component ID Description Category/ Line No. / Conditions Frequency (MHz) Remarks (Figure No.) Examined Construction Coverage Qualified (System)' Item Thickness (Pressure I /Mode and Method Exam Number Temperature) The examination was limited due to Inherent obstructions caused by adjoining components. Disassembly of the CRD mechanisms does not facilitate additional coverage for the 2RPV- CRD 18-03 Weld: 1016psi-IW8-2500-18 1 4.o* required surface examination areas CRDH001A Pipe-to- Austenitic Pressure Surface 8-0 N2A12 APV NIA I NIA I NIA 43% No and redesign of the CAD (N2-ISI- Flange Weld Stainless Steel 550 degrees - (PT) 814.10 0.365" mechanisms to provide access is 068800) (APV) SS304 Temperature not practical. (Att. 2
- Pg. Nos. 2
- 3)
Location CAD 18-03. Limitation due to vertical tubing . Need to ooen insulation access oanels. The examination was limited due to Inherent obstructions caused by adjoining components. Disassembly of the CAD mechanisms does not facilitate additional coverage for the 2APV- CAD 18-03 Weld: 1016 psi - IW8-2500-18 1 4.0" required surface examination areas CADH0018 Pipe-to-Pipe Austenitic Pressure Surface 8-0 N2A12 APV NIA I NIA I NIA 80% No and redesign of the CAD (N2-ISI- Weld Stainless Steel 550 degrees - (PT) 814.10 0.365" mechanisms to provide access is 068900) (APV) SS304 Temperature not practical. (Att. 2
- Pg. Nos. 4
- 5)
Location CAD 18-03. Limitation due to vertical tubing. Need to ooen insulation access nanels. Note:
- 1. The following systems and their abbreviations are listed here: High Pressure Core Spray (CSH), Low Pressure Core Spray (CSL), Reactor Building (Drywell) Equipment Drains (DER), Reactor Core Isolation Cooling (ICS), Reactor Pressure Vessel Instrumentation (ISC), Reactor Recirculation (RCS), Reactor Pressure Vessel (RPV), Reactor Pressure Vessel Closure Head (RPVCH), Standby Liquid Control (SLS), and Reactor Water Cleanup (WCS)
ATTACHMENT 1 10 CFR 50.55a Relief Request 21$1-014 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 6 of 12) Table 2151-014.1 Nine Mile Point Nuclear Station, Unit 2 List of Components with Limited Examination Coverage Class/ Normal Exam Appendix Weld Exam Diameter/ Operating Exam Angle/ Requirements Outage Material of Actual VIII Component ID Description Category/ Line No. / Conditions Frequency (MHz) Remarks (Figure No.) Examined Construction Coverage Qualified (System)' Item Thickness (Pressure I /Mode and Method Exam Number Temperature) The examination was limited due to Inherent obstructions caused by adjoining components. Disassembly of the CAD mechanisms does not facilitate additional coverage lor the 2APV- CAD 30-03 Weld: 1016 psi-IW8-2500-18 1 4.0" required surface examination areas CADH004A Pipe-to- Austenillc Pressure Surface 8-0 N2A12 APV NIA I NIA I NIA 43% No and redesign of the CAD (N2-ISI- Flange Weld Stainless Steel 550 degrees - (PT) 814.10 0.365" mechanisms to provide access is 069400) (APV) SS304 Temperature not practical. (Att. 2
- Pg. Nos. 6
- 7)
Location CAO 30-03. Limitation due to vertical tubing. Need to ooen insulation access oanels. The examination was limited due to Inherent obstructions caused by adjoining components. Disassembly of the CAD mechanisms does not facilitate additional coverage for the 2APV- Weld: 1016psi-CAD 30-03 IW8-2500-18 1 4.0" required surface examination areas CADH0048 Austenillc Pressure Pipe-to-Pipe Surface 8-0 N2A12 APV NIA I NIA I NIA 75% No and redesign of the CAO (N2-ISI- Stainless Steel 550 degrees - (RPV) (PT) 814.10 0.365" mechanisms to provide access is 069500) SS304 Temperature not practical. (Att. 2 - Pg. Nos. 8 -10) Location CAO 30-03. Limitation due to vertical tubing. Need to ooen insulation access oanels. Note: I. The following systems and their abbreviations are listed here: High Pressure Core Spray (CSH), Low Pressure Core Spray (CSL), Reactor Building (Drywell) Equipment Drains (DER), Reactor Core Isolation Cooling (ICS), Reactor Pressure Vessel Instrumentation (ISC), Reactor Recirculation (RCS), Reactor Pressure Vessel (RPV), Reactor Pressure Vessel Closure Head (RPVCH), Standby Liquid Control (SLS), and Reactor Water Cleanup (WCS)
ATTACHMENT 1 10 CFR 50.55a Relief Request 21$1-014 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision O (Page 7 of 12) Table 2151-014.1 Nine Mile Point Nuclear Station, Unit 2 List of Components with Limited Examination Coverage Class/ Normal Exam Appendix Weld Exam Diameter/ Operating Exam Angle/ Requirements Outage Material of Actual VIII Component ID Description Category I Line No./ Conditions Frequency (MHz) Remarks (Figure No.) Examined Construction Coverage Qualified (System)' Item Thickness (Pressure I /Mode and Method Exam Number Temperature) Weld: Austenitic IW8-2500-8(c), Stainless Steel The examination was limited due to 2WCS-09 4.0' 1037 psi - Sweep IW8-2500-9, 1 SA 312TP 45' 12.251 Shear sweep-o-let-to*pipe configuration FW014 2WCS-004- Pressure Let-to-Pipe 10, & 11 A-A N2A12 316L- piping to 70" / 2.25 / Shear 50% Yes (single-sided examination (N2-ISI- 92-1 552 degrees - (WCS) Volumetric A1.16 SA 182 F316L O' I 4.0 I Long coverage) on upstream side. 208400) 0.337' Temperature (UT) - sweep-o-let (Alt. 2 *Pg. No. 11) (fitting) (6000 lbl Weld: Austenitic IW8-2500-8(c), Stainless Steel The examination was limited due to 2WCS-09 Sweep 4.0' 1037 psi - FW015 Let-to-Pipe IW8-2500-9, 1 SA 312TP 2WCS-004- Pressure o* I 4.0 I Long sweep-o-let-to-pipe configuration 10, & 11 A-A N2A12 316L - piping to 45' I 2.251 Shear 50% Yes (single-sided examination (N2-ISI- Suction 98-1 552 degrees - Volumetric A1 .16 SA 182 F316L 70" 12.251 Shear coverage). 208600) (WCS) 0.337' Temperature (UT) - sweep-o-let (Alt. 2
- Pg. No. 12)
(fitting) (6000 lb) The examination was limited due to Inherent obstructions caused by adjoining components. Disassembly of the CAD 2APV- CAD 34-03 Weld: 1016 psi - IW8-2500-18 1 4.0' mechanisms does not facilitate CADH005A Pipe-to- Austenitic Pressure Surface 8-0 N2A13 APV NIA I NIA I NIA 63.8% No additional coverage for the (N2*1SI- Flange Weld Stainless Steel 550 degrees - (PT) 814.10 0.365" required surface examination areas 069600) (APV) SS304 Tempera lure and redesign of the CAD mechanisms to provide access is not practical.
!Alt. 2 *Po. No. 13}
Note: I. The following systems and their abbreviations are listed here: High Pressure Core Spray (CSH), Low Pressure Core Spray (CSL), Reactor Building (Drywell) Equipment Drains (DER), Reactor Core Isolation Cooling (ICS), Reactor Pressure Vessel Instrumentation (ISC), Reactor Recirculation (RCS), Reactor Pressure Vessel (RPV), Reactor Pressure Vessel Closure Head (RPVCH), Standby Liquid Control (SLS), and Reactor Water Cleanup (WCS)
ATTACHMENT 1 10 CFR 50.55a Relief Request 2151-014 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
-lnservice Inspection Impracticality-Revision O (Page 8 of 12)
Table 2151-014.1 Nine Mile Point Nuclear Station, Unit 2 List of Components with Limited Examination Coverage Class/ Normal Exam Appendix Weld Exam Diameter/ Operating Exam Angle/ Requirements Outage Materiel of Actual VIII Component ID Description Category/ Line No./ Conditions Frequency (MHz) Remarks (Figure No.) Examined Construction Coverage Qualified (System)' Item Thickness (Pressure I /Mode and Method Exam Number Temperature) The examination was limited due to inaccessibility. Disassembly of the CAD mechanisms does not 2APV- CAD 34-03 Weld: 1016 psi-IWB-2500-18 1 4.0' facilitate additional coverage for CADH005B Pipe-to-Pipe Austenitic Pressure Surface B-0 N2A13 APV NIA I NIA I NIA 63.8% No the required surface examination (N2-ISI- Weld Stainless Steel 550 degrees - (PT) 914.10 0.365' areas and redesign of the CAD 069700) (APV) SS304 Temperature mechanisms to provide access is not practical. IAtt. 2- Po. No. 141 The examination was limited due to Inherent obstructions caused by adjoining components. 2APV- Disassembly of the CAD CAD 34-59, Weld: 1016psi-IWB-2500-18 1 4.o* mechanisms does not facilitate CADH038A Pipe-to- Austenitic Pressure Surface 9-0 N2A13 APV NIA I NIA I NIA 85.1% No additional coverage for the (N2-ISI- Flange Weld Stainless Steel 550 degrees - (PT) 914.10 0.365' required surface examination areas 076200) (APV) SS304 Temperature and redesign of the CAD mechanisms to provide access is not practical. IAtt. 2- Pa. No. 15) The examination was limited due to inaccessibility. Disassembly of the 2APV- CAD mechanisms does not Weld: 1016 psi-CAD 34-59, IWB-2500-18 1 4.0' facilitate additional coverage for CADH038B Austenitic Pressure (N2-ISI-Pipe-to-Pipe Surface B-0 N2A13 APV NIA I NIA I NIA 74.4% No the required surface examination Stainless Steel 550 degrees - (APV) (PT) 914.10 0.365' areas and redesign of the CAD 076300) SS304 Temperature mechanisms to provide access is not practical. IAtt. 2 - Pa. No. 16) Note:
- 1. The following systems and their abbreviations are listed here: High Pressure Core Spray (CSH), Low Pressure Core Spray (CSL), Reactor Building (Drywell) Equipment Drains (DER), Reactor Core Isolation Cooling (ICS), Reactor Pressure Vessel Instrumentation (ISC), Reactor Recirculation (RCS), Reactor Pressure Vessel (RPV), Reactor Pressure Vessel Closure Head (RPVCH), Standby Liquid Control (SLS), and Reactor Water Cleanup (WCS)
ATTACHMENT 1 10 CFR 50.55a Relief Request 2151-014 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality-Revision O (Page 9 of 12)
Table 2151-014.1 Nine Mile Point Nuclear Station, Unit 2 List of Components with Limited Examination Coverage Class/ Normal Exam Appendix Weld Exam Diameter/ Operating Exam Angle/ Requirements Outage Material of Actual VIII Component ID Description Category/ Line No./ Conditions Frequency (MHz) Remarks (Figure No.) Examined Construction Coverage Qualified (System)' Item Thickness (Pressure I /Mode and Method Exam Number Temperature) The examination was limited due to the configuration of the flange and 2AHS"E1A,H "E1A Weld: Ferritic 50.0" 320 psi - IWC-2500-1 2 the adjacent weld. W101A Flange-to- Steel 2AHS-020- Pressure 45" / 2.25 /Shear Volumetric C-A N2A13 83.8% Yes (Alt. 2 *Pg. Nos. 17 -19) (N2-ISI- Shell SA 516 GA70 185-2 388 degrees - 70" / 2.25 /Shear (UT) C1.10 536000) (RHS) to SA 105 0.9" Temperature Includes essentially 100% of the weld lenath. Weld: The examination was limited due to Austenitic IWB-2500-8(c), pipe-to-weld-o-let configuration. 2SLS-88A- Stainless Steel 3.0" 1240 psi - Pipe-to- IWB-2500-9, 1 45" /5.0 I Shear (Alt. 2
- Pg. Nos. 20
- 21)
FW042A SA 106 GR B - 2SLS-002- Pressure 73% Weld-0-Let 10, & 11 A-A N2A13 60" I 5.0 I Shear Yes (N2-ISI- piping to SA 89-1 560 degrees - 64% (SLS) Volumetric A1 .11 10* I 5.0 I Shear 73% Al-ISi coverage obtained and 158500) 105 - weld-o-let 0.688" Temperature (UT) 64% procedure extended coverage (fitting) (6000 obtained. lb) The examination was limited due to IWB-2500-5 21 .3" head-to-flange weld configuration. Closure 1016 psi - 2APV-AG Volumetric 1 Weld: Ferritic RPV Head 65" / 2.25 / Long (Alt. 2
- Pg. Nos. 22
- 27)
Head-to- Pressure (N2-ISI- (UT) B-A N2A14 Steel to Flange 10* through 75" I 80.25% Yes Flange Weld 550 degrees - 047800) (RPVCH) and Surface 81.40 cs Weld Temperature 2.25 /Long Essentially 100% coverage was (PT/Mn 3.125" achieved for the surface examination. IWB-2500-8(c), 21SC-322B- Weld: 2.0" 1035 psi - Tee-to- IWB-2500-9, 1 The examination was limited due to SW005 Austenitic 21SC-002- Pressure 30" I 5.0 I Shear Reducer 10, & 11 A-A N2R15 85.5% Yes the code plate. (N2-ISI- Stainless Steel RPV-1 550 degrees - 45" I 5.0 I Shear (ISC) Volumetric R1.11 (Alt. 2
- Pg. No. 28) 150100) SS to SS 0.46" Temperature (Un Note:
- 1. The following systems and their abbreviations are listed here: High Pressure Core Spray (CSH), Low Pressure Core Spray (CSL), Reactor Building (Drywell) Equipment Drains (DER), Reactor Core Isolation Cooling (JCS), Reactor Pressure Vessel Instrumentation (ISC), Reactor Recirculation (RCS), Reactor Pressure Vessel (RPV), Reactor Pressure Vessel Closure Head (RPVCH), Standby Liquid Control (SLS), and Reactor Water Cleanup (WCS)
ATTACHMENT 1 10 CFR 50.55a Relief Request 2151-014 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
Revision 0 (Page 10 of 12) Table 2151-014.1 Nine Mile Point Nuclear Station, Unit 2 List of Components with Limited Examination Coverage Class/ Normal Exam Appendix Weld Exam Diameter/ Opereting Exam Angle/ Component ID Description Requirements Outage Material of Actual VIII Category/ Line No./ Conditions Frequency (MHz) Remarks (Figure No.) Examined Construction Coverage Qualified (System)' Item Thickness (Pressure I /Mode and Method Exam Number Temperature) Weld: Austenitic IWB-2500-8(c), Stainless Steel 2SLS-88A- 2.0' 1340 psi - Valve *v10- IWB-2500-9, 1 SA403 45* I 5.0 I Shear The examination was limited due to FW013A 2SLS-150- Pressure to-Reducer 10, & 11 R-A N2R15 WP316L- 70' / 2.25 I Shear 50% Yes valve-to-reducer configuration . (N2-ISI- 88-1 560 degrees - (SLS) Volumetnc R1 .11 valve to SA 10* 15.0 I Shear (Alt. 2 - Pg. Nos. 29 - 30) 156700) 0.344' Temperature (UT) 403 WP316L-reducer (Sch 801 Weld: IWB-2500-8(c), Austenitic 2SLS-88A- 2.0' 1340 psi - o* 14.0 I Long IWB-2500-9, 1 Stainless Steel The examination was limited due to FW015 Pipe-to-Tee 2SLS-150- Pressure 45' 15.0 I Shear 10, & 11 R-A N2R15 SA 312 TP 89% Yes pipe-to-tee configuration. (N2-ISI- (SLS) 88-1 560 degrees - 70" I 5.0 I Shear Volumetric R1 .11 316L- piping to (Alt. 2 - Pg. No. 31) 157100) 0.344' Temperature 70' 12.25 / Shear (UT) SA403WP 316L- tee Weld: IWB-2500-8(c), Austenitic The examination was limited due to 2WCS-09 1 4.o* 1037 psi - IWB-2500-9, Stainless Steel tee-to-pipe configuration. Axial SW024 Tee-to-Pipe R-A 2WCS-004- Pressure 45' / 2.25 /Shear 10, & 11 N2R15 SA 312 TP 89.79% Yes scanning restricted from the tee (N2-ISI- (WCS) R1 .11 & 80-1 552 degrees - 70' / 2.25 /Shear Volumetric 316L- piping to side for 3.0" at the radius of tee. 213900) R1.16 0.337" Temperature (UT) SA403WP (Alt. 2 - Pg. No. 32) 316L- tee Weld: Austenitic IWB-2500-8(c), 2WCS-09 1 Stainless Steel 4.0' 1037 psi- The examination was limited due to Pipe-to- IWB-2500-9, SW025 R-A SA312 TP 2WCS-004- Pressure 45' / 2.25 / Shear pipe-to-flange configuration (single-Flange 10, & 11 N2R15 75% Yes (N2-ISI- R1 .11 & 316L- piping to 80-1 552 degrees - 70' / 2.251 Shear sided examination coverage). (WCS) Volumetric 214300) R1.16 SA 182 F316L 0.337" Temperature (Alt. 2 - Pg. No. 33) (UT)
- flange (1500 lb}
Note:
- l. The following systems and their abbreviations are listed here: High Pressure Core Spray (CSH), Low Pressure Core Spray (CSL), Reactor Building (Drywell) Equipment Drains (DER), Reactor Core Isolation Cooling (ICS), Reactor Pressure Vessel Instrumentation (ISC), Reactor Recirculation (RCS), Reactor Pressure Vessel (RPV), Reactor Pressure Vessel Closure Head (RPVCH), Standby Liquid Control (SLS), and Reactor Water Cleanup (WCS)
ATTACHMENT 1 10 CFR 50.55a Relief Request 2181-014 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
-lnservice Inspection Impracticality--
Revision O (Page 11 of 12) Table 2151-014.1 Nine Mile Point Nuclear Station, Unit 2 List of Components with Limited Examination Coverage Class/ Normal Exam Appendix Weld Exam Diameter/ Operating Exam Angle/ Requirements Outage Material of Actual VIII Component ID Description Category/ Line No. / Conditions Frequency (MHz) Remarks (Figure No.) Examined Construction Coverage Qualified (System)' Item Thickness (Pressure I /Mode and Method Exam Number Temperature) Weld: IWB-2500-8(c). Austenitic 2WCS-09 1 4.0" 1037 psi- The examination was limited due to IWB-2500-9, Stainless Steel SW032 Tee-to-Pipe R-A 2WCS-004- Pressure 45' / 2.25 / Shear the branch connection on upstream 10, & 11 N2R15 SA 312 TP 89.79% Yes (N2-ISI- (WCS) R1.11 & 60-1 552 degrees - 10* I 2.25 I Shear side for 6". Volumetric 316L - piping to 216700) R1.16 0.337" Temperature (Att. 2 - Pg. No. 34) (UT) SA403WP 316L- tee Weld: Austenitic IWB-2500-8(c), 2WCS-09 1 Stainless Steel 4.0" 1037 psi - The examination was limited due to Pipe-to- IWB-2500-9, SW033 R-A SA 312 TP 2WCS*004- Pressure 45' / 2.25 /Shear pipe-to-flange configuration (one-Flange 10, & 11 N2R15 50% Yes (N2-ISI- R1 .11 & 316L- piping to 60-1 552 degrees - 70' / 2.25 /Shear sided examination coverage). (WCS) Volumetric 217100) R1.16 SA 182 F316L 0.377" Temperature (Att. 2 - Pg. No. 35) (UT)
- flange (1500 lb)
The examination was limited due to IWB-2500-8(c), 2RCS-64*00- Pipe-to- Weld: 24.0" 1251 psi - pipe-to-valve configuration (single-IWB-2500-9, 1 FWA07 Valve Austenitic 2RCS-024- Pressure 45' / 1.5 /Shear sided examination coverage). 10, & 11 R-A N2R16 50% Yes (N2-ISI- "HYV17A Stainless Steel 2-1 550 degrees
- 60' / 2.0 I Long Examined upstream side of valve Volumetric R1.16 168200) (RCS) SS to SS 1.3" Temperature HYV17A only due to conliguration.
(UT) (Att. 2
- Pg. No. 36 - 38)
The examination was limited due to CSL Nozzle 45' / 1.5 / Phased nozzle safe end-to-safe end IWB-2500-8(c), N5Safe 10.0* 1042 psi - Array Half Path extension configuration. 2RPV-KC23 IWB-2500-9, 1 Weld: Ferntic End-to-Safe 2CSL-010- Pressure 30' / 1.5 / Phased 80.3% (Att. 2
- Pg. Nos. 39 - 42)
(N2-ISI- 10, & 11 R*A N2R16 Steel Yes End 13-1 537 degrees - Array Half Path 70.4% 011600) Volumetric R1.16 CS/INC/CS Extension 0.75" Temperature 40' / 1.5 / Phased 80.3% RI-ISi coverage obtained (UT) (CSL) Array Half Path and 70.4% procedure extended coveraae obtained. Note:
- 1. The following systems and their abbreviations are listed here: High Pressure Core Spray (CSH), Low Pressure Core Spray (CSL), Reactor Building (Drywell) Equipment Drains (DER), Reactor Core Isolation Cooling (ICS), Reactor Pressure Vessel Instrumentation (ISC), Reactor Recirculation (RCS), Reactor Pressure Vessel (RPV), Reactor Pressure Vessel Closure Head (RPVCH), Standby Liquid Control (SLS), and Reactor Water Cleanup (WCS)
ATTACHMENT 1 10 CFR 50.55a Relief Request 2151-014 Proposed Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality-Revision O (Page 12 of 12)
Table 2151-014.1 Nine Mile Point Nuclear Station, Unit 2 List of Components with Limited Examination Coverage Class/ Normal Exam Appendix Weld Exam Diameter/ Operating Exam Angle/ Component ID Description Requirements Outage Material of Line No./ Frequency (MHz) Actual VIII Category/ Conditions Remarks (Figure No.) Examined Construction Coverage Qualified (System)' Item Thickness (Pressure I /Mode and Method Exam Number Temperature) The examination was limited due to 45* / 1.5 /Phased nozzle safe end-to-safe end CSH N16 IWB-2500-8(c), Weld: Ferritic 10.0' 1050 psi - Array Half Path extension configuration. 2RPV-KC32 Safe End-to- IWB-2500-9, 1 Steel 2CSH-010- Pressure 30* / 1.5 / Phased 81.6% (Att. 2 - Pg. Nos. 43 - 46) (N2-ISI- Safe End 10,& 11 R-A N2R16 SB 166 - safe Yes 27-1 550 degrees - Array Half Path 80.3% 006100) Extension Volumetric Rl.16 end to SA 508 0.90" Temperature 40* / 1.5 / Phased 81.6% RI-ISi coverage obtained (CSH) (UT) - extension Array Half Path and 80.3% procedure extended coveraoe obtained. Weld: Ferritic The examination was limited due to IWB-2500-S(c), 2DER-07A- Valve Steel 2.0' 1030 psi - 45* / 5.0 I Shear valve-to-pipe configuration (one-IWB-2500-9, 1 FW002 'MOV128- SA 106GR B- 2DER-002- Pressure 60' I 5.0 I Shear sided examination coverage). 10, & 11 R-A N2R16 33% Yes (N2-ISI- to-Pipe Piping to SA 7-1 550 degrees- 70' I 5.0 I Shear Downstream obstructed by valve, Volumetric Rl .20 012000) (DER) (UT) 105 -valve 0.218' Temperature o* 14.0 I Long pipe clamp 1. 7" upstream of WGL. (30001bl (Att. 2 - P11. Nos. 47 - 48) Note:
- 1. The following systems and their abbreviations are listed here: High Pressure Core Spray (CSH), Low Pressure Core Spray (CSL), Reactor Building (Drywell) Equipment Drains (DER), Reactor Core Isolation Cooling (ICS), Reactor Pressure Vessel Instrumentation (ISC), Reactor Recirculation (RCS), Reactor Pressure Vessel (RPV), Reactor Pressure Vessel Closure Head (RPVCH), Standby Liquid Control (SLS), and Reactor Water Cleanup (WCS)
Attachment 2 Nine Mile Point Nuclear Station Unit 2 Third Inservice Inspection Interval Limited Coverage Non-Destructive Examination Reports
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Liquid Penetrant Examination 2 Procedure: NDEP-PT-3.00 Outage No.: N2RF012 Site/Unit: NMP
;ummary No.: 068800 Procedure Rev.: 1701 Report No.: PT-10-010 Workscope: 1SI Work Order No.: C081919800-100 Page: of 2 Cat.lltem: B-0/814.10 Location: RCA Code :
Drawing No.: ASME Section XI 2004 Edition ISl*COM-037 Description : CRD 18-03 Pipe-to-Flnge Weld System ID: Component ID : 2RPV-CROH001A Mat/Thickness: SS 304 Limitations : Limited due to adjoining components. Light Meter Mfg.: NIA Serial No.:
--------- NIA Illumination:
-------- NIA Temp . Tool Mfg.: EXTECH Side A: °F Seri aI No.: ----OA~*...;.,N;.;;O;.;;E;;..*T...;.,*....;;0....;;9....;;0____
"F Resolution:
Surface Temp .: 0.044" Character Card 83 "F Comparator Block Temp.: Lo/Wo Location: NIA NIA Side B: NIA Surface Condition: Smooth Cleaner Pen et rant Remover Developer Brand MAGNAFLUX MAGNA FLUX MAGNAFLUX MAGNAFLUX Type SKC-S SKL-SP SKC-S SK0-52 Batch No. 05B01K 94F13K 05B01K OOJ14K Time Evap. 5mins. Dwell 10 mins. Evap. Smins. Develop 10 mins. I Time Exam Started: 11:45 Time Exam Completed: 12:45 Indication Loe Loe Diameter Length Type Remarks No. L w R/L No recordable Indications Comments: See attached sketech for limitations. Results : Accept RJ Reject O Evar O Percent Of Coverage Obtained > 90%: No. 43% Reviewed Previous Data : Yes Examiner Level II Date Reviewer Date Woodring, Ryan A. 411612010 Lancaster, Phillip, NOE Level Ill Examiner Level NIA Date NIA Other Level N/A Signature Date NIA Yaeger, William J. Attachment 2 - Page 2 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Supplemental Report Report No.: PT-10-010 Page: 2 of 2 ,ummary No.: 068800
--~~--~~~--~------
Sketch or Pho1o: S:\Common\Ql-NDE\Ql-NDE\N2R12\Datasheet Scanned lmages\2RPV-CRDH-001A.jpg WELD 2 RF\J~ ( R.DH-CO I .A 1S APP~O~llfJA rCL Y2 v? FRON? ;:'LA/II GE 8 8 IOTAL AREA = l8. 16
,..Rf:A EXllJY> Jf.JE D =8 .. ( '13 Ye.)
Attachment 2 - Page 3 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports 0 Constellation Energy r,.,. *..-."rr,...tr* I Liquid Penetrant Examination 2 Procedure
- NDEP-PT-3.00 Outage No
- N2RF012 Site/Unit: NMP Procedure Rev. 1701 Report No : PT*10-011 iummary No.:
068900 Works cope: ISi Work Order No.: C081919800*100 Page: 1 of 2 Code: ASME Section XI 2004 Edition Cat./ltem: B-0/814.10 Location: RCA Drawing No.: ISl-COM-037
Description:
CRD 18-03 Pipe-to-Pipe Weld System ID: Component ID: 2RPV*CRDH0018 Mat./Thickness: SS 304 I NIA Limitations: Limited due to adjoining components. Light Meter Mfg .: NIA Serial No.: NIA Illumination: NIA Temp . Tool Mfg .: EXTECH Serial No.: QA-NDE-T -090 Surface Temp. : _ __;.B..;..3__ "F Comparator Block Temp.: Side A : NIA °F Side B: NIA "F Resolution: 0.044" Character Card LoNVo Location : NIA Surface Condition : Smooth Cleaner Penetrant Remover Developer Brand MAGNAFLUX MAGNAFLUX MAGNAFLUX MAGNAFLUX Type SKC-S SKL-SP SKC*S SKD-52 Batch No. 05801K 94F13K 05B01K OOJ14K Time Evap. 5mlns. Dwell 10 mins. Evap. 5 mlns. Develop 10 mins. I Time Exam Started: 11:45 Time Exam Completed: 12:45 Indication Loe Loe Diameter Length Type Remarks No. L w R/L No recordable indications Comments: See attached sketech for limitations. Results: Accept ["'! Reject n Eval [ i Percent Of Coverage Obtained > 90%: No. 80% Reviewed Previous Data : Yes Examiner Level 11 Date Reviewer Date Woodring, Ryan A. 4116/2010 Lancaster, Phillip, NOE Level Ill Examiner Level NIA Date NIA
-:lther Level NIA Signature Date ANll Review NIA Yaeger, William J . {/.(-
Attachment 2
- Page 4 of 48
Unit 2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Supplemental Report Report No: PT-10-011 Page: 2 of 2 ummary No.: _o_ss_s_o_o___________ Sketch or Photo: S:,Common\Ql-NDEIQl-NDE,N2R121Datasheet Scanned lmages\2RPV-CRDH-001 B JP9 f
/
/
I l J
~ p..; T"Olv\
1-j, ..lf(.W:: 1'CIA! ,-i,.z.*~ _.,, -- *"P. c ( A.i<.['A ,!?)<A,.,.\ 1A;t~L.* :. , .-
- Attachment 2 - Page 5 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports A. Constenntlon e,,_-gy Liquid Penetrant Examination V'-'""'* '~\.'-"'C"' Outage No.: N2RF012 Site/Unit: NMP 2 Procedure : NDEP-PT-3.00
;ummary No.:
-~-------~~-
069400 Procedure Rev. :
~~~-----~
1701 Report No.: PT-10..()12 Workscope: ISi Work Order No.: C081919800-100 Page: of 2 Code : ASME Section XI 2004 Edition Cat./ltem: B-0/814.10 Location: RCA Drawing No.: ISl-COM-037
Description:
CRD 30-03 Pipe-to-Flange Weld System ID: CR. D Ri. 77r Componen\ ID: 2RPV-CRDH004A Mat/Thickness: SS 304 Limitations: Limited due to adjoining components. Light Meter Mfg.: NIA Serial No.: N/A Illumination: NIA Temp. Tool Mfg. : EXTECH Serial No.: QA-NDE-T-090 Surface Temp. : _ _ 8_3__ °F Comparator Block Temp .: Side A: NIA °F Side B: NIA °F Resolution: 0 .044" Character Card LolWo Location: NIA Surface Condition: Smooth Cleaner Pen et rant Remover Developer Brand MAGNAFLUX MAGNAFLUX MAGNAFLUX MAGNAFLUX Type SKC-S SKL-SP SKC-S SKD-S2 Balch No. 05B01K 94F13K 05801K OOJ14K Time Evap. 5mins. Dwell 10 mins. Evap. 5mlns . Develop 10 mins. Time Exam Started: 11 :45 Time Exam Completed: 12:45 Indication Loe Loe Diameter Length Type Remarks No. L w R/L No recordable indications Comments: See attached sketech for limitations. Results : Accept~ Reject 0 Eval O Percent Of Coverage Obtained > 90% : No -43% Reviewed Previous Data: Yes Examiner Level 11 Woodring, Ryan A. Examiner Level NIA Date NIA Jther Level N/A Signature Date NIA Yaeger, Wiiiiam J. I Attachment 2 - Page 6 of 48
Unit 2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Supplemental Report Report No.: PT-10-012 Page: 2 of 2 Jummary No.: _o6_9_4_oo_ _ _ _ _ _ _ _ __ Sketch or Photo: S:\Common\Ql-NOE\Ql*NDE\N2R12\Datasheet Scanned lmages\2RPV*CRDH-004A.JPG w£LD 2RFV-CR.DH-C01.1 A r S A PP'iCO'X IM A rCt. Y :Z *. t...i P f"RCJM ;:-L,4}.JGE e 8 IOTAl A;RFA = i 8 .16
,;.R£A EXAJYJJf.JFD ~ 8 .* ( 1.1-s~)
Attachment 2
- Page 7 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports 0 C<instmlMion Encr<JY
...... ., .** *~. -.~ * .c* Liquid Penetrant Examination 2 Procedure: NDEP-PT-3.00 Outage No.: N2RF012 Site/Unit: NMP
,ummary No.:
------------ 069500 Procedure Rev.: 1701 Report No.:
PT-10-013 Workscope: ISi Work Order No.: C081919800-100 Page: 1 of 3 Code: ASME Section XI 2004 Edition Cat./ltem: B-0/814.10 Location: RCA Drawing No. : ISl-COM-037
Description:
CRD 30-03 Pipe-toPipe System ID: Component ID: 2RPV-CROH004B Mat.rrhickness: SS 304 Limitations: Limited due to adjoining components. Light Meter Mfg.: NfA Serial No.: N/A Illumination: N/A Temp. Tool Mfg.: EXTECH Serial No.: OA-NDE* T-090 Surface Temp.:
---- 83 °F Comparator Block Temp.: Side A: NIA "F Side B: N/A *F Resolution: 0.044" Character Card LoNVo Location : N/A Surface Condition: Smooth Cleaner Penetrant Remover Developer Brand MAGNAFLUX MAGNAFLUX MAGNAFLUX MAGNAFLUX Type SKC-S SKL-SP SKC-S SK0-52 Balch No. 05B01K 94F13K 05B01K OOJ14K rime Evap. 5mins. Dwell 10 mins. Evap. 5 mlns. Develop 10 mins.
Time Exam Started: 11:45 Time Exam Completed: 12:45 Indication Loe Loe Diameter Length Type Remarks No. L w R/L 1 3.1" 0.6" 0.10" N/A Rounded Verified previous indication. Comments: See attached sketch for limitations and indication layout. Results: Accept r~ Reject O Eval [J Percent Of Coverage Obtained > 90%: No - 75% Reviewed Previous Data: Yes Examiner Level II Date Reviewer Date Woodring, Ryan A. 411612010 Lancaster, Phlllip, NOE Level Ill Examiner Level NIA Date N/A Jther Level NIA Signature Date NIA Yaeger, William J. Attachment 2 - Page 8 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Supplemental Report Report No.: PT-10-013 Page: 2 of 3 ,ummary No.: 069500
~~~~~~~~~~~~
Sketch or Photo: S*\Common\Ol*NDE\Ql-NDE\N2R12\Datasheet Scanned lmages\2RPV*CRDH-0048-indication jpg ntC/#'~ 1# /J en m:S Wrhl 41 riu C.iflln ~ 71'.:s E..f V HJ ;;v Le-ff Attachment 2 - Page 9 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports Supplemental Report Report No.: PT-10-013 Page: 3 of 3 .1.1mmary No.: _o_s_95_o_o_ _ _ _ _ _ _ _ __ Sketch or Photo: S:\Common\Ol-NDE\Ql-NDEIN2R12\Datasheet Scanned lmages\2RPV-CRDH*004B-limitation.jpg f FOV/.JDATIO~ WAl-L le>TA L .AR.£A:-*/~*.{( *' A~..f';'I E.kAIVIJNcD~* 1 u ,,
% c CMPt.ETE::: ?:.->-.J(.
Attachment 2 - Page 10 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Supplemental Report Report No.: UT-10-014 Page: 4 of 4 Summary No.: 208400 Examiner: Huhe, Troy Examiner: NIA
-, ~ H......l Level: 11-PDI Level: NIA Reviewer:
Site Review: Date: Date: 4/11J 1 ~ r i 4/; 2//0 I o Other: NIA Level: NIA ANll Review: Date: f..t 2 -10 Comments: Exams perfonned to maintain 5% to 20% ID roll. Circ exams perfonned on both sides of base material and weld crown with skew angles to examine the additional required exam volume. o* exam perfonned to locate counterbore. Counterbore located as previously recorded. See sketch. Increased exam volume due to Rl-151 requirements. See attached coverage plot. Single sided exam due to component confuiguration 50% coverage. = Sketch or Photo: S:ICommon\Ql-NDEIQl-NDEIN2R121Datasheet Scanned lmages\2WCS-09-05-FW014.jpg 2 ~ (. .5 - c ~ - a S _ Fv,c o ' L{ Attachment 2 - Page 11 of 48
Unit 2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Supplemental Report
.:xelon Report No.: UT-10-012 Page: 3 of 4 Summary No.: 208600
~~~~~~~~~~~~~
Examiner: Mahoney, Patrick Level: 11-PDI Reviewer: Lancaster, Phillip, NOE Level I Date: 4/16/2010 Examiner: NIA
~_.;_~~~~~~~~~
Level: NIA Site Review: Ciiento, Joseph, NOE Level Ill Date: 4/16/2010 Other: NIA
~~~~~~~~~~~
Level: N/A ANll Review: Yaeger, William J. Date: 4/1712010 Comments: Single sided examination due to configuration (50% Coverage Achieved). Sketch or Photo: O:\Outage Data\Nine Mile\Datasheet Scanned lmages\2WCS-09-05-FW015.jpg 2WCS-09-05-FW015 Sweep-a-let Flow Pipe Attachment 2 - Page 12 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports Liquid Penetrant Examination Site/Unit: Summary No.: NMP
-----~----~
069600 2 Procedure: Procedure Rev.: NDEP.PT-3.00
-------~~
1800 Outage No.: Repor:t No.: N2RF013 ISi.PT-12-007
------------~
Worbcope: ISi Work Order No.: C90959883 Page: 1 of 1 Code: ASME Section XI 2004 Edition Cat./ltem: B.0/814.10 Location: Drywell, Under Vessel Drawing No.: ISl-COM-037
Description:
CRD 34-03 Pipe-to-Flange Weld System ID: RPV
------~--------~-------------------~---
Component ID: 2RPV-CROH005A Mat.fThickness: SS/NA Limitations: Appro>elmately 63.8% Coverage Due to Obstructions Light Meter Mfg.: NIA Serial No.: NIA Illumination: NIA
-------~
Temp. Tool Mfg.: EXTECH Serial No.: QA-NDE-T-092 Surface Temp.: 77 .2 "F Comparator Block Temp.: Side A: NIA "F Side B: N/A "F Resolution: 0.044" Character Card LoNVo Location: N/A Surface Condition: As-Welded Visible~ Cleaner Penetrant Remover Developer Fluorescent 0 Brand MAGNAFLUX MAGNAFLUX MAGNAFLUX MAGNAFLUX Type SKC-S SKL-SP SKC-S SKD-$2 Batch No. 10C01K 94F13K 10C01K 05J05K Time Evap. 5 Dwell 10 Evap. 5 Develop 10 Time Exam Started: 1137 Time Exam Completed: 1220 Indication Loe Loe Diameter Length Type Remarks No. L w R/L NIA NRI Comments: Limited e>eam due to obstructions (Insert and Withdraw lines, Shoot-out Steel, Cables, etc). Coverage Included appro>elmately 12 linear Inches of weld. The circumference of this pipe Is appro>elmately 18.8". Results: Accept~ Reject 0 Eval O Percent Of Coverage Obtained > 90%: No/ 63.B*AJ Reviewed Previous Data: Yes Examiner Signature Date Benson, Michael Examiner Level NIA Other Level Signature NIA Attachment 2 - Page 13 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Liquid Penetrant Examination Site/Unit: Summary No.: NMP
~---------~
089700 2 Procedure: Procedure Rev.: NDEP*PT-3.00 1800 Outage No.: Report No.: N2RF013 ISl.PT-12..005
----------~
Workscope: ISi Work Order No.: C90959883 Page: 1 of 1 Code: ASME Section XI 2004 Edition Cat.lltem: B.Q/814.10 Location: Drywell, UnderVessel Drawing No.: ISl-COM..037
Description:
CRD 34-03 Plpe*to-Plpe Weld System ID: RPV Component ID: 2RPV-CRDH0058 Mat/Thickness: SS/NA limitation a: 63.8% Due to Inaccessibility Light Meter Mfg.: Temp. Tool Mfg.: N/A EXTECH Serial No.:
-------- NIA Serial No.: _ __.QA;;..,,;,,,o*N,..D
....E..,*,..T_..0....;;.9-.2_ _
Illumination: Surface Temp.: NIA 77.2 *F Comparator Block Temp.: Side A: NIA "F Side B: NIA "F Resolution: 0.044" Character Card Lo/Wo Location: NIA Surface Condition: As*Welded Visible~ Cleaner Penetrant Fluorescent 0 Remover Developer Brand MAGNA FLUX MAGNAFLUX MAGNAFLUX MAGNAFLUX Type SKC-S SKL-SP SKC-S SKD-52 Batch No. 10C01K 94F13K 10C01K OSJOSK Time Evap. 5 Dwell 10 Evap. 5 Develop 10 Time Exam Started: 1248 Time Exam Completed: 1330 lndicaUon Loe Loe Diameter Length Type Remarks No. L w R/L NIA NRI Comments: Limited Exam due to lnaccesslblllty, Coverage Included approximately 12 linear Inches of weld. Circumference of this piping approximately 18.8". Results: Accept~ Reject D Eval D NIA Percent Of Coverage Obtained > 90%: No/83.8% Reviewed Previous Data: Yes Examiner Date Reviewer Signature Date 515/2012 z Examiner N/A Other Level NIA Signature NIA Attachment 2 - Page 14 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Liquid Penetrant Examination Site/Unit: NMP 2 Procedure: NDEP-PT-3.00 Outage No.: Summary No.: 076200 Procedure Rev.: 1800 N2RF013 Report No.: ISl-PT-12-008 Works cope:
------------ ISi Work Order No.: C90959883 Page: 1 of 1 Code: ASME Section XI 2004 Edition Cat./ltem: B-O/B14.1 O Location: Drywell, Under Vessel Drawing No.: ISl-COM-037
Description:
CRD 34-59, Pipe-to-Flange Weld System ID: RPV Component ID: 2RPV-CRDH038A Matffhickness: SS/NA Limi~ns: 6S. I .34'% Coverage of weld due to obstructions 1fW s1 1Rt1k Light Meter Mfg.: N/A Serial No.: N/A Illumination: NIA Temp. Tool Mfg.: Comparator Block Temp. : EXTECH Side A: NIA °F Serial No.: Side B: NIA °F QA-NDE-T-092 Resolution: Surface Temp.: 0.044" Character Card 77 °F LoNl/o Location: NIA Surface Condition; As-Welded Visible iil Cleaner Penetrant Remover Developer Fluorescent 0 Brand MAGNAFLUX MAGNAFLUX MAGNAFLUX MAGNAFLUX Type SKC-S SKL-SP SKC-S SKD-52 Batch No. 10C01K 94F13K 10C01K 05J05K Time Evap. 5 Dwell 10 Evap. 5 Develop 10 Time Exam Started: 1340 Time Exam Completed: 1440 Indication Loe Loe Diameter Length Type Remarks No. L w RIL N/A NRI Comments: Limited Exam due to obstructions ( insert and withdraw lines ) Coverage included approximately 16 linear inches of weld. The circumference of this piping is approximately 18.8". Results: Accept ~ Reject LJ Eval O N/A Percent Of Coverage Obtained > 90%: No/ 85.1% Reviewed Previous Data: Yes Examiner Signature Date Benson, Mlchae Examiner Level Signature NIA Other Level N/A Signature N/A
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Liquid Penetrant Examination Site/Unit: NMP 2 Procedure: NDEP-PT-3.00 Outage No.: N2RF013 Summary No.: 076300 Procedure Rev.: 1800 Report No.: ISl-PT-12-006 Workscope: ISi Work Order No.: C90959883 Page: 1 of 1 Code: ASME Section XI 2004 Edition Cat./ltem: B-0/814.10 Location: Drywall, Under Vessel Drawing No.: ISl-COM-037
Description:
CRD 34-59, Pipe-to-Pipe System ID: RPV Component ID: 2RPV-CRDH038B Mat.fThickness: SS/NA Limitations: 74.4% Coverage of weld due to inaccessibility Light Meter Mfg.: NIA Serial No.: N/A Illumination: N/A Temp. Tool Mfg.: EXTECH Serial No.: QA-NDE-T-092 Surface Temp.: 77.2 "F Comparator Block Temp.: Side A: NIA °F Side B: N/A °F Resolution: 0.044" Character Card Lo/Wo Location: N/A Surface Condition: As-Welded Visible bl! Cleaner Penetrant Remover Developer Fluorescent Q Brand MAGNAFLUX MAGNAFLUX MAGNAFLUX MAGNAFLUX Type SKC-S SKL..SP SKC..S SKD-S2 Batch No. 10C01K 94F13K 10C01K 05J05K Time Evap. 5 Dwell 10 Evap. 5 Develop 10 Time Exam Started: 1340 Time Exam Completed: 1430 Indication Loe Loe Diameter Length Type Remarks No. L w R/L N/A NRI Comments: Limited exam due to inaccessibility. Coverage included approximately 14 linear inches of weld. Circumference of this piping is approximately 18.8" Results: Accept ~ Reject O Eval fJ NIA Percent Of Coverage Obtained > 90%: No/74.4% Reviewed Previous Data: Yes Signature Date g~ Examiner Level Ill Date Reviewer Herold, John F t/,,"I 5/5/2012 N 'A-Examiner Level NIA Date N/A Other Level N/A Signature Date N/A
Unit Nine Mile Point Nuclear Plant Third ISi 2 Interval L'mited I Coverage NDE Reports Supplemental Report Report No ISl-UT-12-039 Page- 2 ot 4 "uomna1y N I
> Siie Rewew i,
\ft;a*'cl]'ro, r;e T11td L
~
I f~cv1ewer o 536000 ,,,, Le,el II-POI 1 r _ t . ** ' "_..
-==--- ------
Crothers,~~i:n~o~n~P~-~~;,~*:J~-===-~Le:v:e>l-=T=R=-N----~':._ ~ " E<aon'"m S*lley. Moch'< SC- Le"I _111_ ANll R,,,.,., !f( L Other* Jones. Kelvin Ex<muner ____
*>111111en1tAs HW101A 2RHS-E -
Sketch 1 Sketch o1 Photo 2R~SJ-~1A-HW102A d' cent Weld 0 1" 2" 3" I I -- I I I era e limited by flange . I J143" of weld, cov g nd ad1acent weld. fil~l 13" of weld, coverage lim . ited by flange a B l y-1 I Weld Details - 56 I Wtdt0h)~(2.4"
\ I Weld Length - 1 - 1 4" (typical) . , ' . '
,' Flange I
- Weld Crown x 0.9") =2 16 rn ' ,, I I
* (ABC * * ,
- Exam area . IWC -2500-1 I
- Code Figure 0 0 9" c
Attachment 2 - Page 17 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Supplemental Report ISl-UT*l 2-039 1:rnrn HV Nn 536000 > I <1111111er Salley. Michael />11 ) Level 11-PDI l~F-Vlf'Wt" C .
\ '1,-11. f (
I ./!,,,.
-r-
,rl/{ ('I I.
J.. ~'; 1 Di1te .:/I /..: r.7, /,il '*., I f ., lllllllP.1 Crothers. Simon P. Sc Level Ill 11e f~ev1ew * "'ilUaO T.-1. \. .*! _,./" Date
't 2~).-12...
1 ither Jones. Kelvm i<.-S Levr~I TRN ANll Hr>v1ew: t.;;/L_.*---* I ft'. I D:ile s1zd-~--.: r1 1 lllnlPPI'> 2RHS-E1A-HW101A Sketch 2
);.,, 11 h rn Phnl11
[] Axial coverage ltm1ted by flange 143" ol 156" Shell
- Exam area= 2 16 m2
- Examined 2 16 - ( 1 O" x 0 5")/2 =1 91 in'
- 1911216=88.4%
- tl84'1ox(143"of156")=81% 0 1" 2" 3*
I I I I Adjacent Weld 2RHS-E1A-HW102A D Axial coverage limited by flange and ad1acent weld D 13" of 1!:>6 Flange
'~ l
- l::xam area= 2 16 in~
2
- Examined 2 16 - (1O"x0 5")12 - (0 3" x 0 15' = 1 89 in
- 189/216=875Yo
- 87 5°/., x (13" of 156") =7 3<y.,
Total Axial Coverage: 81% + 7.3% =88.3'Yo Attachment 2 - Page 18 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports o* . _,., . . 1:,.,~, ** Supplemental Report Rvporr No ISt-UT-12-039 ' u1n111riry No 536000 t x,1111111e1 Salley. Michael ,,,, :1 5 Level 11-PDI 1* ,;::11111ner Crothers, Sunon P. Sc Ill Sile F~eview. Date ***/ * . ,.*) . I ,'__ 1Jlt1Pr Jones. Kelvin l{..T Level TRN ANll Review. Dale S/i~// Z...
~*
1:ornn1!illl'> 2RHS-t: 1A-HW101A Sketch 3 kP!Ch 01 Pl1oln I C1rc coverage I l limited by flange I I 156" of 156" Shell I I I, 1 Flanqe II I
-------:.l.l.WU.LJ.ill.U..W.U..W.U..W.Wl.l.L.W.~WJ..l.W.WCUUJ:l.W- - - * * - - *- - -
- F:xam area = 2. 16 111 2
- Examined: (1.9 x 0.9) =1 71111'
- 17112.16==79.2%
0 1" 2* 3' I I I Coverage Cale:
- Axial Coverage: 88.3%
- Gire Coverage: 79.2%
- Total Coverage: (88.3 + 79.2)/2 =83.8%
Attachment 2 - Page 19 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Supplemental Report Report No ISi-UT 082 Page: 2 of 5 Summary No.: 158500 Examiner. Crothers, Simon P. SC Level: Ill Reviewer. J..~.. ,2..u:<Z.\ t* .<"~ D~te: S:7-J2. Examiner* Jones, Kelvin l(r Level : TRN Site Review Cilento, Joseph, Level Ill Date: )'~1*rv Other NIA Level: NIA ANll Review Rose, Charles C;A Date: -::/-;:/; L
> I L. omrnents 2SLS-88A-FW042A Sketch 1: Code Coverage S~ e~PhQto.
~ Cooe Coverage Axial Exam Area:
* (1 .1" x 0.23") = 0.25 m2 Examined:
- 0 25- (0.05 x 0.15)/2 -(0 15 x 0.15)12 =0 241n 2
- 0 24 I 0.25 =96%
0 68" filiillIII Code Coverage. Circ Exam Area:
* ( 1 1" x o 23") =O 25 m 2 Examined:
* (0 55 x O 23) =0.125 mi
- 0 12 5 I 0 25 =50%
Weld-a-let Code Coverage Cale: 0 I"' 2" 3"
- Axial= 96% I I I I
- Circ = 50%
- Total = (96 + 50)/2 =73%
Attachment 2 - Page 20 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Supplemental Report l'eport No. ISl-UT-12-082 Page. 3 of 5 Summary No 158500 Examiner Crothers, Simon P. SC Level Ill Reviewer ....).,... "> ~\c.\ c;. It~ Date f. tZ-Examiner Jones, Kelvin t(:S- Level TRN Site Review* Cilento, Joseph, Level Ill l\vv Date: ')*7*J]., Other NIA Level N/A ANll Review Rose, Charles ¥ Date: :j_;:) z_ Comments 2SLS-88A-FW042A Sketch 2: R-A Coverage Flow Sf:e~ Ph9IQ..
~ R-A L;overage Axial Exam Area:
* (16"x0.23") =0 37 1n 2 Examined:
- 0.37 -(0.05 x 0 15)/2 - (0 05 x 0 3)/2 - 0 23(0 2 + 0 4)/2
= 0.29 in:z
- 0.29 I 0.37 =78%
[fillill] R-A Coverage: Gire Exam Area:
* ( 1 6" x O 23") =0 37 1n 2 Examined:
* =
(0 8 x O 23) 0 185 1n~
- 0 185 I 0 37 = 50%
Weld-o-let R-A Coverage Cale: 0 1" 2* 3"
- Axial= 78% I I I I
- Gire= 50%
- Total= (78 + 50)/2 = 64%
Attachment 2
- Page 21 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports l'il-Vc-14-001 Structural Integrity Associates, Inc. NDE EXAMINATION SUMNlARY EXAMINA I'ION REl'ORT # ISl-VE-14-001 SI PROJECT# 130121~ Customer: CENG I Site: NMP -, l nit: 2 Outage: N2Hl4 System: R.PV I Component: Closure llcad-tu-l* lange Weld ID: 2RPV-AG Examination Procedure: PDl-lff-12 Rev. D (Sl-UT-192. Re\. ll Code Edition and Addenda: / ASME Scclion Xl :W04, No Addenda Examination Recorll(~): INMP2-14-2RPV-AG I Calibration Data Sheet(s): I NMP2-14-CAL-005 N1v!P2- l 4-CAL-006 Indication Ev:1lu:Hion Ni r\ Shect(s): Cn\'en1ge Data Sheet(s): 2RPV-AG Coverage Examination Scan Pl:m(s): 2RPV-AG Scan Plan
\xiol Scan CovcrJgc: *)h.5°1.
Percent Coverage Achieved: Circ Scun Co*ernge: 64% Total Coverage: 80.25% Summary: Weld# 2RPV*AG was examined lL~ing PDl-UT-12 Rev. D (Sl-UT-192. Rev. I) on 3/3012014. l 'ltrasonic cxaminution meets the requirements of ASME 131'& V Cude. Section XI. Appem.lix VII I. 2004 F.<lition. No
- \ddcnda.
rfo indications were rcl.*ordcd. Sec coverage data sheet for coverage c5tim.:itc details. Richard C. 'vlay Level: II Date: 3-30-14 Examiner: ( __... F*wmincr: N/:\ Level: Nii\ Date: Ni A
..,I Review: John Hayden Lc\'el; 111 Date: a'f/(J'{ /t'f l tility H.cvicw: Level:
-!:t-/~
D:1te:
~
\.\II l{cvicw: l>atc: L///fJt/
...L~
*- I 4
- {.~ *- t<f-Page I of 9 Attachment 2 - Page 22 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports l} Structural Integrity Associates Nine ~lik l'uint Nui.:kar Station U11i1 2 2RPV-A G Coverage ISl-VE-14-00 I PHASEI) AURA\' ULTJ~ASONJC EX.Al\:IJNA TION conmAGE 2RPV-AG !lead-to-Flange In-Service (ISl) Axial Scan l:~<iminutinn Volume I a)Olll 1* l:x..1111 Volume: i---------*- z_o111~ **-----i 1 __ 1
--- - I
[ ~~~~ve;;e=i IS I c:-..am inati0n of Lorn: I uf Lhe I kad-to-Flange weld and base material on each side of the wdd for a Jistance of ~-2t from the Loe of the \Veld was conduch:d fur tl11.; entire drcumfcrcncc of the wclJ. Cmaagc limitatil>ns due: to Head-to-Flange configuration for the full circumlcn.:ntial length of the \\clJ.
,--- AhoVt' drawing is not full scale.
Estimated Zone I Axial (pcrpcndil.:ular to weld) Con*ragc = 93%1 Exam Volum.: I Zom~ I lhkkn<'SS 1"
%.1J11.: I ll'idth ~* \hid \\ 1,t1h + I 2t \ 2 - ! 1.22 **.,. i 1.:\6".x 2)> - -U~"
Zunc I i\rca = Thickness x Width = 8.68in' Vi.fume or .\.lisscd Covcrnuc = o.6in* Volumc C1wcrag('. - (8 .6Xin= - 0.(Jin' )/ 8.6l:l in= = U.\13 '" IOll'J*u 93% _J i i Pagi: 5 of') Attachment 2 - Page 23 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports lJ Structural Integrity Associates Nine:: Mile Point Nudc::iir Swtiou Unit 2 2RPV-AG Covcragc ISJ-V E-1 00 I PHASED ARRAY ULTRASONIC EXAMINATION COVERAGE 2RPV-ACi 1-lcad-to-Fhmgc Jn-Service (ISi) Axinl Scan Examination Volume Layout (Cont.) f=xam Volurnt: lone 2
*\*\~ii\\\~'-%~~~~~~~~"
1\\.\ ,:\\\\*\\" bl e~*11ni11a11on ol'Zom: 2 of the Hc:ad-to-Flange wdd and base matt:rial on cach\~l<le' ofthe weld tor a distance of '1zl from the toe or thi.: weld was contlucted fo r the entire circumfcn:ncc or the weld. Covaagc limitations due to hcui.1-Lo-llange configuration fi.1r lhi: full cin.:umfcn:ntial knglh ol'thc: \H:ld. Above dnming b not full scak. Estimated Zone 2 Axial (pcrpc::ndii:ular to wc.::ld) Coverage=- I00% Exam Vo lume
/1111..: 2 1hi..:l..11c'~ 1.125" /,111.: J \\iJth - \\ ".:id\\ idth ** f.:!1-. 2 t 1.22 ..
- I l.5tJ"'x 2JJ = *l.34" Znn..: 2 Arca= Thickness x Width~ 4.8Sin!
\ tlfllll\C uf \liS~Cd C.1\ lT:Jgl: () in 2
\11lurncCcl\t:rat.: = t4 .XXin,-0111"1 4.1\Xin' 1.0 l!JO"u IOO'Yu Page 6of9 Attachment 2 - Page 24 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports lJ Structural Integrity Associates Nine Mile Point Nuckar SLaLiun Unit 2 2RPV-Ali Coverage ISl-Vl::.-l-HlOI l'llASED AHRA Y LILTRASONlC EXAl\lL""IATION COVERAGE 2RPV-t\G llcaJ-11..1-Fkmge In-Service (ISi) Circumfcn.:ntial Scan Examination Volume Layout
~
\\
t*dlll Volume
'\
r------ L Zonc 1 --1 ( MiS$Cd Coverage J IS I cxamin~11ion or lorn: I or the 1-kad-to-Flange \\cld and base material on c.ich side of the v. clJ for a Jistanci.: or \/;t from the tui.: of the wdd was conducted for the entire dn::umforem:c of the \\cld. Bnth Cin:uml~rcntial sc~ll1!> (J) and (4) hml cuvcwgc limitaLions due to head-to-11angc configuration \\hich prevented scanning clo::,cst to th\.'. llange ot"the cxaminalilm \Olumc for the foll circumferential lcn~th oflhc weld. Above drawing is not full scak. Estimated lone I Circum lt:rcntial coverage= 62% Exam v,)fumc I II Z*Hll.:
~one I th1d.. n1.." . 2" ..
~
I \\ 1dlh \\ cld \\ 1J1h .. I 2t \ 2 -* l I 22" ' ( 1.5u"\ 2)) - -U4" Lune I .-\rca =Thickness x \Vidth = 8.68in' I
\ 'uJumc of /\li%.::d Cn\ crngc 3 25in'
\',)I llini: Cu \cr.1gc - (8.6liin' - 3.25in')l li.tiSin' .62 , JUl."'u b2 %1 I
Page 7uf9 Attachment 2 .. Page 25 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports l> Structural Integrity Associates Nine Mile Point Nuclear Station Unit 2 2RPV-Ati Coverage ISJ-VE-14-00 I PHASE[) ARRAY ULTRASONIC EXAl\UNATION COYERAGE 2RPV-AG Hcad-to-Flangt.: ln-St.:rvicc ( ISi) Circumlercntial Scun l:xamination Volu.mc La)uut lcunl.)
\\
\
E:x.irn Volume \
\
Zone 2
\
f ;,11:;s1~0 ~over;:ige I l~l c ~ a111i11ation ur Zonc 2 ufth1.* Hem.I-to-Flange \\cld and base material on each side of the wdJ for a distance or Y~t from the toe of the weld \Vas conducted for the entire circumference or the weld. Buth Circum ll:n.:ntial sc *m~ (3) and (4) had wwragc limitations due to hcad-to-llangc configuration "hich prc\.cntcd scunning do sc~l tu th..: flange of the C)l.aminati0n volurm: for the full circumferential kngth of the wdJ. Above Jrawing is not full scale. I ~- ---- Estimated Zone 2 Circumferential covera!!c = 66~:------- -
----- l I
l:.xam V.-1l11mc I Zon-= J Z_ l)f 1l.:* -1 1111*, ;. 11 lr.::"t.!t
\,,,,"' * * * -- I I .,, ..
2 wid1h = W .:IJ W idth
- I 121' 2
( 1.2'.! " - (I .5 6" x 2i} -1.34" I Zone 2 Arca= Thid:ncss .-; Width= 4.118in' Volume of~foscJ Cu\cr;1gc - l.65in' v~1lumc O *vcragc (4 .8!\m' - 1.u5i11'1 -U~:-iin' .hti
- 1011':., ~ 6<>'!1.,
Page 8of9 Attachment 2 - Page 26 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports 1::.1-\ I - 1 ~*\JUI Nine Mile Point Unit 2 ~J Structural l1Jtegrity Associates RPV Top Head-to-Flange IA'
\
2RPV-AG Scan Plan
'l i -i:.~~n~ii;;;, oata -------, \
;--- -5~;1-e:1 3-30-2014
----------1
--1 I
~xammers . Richard C. May '
Start Time 1135 r-- F~"i;t~ Time 1400
*----**-***--- I - ---;i---------1 ~~-:-~"-"'*'
~~{'!!~l~~
II ~~~}~~~~~:-! Thcr:~::t:r ~~i ~:~~~;~---_! Axial Zero Datum Circ Zero Datum , I l--=-=:-.. W eld c.,-;:;\orline - 0 Stamp #1 Stud Hole J A f\ Examrnalton Volume
~
! \
Wedd C, II \; I \
--~
\i
. \\
'.~~'
~Zone2 ..."
r Eumlnaiion
-~~~i:.:~ ~T~~~~7:ion [ Pr~:-::-~-S~;;:~: - Scan OlrcclW>n I :.:: *1 I Mu Min Max 111. . Weld Enon Volutn<> Sonsltlvily Uln R R MP MP Ml1orlenlatlon ~
c.
~~:~~-L-.~- ~'.~-!~ I*~ -~ --- ---
l dBl . _ NIA t.J/A NIA NIA Lono 1 33.5 F'orpr.nor.ubr tcWclo
-*~c-1-t1-on_! __ ~c* 10 75* I Momu.al _! 'Ja"~. P~rpendicut.ir1o w.,1tt . _-~~A_!__ JP.Ro. Ni ~
NIA NIA NIA Zorn:i 2 36
~00-l-'1~07:! I :;s* "~n.u:ll Voss;el C1rcu;r,ter1mUat ~ 18 . NIA NIA NtA NIA Z:onu 1 lS.5 Jt;0-1~1-C7~ ;-** 1 .. ~ 75-;- ~Ve;;;-
Manual C1rcurnf.:1unlwl Flal
--e 1 NIA NIA NIA t-1/A Zona 2 35 Pai.:c I) of lJ Attachment 2 - Page 27 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports Exelon Supplemental Report Report No.: ISl-UT-16-039 Page: 3 of 3 Summary No.: 150100
-~-----~------~~
Examiner: Relsewitz, Jack ;r~ Level: 11-PDI Reviewer: Date: 4-z. 5:' (a Examiner: ...:N.::.l:....:A~------------- Level:~ Site Review: >-<"~ * "i o<V"< *. , - . ,., Date: 4~25- lb Other: ...;N,;;;,/;;..;A_ _ _ _ _ _ _ _ _ _ _ __ Level: NIA ANll Review: Niznik, Dean S. J2r- Date: 1.; -.}.. 7-r 6 Comments: No obstructions UPST of weld. 100% coverage achieved during axial and cir. scans. DNST axial scan obstructed by 4.0 In. long code plate: 4.0
=
in.+ 0.500 ln.(Transducer Wedge Width)= 4.5 in. not scanned. 3.25 In. was scanned. 3.25rT.75 Circ. 42% coverage achieved for DNST axial scan. Full coverage achieved for DNST clrc. scan. Pipe Circ UPST=S.125 in. UPST Axial: 100%. ONST Axlal: 42% TTL AxlCirc. Coverage = 342% Pipe Clrc DNST=7.75 In. UPST Circ: 100% DNST Circ: 100% Coveraqe Achleved=342/400 = 85.5% Sketch or Photo: 0 Lo** Attachment 2 - Page 28 of 48
Unit 2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports
~: .. ~L r,_p, 1._ u UT Calibration/Examination Site/Unit: NMP 2 Procedure: GEH-PDl-UT-2 Outage No.. N2RF015 Summary No.: 156700 Procedure Rev.: 8 Report No.. tSl-UT-16-031 Work scope: ISi Work Order No: C92744622-40 Page: 2 of 4 Code: ASME Section XI 2004 Edition Cat/Item R-A/R1.11 Location: PC -El. 306' Drawing No. : 88-A Description Valve *\/10-to-Reducer System ID: SLS Compone nt ID: 2SLS-88A-FW013A Size/Length: I 0.35 In. 6.25 In. I Thickness/Diameter. 0.344 In. 2.0 In.
Limitations: Valve to Reducer configuration Start Time: 1306 Finish Time: 1320 Instrument Settings Search Unit Cal. TI me Date Axial Oriented Search Unit Serial No.: 0206PX Senal No.: SB0046 Checks Calibration Signal Sweep Sound Path Manufacturer. GEIT Manufacturer. GEIT Initial Cal. 1151 411512016 Renector Amplitude o/o Division Model: USN-60SW Linearity* L-16..008 Size. 0.25 In. Model: MSWQC Inter. Cal. 1305 411512016 0.5 In. Notch 80 5.1 1.3 in. Delay: 7.7184 j.ISeC. Range. 2.5 In. Center Freq.: Inter. Cal. NIA N/A Freq 2.25 MHz NIA Inter. Cal. NIA M'll CalNel: 0.1221 ln/µsec. Pulser Type* Square Exam Angle: 10* Squint Angle: N/A Damping: 5000hms Re1ect: 0%
---- se*
NIA Final Cal. 1425 411512016 NIA PRF: Auto High SU Freq.: 2.25 MHz Measured Angle: Exit Point 0.25 In. # Mode: of Elements Shear 1 Couplant NIA Frequency: 2.25 MHz Rectify: Fullwave - - Cal Batch. 00325 Circumferential Oriented Search Unit Config.: Single Focus: NIA Voltage: 450V Pulse Width: 220 ns Type: ULTRAGELll Calibration Signal Sweep Shape* Round Contour NIA Reftector Amplitude% Division Sound Path Gate Mode:: NIA Display Delay: NIA Mfg. SONOTECH Wedge Style: MSWQC NIA Ax. Gain (dB) 51.9 Circ. Gain (dB): NIA Exam Batch 00325 Search Unit Cable NIA 1 Screen Div.= 0.25 Sound Path Type: ULTRAGELll in. of Calibration Block Type: RG-174 Length: 6 ft. No. Conn. Scan Coverage 0 Mfg.: SONOTECH NIA NIA Cal. Block No.: 12-1181 Reference/Simulator Block Upstream O Downstream~ Scan dB. ~ Reference Block Thickness 0.5 ln.-2.0 In. Dia.: Flat Gain Signal Sweep CWLJ CCW LJ Scan dB: NIA Senal No.: 94-6005 Sound Path dB Reflector Amplitude% Division Cal Blk Temp. 82" Temp Tool: 0003091668 Type: Rompas 304 SS Exam Surface: 0.0. 36.9 NSDH 80 3.2 0.8in. Comp. Temp. _!!:... Temp. Tool: 0003091668 Surface Cond1bon: NIA Ground Recordable lndlcatlon(s): Yes O No~ (If Yes Ref. Attached Ultrasonic Indication Report.) NIA Results. Accept~ Reiect O Info C Comments: No recordable Indications. No counterbore detected. 10* was utilized on DNST side due to component Percent Of Coverage Obtained > 90%* No-50% Reviewed Previous Data: Yes configuratation. Examiner Hiiborn, Marie R. Level 111-PDI
~;t!L Date 411512016 I Reviewer Siever, Theodore, Level Ill Date
'-' -Z2. - \ (r;,
Examiner Level N/A Signature Date I Site Review Date N/A 1ToDO M.G1NJ:S(2... ~/23/11:, Other NIA Level NIA Signature Date I ANll Review Niznik, Dean S.
~ 2,'/JJ Signf."re
'-f-~S-/r, Date Attachment 2 - Page 29 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports ~Exelon Supplemental Report Report No.: ISl-UT-16--031 Page: 4 of 4 Summary No.: 156700
~-~-~--~-----~-~
Examiner: Hilborn, Mark R. Examiner: NIA
/Zf>tll
~
Level: 111-PDI Level : ~ Reviewer: Site Review: Ginder, Todd M. s;z* n,, Date: 4/2212016 Date: 4/23/2016 other: '""'N..;;./~A'--------------- Level: N/A ANll Review: Niznik, Dean S. ~-- Date: t./ -V-**/G Comments: Previous Data: W 1-6.24-06-0014 (2006) Sketch or Photo: r::'Lt>vJ VALV£' R. £0\..\ c.£ fL
~---_,,,...
~<i:_. -,a* q T*
~-U/ i. '
- t." * '1.. r*
Attachment 2 - Page 30 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports
--==='
Exelon Supplemental Report Report No. : ISl-UT-16--046 Page: 5 of 5 Summary No.: 157100 Examiner: Hilborn, Mark R. fa1 /Lit Level: Ill-POI Reviewer: Siever, Theodore, Level Ill Date* 4~-\c;,, Examiner: ...;N;..:;/;.:.A.:...__ _ _ _ _ _ _ _ _ _ _ _ __ Level: N/A Site Review: -HfA GNa:;i? 7DCD Date: 1/-:Jlf*/f. Other: """N/.;;;.;;...;A_ _ _ _ _ _ _ _ _ _ _ _ __ Level: N/A ANll Review: Niznik, Dean S. ~ Date: '/ - )..) "'7../~ Comments: Eamination limited due to pipe to tee configuration on DNST side of weld CW from 1.75 in. to 4.5in. Exam area in.2 =1.35 in. x 6.25 in= 8.44 in. UPST = 100% Coverage achieved= 89% Inaccessible area= 1.35 in x 2.75 in.= 3.7 in. DNST 56%= Scanned area= 1.35 in. x 3.5 in.= 4.73 in. CW= 100% Percent achieved on DNST - 56.0% = CCW 100% Sketch or Photo: FL.Du..J P\PS 1£'/:.
~--------~~;~*-~?~?~:::::::!*
s--~ =; __ ~
*~* ~s*
----------'"'"--r1- ~ ~------.-~~!o...._------01*
.4" .2" 1.7" .2.7"'
Attachment 2 - Page 31 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports .,~ Exelon Supplemental Report Report No.: ISl-UT-16-057 Page: 3 of 3 Summary No.: 213900
~--------~~~----------
Examiner: Bullen, James, M _-;:?;.......;:r~...i;.c.li.. Level: 11-PDI Reviewer: Siever, Theodore, Level Ill ate: \.\-21.H i.:i Examiner: NIA Level: NIA Site Review: G1NDER, TTJC{) Date: ~*J,l{-/J:, Other: NIA Level: NIA ANll Review: Niznik, Dean S. Date: '{ -rJ-7-lfr> Comments: 2WCS..09-05-SW024 Weld Length 14.7"
- 1. 8.7 + 14.7=59.18=14.796% lntradose limitation area = 3.0"
- 2. 25%
- 3. 25%
- 4. 25%
=89.79%
F'Low
'I s:s I
~----.-.:.Z-1___
\
\ '
I
----~------~--
o.~'" o*.31o* v 0.3,2- O,J'f" 0.1(.J'" Attachment 2 - Page 32 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports .:;;:- Exelon Supplemental Report Report No.: ISl*UT-16-056 Page: 3 of 3 Summary No.: 214300
------~~~--~~
Examiner. Bullen, James, M.4..,,,.-d'~ Level: ~ ~Date: 1\-2..5-\-b
,:=
Reviewer: Siever, Theodore, Level Ill Examiner: N/A / Level: N/A Site Review: Ctt..1::').(rr:1 J. Jl-~te: 4'-U--16 Other: NIA Level: NIA ANll Review: Niznik, Do.;s. Date: ¥- iJ-/.< Comments: Profile not to scale. 2WCS-09-05-SW025 Weld Length 14.7"
- 1. 25%
- 2. 0%
- 3. 25%
- 4. 25%
= 75%
rLOW
~---~- '~---
_ _ _ _.-.;3__ _ _
\
\ ,'
I _ ___,_,._ _-'I!!&...._ __
~.31$' l>.35'" ..., Cl.311" o.~b" D. 'i .l' Attachment 2 - Page 33 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports ,- Exelon Supplemental Report Report No. : ISl-UT-16-064 Page: 3 of 3 Summary No.: 216700 Examiner: Huhe, Troy -r-~f-(~ Level: 11-PDI Reviewer: Siever, Theodore, Level Ill . ~Dale: 412512016 Examiner: NIA Level: NIA Site Review: C1t.UJI'~ :J.J. 1,LT-rIC Dale: J..2-16 Other: NIA Level: NIA ANll Review: Niznik, Dean S. .A---- Date: J--l-{. J, Comments: WCS-09..05-SW032 Weld Length 14.7"
=
1 8.7 + 14.7 59.18 = 14.796% lntradose limitation area 3.0" 2 25% 3 25% 4 25%
- 89.796%
Attachment 2 - Page 34 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports ~-- Exelon Supplemental Report Report No.: ISl-UT-16-065 Page: 3 of 3 Summary No.: 217100 Examiner: Huhe, Troy Examiner: N/A
-r., /./~ Level: II-POI Level: NIA Reviewer:
Site Review: Siever, Theodore, Level Ill ~ate: \.\-2'2-l t,o cic.~1 T*S, IA. ,....w ~ .£,_-z.. n, I Other: N/A Level: N/A ANll Review: Niznik, Dean S. ~ Date: J-;:.? -/{. Comments: WCS-09-05-SW033 Weld Length 14.7" 1 25% lntradose limitation area 3.0" 2 0% 3 12.5% 4 12.5%
=50%
0
\
\
I I I "
. 31" - *!>Z.' * ?>1 Attachment 2 - Page 35 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Cov~rage NOE Reports UT Calibration/Examination -~
.<E' LO I Sile/Unit: NMP 2 Procedure: Efl-AA-335-031 Outage No.: N2A16 Summary No. : N2-ISl-168200 Procedure Rev.: 8 Report No.: ISl-UT-18-025 Workscope: AUG Work Order No.: C9346027 4-085 Page: 2 of 4 Code: ASME Sect XI, 2004Ed Cat./llem: R-A/R1.16 Localion: 249' ow Drawing No.: ISl-064-000-002
Description:
Pipe-to-Valve *HVV17A System ID: ISl*RCS
~------------------------------------------------------~
Component ID: 2RCS-64-00*FWA07 Size/Length: 1.85" /75" Thickness/Diameter: 1.317" I 24" Limitations: Single sided; examined UIS side of valve HVV17A only due to configuration Start Time: 1736 Finish Time: 1817 Instrument Settings Search Unit Cal. Axial Oriented Search Unit Time Date Serial No.: 02554H Serial No.: 00-991 Checks Calibration Signal Sweep Sound Path Manufacturer: GEIT Manufacturer: RTD Initial Cal. 1648 5/3/2018 Reflector Amplitude% Division Model: USN-60SW Linearity: L-18-009 Size: 2(15x25)mm Model: 60 TAL2-Aust Inter. Cal. NIA 1.5" ID Notch 83% 6.8 2.705" Delay: 12.1309 Range: 4.0" Inter. Cal. NIA NIA NIA NIA NIA Freq.: 2.0 Center Freq.: NIA Inter. Cal. NIA NIA NIA N/A M'tlCalNel: 0.2367 Pulser Type: Square Exam Angle: so* Squint Angle: s* NIA Final Cal. 1845 51312018 NIA NIA NIA NIA Damping: 5000hms Re1ect: 0% Measured Angle: so* Mode: PRF: Auto High SU Freq.: 2.0 Exit Point 0.70 8 Long. II of Elements: 2 Couplant NIA NIA NIA NIA Frequency: 2.0MHz Rectify: Fullwave - - Cal . Batch: 12125 Circumferential Oriented Search Unit Config.: oual(!:>s 5rocus: FD25 Type: ULTRAGELll Calibration Signal Sweep Voltage: 450 Pulse Width: 250 Shape: Recf.'Wt;~ *t~r: Flat Reflector Amplitude% Division Sound Path Gate Mode: Peak Display Delay: 0.000 Mlg.: MAGNAFLUX Wedge Style: Integral NIA NIA NIA NIA Ax. Gain (dB): 56 Circ. Gain (dB): NIA Exam Batch: 12125 Search Unit Cable NIA NIA NIA N/A Type: ULTAAGELll 1 Screen Div. = 0.4 in. of Sound Path 6' No. Conn.: o Calibration Block Type: RG-174 Length: Scan Coverage
- - Mfg.: MAGNAFLUX NIA NIA NIA NIA NIA NIA NIA NIA Cal. Block No. CAL*PDl-009 Reference/Simulator Block Upstream ~ Downstream f] Scan dB: 70 Reference Block Thickness 0.5" -2.0" Dia.: Flat CW I CCW [ ] Scan dB: NIA
-- Serial No.: 94-6005 Gain dB Signal Sweep Reflector Amplitude% Division Sound Palh Cal. Blk. Temp. N/A Temp. Tool: NIA Exam Surface: O.D.
-- Type: SS 56 NSDH 40% 2.5 0.609" Comp. Temp. NIA Temp. Tool: NIA NIA NIA NIA NIA N/A Surface Condition: Flush Recordable lndication(s): Yes No"' (If Yes, Ref. Attached Ultrasonic Indication Report.) NIA N/A NIA NIA NIA Resulls: Accept .,, Reject Info Comments: UT of component 2RCS-64-00-FWA07; Pipe-to-Valve
*HVV17A Percent Of Coverage Obtained > 90%: No-50% Reviewed Previous Data: Yes Examiner Level II Date I Reviewer Date Vaiden, Paul 5/312018 s.
Examiner Level NIA Signature Date Date NIA Other Level N/A Signature Date Date N/A ~~{,--
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports
..:=::::;
Supplemental Report --- Exelon Report No.: ISl*UT-18-025 Page: 3 of 4 Summary No.: N2-ISl-168200 Sketch or Photo: O:\Outage Oata\Nme Mile\N2RF016\ISl\Sketches\2ACS-64-00-FWA07 (2).JPG
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<> Counterbore OS: None detected
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Attachment 2 - Page 37 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports ~~Exelon Supplemental Report Report No.: ISl-UT-18-025 Page: 4 of 4 Summary No.: N2-ISl-168200 Sketch or Photo: O:\Outage Data\Nine M11e\N2RF016\ISl\Sketches\2ACS-64-00-FWA07 (1).JPG Flow Sketch 2 ~ 60° RL 60° RL ( FD-25 FD-25
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Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports @ Structural Integrity Associates, Inc. NOE
SUMMARY
ISi Report No.: ISl-VE-18-003 SI Project No.: #1600586 ISi Summary No.: N2-ISl-011600 Customer: Exelon Site: Nine Mile Point I Unit: 2 Outage: N2R16 System: Component: Weld Number: LP Core Spray 2RPV-KC23 (NS) LP Core Spray 2RPV-KC23 Examination Procedure: Sl-UT-218, Rev. 0 ASME Section XI ASME Section XI 2004, No Addenda Edition I Addenda: Examination Record: NMP2-18-AUT-003 Calibration Data Sheets: NMP-18-CAL-013, NMP-18-CAL-014, NMP-18-CAL-015 Indication Evaluation Sheet: NIA Coverage Data Sheet: NMP2-18-AUT-003 Examination Scan Plan: 2RPV-KC23 N5 Scan Plan Risked-lnfonned Coverage: 80.3% Exam Coverage Achieved: Procedure Extended Coverage: 70.4% Summary: No Indications associated with IGSCC were noted in the examination volume. Intermittent (360°) ID geometry and weld interface noise were observed. See coverage data sheet for coverage estimate details. 2RPV-KC23 (N5) LP Core Spray DM weld was examined using Sl-UT-218, Rev. 0 on 04/24/2018. Examination meets the requirements of ASME BP&V Code, Section XI, 2004 Edition, no addenda with risk-informed program. o~TiftfM Examiner: Wade Holloway Level: III Date: Examiner: Joshua Sheers Level: III Date: SI Review: John J. Hayden Level: III Date: tJ'f/2. /I? Exelon Review: ;).J. c fl Level: -;-;;-- Date:
-=-
4~2 7-1e ANH Review: Jon Morris Date: L.\, *::)b -\~ Page_/_ of)~ Attachment 2 - Page 39 of 48
Unit2
- 55) StructL , Integrity Associates, Inc. Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Examination Data Sheet No.: NMP2-18-AUT-003 PHASED ARRAY ULTRASONIC EXAMINATION RECORD N5 Safe End-to-Extension General Configuration Weld
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Safe End SB166 lnconel Safe End Extension o.aa* Carbon Steel SA508 1/3T 0 30" Upstream Flow .... Downstream (-)
., (+)
,- I ASME Secrion XI Examinarlon Volume RI - /SI I j Procedure Extended Volume Page I.:< of .::?::f Attachment 2 - Page 40 of 48
Unit2 ~ Struct, 'Integrity Associates, Inc. Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports Examination Data Sheet No.: NMP2-18-AUT-003 PHASED ARRAY ULTRASONIC EXAMINATION RECORD N5 Safe End-to-Extension Axial Examination Coverage Weld {+) Cf. LKDN TRLO LKDN TRSO
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Safe End I
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SB166 lnconel l Safe End Extension Carbon Steel SA508 \" ', I -.... I Upsueam Flow Downstream (*) (+) ASME SecUon XI Ex11mlnt1tlon Volumo RI* ISi I l Procedure Extended Volume Page 13 of o?Lj Attachment 2 - Page 41 of 48
Unit2 ~ Strucll 1 Integrity Associates, Inc. Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Examination Data Sheet No.: NMP2-18-AUT-003 PHASED ARRAY ULTRASONIC EXAMINATION RECORD NS Safe End-to-Extension Circumferential Examination Coverage Weld Cf LKCWO Safe End SB166 lnconel Safe End Extension Carbon Steel SA508 Upstream Flow Downstream (+) 7 (*) r~--ul ASME Section XI Examlnarion Volume RI - ISi I IProcedure Extended Volume
~
The examination beam skew paths shown above in blue represent the actual beam skew angles generated by the ultrasonic technique. However, only the beam skew paths shown in red are qualified by the procedure for examination coverage. Page fl of.::!:/. Attachment 2 - Page 42 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports @Structural Integrity Associates, Inc. NOE
SUMMARY
ISi Report No.: ISl-VE-16-001 SI Project No.: #1600586 ISi Summary No.: N2-ISl-006100 Customer: Exelon Site: Nine Mile Point I Unit: 2 Outage: N2R 16 System: Component: Weld Number: HP Core Spray 2RPV-KC32 N16 HP Core Spray 2RPV-KC32 Examination Procedure: Sl-UT-218, Rev. 0 ASME Section XI ASME Section XI 2004, No Addenda Edition I Addenda: Examination Record: NMP2-18-AUT-004 Calibration Data Sheets: NMP-18-CAL-016, NMP-18-CAL-017, NMP-18-CAL-018 Indication Evaluation Sheet: NIA Coverage Data Sheet: NMP2-18-AUT-004 Examination Scan Plan: 2RPV-KC32 N 16 Scan Plan Risked-Informed Coverage: 81.6% Exam Coverage Achieved: Procedure Extended Coverage: 80.3% Summarv: No Indications associated with IGSCC were noted in the examination volume. Intermittent (360°) ID geometry and weld interface noise were observed. See coverage data sheet for coverage estimate details. 2RPV-KC32 (N16} HP Core Spray OM weld was examined using Sl-UT-218, Rev. O on 04/24/2018 and 04/25/18. Examination meets the requirements of ASME BP&V Code, Section XI, 2004 Edition, no addenda with risk-Informed program.
//J/L/ i}r:,ko1S Examiner:
Examiner: SI Review: Wade Holloway Joshua Sheeran Z John J. Hayden~~~.J1_
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p Level: Level: Level: III III III Date: Date: Date:
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O'f/2"/;t' Exelon Review: J.J". CtLif>t.TO_ J . -r:-§:1.. Level:
~
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-- Date: 4--Z..1-LR ANH Review: Jon Morris ~' ~~ .. ~ Date: L.\l'~b-\<l 1 " '
Pagej_of j~ Attachment 2 - Page 43 of 48
Unit2 ~ Struct~ Integrity Associates, Inc. Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports Examination Data Sheet No.: NMP2-18-AUT-004 PHASED ARRAY ULTRASONIC EXAMINATION RECORD N16 Safe End-to-Extension General Configuration Weld
~
Safe End I 1 i* ~ o.so* Safe End lnconel SB166 II Extension o.ss* SA508 1/3T 029" Flow Upstream (*)
,... Downsrream
(+) f -1 ASME Section XI Examination Volume RI* /SI I j Procedure Extended Volume Page I.,,:? of.::?::!. Attachment 2 - Page 44 of 48
Unit2 ~ Struct. 'Integrity Associates, Inc. Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Examination Data Sheet No.: NMP2-18-AUT-004 PHASED ARRAY ULTRASONIC EXAMINATION RECORD N16 Safe End-to-Extension Axial Examination Coverage (+) (-) LKDN TRLO LKDN TRS 0 I SafeE~d I \~' W' . 1 4 Safe End / t lnconel SB166 I Extension SA508 Upstream Flow ... Downstream {*) 7 {+) ASME Section XI Examination Volume RI - ISi I I Procedure Extended Volume Page I3 of -2.t./ Attachment 2 - Page 45 of 48
Unit2 ~ StruclL , Integrity Associates, Inc. Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Examination Data Sheet No.: NMP2-18-AUT-004 PHASED ARRAY ULTRASONIC EXAMINATION RECORD N16 Safe End-to-Extension Circumferential Examination Coverage Weld
~
.-----... r----i LKCWO Safe End Safe End lnconel 58166 II Extension SA508 Upsrream Flow Downsrream
{+) 7 (*) [ -m-J ASME Soction XI Examination Volume RI - /SJ I I Procedure Extended Volume Note: The examination beam skew paths shown above in blue represen t the actual beam skew angles generated by the ultrasonic technique. However, only the beam skew paths shown in red are qualified by the procedure for examination coverage. Page /"-/of ~.!./ Attachment 2 - Page 46 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports Supplemental Report ~Exelon Report No.: ISl*UT-18-002 Page: 5 of 6 Summary No.: N2-ISl*012000 Examiner: Kunze, Paul R. Examiner: NIA I z#IG Level: Level: II NIA Reviewer: Site Review: Date: Date:
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0-/1 Level: NIA ANll Review: Date: , (- ,_/( Other: NIA Comments: 2DEA-07A-FW002 Sketch or Photo: 0:\0utage Data\Nine Mile\N2AFO 1611Sl\Skelches\2DEA-07A-FW002.JP9
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Attachment 2 - Page 47 of 48
Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports
- -c.,,:::. Exelon Supplemental Report Report No.: ISl-UT-18-002 Page: 6 of 6 Summary No.: N2-ISl-012000 ~
Examiner: Kunze, Paul A. Examiner: N/A
~--------------~
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Date: S:-Z-f& Date:-:; Date: *, t;1 { Comments: 2DER-07A*FW002 Sketch or Photo: O:\Outage Data\Nine Mile\N2RF016\ISl\Sketches\2DEA-07A-FW002 (1).jpg Area required to scan .08 x 1.5 = 0.48 Scan Direction Coverage ON Stream Direction 0.08 x 0 = 0.00 UP Stream Direction (.08 x .90) + (.3 x .08 x .5) = 0.084 CCW Direction 0.08 x 0.5 =0.04 CW Direction 0.08 x 0.5 = 0.04 Area Scanned 0.16 All dimensions in sq.in. Area Scanned Total= 33% Attachment 2 - Page 48 of 48}}