ML12277A164
| ML12277A164 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 09/27/2012 |
| From: | Hartz L Dominion, Dominion Energy Kewaunee |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 12-608 | |
| Download: ML12277A164 (38) | |
Text
Dominion Energy Kewaunee, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060
. 10D@.ninioin September 27, 2012 ATTN: Document Control Desk Serial No.12-608 U. S. Nuclear Regulatory Commission LIC/JG/R0 Washington, DC 20555-0001 Docket No.: 50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION REACTOR VESSEL INTERNALS INSPECTION PLAN REVIEW REQUEST RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION By application dated December 12, 2011 (Reference 1), Dominion Energy Kewaunee, Inc. (DEK) requested approval of the inspection plan for reactor vessel internal (RVI) components at Kewaunee Power Station (KPS). This inspection plan was submitted to fulfill certain requirements of Renewed Operating License DPR-43, Section 2.C(15)(b);
specifically, Commitment Items 1 and 2 of Appendix A of NUREG-1958, "Safety Evaluation Report Related to the Kewaunee Power Station," dated January 2011. The inspection plan was supplemented on June 28 (Reference 2) and August 30, 2012 (Reference 3).
Subsequently, the Nuclear Regulatory Commission (NRC) transmitted a request for additional information (RAI) regarding the inspection plan (Reference 4). The NRC questions were discussed with NRC staff to obtain clarification, during a telephone conference on August 29, 2012. The DEK response is provided in Attachment 1 to this letter.
If you have questions or require additional information, please feel free to contact Mr.
Jack Gadzala at 920-388-8604.
Very truly yours, Leslie N. Hartz Vice President - Nuclear Support Services
Attachment:
- 1. Response to Request for Additional Information, KPS RVI Inspection Plan
Serial No.12-608 Page 2 of 2
References:
- 1. Letter from J. Alan Price (DEK) to Document Control Desk (NRC), "Reactor Vessel Internals Inspection Plan Review Request," dated December 12, 2011.
- 2. Letter from J. Alan Price (DEK) to Document Control Desk (NRC), "Reactor Vessel Internals Inspection Plan Review Request, Supplement and Response to Request for Additional Information," dated June 28, 2012.
- 3. Letter from J. Alan Price (DEK) to Document Control Desk (NRC), "Reactor Vessel Internals Inspection Plan Review Request, Supplement and Response to Request for Additional Information," dated August 30, 2012.
- 4. Email from Karl [). Feintuch (NRC) to Jack Gadzala (DEK) et al, "ME7727 -
Kewaunee - Draft Request for Additional Information Re: RVI components Inspection Plan - RAII-Cher-021 to -022," dated August 21, 2012.
Commitments made by this letter: NONE cc: Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. Karl D. Feintuch Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station
Serial No.12-608 ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REACTOR VESSEL INTERNALS INSPECTION PLAN REVIEW REQUEST KPS RVI INSPECTION PLAN KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
Serial No.12-608 Attachment 1 Page 1 of 5 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION INSPECTION PLAN FOR THE AUGMENTED INSERVICE INSPECTION PROGRAM FOR EXAMINATION OF REACTOR VESSEL INTERNALS On August 21, 2012, the NRC transmitted a request for additional information (RAI)
(Reference 1) concerning the inspection plan for reactor vessel internal (RVI) components at Kewaunee Power Station (KPS). This inspection plan was submitted to fulfill certain requirements of Renewed Operating License DPR-43, Section 2.C(15)(b);
specifically, Commitment Items 1 and 2 of Appendix A of NUREG-1958, "Safety Evaluation Report Related to the Kewaunee Power Station," dated January 2011.
The RAI questions were discussed with NRC staff to obtain clarification, during a telephone conference on August 29, 2012. During this telephone conference, the staff requested additional documentation related to specific Inservice Inspection (ISI)
Program aspects to assist in their review. The requested documentation is provided as an enclosure to this attachment.
In their August 21, 2012 request, NRC staff stated the following:
"Item 5 in Action Item 8 of the NRC staffs Safety Evaluation (SE), Revision 1 (dated December 16, 2011) for the MRP-227 addresses the fatigue evaluation of the reactor vessel internals (RVI) components which is described below:
- 1. Pursuant to 10 CFR 54.21(c)(1), the applicant is required to identify all analyses in the current licensing bases (CLB) for their RVI components that conform to the definition of a time limited aging analysis (TLAA) in 10 CFR 54.3 and shall identify these analyses as TLAAs for the application in accordance with the TLAA identification requirement in 10 CFR 54.21(c)(1). MRP-227, as approved by the NRC, does not specifically address the resolution of TLAAs that may apply to applicant/licensee RVI components. Hence, applicants/licensees who implement MRP-227, as approved by the NRC, shall still evaluate the CLB for their facilities to determine if they have plant-specific TLAAs that shall be addressed. If so, the applicant's/licensee's TLAA shall be submitted for NRC review along with the applicant's/licensee's application to implement the NRC-approved version of MRP-227.
- 2. For those cumulative usage factor (CUF) analyses that are TLAAs, the applicant may use the PWR Vessel Internals Program (PWRVIP) as the basis for accepting these CUF analyses in accordance with 10 CFR 54.21(c)(1)(iii) only if the RVI components in the CUF analyses are periodically inspected for fatigue-induced cracking in the components during the period of extended operation.
The periodicity of the inspections of these components shall be justified to be adequate to resolve the TLAA. Otherwise, acceptance of these TLAAs shall be done in accordance with either 10 CFR 54.21 (c)(1)(i) or (ii), or in accordance with 10CFR54.21(c)(1)(iii) using the applicant's program that corresponds to
Serial No.12-608 Attachment 1 Page 2 of 5 NUREG-1801, Revision 2, AMP X.M1, "Metal Fatigue of Reactor Coolant Pressure Boundary Program". To satisfy the evaluation requirements of ASME Code,Section III, Subsection NG-2160 and NG-3121, the existing fatigue CUF analyses should include the effects of the reactor coolant system water environment."
The RAI questions, which are related to fatigue analysis as part of TLAA, are provided below followed by the DEK response.
NRC Question ME7727-RAII-EVIB-Cher-021-2012-08-21 Table 4.3-2 of the KPS USAR, Revision 23, states that cumulative usage factor (CUF) analyses were performed on the core support guide at KPS. The NRC staff requests that the licensee confirm the following information: (1) CUF factor (0.204) listed in Table 4.3-2 is valid for the extended period of operation, and, (2) if the existing CUF analyses for the core support guide include the effects of the reactor coolant system water environment.
Response
The CUF of 0.204 is for the low alloy steel (LAS) base material of the vessel shell.
There are no fatigue analyses (CUF analyses) applicable to the Kewaunee reactor vessel internals.
(1) The CUF of 0.204 listed in KPS USAR Table 4.3-2 is valid for the extended period of operation based on tracking plant thermal cycles as described in USAR Section 15.5.2.
(2) The core support guide location of the reactor vessel (radial key/clevis interface) was identified for a TLAA in the KPS license renewal application (August 12, 2008) and was evaluated for the effects of the reactor coolant water environment on fatigue usage. This location is identified in NUREG/CR-6260 as "Reactor Vessel Shell and Lower Head." Applying the Fen multiplier of 2.455 (for low alloy steel) to the CUF value of 0.204 produces a value of 0.5008, which is below unity and therefore acceptable.
Therefore, as described in USAR 15.4.2.1.5, the CUF for the core support guide
("Reactor Vessel Shell and Lower Head" location), considering the effects of the reactor coolant water environment, continues to meet fatigue limits considering 60 years of plant operation.
Serial No.12-608 Attachment 1 Page 3 of 5 NRC Question ME7727-RAII-EVIB-Cher-022-2012-08-21 The licensee is requested to confirm that there is no other TLAA evaluation performed on any other RVI components at Kewaunee Power Station (KPS).
Response
As documented in the KPS license renewal application (August 12, 2008), there are no TLAAs applicable to the KPS reactor vessel internals.
The core support guide (clevis) is welded to the reactor pressure vessel and not a portion of the RVI. No fatigue analysis was completed for the KPS reactor internals since the internals were constructed before ASME Section III, Subsection NG was adopted. Therefore, there are no fatigue-related TLAA evaluations performed for the RVI.
Supplemental Information During a conference call between NRC staff and DEK personnel on August 29, 2012, to discuss the above questions, the NRC staff inquired whether DEK maintains documentation that lists specific reactor vessel internals components that are inspected as part of the Inservice Inspection (ISI) Program. In response to the staffs inquiry, DEK is providing for reference four KPS ISI plan forms applicable to the RV internals inspections.
These four forms were developed for inspections as follows:
Form 49177 - 2015 All and Core Barrel Removed This form was developed for inspections which occur every 10 years when the core barrel is removed (this had been the inspection guidance until the adoption of MRP-227).
Form 49177 - 2015 All and Core Barrel Removed and MRP-227 This form was developed for inspections which occur every 10 years when the core barrel is removed, plus MRP-227 items.
Form 49177 - Outaqe Fuel In This form was developed for inspections which occur during outages when the nuclear fuel in the core is not fully offloaded (excluding outages when the core barrel is removed, which is covered by the first two listed forms). Inspections of specific items listed on this form are staggered over successive outages, such that the specific underlying items are inspected at the frequency required by the ASME Code (typically 40-month intervals).
Serial No.12-608 Attachment 1 Page 4 of 5 Form 49177 - Outage Fuel Out This form was developed for inspections which occur during outages when the nuclear fuel in the core is fully offloaded (excluding outages when the core barrel is removed, which is covered by the first two listed forms). Inspections of specific items listed on this form are staggered over successive outages, such that the specific underlying items are inspected at the frequency required by the ASME Code (typically 40-month intervals).
These four KPS ISI plan forms are enclosed with this Attachment.
REFERENCES
- 1. Email from Karl D. Feintuch (NRC) to Jack Gadzala (DEK) et al, "ME7727 -
Kewaunee - Draft Request for Additional Information Re: RVI components Inspection Plan - RAII-Cher-021 to -022," dated August 21, 2012.
- 2. Letter from J. Alan Price (DEK) to Document Control Desk (NRC), "Reactor Vessel Internals Inspection Plan Review Request, Supplement and Response to Request for Additional Information," dated June 28, 2012.
- 3. Letter from J. Alan Price (DEK) to Document Control Desk (NRC), "Reactor Vessel Internals Inspection Plan Review Request," dated December 12, 2011.
- 4. Westinghouse Electric Company (Westinghouse) letter WPS-08-28, Revision 2, "Dominion Energy Kewaunee, Kewaunee Power Station, KPS Reactor Vessel Internals Fabrication and Design Information, LTR-ARIDA-08-63, Revision 3, Summary Report for the Fabrication and Design Information for KPS Reactor Vessel Internals," dated December 22, 2008.
- 5. Materials Reliability Program: PWR Internals Material Aging Degradation Mechanism Screening and Threshold Values (MRP-175) - EPRI Report 1012081,2005.
- 6. MRP-191, Revision 0, "Materials Reliability Program: Screening, Categorization and Ranking of Reactor Internals of Westinghouse and Combustion Engineering PWR [pressurized water reactor] Designs" (proprietary).
- 7. Westinghouse Electric Company (Westinghouse) letter WPS-11-55, "Dominion Energy Kewaunee, Kewaunee Power Station, Kewaunee Surveillance Capsule A Location and Withdrawal Schedule Evaluation," dated December 15, 2011.
- 8. EPRI Report 1016596, "Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-Rev. 0)," December 2008, Electric Power Research Institute (EPRI), Palo Alto, California.
- 9. Final Safety Evaluation (SE) of EPRI Report, Materials Reliability Program Report 1016596 (MRP-227), Revision 0, "Pressurized Water Reactor (PWR)
Internals Inspection and Evaluation Guidelines," dated June 22, 2011.
Serial No.12-608 Attachment 1 Page 5 of 5
- 10. Letter from Ann Marie Stone (NRC) to David A. Heacock (Dominion), "Kewaunee Power Station - NRC Post Approval Site Inspection for License Renewal Inspection Report 05000305/2012-007," dated May 16, 2012.
Serial No.12-608 Attachment 1 Enclosure ENCLOSURE TO ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REACTOR VESSEL INTERNALS INSPECTION PLAN REVIEW REQUEST Form 49177 - 2015 All and Core Barrel Removed (5 pages)
Form 49177 - 2015 All and Core Barrel Removed and MRP-227 (19 pages)
Form 49177 - Outage Fuel In (2 pages)
Form 49177 - Outage Fuel Out (3 pages)
KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
PLANT: Kewaunee PROCEDURE:
JNIT: No.1 DATE:
NTERVAL: 4th ERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1,2, 3, 4 and 5: M-1199 EXAMINER:
COMPONENT COMPONENT TAPE RELEVANT NO RELEVANT REMARKS EXAMINER LOCATION LOCATION CONDITIONS CONDITIONS INITIALS Upper Support Plate Thermocouple Conduits, 3600 Connections and Support Brackets associated with Instrument Penetrations (Figure 1) VT-3, Upper Support Plate (Figure 1) VT-3 3600 Upper Core Plate Guide Tubes (including Split 3600 Peripheral Pins), Support Columns & Flow Mixers (Fig. 2)
Upper Core Plate Alignment Keyways 00 (Figure 2) VT-3 900 1800 2700 Upper Core Plate Fuel Assembly Guide Pins 3600 Peripheral (Figure 2) VT-3 Upper Core Plate (Figure 2) VT-3 3600 Peripheral Page 1 of 5 Form 49177 - 2015 All and Core Barrel Removed
PLANT: Kewaunee PROCEDURE:
UNIT: No. 1 DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1199 EXAMINER:
COMPONENT COMPONENT 1COMPONENT LOCATION TAPE RELEVANT LOCATION jCONDITIONS NO RELEVANT CONDITIONS REMARKS EXAMINER REMARKS INITIALS Reactor Vessel Interior Mating Surfaces with 3600 Reactor Vessel Closure Head and Reactor Vessel Upper internals (Figure 5). V,-3 Core Barrel Head and Vessel Alignment Pins 00 (Figure 3) VT-3 900 1800 2700 Core Barrel Flange Flow Nozzles (Figure 3) 24 Total VT-3 Flange to Core Barrel Weld (Figure 4) 3600 Located in Upper Core Barrel VT-3 (From ID)
Core Barrel Midplane Weld (Figure 4) Located 3600 above Upper Core Plate Guide Keys in Core Barrel VT-3 (From ID)
Upper Core Plate Guide Keys in Core Barrel 00 (Figure 3) VT-3 900 1800 2700 Paae 2 of 5 Form 49177 - 2015 All and Core Barrel Removed
PLANT: Kewaunee PROCEDURE:
UNIT: No. 1 DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1199 EXAMINER:
COMPONENT COMPONENT TAPE RELEVANT NO RELEVANT EMARKS EXAMINER LOCATION LOCATION CONDITIONS CONDITIONS R INITIALS Core Barrel Baffle Formers and Baffle Bolting 3600 and 100%
(Figure 4) VT-3 Rows Core Barrel Lower Core Plate Support Column 3600 Bolting (Figure 4) VT-3 Page 3 of 5 Form 49177 - 2015 All and Core Barrel Removed
PLANT: Kewaunee - PROCEDURE:
UNIT: No. 1 DATE:
INTERVAL: 4th PERIOD: 3rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1194: M-1199: IWB-2500-7(a) EXAMINER:
COMPONENT CCOMPONENT LOCATION TAPE LOCATION RELEVANT NO RELEVANT REMARKS EXAMINER CONDITIONS CONDITIONS INITIALS Reactor Vessel Inlet, Outlet and Safety Injection 28.500 RV-IR7 Nozzle Inside Radius Sections (Core Barrel 108.460 RV-IR8 Removed) Figure 5 and ASME Section Xl 1998 148.500 RV-iR9 Edition 2000 Addenda IWB-2500-7 (a) Surface 208.510 RV-IR10 M-N. Enhanced VT-1 Requirements (1 Mil Wire 288.510 RV-IR11 as a Calibration Standard) to satisfy ASME 328.500 RV-IR6 Boiler and Pressure Vessel Code Section XI:
Code Case N-648-1 Reactor Vessel Radial Support Keyways and 00 Fastening Devices (Core Barrel Removed) 90o includes for Alloy 600 Program: Core Guide 1800 Lug, Weld and Shell Cladding and for NRC 2700 Commitment - Examination for Loss of Material (wear) and cracking. Figure 5 VT-3 Reactor Vessel Instrumentation Tubes (36 3600 Total) Core Barrel Removed Figure 4 and M-1193. VT-3 Core Barrel (Exterior) Core Barrel Lower 3600 Midplane Weld VT-1 Core Barrel (Exterior) Core Barrel Lower 3600 Bottom Weld VT-3 Page 4 of 5 Form 49177 - 2015 All and Core Barrel Removed
PLANT: Kewaunee PROCEDURE:
UNIT: No. 1 DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1 193: M-1 199 EXAMINER:
COMPONENT LOCATION TAPE RELEVANT NO RELEVANT EXAMINER LOCATION CONDITIONS CONDITIONS INITIALS Core Barrel (Exterior) Irradiation Specimen 570 Guides-Basket Welds and Fastening Devices 67o (Core Barrel Removed) Figure 4 VT-1 770 2370 2470 2570 Core Barrel (Exterior) Outlet and Safety 28.500 Injection Nozzle Interface Mating Surfaces 108.460 (Core Barrel Removed) Figure 4 and Figure 5 208.510 VT-3 288.510 Core Barrel (Exterior) Upper Section of 3600 Thermal Shield Hang-Off Pads, Dowels, Fastening Devices, Flexures and Fasteners of the Thermal Shield (Core Barrel Removed)
Figure 4 VT-3 Core Barrel (Exterior) Radial Support Guides - 00 Welds and Fastening Devices (Core Barrel 900 Removed) Includes for Alloy 600 Program: 1800 Core Radial Support Guides. Figure 4 VT-i 2700 Core Barrel (Exterior) Secondary Core Support As Accessible Assembly and Instrumentation Thimble Guides (Core Barrel Removed) Figure 4 VT-3 Page 5 of 5 Form 49177 - 2015 All and Core Barrel Removed
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No.1 ASME Boiler and Pressure Vessel Code Section Xl Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1 199 COMPONENT COMPONENT LOCATION IREXAMINER INITIALS Upper Support Plate Thermocouple Conduits, 3600 Connections and Support Brackets associated with Instrument Penetrations (Figure 1) VT-3 Upper Support Plate (Figure 1) VT-3 3600 Upper Core Plate Guide Tubes(including Split 3600 Peripheral pins), Support Columns and Flow Mixers (Figure 2) VT-3 Upper Core Plate Alignment Keyways 00 (Figure 2) VT-3 900 1800 2700 Upper Core Plate Fuel Assembly Guide Pins 3600 Peripheral (Figure 2) VT-3 Upper Core Plate (Figure 2) VT-3 3600 Peripheral Page 1 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No.1 ASME Boiler and Pressure Vessel Code Section XI Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1199 EXAMINER:
COMPONENT TAPE RI REMAR EXAMINER COMPONENT LOCATION LOCATION N
__ INITIALS-Reactor Vessel Interior Mating Surfaces with 3600 Reactor Vessel Closure Head and Reactor Vessel Upper Internals (Figure 5) VT-3 Core Barrel Head and Vessel Alignment Pins 00 (Figure 3) VT-3 900 1800 2700 Core Barrel Flange Flow Nozzles (Figure 3) 24 Total VT-3 Flange to Core Barrel Weld (Figure 4) 3600 Located in Upper Core Barrel VT-1 (From ID)
Core Barrel Midplane Weld (Figure 4) Located 3600 above Upper Core Plate Guide Keys in Core Barrel VT-1 (From ID)
Core Barrel Lower Midplane Weld (Figure 4) 3600 VT-1 (From OD)
Page 2 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No.1 ASME Boiler and Pressure Vessel Code Section Xl Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1199 EXAMINER:
COMPONENT TAPE N FN EXAMINER
_COMPONENT LOCATION LOCATION NI NRI RI REMARKS INITIALS Core Barrel Lower Bottom Weld (Figure 4) VT- 3600 1 (From OD)
Upper Core Plate Guide Keys in Core Barrel 00 (Figure 3) VT-3 900 1800 2700 Core Barrel Baffle Formers and Baffle Bolting 3600 and 100%
(Figure 4) VT-3 Rows Core Barrel Lower Core Plate Support Column 3600 Bolting (Figure 4) VT-3 Page 3 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No.1 ASME Boiler and Pressure Vessel Code Section XI Examinations DATE:
INTERVAL: 4th PERIOD: 3rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1194: M-1199: IWB-2500-7(a) EXAMINER:
COMPONENT COMPONENT TAPE NI NRI RI REMARKS EXAMINER LOCATION LOCATION I INITIALS Reactor Vessel Inlet, Outlet and Safety Injection 28.500 RV-IR7 Nozzle Inside Radius Sections (Core Barrel 108.460 RV-IR8 Removed) Figure 5 and ASME Section XI 1998 148.500 RV-IR9 Edition 2000 Addenda IWB-2500-7 (a) Surface 208.510 RV-IR10 M-N. Enhanced VT-1 Requirements (1 Mil Wire 288.510 RV-IR11 as a Calibration Standard) to satisfy ASME 328.500 RV-IR6 Boiler and Pressure Vessel Code Section XI:
Code Case N-648-1 Reactor Vessel Radial Support Keyways and 00 Fastening Devices (Core Barrel Removed) 900 includes for Alloy 600 Program: Core Guide 1800 Lug, Weld and Shell Cladding and for NRC 2700 Commitment - Examination for Loss of Material (wear) and cracking. Figure 5 VT-3 Reactor Vessel Instrumentation Tubes (36 3600 Total) Core Barrel Removed Figure 4 and M-1193. VT-3 Page 4 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No.1 ASME Boiler and Pressure Vessel Code Section XI Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENT COMPONENT TAPE NI NRI RI REMARKS EXAMINER I LOCATION I LOCATION INITIALS Core Barrel (Exterior) Irradiation Specimen 570 Guides-Basket Welds and Fastening Devices 670 (Core Barrel Removed) Figure 4 VT-1 770 2370 2470 2570 Core Barrel (Exterior) Outlet and Safety 28.500 Injection Nozzle Interface Mating Surfaces 108.460 (Core Barrel Removed) Figure 4 and Figure 5 208.510 VT-3 288.510 Core Barrel (Exterior) Upper Section of 3600 Thermal Shield Hang-Off Pads, Dowels, Fastening Devices, Flexures and Fasteners of the Thermal Shield (Core Barrel Removed)
Figure 4 VT-3 Core Barrel (Exterior) Radial Support Guides - 00 Welds and Fastening Devices (Core Barrel 900 Removed) Includes for Alloy 600 Program: 1800 Core Radial Support Guides. Figure 4 VT-1 2700 Core Barrel (Exterior) Secondary Core Support As Accessible Assembly and Instrumentation Thimble Guides (Core Barrel Removed) Figure 4 VT-3 Page 5 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No.1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENT ICOMPONENT TAPE NI NRI RI REMARKS EXAMINER
_ LOCATION LOCATION I _ INITIALS Core Barrel Baffle Former Assembly VT-3 to Baffle Former check for evidence of distortion. Reference 3600 Figures 4-24, 4-25, 4-26 and 4-27 of MRP-227.
Core Barrel Baffle Former Assembly VT-3 to Baffle- Edge Bolts check for evidence of distortion. Reference 688 Edge Bolts Figure 4-23 of MRP-227. From Core Barrel Inside Reactor Vessel Bottom-Mounted 36 Total Instrumentation (BMI) Column Bodies VT-3 Reference Figure 4-35 of MRP-227.
Reactor Vessel Bottom-Mounted 16 Total Instrumentation (BMI) Column Cruciform's EVT-1 Page 6 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No. 1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENT TAPE NI NRI RIRI REMARKS INITIALR COMPONENT
_ LOCATION LOCATION INITIALS Upper Internals Upper Core Plate - Mixing 100% of Devices - 34 Total - EVT-1 Accessible Surfaces Upper Internals Upper Core Plate - Instrument 100% of Columns - Supports - 19 Total - EVT-1 Accessible Surfaces Upper Internals Upper Core Plate - Instrument 100% of Columns - Clamps - 28 Total - EVT-1 Accessible Surfaces Upper Internals Upper Core Plate - Support 100% of Columns Bases - 16 Total - EVT-1 Accessible Surfaces Upper Internals Upper Core Plate - Support 100% of Columns Thermocouple Stops - 39 Total - Accessible EVT-1 Surfaces Page 7 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No. 1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENT TAPE NI NRI RI REMARKS EXAMINER COMPONENT
_ LOCATION LOCATION I 1 INITIALS Core Barrel Assembly - Core Barrel Upper 100%
Flange - EVT-1: Fig. 4-34 MRP-227 Core Barrel Assembly - Core Barrel Outlet 28.5' Nozzles - EVT-1 : Fig. 4-34 MRP-227 208.50 Core Barrel Assembly - Core Barrel Safety 108.5' Injection Nozzles - EVT-1 : Fig. 4-34 MRP-227 288.5' Core Barrel Assembly - Upper-Core Barrel 100% of one side of the accessible Flange To Core Barrel Weld - EVT-1 surfaces and the Table 4-3 Page 4-26 MRP-227 adjacent base metal.
Core Barrel Assembly - Core Barrel Mid Plane 100% of one side of Weld - EVT-1 Table 4-3 Page 4-26 MRP-227 the accessible surfaces and the adjacent base metal Core Barrel Assembly - Core Barrel Lower Mid 100% of one side of Plane Weld - EVT-1 Table 4-3 Page 4-26 MRP- the accessible 227 surfaces and the adjacent base metal Core Barrel Assembly - Core Barrel Lower 100% of one side of Bottom Weld - EVT-1 Table 4-3 Page 4-26 the accessible MRP-227 surfaces and the adjacent base metal Page 8 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No. 1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENTLNI COMPONENT LOCATION TAPE [RREMARKS R LOCATION;NI EXAMINER INITIALS INITIALS UPPER INTERNALS Upper Support Plate Control Rod Drive Tubes Position 2F (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position.2H (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 3E (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 3G (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 31 (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws PaQe 9 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No.1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1; 2, 3, 4 and 5: M-1 193: M-1 199 EXAMINER:
COMPONENT COMPONENT TAPE NI NRI RI REMARKS EXAMINER
_ LOCATION LOCATION _ I INITIALS UPPER INTERNALS Upper Support Plate Control Rod Drive Tubes Position 4D (C-RGT- - Lower Flange Welds - EVT,-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes (CRGT) - Lower Flange Welds - EVT-1 To Position 4J Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 5C (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 5E (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 5G (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Paae 10 of 19
____________________________________________ 1 10 of_________
19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No. 1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENT TAPE NRI NNCOMPONENT RI REMARKS EXAMINER I LOCATION LOCATION N INITIALS UPPER INTERNALS Upper Support Plate Control Rod Drive Tubes Position 51
...RGT) - Lower Flange Welds - E rr-, To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 5K (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 6B (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 6F (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes (CRGT) - Lower Flange Welds - EVT-1 To Position 6H.
Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Position 6L Flaws Page 11 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No.1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENT TAPE I REMARKS EXAMINER COMPONENT LOCATION LOCATION NI _ _ _ INITIALS UPPER INTERNALS Upper Support Plate Control Rod Drive Tubes Position 7C (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes (CRGT) - Lower Flange Welds - EVT-1 To Position 7E Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes (CRGT) - Lower Flange Welds - EVT-1 To Position 7G Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes (CRGT) - Lower Flange Welds - EVT-1 To Position 71 Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes (CRGT) - Lower Flange Welds - EVT-1 To Position 7K Determine Presence Of Crack Like Surface Flaws Paae 12 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No.1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENT I MPONENT TAPE NI NRI RI REMARKS EXAMINER I LOCATION LOCATION I INITIALS UPPER INTERNALS Upper Support Plate Control Rod Drive Tubes Position 8B (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 8F (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 8H (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 8L (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 9C (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Paqe 13 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No. 1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1 193: M-1 199 EXAMINER:
COMPONENT TAPE EXAMINER COMPONENT
_________________ [ OCOMPONENT LOCATION ]LOCATION CATAPE NI NRI
____________________INITIALS RI REMARKS EXAMINER UPPER INTERNALS Upper Support Plate Control Rod Drive Tubes Position 9E (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 9G (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 91 (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 9K (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 10D (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Paae 14 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No. 1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENT COMPONENT TAPE NI NRI RI REMARKS EXAMINER
_ LOCATION LOCATION I [I INITIALS UPPER INTERNALS Upper Support Plate Control Rod Drive Tubes Position 1OJ (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 11 E (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 11 G (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 111 (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Upper Support Plate Control Rod Drive Tubes Position 12F (CRGT) - Lower Flange Welds - EVT,-1 To Determine Presence Of Crack Like Surface Flaws Paae 15 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No.1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENT COMPONENT TAPE NI NRI RI REMARKS EXAMINER LOCATION LOCATION I I_ I INITIALS UPPER INTERNALS Upper Support Plate Control Rod Drive Tubes Position 12H (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Page 16 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No.1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENT COMPONENT TAPE NI NRI RI REMARKS EXAMINER COMPONENT LOCATION LOCATION NI RI
___ _REMARKS _ INITIALS Reactor Vessel Interior Surface Alignment and 100%
Interfacing Components Clevis Insert Bolts -
VT,-3 Core Barrel Assembly-Core Barrel Flange - 100%
VT-3 For Loss of Material (Wear)
Upper Internals Assembly - Upper Support 100%
Ring or Skirt - VT-3 For Cracking (IASCC, Fatigue)
Core Barrel Lower Internals Assembly - Lower 100%
Core Plate-VT-3 for Evidence of Distortion and/or Loss of Bolt Integrity. Cracking (IASCC, Fatigue)
Core Barrel Lower Internals Assembly - Lower Core Plate-VT-3 for Loss of Material (Wear) 100%
Upper Internals Alignment and Interfacing 100%
Components Upper Core Plate Alignment Pins
- VT-3 Examination for Loss of Material (Wear)
Page 17 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No.1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENT TAPE EXAMINER COMCOMPONEN C NI NRI RI REMARKS LOCATION LOCATION _ INITIALS Core Barrel Lower Support Forging 100%
EVT-1 Reference Figure 4-33 of MRP-227 Upper Internals Upper Core Plate EVT-1 100%
Core Barrel Lower Support Assembly - Lower 100%
Support Column Bodies (Non Cast) EVT-1 Page 18 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: WDI-ISI-088 UNIT: No. 1 MRP-227 Examinations DATE:
INTERVAL: 4th PERIOD: 3 rd OUTAGE: 4th EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1193: M-1199 EXAMINER:
COMPONENT COMPONENT TAPE NI NRI RI REMARKS EXAMINER I LOCATION LOCATION j [ INITIALS Core Barrel Thermal Shield Assembly - 00 Thermal Shield Flexures - V/-r"31 Reference Figures 4-29 and 4-36 of MRP-227 Core Barrel Thermal Shield Assembly - 900 Thermal Shield Flexures - VT-3 Reference Figures 4-29 and 4-36 of MRP-227 Core Barrel Thermal Shield Assembly - 1800 Thermal Shield Flexures - VT-3 Reference Figures 4-29 and 4-36 of MRP-227 Core Barrel Thermal Shield Assembly - 2700 Thermal Shield Flexures - VT-3 Reference Figures 4-29 and 4-36 of MRP-227 Page 19 of 19 Form 49177 - 2015 All and Core Barrel Removed and MRP-227
PLANT: Kewaunee PROCEDURE: ER-AA-NDE-VT-608 Rev. 0 UNIT: No.1 DATE:
INTERVAL: 4th PERIOD: 2nd UTAGE: 2nd EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1199 EXAMINER:
COMPONENT TAPE NI NRI RI REMARKS EXAMINER COMPONENT LOCATION LOCATION INITIALS Upper Support Plate Thermocouple Conduits, 3600 Connections and Support Brackets associated with Instrument Penetrations (Figure 1) VT-3 Upper Support Plate (Figure 1) VT-3 3600 Upper Core Plate Guide Tubes(including Split 3600 Peripheral Pins), Support Columns and Flow Mixers (Figure 2) VT-3 Upper Core Plate Alignment Keyways 00 (Figure 2) VT-3 900 1800 2700 Upper Core Plate Fuel Assembly Guide Pins 3600 Peripheral (Figure 2) VT-3 Upper Core Plate (Figure 2) VT-3 3600 Peripheral Page 1 of 2 Form 49177 - Outage Fuel In
PLANT: Kewaunee PROCEDURE: ER-AA-NDE-VT-608 Rev. 0 UNIT: No. 1 DATE:
INTERVAL: 4th PERIOD: 2nd OUTAGE: 2nd EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1199 EXAMINER:
COMPONENT TAPE NI NRI RI REMARKS EXAMINER COMPONENT I LOCATION LOCATION INITIALS Reactor Vessel Interior Mating Surfaces with 3600 Reactor Vessel Closure Head and Reactor Vessel Upper Internals (Figure 5) VT-3 Core Barrel Head and Vessel Alignment Pins 00 (Figure 3) VT-3 900 1800 2700 Core Barrel Flange Flow Nozzles (Figure 3) 24 Total VT-3 Flange to Core Barrel Weld (Figure 4) 3600 Located in Upper Core Barrel VT-3 Core Barrel Midplane Weld (Figure 4) Located 3600 above Upper Core Plate Guide Keys in Core Barrel VT-3 Upper Core Plate Guide Keys in Core Barrel 00 (Figure 3) VT-3 900 1800 2700 Paae 2 of 2 Form 49177 - Outage Fuel In
PLANT: Kewaunee PROCEDURE: ER-AA-NDE-VT-608 Rev. 0 UNIT: No. 1 DATE:
INTERVAL: 4th PERIOD: 2nd OUTAGE: 2nd EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1199 EXAMINER:
COMPONENT TAPE EXAMINER COMPONENT
_________________LOCATION [COMPON I TAP NTNI jLOCATION NRI
____________________ RI L REMARKS j INITIALS INER Upper Support Plate Thermocouple Conduits, 3600 Connections and Support Brackets associated with Instrument Penetrations (Figure 1) VT-3 Upper Support Plate (Figure 1) VT-3 3600 Upper Core Plate Guide Tubes (including Split 3600 Peripheral Pins), Support Columns & Flow Mixers (Fig 2)
VT-3 Upper Core Plate Alignment Keyways 00 (Figure 2) VT-3 900 1800 2700 Upper Core Plate Fuel Assembly Guide Pins 3600 Peripheral (Figure 2) VT-3 Upper Core Plate (Figure 2) VT-3 3600 Peripheral Paqe 1 of 3 Form 49177 - Outage Fuel Out
PLANT: Kewaunee PROCEDURE: ER-AA-NDE-VT-608 Rev. 0 UNIT: No. 1 DATE:
INTERVAL: 4th PERIOD: 2nd OUTAGE: 2nd EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1199 EXAMINER:
COMPONENT COMPONENT TAPE NI NRI RI I REMARKS EXAMINER
_ LOCATION LOCATION t INITIALS Reactor Vessel Interior Mating Surfaces with 3600 Reactor Vessel Closure Head and Reactor Vessel Upper Internals (Figure 5) VT-3 Core Barrel Head and Vessel Alignment Pins 00 (Figure 3) VT-3 900 1800 2700 Core Barrel Flange Flow Nozzles (Figure 3) 24 Total VT-3 Flange to Core Barrel Weld (Figure 4) 3600 Located in Upper Core Barrel VT-3 Core Barrel Midplane Weld (Figure 4) Located 3600 above Upper Core Plate Guide Keys in Core Barrel VT-3 Upper Core Plate Guide Keys in Core Barrel 00 (Figure 3) VT-3 900 1800 2700 Page 2 of 3 Form 49177 - Outage Fuel Out
PLANT: Kewaunee PROCEDURE: ER-AA-NDE-VT-608 Rev. 0 UNIT: No. 1 DATE:
INTERVAL: 4th PERIOD: 2nd OUTAGE: 2nd EXAMINER:
REFERENCE DWGS: Figure 1, 2, 3, 4 and 5: M-1199 EXAMINER:
COMPONENT COMPONENT TAPE 1I NRI RI REMARKS EXAMINER I LOCATION LOCATION INITIALS Core Barrel Baffle Formers and Baffle Bolting 3600 and 100%
(Figure 4) VT-3 Rows Core Barrel Lower Core Plate Support Column 3600 Bolting (Figure 4) VT-3 Paqe 3 of 3 Form 49177:- Outage Fuel Out