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
. 10D@.ninioin Dominion Energy Kewaunee, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 September 27, 2012 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Serial No.12-608 LIC/JG/R0 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 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 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 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 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 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 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, Connections and Support Brackets associated with Instrument Penetrations (Figure 1) VT-3, Upper Support Plate (Figure 1) VT-3 Upper Core Plate Guide Tubes (including Split Pins), Support Columns & Flow Mixers (Fig. 2)
Upper Core Plate Alignment Keyways (Figure 2) VT-3 Upper Core Plate Fuel Assembly Guide Pins (Figure 2) VT-3 Upper Core Plate (Figure 2) VT-3 3600 3600 3600 Peripheral 00 900 1800 2700 3600 Peripheral 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 1 COMPONENT TAPE RELEVANT NO RELEVANT REMARKS EXAMINER COMPONENT LOCATION LOCATION jCONDITIONS CONDITIONS REMARKS INITIALS Reactor Vessel Interior Mating Surfaces with Reactor Vessel Closure Head and Reactor Vessel Upper internals (Figure 5). V,-3 Core Barrel Head and Vessel Alignment Pins (Figure 3) VT-3 Core Barrel Flange Flow Nozzles (Figure 3)
VT-3 Flange to Core Barrel Weld (Figure 4)
Located in Upper Core Barrel VT-3 (From ID)
Core Barrel Midplane Weld (Figure 4) Located above Upper Core Plate Guide Keys in Core Barrel VT-3 (From ID)
Upper Core Plate Guide Keys in Core Barrel (Figure 3) VT-3 3600 00 900 1800 2700 24 Total 3600 3600 00 900 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 (Figure 4) VT-3 Core Barrel Lower Core Plate Support Column Bolting (Figure 4) VT-3 3600 and 100%
Rows 3600 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 COMPONENT TAPE RELEVANT NO RELEVANT REMARKS EXAMINER C LOCATION LOCATION CONDITIONS CONDITIONS INITIALS Reactor Vessel Inlet, Outlet and Safety Injection Nozzle Inside Radius Sections (Core Barrel Removed) Figure 5 and ASME Section Xl 1998 Edition 2000 Addenda IWB-2500-7 (a) Surface M-N. Enhanced VT-1 Requirements (1 Mil Wire as a Calibration Standard) to satisfy ASME Boiler and Pressure Vessel Code Section XI:
Code Case N-648-1 Reactor Vessel Radial Support Keyways and Fastening Devices (Core Barrel Removed) includes for Alloy 600 Program: Core Guide Lug, Weld and Shell Cladding and for NRC Commitment - Examination for Loss of Material (wear) and cracking. Figure 5 VT-3 Reactor Vessel Instrumentation Tubes (36 Total) Core Barrel Removed Figure 4 and M-1193. VT-3 Core Barrel (Exterior) Core Barrel Lower Midplane Weld VT-1 Core Barrel (Exterior) Core Barrel Lower Bottom Weld VT-3 28.500 RV-IR7 108.460 RV-IR8 148.500 RV-iR9 208.510 RV-IR10 288.510 RV-IR11 328.500 RV-IR6 00 90o 1800 2700 3600 3600 3600 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 TAPE RELEVANT NO RELEVANT EXAMINER LOCATION LOCATION CONDITIONS CONDITIONS INITIALS Core Barrel (Exterior) Irradiation Specimen Guides-Basket Welds and Fastening Devices (Core Barrel Removed) Figure 4 VT-1 Core Barrel (Exterior) Outlet and Safety Injection Nozzle Interface Mating Surfaces (Core Barrel Removed) Figure 4 and Figure 5 VT-3 Core Barrel (Exterior) Upper Section of 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 -
Welds and Fastening Devices (Core Barrel Removed) Includes for Alloy 600 Program:
Core Radial Support Guides. Figure 4 VT-i Core Barrel (Exterior) Secondary Core Support Assembly and Instrumentation Thimble Guides (Core Barrel Removed) Figure 4 VT-3 570 67o 770 2370 2470 2570 28.500 108.460 208.510 288.510 3600 00 900 1800 2700 As Accessible 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 I EXAMINER R INITIALS Upper Support Plate Thermocouple Conduits, Connections and Support Brackets associated with Instrument Penetrations (Figure 1) VT-3 Upper Support Plate (Figure 1) VT-3 Upper Core Plate Guide Tubes(including Split pins), Support Columns and Flow Mixers (Figure 2) VT-3 Upper Core Plate Alignment Keyways (Figure 2) VT-3 3600 3600 3600 Peripheral 00 900 1800 2700 3600 Peripheral 3600 Peripheral Upper Core Plate Fuel (Figure 2) VT-3 Assembly Guide Pins Upper Core Plate (Figure 2) VT-3 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 Reactor Vessel Closure Head and Reactor Vessel Upper Internals (Figure 5) VT-3 Core Barrel Head and Vessel Alignment Pins (Figure 3) VT-3 Core Barrel Flange Flow Nozzles (Figure 3)
VT-3 Flange to Core Barrel Weld (Figure 4)
Located in Upper Core Barrel VT-1 (From ID)
Core Barrel Midplane Weld (Figure 4) Located above Upper Core Plate Guide Keys in Core Barrel VT-1 (From ID)
Core Barrel Lower Midplane Weld (Figure 4)
VT-1 (From OD) 3600 00 900 1800 2700 24 Total 3600 3600 3600 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-1 (From OD)
Upper Core Plate Guide Keys in Core Barrel (Figure 3) VT-3 Core Barrel Baffle Formers and Baffle Bolting (Figure 4) VT-3 Core Barrel Lower Core Plate Support Column Bolting (Figure 4) VT-3 3600 00 900 1800 2700 3600 and 100%
Rows 3600 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 Nozzle Inside Radius Sections (Core Barrel Removed) Figure 5 and ASME Section XI 1998 Edition 2000 Addenda IWB-2500-7 (a) Surface M-N. Enhanced VT-1 Requirements (1 Mil Wire as a Calibration Standard) to satisfy ASME Boiler and Pressure Vessel Code Section XI:
Code Case N-648-1 Reactor Vessel Radial Support Keyways and Fastening Devices (Core Barrel Removed) includes for Alloy 600 Program: Core Guide Lug, Weld and Shell Cladding and for NRC Commitment - Examination for Loss of Material (wear) and cracking. Figure 5 VT-3 Reactor Vessel Instrumentation Tubes (36 Total) Core Barrel Removed Figure 4 and M-1193. VT-3 28.500 RV-IR7 108.460 RV-IR8 148.500 RV-IR9 208.510 RV-IR10 288.510 RV-IR11 328.500 RV-IR6 00 900 1800 2700 3600 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 Guides-Basket Welds and Fastening Devices (Core Barrel Removed) Figure 4 VT-1 Core Barrel (Exterior) Outlet and Safety Injection Nozzle Interface Mating Surfaces (Core Barrel Removed) Figure 4 and Figure 5 VT-3 Core Barrel (Exterior) Upper Section of 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 -
Welds and Fastening Devices (Core Barrel Removed) Includes for Alloy 600 Program:
Core Radial Support Guides. Figure 4 VT-1 Core Barrel (Exterior) Secondary Core Support Assembly and Instrumentation Thimble Guides (Core Barrel Removed) Figure 4 VT-3 570 670 770 2370 2470 2570 28.500 108.460 208.510 288.510 3600 00 900 1800 2700 As Accessible 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 check for evidence of distortion. Reference Figures 4-24, 4-25, 4-26 and 4-27 of MRP-227.
Core Barrel Baffle Former Assembly VT-3 to check for evidence of distortion. Reference Figure 4-23 of MRP-227.
Reactor Vessel Bottom-Mounted Instrumentation (BMI) Column Bodies VT-3 Reference Figure 4-35 of MRP-227.
Reactor Vessel Bottom-Mounted Instrumentation (BMI) Column Cruciform's EVT-1 Baffle Former 3600 Baffle-Edge Bolts 688 Edge Bolts From Core Barrel Inside 36 Total 16 Total 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 COMPONENT TAPE NI NRI RIRI REMARKS INITIALR LOCATION LOCATION INITIALS Upper Internals Upper Core Plate - Mixing Devices - 34 Total - EVT-1 Upper Internals Upper Core Plate - Instrument Columns - Supports - 19 Total - EVT-1 Upper Internals Upper Core Plate - Instrument Columns - Clamps - 28 Total - EVT-1 Upper Internals Upper Core Plate - Support Columns Bases - 16 Total - EVT-1 Upper Internals Upper Core Plate - Support Columns Thermocouple Stops - 39 Total -
EVT-1 100% of Accessible Surfaces 100% of Accessible Surfaces 100% of Accessible Surfaces 100% of Accessible Surfaces 100% of Accessible 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 COMPONENT TAPE NI NRI RI REMARKS EXAMINER
_ LOCATION LOCATION I 1
INITIALS Core Barrel Assembly - Core Barrel Upper Flange - EVT-1: Fig. 4-34 MRP-227 Core Barrel Assembly - Core Barrel Outlet Nozzles - EVT-1 : Fig. 4-34 MRP-227 Core Barrel Assembly - Core Barrel Safety Injection Nozzles - EVT-1 : Fig. 4-34 MRP-227 Core Barrel Assembly -
Upper-Core Barrel Flange To Core Barrel Weld - EVT-1 Table 4-3 Page 4-26 MRP-227 Core Barrel Assembly - Core Barrel Mid Plane Weld - EVT-1 Table 4-3 Page 4-26 MRP-227 Core Barrel Assembly - Core Barrel Lower Mid Plane Weld - EVT-1 Table 4-3 Page 4-26 MRP-227 Core Barrel Assembly - Core Barrel Lower Bottom Weld - EVT-1 Table 4-3 Page 4-26 MRP-227 100%
28.5' 208.50 108.5' 288.5' 100% of one side of the accessible surfaces and the adjacent base metal.
100% of one side of the accessible surfaces and the adjacent base metal 100% of one side of the accessible surfaces and the adjacent base metal 100% of one side of the accessible 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:
COMPONENT TAPE
[RREMARKS EXAMINER COMPONENTLNI INITIALS LOCATION LOCATION;NI R
INITIALS UPPER INTERNALS Upper Support Plate Control Rod Drive Tubes (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 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 Flaws Upper Support Plate Control Rod Drive Tubes (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 Determine Presence Of Crack Like Surface Flaws Position 2F Position.2H Position 3E Position 3G Position 31 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 (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 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 Flaws Upper Support Plate Control Rod Drive Tubes (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 Determine Presence Of Crack Like Surface Flaws Position 4D Position 4J Position 5C Position 5E Position 5G Paae 10 of 19 10 of_________
19 1
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 NCOMPONENT TAPE N
NRI 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 N I INITIALS UPPER INTERNALS Upper Support Plate Control Rod Drive Tubes (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 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 Flaws Upper Support Plate Control Rod Drive Tubes (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 Determine Presence Of Crack Like Surface Flaws Position 7C Position 7E Position 7G Position 71 Position 7K 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 (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 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 Flaws Upper Support Plate Control Rod Drive Tubes (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 Determine Presence Of Crack Like Surface Flaws Position 8B Position 8F Position 8H Position 8L Position 9C 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 CATAPE NI NRI RI REMARKS EXAMINER LOCATION ]LOCATION
____________________INITIALS UPPER INTERNALS Upper Support Plate Control Rod Drive Tubes (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 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 Flaws Upper Support Plate Control Rod Drive Tubes (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 Determine Presence Of Crack Like Surface Flaws Position 9E Position 9G Position 91 Position 9K Position 10D 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 (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 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 Flaws Upper Support Plate Control Rod Drive Tubes (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 Determine Presence Of Crack Like Surface Flaws Position 1OJ Position 11 E Position 11 G Position 111 Position 12F 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 (CRGT) - Lower Flange Welds - EVT-1 To Determine Presence Of Crack Like Surface Flaws Position 12H 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 Interfacing Components Clevis Insert Bolts -
VT,-3 Core Barrel Assembly-Core Barrel Flange -
VT-3 For Loss of Material (Wear)
Upper Internals Assembly - Upper Support Ring or Skirt - VT-3 For Cracking (IASCC, Fatigue)
Core Barrel Lower Internals Assembly - Lower 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)
Upper Internals Alignment and Interfacing Components Upper Core Plate Alignment Pins
- VT-3 Examination for Loss of Material (Wear) 100%
100%
100%
100%
100%
100%
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 EVT-1 Reference Figure 4-33 of MRP-227 Upper Internals Upper Core Plate EVT-1 Core Barrel Lower Support Assembly - Lower Support Column Bodies (Non Cast) EVT-1 100%
100%
100%
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 -
Thermal Shield Flexures - V/-r"31 Reference Figures 4-29 and 4-36 of MRP-227 Core Barrel Thermal Shield Assembly -
Thermal Shield Flexures - VT-3 Reference Figures 4-29 and 4-36 of MRP-227 Core Barrel Thermal Shield Assembly -
Thermal Shield Flexures - VT-3 Reference Figures 4-29 and 4-36 of MRP-227 Core Barrel Thermal Shield Assembly -
Thermal Shield Flexures - VT-3 Reference Figures 4-29 and 4-36 of MRP-227 00 900 1800 2700 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 COMPONENT TAPE NI NRI RI REMARKS EXAMINER LOCATION LOCATION INITIALS Upper Support Plate Thermocouple Conduits, Connections and Support Brackets associated with Instrument Penetrations (Figure 1) VT-3 Upper Support Plate (Figure 1) VT-3 Upper Core Plate Guide Tubes(including Split Pins), Support Columns and Flow Mixers (Figure 2) VT-3 Upper Core Plate Alignment Keyways (Figure 2) VT-3 Upper Core Plate Fuel Assembly Guide Pins (Figure 2) VT-3 Upper Core Plate (Figure 2) VT-3 3600 3600 3600 Peripheral 00 900 1800 2700 3600 Peripheral 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 COMPONENT TAPE NI NRI RI REMARKS EXAMINER I LOCATION LOCATION INITIALS Reactor Vessel Interior Mating Surfaces with Reactor Vessel Closure Head and Reactor Vessel Upper Internals (Figure 5) VT-3 Core Barrel Head and Vessel Alignment Pins (Figure 3) VT-3 Core Barrel Flange Flow Nozzles (Figure 3)
VT-3 Flange to Core Barrel Weld (Figure 4)
Located in Upper Core Barrel VT-3 Core Barrel Midplane Weld (Figure 4) Located above Upper Core Plate Guide Keys in Core Barrel VT-3 Upper Core Plate Guide Keys in Core Barrel (Figure 3) VT-3 3600 00 900 1800 2700 24 Total 3600 3600 00 900 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
[COMPON I
TAP NTNI NRI RI L REMARKS j
INER
_________________LOCATION jLOCATION INITIALS Upper Support Plate Thermocouple Conduits, Connections and Support Brackets associated with Instrument Penetrations (Figure 1) VT-3 Upper Support Plate (Figure 1) VT-3 Upper Core Plate Guide Tubes (including Split Pins), Support Columns & Flow Mixers (Fig 2)
VT-3 Upper Core Plate Alignment Keyways (Figure 2) VT-3 Upper Core Plate Fuel Assembly Guide Pins (Figure 2) VT-3 Upper Core Plate (Figure 2) VT-3 3600 3600 3600 Peripheral 00 900 1800 2700 3600 Peripheral 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 Reactor Vessel Closure Head and Reactor Vessel Upper Internals (Figure 5) VT-3 Core Barrel Head and Vessel Alignment Pins (Figure 3) VT-3 Core Barrel Flange Flow Nozzles (Figure 3)
VT-3 Flange to Core Barrel Weld (Figure 4)
Located in Upper Core Barrel VT-3 Core Barrel Midplane Weld (Figure 4) Located above Upper Core Plate Guide Keys in Core Barrel VT-3 Upper Core Plate Guide Keys in Core Barrel (Figure 3) VT-3 3600 00 900 1800 2700 24 Total 3600 3600 00 900 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 (Figure 4) VT-3 Core Barrel Lower Core Plate Support Column Bolting (Figure 4) VT-3 3600 and 100%
Rows 3600 Paqe 3 of 3 Form 49177:- Outage Fuel Out