Text

End of Interval Relief Associated with the Third Ten-Year Inservice Inspection (ISI) Interval
	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)
	v • d • e

{{#Wiki_filter:Exelon Generation ~. 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. 50-410 200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.55a

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)(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 Relief Request 2181-014

ATTACHMENT 1 1 O 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:

Reference:

Examination Category: Item Number:

== Description:== Component Number: 1&2 IWB-2500, Table IWB-2500-1, IWC-2500, Table IWC-2500-1, ASME Code Case N-460, ASME Code Case N-578-1, Table 1, ASME Code Case N-716, Table 1. 8-A, 8-0, C-A, R-A 81.40, 814.10, C1.10, R1.11, R1.16, R1.20 Limited Examination Coverage 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 1 O CFR 50.55a Relief Request 2181-014 in Accordance with 1 O 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 1 O 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 1 O CFR 50.55a Relief Request 2151-014 in Accordance with 1 O 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.

8.

Precedents ATTACHMENT 1 10 CFR 50.55a Relief Request 21SIM014 in Accordance with 1 O CFR 50.55a(g)(5)(iii) MMlnservice Inspection lmpracticalityMM Revision O (Page 4 of 12) 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).

Component ID 2RPV-CRDH001A (N2-ISI-068800) 2APV-CADH0018 (N2-ISI-068900) Note:

1.

Exam Weld Description Requirements (System)' (Figure No.) and Method CRD 18-03 IW8-2500-18 Pipe-to-Surface Flange Weld (PT) (APV) CAD 18-03 IW8-2500-18 Pipe-to-Pipe Surface Weld (PT) (APV) ATTACHMENT 1 1 O 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 Diameter/ Operating Exam Angle/ Exam Outage Material of Actual Category/ Line No. / Conditions Frequency (MHz) Coverage Examined Construction Item Thickness (Pressure I /Mode Number Temperature) Weld: 1016psi-1 4.o* Austenitic Pressure 8-0 N2A12 APV NIA I NIA I NIA 43% 814.10 Stainless Steel 0.365" 550 degrees - SS304 Temperature Weld: 1016 psi - 1 4.0" Austenitic Pressure 8-0 N2A12 APV NIA I NIA I NIA 80% 814.10 Stainless Steel 0.365" 550 degrees - SS304 Temperature Appendix VIII Qualified Remarks Exam The examination was limited due to Inherent obstructions caused by adjoining components. Disassembly of the CRD mechanisms does not facilitate additional coverage for the required surface examination areas No and redesign of the CAD mechanisms to provide access is 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 required surface examination areas No and redesign of the CAD mechanisms to provide access is not practical. (Att. 2

Pg. Nos. 4
5)

Location CAD 18-03. Limitation due to vertical tubing. Need to ooen insulation access nanels. 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)

Component ID 2APV-CADH004A (N2-ISI-069400) 2APV-CADH0048 (N2-ISI-069500) Note: I. Exam Weld Description Requirements (System)' (Figure No.) and Method CAD 30-03 IW8-2500-18 Pipe-to-Surface Flange Weld (PT) (APV) CAD 30-03 IW8-2500-18 Pipe-to-Pipe Surface (RPV) (PT) ATTACHMENT 1 1 O 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 Diameter/ Operating Exam Angle/ Category/ Outage Material of Line No. / Conditions Frequency (MHz) Actual Item Examined Construction Thickness (Pressure I /Mode Coverage Number Temperature) Weld: 1016 psi-1 4.0" 8-0 N2A12 Austenillc APV Pressure NIA I NIA I NIA 43% 814.10 Stainless Steel 0.365" 550 degrees - SS304 Temperature Weld: 1016psi-1 Austenillc 4.0" Pressure 8-0 N2A12 Stainless Steel APV 550 degrees - NIA I NIA I NIA 75% 814.10 0.365" SS304 Temperature Appendix VIII Remarks Qualified Exam The examination was limited due to Inherent obstructions caused by adjoining components. Disassembly of the CAD mechanisms does not facilitate additional coverage lor the required surface examination areas No and redesign of the CAD mechanisms to provide access is 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 required surface examination areas No and redesign of the CAO mechanisms to provide access is not practical. (Att. 2 - Pg. Nos. 8 -10) Location CAO 30-03. Limitation due to vertical tubing. Need to ooen insulation access oanels. 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)

Component ID 2WCS-09 FW014 (N2-ISI-208400) 2WCS-09 FW015 (N2-ISI-208600) 2APV-CADH005A (N2*1SI-069600) Note: I. Exam Weld Description Requirements (System)' (Figure No.) and Method IW8-2500-8(c), Sweep IW8-2500-9, Let-to-Pipe 10, & 11 (WCS) Volumetric (UT) Sweep IW8-2500-8(c), Let-to-Pipe IW8-2500-9, Suction 10, & 11 (WCS) Volumetric (UT) CAD 34-03 IW8-2500-18 Pipe-to-Surface Flange Weld (PT) (APV) ATTACHMENT 1 10 CFR 50.55a Relief Request 21$1-014 Proposed Alternative in Accordance with 1 O 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 Diameter/ Operating Exam Angle/ Category I Outage Material of Line No./ Conditions Frequency (MHz) Actual Item Examined Construction Thickness (Pressure I /Mode Coverage Number Temperature) Weld: Austenitic Stainless Steel 4.0' 1037 psi - 1 SA 312TP 2WCS-004-Pressure 45' 12.251 Shear A-A N2A12 316L-piping to 92-1 552 degrees - 70" / 2.25 / Shear 50% A1.16 SA 182 F316L O' I 4.0 I Long - sweep-o-let 0.337' Temperature (fitting) (6000 lbl Weld: Austenitic Stainless Steel 4.0' 1037 psi - 1 SA 312TP 2WCS-004-Pressure o* I 4.0 I Long A-A N2A12 316L - piping to 98-1 552 degrees - 45' I 2.251 Shear 50% A1.16 SA 182 F316L 0.337' Temperature 70" 12.251 Shear - sweep-o-let (fitting) (6000 lb) Weld: 1016 psi - 1 4.0' 8-0 N2A13 Austenitic APV Pressure NIA I NIA I NIA 63.8% 814.10 Stainless Steel 0.365" 550 degrees - SS304 Tempera lure Appendix VIII Remarks Qualified Exam The examination was limited due to sweep-o-let-to*pipe configuration Yes (single-sided examination coverage) on upstream side. (Alt. 2 *Pg. No. 11) The examination was limited due to sweep-o-let-to-pipe configuration Yes (single-sided examination coverage). (Alt. 2

Pg. No. 12)

The examination was limited due to Inherent obstructions caused by adjoining components. Disassembly of the CAD mechanisms does not facilitate No additional coverage for the required surface examination areas and redesign of the CAD mechanisms to provide access is not practical. !Alt. 2 *Po. No. 13} 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)

Component ID 2APV-CADH005B (N2-ISI-069700) 2APV-CADH038A (N2-ISI-076200) 2APV-CADH038B (N2-ISI-076300) Note:

1.

Weld Exam Description Requirements (System)' (Figure No.) and Method CAD 34-03 Pipe-to-Pipe IWB-2500-18 Surface Weld (PT) (APV) CAD 34-59, IWB-2500-18 Pipe-to-Surface Flange Weld (PT) (APV) CAD 34-59, IWB-2500-18 Pipe-to-Pipe Surface (APV) (PT) ATTACHMENT 1 1 O CFR 50.55a Relief Request 2151-014 Proposed Alternative in Accordance with 1 O 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 Diameter/ Operating Exam Angle/ Actual Category/ Outage Materiel of Line No./ Conditions Frequency (MHz) Examined Construction Coverage Item Thickness (Pressure I /Mode Number Temperature) 1 Weld: 4.0' 1016 psi-Austenitic Pressure B-0 N2A13 APV NIA I NIA I NIA 63.8% 914.10 Stainless Steel 0.365' 550 degrees - SS304 Temperature Weld: 1016psi-1 4.o* N2A13 Austenitic APV Pressure NIA I NIA I NIA 85.1% 9-0 914.10 Stainless Steel 0.365' 550 degrees - SS304 Temperature 1 Weld: 4.0' 1016 psi-Austenitic Pressure B-0 N2A13 APV NIA I NIA I NIA 74.4% Stainless Steel 550 degrees - 914.10 SS304 0.365' Temperature Appendix VIII Remarks Qualified Exam The examination was limited due to inaccessibility. Disassembly of the CAD mechanisms does not facilitate additional coverage for No the required surface examination areas and redesign of the CAD mechanisms to provide access is not practical. IAtt. 2-Po. No. 141 The examination was limited due to Inherent obstructions caused by adjoining components. Disassembly of the CAD mechanisms does not facilitate No additional coverage for the required surface examination areas 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 CAD mechanisms does not facilitate additional coverage for No the required surface examination areas and redesign of the CAD mechanisms to provide access is not practical. IAtt. 2 - Pa. No. 16) 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)

Component ID 2AHS"E1A,H W101A (N2-ISI-536000) 2SLS-88A-FW042A (N2-ISI-158500) 2APV-AG (N2-ISI-047800) 21SC-322B-SW005 (N2-ISI-150100) Note:

1.

Exam Weld Description Requirements (System)' (Figure No.) and Method "E1A Flange-to-IWC-2500-1 Shell Volumetric (RHS) (UT) IWB-2500-8(c), Pipe-to-IWB-2500-9, Weld-0-Let 10, & 11 (SLS) Volumetric (UT) Closure IWB-2500-5 Head-to-Volumetric Flange Weld (UT) (RPVCH) and Surface (PT/Mn IWB-2500-8(c), Tee-to-IWB-2500-9, Reducer 10, & 11 (ISC) Volumetric (Un ATTACHMENT 1 1 O 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 Category/ Outage Material of Diameter/ Operating Exam Angle/ Examined Construction Line No./ Conditions Frequency (MHz) Actual Item Thickness (Pressure I /Mode Coverage Number Temperature) Weld: Ferritic 2 50.0" 320 psi - C-A N2A13 Steel 2AHS-020-Pressure 45" / 2.25 /Shear C1.10 SA 516 GA70 185-2 388 degrees - 70" / 2.25 /Shear 83.8% to SA 105 0.9" Temperature Weld: Austenitic 1 Stainless Steel 3.0" 1240 psi - A-A N2A13 SA 106 GR B - 2SLS-002-Pressure 45" /5.0 I Shear 73% A1.11 piping to SA 89-1 560 degrees - 60" I 5.0 I Shear 64% 105 - weld-o-let 0.688" Temperature 10* I 5.0 I Shear (fitting) (6000 lb) 21.3" 1 Weld: Ferritic RPV Head 1016 psi - B-A N2A14 Steel to Flange Pressure 65" / 2.25 / Long 81.40 cs Weld 550 degrees - 10* through 75" I 80.25% 3.125" Temperature 2.25 /Long Weld: 1 2.0" 1035 psi - A-A N2R15 Austenitic 21SC-002-Pressure 30" I 5.0 I Shear R1.11 Stainless Steel RPV-1 550 degrees - 45" I 5.0 I Shear 85.5% SS to SS 0.46" Temperature Appendix VIII Qualified Remarks Exam The examination was limited due to the configuration of the flange and the adjacent weld. Yes (Alt. 2 *Pg. Nos. 17 -19) Includes essentially 100% of the weld lenath. The examination was limited due to pipe-to-weld-o-let configuration. (Alt. 2

Pg. Nos. 20
21)

Yes 73% Al-ISi coverage obtained and 64% procedure extended coverage obtained. The examination was limited due to head-to-flange weld configuration. (Alt. 2

Pg. Nos. 22
27)

Yes Essentially 100% coverage was achieved for the surface examination. The examination was limited due to Yes the code plate. (Alt. 2

Pg. No. 28)

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)

Component ID 2SLS-88A-FW013A (N2-ISI-156700) 2SLS-88A-FW015 (N2-ISI-157100) 2WCS-09 SW024 (N2-ISI-213900) 2WCS-09 SW025 (N2-ISI-214300) Note:

l.

Exam Weld Description Requirements (Figure No.) (System)' and Method IWB-2500-8(c), Valve *v10-IWB-2500-9, to-Reducer 10, & 11 (SLS) Volumetnc (UT) IWB-2500-8(c), IWB-2500-9, Pipe-to-Tee 10, & 11 (SLS) Volumetric (UT) IWB-2500-8(c), Tee-to-Pipe IWB-2500-9, (WCS) 10, & 11 Volumetric (UT) IWB-2500-8(c), Pipe-to-IWB-2500-9, Flange 10, & 11 (WCS) Volumetric (UT) ATTACHMENT 1 1 O CFR 50.55a Relief Request 2151-014 Proposed Alternative in Accordance with 1 O 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 Diameter/ Opereting Exam Angle/ Category/ Outage Material of Line No./ Conditions Frequency (MHz) Actual Examined Construction Coverage Item Thickness (Pressure I /Mode Number Temperature) Weld: Austenitic Stainless Steel 2.0' 1340 psi - 1 SA403 2SLS-150-Pressure 45* I 5.0 I Shear R-A N2R15 WP316L-88-1 560 degrees - 70' / 2.25 I Shear 50% R1.11 valve to SA 0.344' Temperature 10* 15.0 I Shear 403 WP316L-reducer (Sch 801 Weld: Austenitic 2.0' 1340 psi - o* 14.0 I Long 1 Stainless Steel R-A N2R15 SA 312 TP 2SLS-150-Pressure 45' 15.0 I Shear 89% 88-1 560 degrees - 70" I 5.0 I Shear R1.11 316L-piping to 0.344' Temperature 70' 12.25 / Shear SA403WP 316L-tee Weld: 1 Austenitic 4.o* 1037 psi - R-A Stainless Steel 2WCS-004-Pressure 45' / 2.25 /Shear R1.11 & N2R15 SA 312 TP 80-1 552 degrees - 70' / 2.25 /Shear 89.79% R1.16 316L-piping to 0.337" Temperature SA403WP 316L-tee Weld: Austenitic 1 Stainless Steel 4.0' 1037 psi-R-A N2R15 SA312 TP 2WCS-004-Pressure 45' / 2.25 / Shear 75% R1.11 & 316L-piping to 80-1 552 degrees - 70' / 2.251 Shear R1.16 SA 182 F316L 0.337" Temperature - flange (1500 lb} Appendix VIII Remarks Qualified Exam The examination was limited due to Yes valve-to-reducer configuration. (Alt. 2 - Pg. Nos. 29 - 30) The examination was limited due to Yes pipe-to-tee configuration. (Alt. 2 - Pg. No. 31) The examination was limited due to tee-to-pipe configuration. Axial Yes scanning restricted from the tee side for 3.0" at the radius of tee. (Alt. 2 - Pg. No. 32) The examination was limited due to Yes pipe-to-flange configuration (single-sided examination coverage). (Alt. 2 - Pg. No. 33) 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)

Component ID 2WCS-09 SW032 (N2-ISI-216700) 2WCS-09 SW033 (N2-ISI-217100) 2RCS-64*00-FWA07 (N2-ISI-168200) 2RPV-KC23 (N2-ISI-011600) Note:

1.

Exam Weld Requirements Description (Figure No.) (System)' and Method IWB-2500-8(c). IWB-2500-9, Tee-to-Pipe 10, & 11 (WCS) Volumetric (UT) IWB-2500-8(c), Pipe-to-IWB-2500-9, Flange 10, & 11 (WCS) Volumetric (UT) IWB-2500-8(c), Pipe-to-IWB-2500-9, Valve 10, & 11 "HYV17A Volumetric (RCS) (UT) CSL Nozzle IWB-2500-8(c), N5Safe IWB-2500-9, End-to-Safe 10, & 11 End Volumetric Extension (UT) (CSL) ATTACHMENT 1 1 O CFR 50.55a Relief Request 2181-014 Proposed Alternative in Accordance with 1 O 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 Outage Material of Diameter/ Operating Exam Angle/ Actual Category/ Examined Construction Line No. / Conditions Frequency (MHz) Coverage Item Thickness (Pressure I /Mode Number Temperature) Weld: 1 Austenitic 4.0" 1037 psi-Stainless Steel R-A N2R15 SA 312 TP 2WCS-004-Pressure 45' / 2.25 / Shear 89.79% R1.11 & 316L - piping to 60-1 552 degrees - 10* I 2.25 I Shear R1.16 SA403WP 0.337" Temperature 316L-tee Weld: Austenitic 1 Stainless Steel 4.0" 1037 psi - R-A SA 312 TP 2WCS*004-Pressure 45' / 2.25 /Shear N2R15 50% R1.11 & 316L-piping to 60-1 552 degrees - 70' / 2.25 /Shear R1.16 SA 182 F316L 0.377" Temperature - flange (1500 lb) 1 Weld: 24.0" 1251 psi - R-A N2R16 Austenitic 2RCS-024-Pressure 45' / 1.5 /Shear 50% R1.16 Stainless Steel 2-1 550 degrees

60' / 2.0 I Long SS to SS 1.3" Temperature 45' / 1.5 / Phased 1

Weld: Ferntic 10.0* 1042 psi - Array Half Path R*A N2R16 Steel 2CSL-010-Pressure 30' / 1.5 / Phased 80.3% R1.16 CS/INC/CS 13-1 537 degrees - Array Half Path 70.4% 0.75" Temperature 40' / 1.5 / Phased Array Half Path Appendix VIII Qualified Remarks Exam The examination was limited due to Yes the branch connection on upstream side for 6". (Att. 2 - Pg. No. 34) The examination was limited due to pipe-to-flange configuration (one-Yes sided examination coverage). (Att. 2 - Pg. No. 35) The examination was limited due to pipe-to-valve configuration (single-Yes sided examination coverage). Examined upstream side of valve HYV17A only due to conliguration. (Att. 2

Pg. No. 36 - 38)

The examination was limited due to nozzle safe end-to-safe end extension configuration. Yes (Att. 2

Pg. Nos. 39 - 42) 80.3% RI-ISi coverage obtained and 70.4% procedure extended coveraae obtained.

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)

Component ID 2RPV-KC32 (N2-ISI-006100) 2DER-07A-FW002 (N2-ISI-012000) Note:

1.

Exam Weld Description Requirements (System)' (Figure No.) and Method CSH N16 IWB-2500-8(c), Safe End-to-IWB-2500-9, Safe End 10,& 11 Extension Volumetric (CSH) (UT) IWB-2500-S(c), Valve 'MOV128-IWB-2500-9, 10, & 11 to-Pipe Volumetric (DER) (UT) ATTACHMENT 1 1 O CFR 50.55a Relief Request 2151-014 Proposed Alternative in Accordance with 1 O 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 Diameter/ Operating Exam Angle/ Category/ Outage Material of Line No./ Conditions Frequency (MHz) Actual Item Examined Construction Thickness (Pressure I /Mode Coverage Number Temperature) Weld: Ferritic 45* / 1.5 /Phased 1 Steel 10.0' 1050 psi - Array Half Path R-A N2R16 SB 166 - safe 2CSH-010-Pressure 30* / 1.5 / Phased 81.6% Rl.16 end to SA 508 27-1 550 degrees - Array Half Path 80.3% - extension 0.90" Temperature 40* / 1.5 / Phased Array Half Path Weld: Ferritic Steel 2.0' 1030 psi - 45* / 5.0 I Shear 1 SA 106GR B-2DER-002-Pressure 60' I 5.0 I Shear R-A N2R16 33% Rl.20 Piping to SA 7-1 550 degrees-70' I 5.0 I Shear 105 -valve 0.218' Temperature o* 14.0 I Long (30001bl Appendix VIII Remarks Qualified Exam The examination was limited due to nozzle safe end-to-safe end extension configuration. Yes (Att. 2 - Pg. Nos. 43 - 46) 81.6% RI-ISi coverage obtained and 80.3% procedure extended coveraoe obtained. The examination was limited due to valve-to-pipe configuration (one-sided examination coverage). Yes Downstream obstructed by valve, pipe clamp 1. 7" upstream of WGL. (Att. 2 - P11. Nos. 47 - 48) 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) 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 Site/Unit: NMP 2 Procedure: NDEP-PT-3.00 Outage No.: N2RF012

ummary No.

068800 Procedure Rev.: 1701 Report No.: PT-10-010 Workscope: 1 SI Work Order No.: C081919800-100 Page: of 2 Code: ASME Section XI 2004 Edition Cat.lltem: B-0/814.10 Location: RCA Drawing No.: 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.: Seri a I No.:

OA~*...;.,N;.;;O;.;;E;;..*T...;.,*....;;0....;;9....;;0 ___ _

Surface Temp.: 83 "F EXTECH Comparator Block Temp.: Side A: NIA °F Side B: NIA "F Resolution: 0.044" Character Card Lo/Wo Location: NIA Cleaner Pen et rant Brand MAGNAFLUX MAGNA FLUX Type SKC-S SKL-SP Batch No. 05B01K 94F13K Time Evap. 5mins. Dwell 10 mins. I Time Exam Started: 11:45 Indication Loe Loe Diameter Length Type No. L w R/L Comments: See attached sketech for limitations. Results: Accept RJ Reject O Percent Of Coverage Obtained > 90%: Evar O No. 43% Examiner Level II Date Woodring, Ryan A. 411612010 Examiner Level NIA Date NIA Other Level N/A Signature Date NIA Surface Condition: Smooth Remover Developer MAGNAFLUX MAGNAFLUX SKC-S SK0-52 05B01K OOJ14K Evap. Smins. Develop 10 mins. Time Exam Completed: 12:45 Remarks No recordable Indications Reviewed Previous Data: Yes Reviewer Date Lancaster, Phillip, NOE Level Ill Yaeger, William J. - 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 R F\\J~ ( R.DH-CO I.A 1S APP~O~llfJA rCL Y 2 v? FRON? ;:'LA/II GE 8 8 IOTAL AREA = l8. 16 ,..Rf:A EXllJY> Jf.JE D = 8.. ( '13 Ye.) - 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 Site/Unit: NMP 2 Procedure* NDEP-PT-3.00 Outage No

N2RF012 iummary No.:

068900 Procedure Rev. 1701 Report No: PT *10-011 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 Limitations: Limited due to adjoining components. Light Meter Mfg.: NIA Serial No.: NIA Temp. Tool Mfg.: EXTECH Serial No.: QA-NDE-T -090 Comparator Block Temp.: Side A: NIA °F Side B: NIA "F Resolution: I LoNVo Location: NIA Cleaner Penetrant Brand MAGNAFLUX MAGNAFLUX Type SKC-S SKL-SP Batch No. 05801K 94F13K Time Evap. 5mlns. Dwell 10 mins. Time Exam Started: 11:45 Indication Loe Loe Diameter Length Type No. L w Comments: See attached sketech for limitations. Results: Accept ["'! Reject n Percent Of Coverage Obtained > 90%: R/L Eval [ i No. 80% Surface Condition: Remover MAGNAFLUX SKC*S 05B01K Evap. 5 mlns. Time Exam Completed: No recordable indications Reviewed Previous Data: Examiner Level 11 Date Reviewer Mat./Thickness: SS 304 I NIA Illumination: NIA Surface Temp.: _ __;.B..;..3 __ "F 0.044" Character Card Smooth Developer MAGNAFLUX SKD-52 OOJ14K Develop 10 mins. 12:45 Remarks Yes Date Woodring, Ryan A. 4116/2010 Lancaster, Phillip, NOE Level Ill Examiner NIA -:lther NIA Level NIA Level NIA Signature Date Date ANll Review Yaeger, William J. {/.(-

Page 4 of 48

Unit 2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Supplemental Report ummary No.: _o_ss_s_o_o __________ _ Sketch or Photo: S:,Common\\Ql-NDEIQl-NDE,N2R121Datasheet Scanned lmages\\2RPV-CRDH-001 B JP9 1'CIA! A.i<.[' A f ,-i,.z.*~ _.,, -- *"P. c ( ,!?)<A,.,.\\ 1A;t~L.*

.,.- * - Page 5 of 48

/ / Report No: Page: J l I ~ p..; T"Olv\\ 1-j,.. lf(.W:: PT-10-011 2 of 2

Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports A. Constenntlon e,,_-gy V'-'""'* '~\\.'-"'C"' Liquid Penetrant Examination Site/Unit: NMP 2 Procedure: NDEP-PT-3.00 Outage No.: N2RF012 069400 Procedure Rev.: 1701 Report No.: PT-10..()12

ummary No.

-~-------~~- ~~~-----~ 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 Limitations: Limited due to adjoining components. Light Meter Mfg.: NIA Serial No.: N/A Temp. Tool Mfg.: EXTECH Serial No.: QA-NDE-T-090 Comparator Block Temp.: Side A: NIA °F Side B: NIA °F Resolution: LolWo Location: NIA Cleaner Pen et rant Brand MAGNAFLUX MAGNAFLUX Type SKC-S SKL-SP Balch No. 05B01K 94F13K Time Evap. 5mins. Dwell 10 mins. Time Exam Started: 11 :45 Indication Loe Loe Diameter Length Type No. L w R/L Comments: See attached sketech for limitations. Results: Accept~ Reject 0 Percent Of Coverage Obtained > 90%: Eval O No -43% Examiner Level 11 Woodring, Ryan A. Examiner Level NIA Date NIA Jther Level N/A Signature Date NIA Surface Condition: Remover MAGNAFLUX SKC-S 05801K Evap. 5mlns. Time Exam Completed: No recordable indications Reviewed Previous Data: Yaeger, Wiiiiam J. I - Page 6 of 48 Mat/Thickness: SS 304 Illumination: NIA Surface Temp.: __ 8_3 __ °F 0.044" Character Card Smooth Developer MAGNAFLUX SKD-S2 OOJ14K Develop 10 mins. 12:45 Remarks Yes

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 r Ct. 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~)

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 Site/Unit: NMP 2 Procedure: NDEP-PT-3.00 Outage No.: N2RF012 ,ummary No.: ------------ 1701 Report No.: ------ 069500 Procedure Rev.: 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 Percent Of Coverage Obtained > 90%: Examiner Level II Woodring, Ryan A. Examiner Level NIA N/A Jther Level NIA Signature NIA Eval [J No - 75% Date 411612010 Date Date Reviewed Previous Data: Reviewer Lancaster, Phlllip, NOE Level Ill Yaeger, William J. - Page 8 of 48 Yes Date

Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Supplemental Report Report No.: PT-10-013 ,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 - Page 9 of 48 Page: 2 of 3

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 le>TA L.AR.£ A:-*/~*.{( *' A~..f';'I E.kAIVIJNcD~* 1 u,, % c CMPt.ETE::: ?:.->-.J(. FOV/.JDATIO~ WAl-L - 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 -, ~ H......l Level: 11-PDI Reviewer: Date: 4/11J 1 ~ r i Examiner: NIA Level: NIA Site Review: Date: 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{ - Page 11 of 48

Unit 2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports .:xelon Supplemental Report 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 - Page 12 of 48

Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports Liquid Penetrant Examination Site/Unit: NMP 2 Procedure: NDEP.PT-3.00 Outage No.: N2RF013

~----~

~~

Summary No.: 069600 Procedure Rev.: 1800 Repor:t No.: ISi.PT 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 Fluorescent 0 Remover Developer 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 Percent Of Coverage Obtained > 90%: Eval O No/ 63.B*AJ Reviewed Previous Data: Examiner Benson, Michael Examiner Level NIA Other NIA Level Signature - Page 13 of 48 Yes Signature Date

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.: 089700 Procedure Rev.: 1800 Report No.: 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.: N/A Serial No.: NIA Illumination: NIA Temp. Tool Mfg.: EXTECH Serial No.: __ _.QA;;..,,;,,,o*N,..D.... E..,*,..T_..0....;;.9-.2 __ Surface Temp.: 77.2 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 NIA Percent Of Coverage Obtained > 90%: Eval D No/83.8% Reviewed Previous Data: Examiner Examiner N/A Other NIA Level NIA Signature Date Reviewer 515/2012 z - Page 14 of 48 Yes Signature

F Date

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.: 076200 Procedure Rev.: 1800 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 Limi~ns: 6S. I.34'% Coverage of weld due to obstructions 1fW s1 1Rt1k Light Meter Mfg.: N/A Serial No.: Temp. Tool Mfg.: EXTECH Serial No.: N/A QA-NDE-T-092 Comparator Block Temp.: Side A: NIA °F Side B: NIA °F Resolution: LoNl/o Location: NIA Surface Condition; Visible iil Cleaner Penetrant Fluorescent 0 Remover Brand MAGNAFLUX MAGNAFLUX MAGNAFLUX Type SKC-S SKL-SP SKC-S Batch No. 10C01K 94F13K 10C01K Time Evap. 5 Dwell 10 Evap. 5 Time Exam Started: 1340 Time Exam Completed: Indication Loe Loe Diameter Length Type No. L w RIL N/A NRI Comments: Matffhickness: SS/NA Illumination: NIA Surface Temp.: 77 °F 0.044" Character Card As-Welded Developer MAGNAFLUX SKD-52 05J05K Develop 10 1440 Remarks 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 Percent Of Coverage Obtained > 90%: Eval O No/ 85.1% Examiner Benson, Mlchae Examiner Level NIA Other N/A Level N/A Signature Signature N/A Reviewed Previous Data: Yes Signature Date

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 Fluorescent Q Remover Developer 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 Percent Of Coverage Obtained > 90%: Eval fJ No/74.4% Examiner Level Ill g~ Date Herold, John F t/,,"I 5/5/2012 Examiner Level NIA Date N/A Other Level N/A Signature Date N/A NIA Reviewed Previous Data: Yes Reviewer Signature Date N 'A-

Nine Mile Point Nuclear Plan Unit 2 L'mited Coverage N t Third ISi Interval I DE Reports Supplemental Report Report No Page-ISl-UT-12-039 2 ot

a* i, r;e T11td L

\\f 1 r _ t. ** f~cv1ewer o 536000 Le,el II-POI t 'cl]'ro, ' ". "uomna1y N I I, Siie Rewew S*lley. Moch'< Le"I _111_ !f( -==--- E<aon'"m SC-ANll R,,,.,., L ~ Ex<muner Crothers,~~i:n~o~n~P~ - ~~;,~

:J~--===-~Le:v:e>l-=T=R=-

N ----~':._ ____ ~ Kelvin Other* Jones.

>111111en1tAs HW101A 2RHS-E Sketch 1 Photo Sketch o1 0

1" d' cent Weld 2R~SJ-~1A-HW102A 2" 3" era e limited by flange. I J 143" of weld, cov g nd ad1acent weld. . ited by flange a fil~l 13" of weld, coverage lim I I I I I -- Weld Details 56 Weld Length - 1 - 1 4" (typical) Weld Crown Wtdt0h)~(2.4" x 0.9") = 2 16 rn (ABC Exam area. IWC-2500-1 Code Figure Page 17 of 48 - \\ '. 0 9" Flange B l y-1 I I I I I I I 0 c 4

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,-1 I./!,,

1. f (

-r-I ,rl/{ (' I. ~'; 1 Di1te J.. I f., lllllllP.1 Crothers. Simon P. Sc Level Ill 11e f~ev1ew * "'ilUaO T.-1. \\..*! _,./" Date

ft' I

D:ile Levr~I TRN ANll Hr>v1ew:

t. ;/L_.*---*

I 1 ither Jones. Kelvm i<.-S 1 lllnlPPI'> 2RHS-E1A-HW101A Sketch 2 );.,, 11 h rn Phnl11 [] Axial coverage ltm1ted by flange 143" ol 156" Exam area= 2 16 m2 Shell Examined 2 16 - ( 1 O" x 0 5")/2 = 1 91 in' D D 1911216=88.4% tl84'1ox(143"of156")=81% 0 Adjacent Weld 2RHS-E1A-HW102A Axial coverage limited by flange and ad1acent weld 13" of 1!:>6 l::xam area= 2 16 in~ I Examined 2 16 - (1O"x0 5")12 - (0 3" x 0 15' = 1 89 in2 189/216=875Yo 87 5°/., x (13" of 156") = 7 3<y., Total Axial Coverage: 81% + 7.3% = 88.3'Yo - Page 18 of 48 1" I 2" I Flange l ~ .:/ /..: r.7 /,i., I.. l '* 't 2~).-12... s1zd-~--.: r1 3* I

Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports o*. _,.,... 1:,.,~, ** Supplemental Report Rvporr No ' u1n111riry No 536000 t x,1111111e1 Salley. Michael ,,,, :1 5 Level 11-PDI 1*,;::11111ner Crothers, Sunon P. Sc Ill Sile F~eview. 1Jlt1Pr Jones. Kelvin 1:ornn1!illl'> 2RHS-t: 1A-HW101A Sketch 3 kP!Ch 01 Pl1oln l C1rc coverage limited by flange 156" of 156" l{..T Level TRN ANll Review. Shell ISt-UT-12-039 Date Dale

/ *, *). I '

S/i~// Z... ~* I, II I I I I I I 1 Flanqe 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 1112 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% - Page 19 of 48

Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Summary No.: 158500 Examiner. Crothers, Simon P. Examiner* Jones, Kelvin Other NIA 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: SC l(r Supplemental Report Report No ISi-UT 082 Page: 2 of 5 Level: Ill Reviewer. J..~..,2..u:<Z.\\,. .<"~ D~te : S:7-J2. t* Level: TRN Site Review Cilento, Joseph, Level Ill Date: )'~1*rv Level: NIA ANll Review Rose, Charles C;A Date: -::/-;:/; L I 0 25- (0.05 x 0.15)/2 -(0 15 x 0.15)12 = 0 241n2 0 24 I 0.25 = 96% 0 68" filiillIII Code Coverage. Circ Exam Area: ( 1 1" x o 23") = O 25 m2 Examined: (0 55 x O 23) = 0.125 mi 0 12 5 I 0 25 = 50% Weld-a-let 0 I"' Code Coverage Cale: 2" 3" Axial= 96% I I I I Circ = 50% Total = (96 + 50)/2 = 73% - 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 Comments 2SLS-88A-FW042A Sketch 2: R-A Coverage Sf:e~ Ph9IQ.. ~ R-A L;overage Axial Exam Area: (16"x0.23") = 0 37 1n 2 Examined: Level N/A ANll Review 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 1n2 Examined: (0 8 x O 23) = 0 185 1n~ 0 185 I 0 37 = 50% R-A Coverage Cale: 0 Axial= 78% I Gire= 50% Total= (78 + 50)/2 = 64%

Page 21 of 48 Rose, Charles

¥ Date: :j_;:) z_ Flow Weld-o-let 1" 2* 3" I I I

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(~): I NMP2-14-2RPV-AG I I NMP2-14-CAL-005 Calibration Data Sheet(s): 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. Examiner: Richard C. 'vlay F*wmincr: N/:\\ ..,I Review: John Hayden l tility H.cvicw: \\.\\II l{cvicw: ( __ Level: Level: Lc\\'el; Level: Page I of 9 - Page 22 of 48 II Nii\\ 111 ~ ...L~ Date: 3-30-14 Date: Ni A Date: a'f /(J'{ /t'f D:1te: -!:t-/~ l>atc: L///fJt/ I 4 - {.~ *- t<f-

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-AG Coverage l:x..1111 Volume: i---------*- 1 __ z_o111~ 1 **-----i I [ ~~~~ve;;e=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* ISl-VE-14-00 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 I Exam Volum.: 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' i i Vi.fume or.\\.lisscd Covcrnuc = o.6in* _J Volumc C1wcrag('. - (8.6Xin= - 0.(Jin')/ 8.6l:lin= = U.\\13 '" IOll'J*u 93% Pagi: 5 of') - 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 f=xam Volurnt: lone 2 PHASED ARRAY ULTRASONIC EXAMINATION COVERAGE 2RPV-ACi 1-lcad-to-Fhmgc Jn-Service (ISi) Axinl Scan Examination Volume Layout (Cont.) ISJ-V E-1 00 I

\\*\\~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 for 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=- I 00% Exam Volume /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: () in2 \\11lurncCcl\\t:rat.: = t4.XXin,-0111"1 4.1\\Xin' 1.0 l!JO"u IOO'Yu Page 6of9 - 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 t*dlll Volume 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 ~ \\ \\ '\\ r------ --1 L Zonc 1 ( MiS$Cd Coverage J I 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 ~one I th1d.. n1..". 2" I Z*Hll.: I \\\\ 1dlh ~ \\\\ cld \\\\ 1J1h.. I 2t \\ 2 -* l I 22" ' ( 1.5u"\\ 2)) - -U4" Lune I.-\\rca =Thickness x \\Vidth = 8.68in' I 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 Page 7uf9.. 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 E:x.irn Volume Zone 2 PHASE[) ARRAY ULTRASONIC EXAl\\UNATION COYERAGE 2RPV-AG Hcad-to-Flangt.: ln-St.:rvicc ( ISi) Circumlercntial Scun l:xamination Volu.mc La)uut lcunl.) \\ \\ \\ \\ \\ \\ 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 Z 1

1 1111*,;. 11 * * * - I I.,,..

_ l)f l.: - \\,,,,"' lr.::"t.!t - J Zon-= 2 wid1h = W.:IJ Width

I 121' 2

( 1.2'.!" - (I.56"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 - Page 26 of 48

Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports ~J Structural l1Jtegrity Associates i -i:.~~n~ii;;;, oata

--- -5~;1-e: 1 3-30-2014

--1

1

~xammers. Richard C. May Start Time 1135 r-- F~"i;t~ Time 1400 I - ---;i---------1 I ~~~}~~~~~: -! Thcr:~::t:r ~~i ~:~~~;~---_! I Axial Zero Datum Circ Zero Datum l--=-=:-.. Weld c.,-;:;\\orline - 0 Stamp

1 Stud Hole J Wedd C,

A f\\ ! \\ I \\ I ; I \\ --~ \\ i \\ . \\ Nine Mile Point Unit 2 RPV Top Head-to-Flange 2RPV-AG Scan Plan I Examrnalton Volume '.~~' ~ Zone2 -~~~i:.:~ ~T~~~~7:ion [ Pr~:-::-~ -S~;;:~: - Scan OlrcclW>n I :.:: *1 Uln R I r Eumlnaiion Mu Min Max 111.. Enon Volutn<> Sonsltlvily R MP MP Ml1orlenlatlon ~ ldBl._ NIA ~~:~~-L-.~- ~'.~-!~ F'orpr.nor.ubr tcWclo I*~-~ -*~c-1-t1-on_! __ ~c* 10 75* I Momu.al _! 'Ja"~. P~rpendicut.ir1o w.,1tt. _-~~A_!_ _ JP.Ro. Ni~ ~00-l-'1~07:! I

s*

"~n.u :ll Voss;el C1rcu;r,ter1mUat ~ 1 8 Jt;0-1~1-C7~ ;-** 1.. ~ 75-;- Manual ~Ve;;;- C1rcurnf.:1unlwl Flal 1 e NIA NIA t.J/A NIA NIA NIA NIA NIA NIA NtA NIA NIA NIA t-1/A Pai.:c I) of lJ - Page 27 of 48 Lono 1 33.5 Zorn:i 2 36 Z:onu 1 lS.5 Zona 2 35 Weld

c.

IA' \\ ' l \\ I 1::.1-\\ I - 1 ~*\\JUI ~~-:-~"-"'*' ~~{'!!~l~~ ~

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: Examiner:...:N.::.l:....:A~------------- Level:~ Site Review: >-<"~

"i o<V"< *.,

Date: 4-z. 5:' (a Date: 4~25-lb Date: 1.; -.}.. 7-r 6 Other:...;N,;;;,/;;..;A ____________ Level: NIA ANll Review: Niznik, Dean S. J2r-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 Sketch or Photo: scan. Full coverage achieved for DNST clrc. scan. Pipe Circ UPST=S.125 in. UPST Axial: 100%. Pipe Clrc DNST=7.75 In. UPST Circ: 100% 0 Lo** ONST Axlal: 42% DNST Circ: 100% - Page 28 of 48 TTL AxlCirc. Coverage = 342% Coveraqe Achleved=342/400 = 85.5%

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 Com pone n t ID: 2SLS-88A-FW013A Size/Length: 0.35 In. I 6.25 In. Thickness/Diameter. 0.344 In. I 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: MSW QC Inter. Cal. 1305 411512016 0.5 In. Notch 80 5.1 1.3 in. Delay: 7.7184 j.ISeC. Range. 2.5 In. Freq 2.25 MHz Center Freq.: NIA Inter. Cal. NIA N/A Square Inter. Cal. NIA N/A M'll CalNel: 0.1221 ln/µsec. Pulser Type* Exam Angle: 10* Squint Angle: NIA Final Cal. 1425 411512016 NIA Damping: 5000hms Re1ect: 0% Measured Angle: se* Mode: Shear Couplant NIA PRF: Auto High SU Freq.: 2.25 MHz Exit Point 0.25 In.

of Elements 1

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 Sound Path Shape* Round Contour NIA Reftector Amplitude% Division Mfg. SONOTECH Gate Mode:: NIA Display Delay: NIA Wedge Style: MSWQC NIA Ax. Gain (dB) 51.9 Circ. Gain (dB): NIA Exam Batch 00325 Search Unit Cable NIA 1 0.25 in. of Sound Path Length: 6 ft. No. Conn. Type: ULTRAGELll NIA Screen Div.= Type: RG-174 0 Mfg.: SONOTECH NIA Calibration Block Scan Coverage Cal. Block No.: 12-1181 Upstream O Downstream~ Scan dB. ~ Reference Block Reference/Simulator Block Gain Signal Sweep Sound Path Thickness 0.5 ln.-2.0 In. Dia.: Flat CWLJ CCW LJ Scan dB: NIA Senal No.: 94-6005 dB Reflector Amplitude% Division Cal Blk Temp. 82" Temp Tool: 0003091668 Exam Surface: 0.0. Type: Rompas 304 SS 36.9 NSDH 80 3.2 0.8in. Comp. Temp. _!!:... Temp. Tool: 0003091668 Surface Cond1bon: Ground NIA 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 configuratation. Percent Of Coverage Obtained > 90%* No-50% Reviewed Previous Data: Examiner Level 111-PDI Hiiborn, Marie R. ~;t!L Examiner Level N/A Signature N/A Other Level NIA Signature NIA Yes Date I Reviewer 411512016 Siever, Theodore, Level Ill Date I Site Review 1ToDO M. G1NJ:S(2... Date I ANll Review Niznik, Dean S. - Page 29 of 48 ~ 2 Signf."re ,'/JJ Date '-' -Z2. - \\ (r;, Date ~/23/11:, Date '-f-~S-/r,

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. /Zf>tll Level: 111-PDI Reviewer: Examiner: NIA ...;..;.;.;...;;.... ____________ ~ Level : ~ Site Review: Ginder, Todd M. s;z* n,, other: '""'N..;;./~A'--------------- Level: N/A ANll Review: Niznik, Dean S. ~-- Date: 4/2212016 Date: 4/23/2016 Date: t./ -V-**/G Comments: Previous Data: W 1-6.24-06-0014 (2006) Sketch or Photo: VALV£' r::'Lt>vJ ~---_,,,... R. £0\\..\\ c.£ fL ~ <i:_. -,a* q T* ~-U/

i.

t."
'1.. r* - 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: Summary No.: 157100 Examiner: Hilborn, Mark R. fa1 /Lit Level: Ill-POI Reviewer: Siever, Theodore, Level Ill Examiner:...;N;..:;/;.:.A.:..._ _____________ _ Level: N/A Site Review: -HfA GNa:;i? 7DCD Other: """N/.;;;.;;...;A _____________ Level: N/A ANll Review: Niznik, Dean S. ~ 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"' - Page 31 of 48 5 of 5 Date* 4~-\\c;,, Date: 1/-:Jlf * /f. Date: '/ - )..) "'7../~

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 Examiner: NIA Level: NIA Site Review: G1NDER, TTJC{) ate: \\.\\-21.H i.:i Date: ~*J,l{-/J:, Date: '{ -rJ-7-lfr> Other: NIA Comments: 2WCS..09-05-SW024

1. 8.7 + 14.7=59.18=14.796%

2.

25%

3.

25%

4.

25% = 89.79% Level: NIA ANll Review: Niznik, Dean S. Weld Length

14. 7" lntradose limitation area = 3.0" F'Low

\\ I s:s 'I I ~----.-.:.Z-1___ \\ '

~------~--

o.~'" o *.31o* v 0.3,2-O,J'f" 0.1(.J'" - 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: ~ Examiner: N/A / Level: N/A Reviewer: Siever, Theodore, Level Ill ~Date: 1\\-2..5-\\-b Ctt..1::').(rr:1 J. Jl-~te: 4'-U--16 Niznik, Do.; s.,:= Date: ¥- iJ-/.< Site Review: Other: NIA Level: NIA ANll Review: Comments: Profile not to scale. 2WCS-09-05-SW025 Weld Length 14.7"

1.

25%

2.

0%

3.

25%

4.

25% = 75% rLOW \\ I ~---~- '~--- .-.;3 ___ \\ -'I!!&.... __ ~.31$' l>.35'"..., Cl.311" o.~b" D. 'i.l' - Page 33 of 48

Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Exelon Summary No.: 216700 Examiner: Huhe, Troy -r-~f-(~ Examiner: NIA Other: NIA Comments: WCS-09..05-SW032 1 8.7 + 14.7 = 59.18 = 14.796% 2 25% 3 25% 4 25%

89.796%

Supplemental Report Level: 11-PDI Reviewer: Level: NIA Site Review: Level: NIA ANll Review: Weld Length lntradose limitation area , - Page 34 of 48 Report No.: ISl-UT-16-064 Page: 3 of 3 Siever, Theodore, Level Ill. ~Dale: 412512016 C1t.UJI'~ :J.J. Niznik, Dean S. 14.7" 3.0" 1,LT-rIC Dale: J..2-16 .A---- Date: J--l-{. J,

Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports ~-- Exelon Summary No.: 217100 Examiner: Huhe, Troy -r Examiner: N/A Other: N/A Comments: WCS-09-05-SW033 1 2 3 4 25% 0% 12.5% 12.5% =50% /./~ Supplemental Report Report No.: ISl-UT-16-065 Page: 3 of 3 Level: II-POI Reviewer: Siever, Theodore, Level Ill ~ate: \\.\\-2'2-l t,o ~ .£,_-z.. n, Level: NIA Site Review: Level: N/A ANll Review: Weld Length lntradose limitation area \\ I cic.~1 T*S, Niznik, Dean S. 0 14.7" 3.0" \\ I I . 31"

!>Z.'
?> 1 - Page 35 of 48 IA.,....w I

~ Date: J-;:.? -/{.

Unit2 -~ .<E' LO I Nine Mile Point Nuclear Plant Third ISi Interval Limited Cov~rage NOE Reports UT Calibration/Examination 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. Time Date Axial Oriented Search Unit Serial No.: 02554H Serial No.: 00-991 Checks Calibration Signal Sweep Manufacturer: GEIT Manufacturer: RTD Initial Cal. 1648 5/3/2018 Reflector Amplitude% Division Sound Path 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" Freq.: 2.0 Center Freq.: NIA Inter. Cal. NIA NIA NIA NIA NIA M'tlCalNel: 0.2367 Pulser Type: Square Squint Angle: Inter. Cal. NIA NIA NIA NIA N/A Exam Angle: so* s* Damping: Final Cal. 1845 51312018 NIA NIA NIA NIA 5000hms Re1ect: 0% Measured Angle: so* Mode: Long. PRF: Couplant NIA NIA NIA NIA Auto High SU Freq.: 2.0 Exit Point 0.70 8 II of Elements: 2 Frequency: 2.0MHz Rectify: Fullwave -- Cal. Batch: 12125 Circumferential Oriented Search Unit Config.: oual(!:>s5rocus: FD25 Voltage: 450 Pulse Width: 250 Gate Mode: Peak Display Delay: 0.000 Ax. Gain (dB): 56 Circ. Gain (dB): NIA 1 Screen Div. = 0.4 in. of Sound Path Calibration Block Cal. Block No. CAL*PDl-009 Thickness 0.5" -2.0" Dia.: Flat Cal. Blk. Temp. N/A Temp. Tool: NIA Comp. Temp. NIA Temp. Tool: NIA Recordable lndication(s): Yes No"' Resulls: Accept.,, Reject Percent Of Coverage Obtained > 90%: No-50% Examiner Level II Vaiden, Paul Examiner Level NIA NIA Other Level N/A N/A Recf.'Wt;~ *t~r: Type: ULTRAGELll Calibration Signal Sweep Sound Path Shape: Flat Mlg.: MAGNAFLUX Reflector Amplitude% Division Wedge Style: Integral NIA NIA NIA NIA Search Unit Cable Exam Batch: 12125 NIA NIA NIA N/A Type: RG-174 Length: No. Conn.: o Type: ULTAAGELll NIA NIA NIA NIA 6' - Mfg.: MAGNAFLUX Scan Coverage NIA NIA NIA NIA Upstream ~ Downstream f] Scan dB: 70 Reference Block Reference/Simulator Block Gain Signal Sweep Sound Palh CW I CCW [] Scan dB: NIA Serial No.: 94-6005 dB Reflector Amplitude% Division Exam Surface: O.D. Type: SS 56 NSDH 40% 2.5 0.609" Surface Condition: Flush NIA NIA NIA NIA N/A (If Yes, Ref. Attached Ultrasonic Indication Report.) NIA N/A NIA NIA NIA Info Comments: UT of component 2RCS-64-00-FWA07; Pipe-to-Valve

HVV17A Reviewed Previous Data:

Yes Date I Reviewer Date 5/312018

s.

Signature Date Date Date Signature Date ~~{,--

Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports ..:=::::; Exelon Supplemental Report Summary No.: N2-ISl-168200 Sketch or Photo: O:\\Outage Oata\\Nme Mile\\N2RF016\\ISl\\Sketches\\2ACS-64-00-FWA07 (2).JPG Sketch 1 !-low . ") /-; ~ ~ ~ I L--L--- ~pe

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l1~J I~ Code c:civ~n:;ge: t>i1% ..- xar:- l,Jverage ~ 50% a::; 1_,c;, smgie s. '": acce::;s ;ule:s () ~ l _ _L ___ I I _l _ _ L__I /\\Xiai Exarn* Scanned at;ross flush wdd cr.:wm wn1le irtain~air : ny probe contact. o Circ Exam: Scanned US and on weld cww11 o Ccunterbore US* Located 1" from weld centerl:nc.. Counterbore OS: None detected () wcw ::: 1.85 ":.::'.' c~::le~:;r;::~~ftJ~ - Page 37 of 48 Report No.: ISl*UT-18-025 Page: 3 of 4

Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports ~~Exelon Supplemental Report Summary No.: N2-ISl-168200 Sketch or Photo: O:\\Outage Data\\Nine M11e\\N2RF016\\ISl\\Sketches\\2ACS-64-00-FWA07 (1).JPG Sketch 2 ( I ...... ~~~~-~ 60° RL FD-25 _Min f-'D / 60% ~ Flow .l ~ ~ 60° RL FD-25 I /~HYV'i7A Probe FD/ 75% ------ 1 I I I ! / ~, __.i. Max !-n I i 10% _____. [ _,:.-:-::1 ~;,,*~ *'J ............... '1 ,~ ~ R-1~.,_,overage ~~ ~~ code t_;'Jvcrafjt: Report No.: ISl-UT-18-025 Page: 4 of 4 Far sid6 d.......,: I e>~a1 *1in . I l I 1** ~ ,.~ ~ f'),

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i I

I J __ L__J_ __ _J __ _J - Page 38 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-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 Exam Coverage Achieved: Risked-lnfonned Coverage: 80.3% 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. Examiner: Wade Holloway Level: III Date: o~TiftfM 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)~ - 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 Safe End Extension Carbon Steel SA508 o.aa* 1/3T 0 30" Upstream (-) N5 Safe End-to-Extension General Configuration Weld ~. Flow Safe End SB166 lnconel Downstream (+) I ASME Secrion XI Examinarlon Volume RI - /SI I j Procedure Extended Volume Page I.:< of.::?::f - Page 40 of 48

~

Struct,

'Integrity Associates, Inc. Unit2 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 LKDN TRLO LKDN TRSO ~ {+) Safe End Extension Carbon Steel SA508 N5 Safe End-to-Extension Axial Examination Coverage Weld Cf. \\""~ \\"., I Upsueam Flow (*) Safe End I SB166 lnconel l Downstream (+) I ASME SecUon XI Ex11mlnt1tlon Volumo RI* ISi I l Procedure Extended Volume Page 13 of o?Lj - Page 41 of 48

~ Strucll 1 Integrity Associates, Inc. Unit2 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 LKCWO Safe End Extension Carbon Steel SA508 NS Safe End-to-Extension Circumferential Examination Coverage Upstream (+) Weld Cf Flow 7 Safe End SB166 lnconel Downstream (*) r~--ul ASME Section XI Examlnarion Volume RI - ISi I I Procedure Extended Volume Page fl of.::!:/. ~ 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 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 Exam Coverage Achieved: Risked-Informed Coverage: 81.6% 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. Examiner: Wade Holloway //J/L/ Level: III Date: i}r:,ko1S Examiner: Joshua Sheeran Z \\I._.) p Level: III Date: ol!/ £ i ft,/ J'i? John J. Hayden~~ ~.J1_ SI Review: Level: III Date: ~- O'f/2"/;t' J.J". CtLif>t.TO_ J. -r:-§:1.. ~ Exelon Review: Level: J.!.L Date: 4--Z..1-LR ANH Review: Jon Morris ~' ~~ .. ~ Date: L.\\l'~b-\\<l 1 " Pagej_of j~ - Page 43 of 48

~ Struct~ Unit2 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 ~ o.so* Safe End I 1 i* ~ I Safe End I lnconel SB166 Extension SA508 o.ss* 1/3T 029" Upstream (*) Flow Downsrream (+) f -1 ASME Section XI Examination Volume RI* /SI I j Procedure Extended Volume Page I.,,:? of.::?::!. - Page 44 of 48

~ Struct. 'Integrity Associates, Inc. (+) LKDN TRLO LKDN TRS 0 Unit2 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 (-) I SafeE~ 1 d I 4 \\~ ' t W'.. Extension SA508 Safe End / lnconel SB166 I Upstream {*) Flow 7 Downstream {+) ASME Section XI Examination Volume RI - ISi I I Procedure Extended Volume Page I 3 of -2.t./ - Page 45 of 48

~ StruclL , Integrity Associates, Inc. LKCWO Safe End Extension SA508 Unit2 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 Upsrream {+) N16 Safe End-to-Extension Circumferential Examination Coverage Weld ~ r----i Flow 7 I Safe End I lnconel 58166 Downsrream (*) [ -m-J ASME Soction XI Examination Volume RI - /SJ I I Procedure Extended Volume Page /"-/of ~.!./ Note: 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 46 of 48

~Exelon Summary No.: N2-ISl*012000 Examiner: Kunze, Paul R. I Examiner: NIA Other: NIA Comments: 2DEA-07A-FW002 Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NDE Reports Supplemental Report z#IG Level: II Reviewer: Level: NIA Site Review: Level: NIA ANll Review: Report No.: ISl*UT-18-002 Page: 5 of 6 Date: ? z -/ (?'" Date: 0-/1 Date:, (-,_/ ( Sketch or Photo: 0:\\0utage Data\\Nine Mile\\N2AFO 1611Sl\\Skelches\\2DEA-07 A-FW002.JP9 ..o,,,... Ci:.,,() "°' <~ 81tv r I I \\/Q Ive.. MOV/;J._8 r***** --*- ~ >ao I / .. *~ * -.-J.. / I

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Unit2 Nine Mile Point Nuclear Plant Third ISi Interval Limited Coverage NOE Reports Supplemental Report

-c.,,:::. Exelon Report No.:

ISl-UT-18-002 Summary No.: N2-ISl-012000 ~ Examiner: Kunze, Paul A. /i.F~ Examiner: N/A ~--------------~ Other:....;N/;.;o.,;..A~-------------- Comments: 2DER-07A*FW002 Level: Level: Level: II NIA N/A Sketch or Photo: O:\\Outage Data\\Nine Mile\\N2RF016\\ISl\\Sketches\\2DEA-07A-FW002 (1).jpg Area required to scan Scan Direction ON Stream Direction UP Stream Direction CCW Direction CW Direction All dimensions in sq.in. Page: 6 of 6 Aev~wer. ~~~* Site Review: = ~ lt-e - 1 ~~ I ~ ANll Review: Date: S:-Z-f& Date:-:; t;1 Date: { .08 x 1.5 = 0.48 Coverage 0.08 x 0 = 0.00 (.08 x.90) + (.3 x.08 x.5) = 0.084 0.08 x 0.5 = 0.04 0.08 x 0.5 = 0.04 Area Scanned 0.16 Area Scanned Total= 33% - Page 48 of 48}}

v t e Letter Sequence Request
EPID:L-2019-LLR-0099, End of Interval Relief Associated with the Third Ten-Year Inservice Inspection (ISI) Interval (Approved, Closed)
Initiation Request Acceptance Administration Questions Answers Results Approval Other:
MONTHYEAR2019-09-24 [Table View]

ML19267A024

Text

Subject:

Reference:

Applicable Code Edition and Addenda

SUMMARY

SUMMARY

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