NRC-20-0030, Submittal of Relief Request RR-A42 for Inservice Inspection Impracticality During the Third Ten-Year Inservi?E Inspection Interval
| ML20121A132 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/30/2020 |
| From: | Peter Dietrich DTE Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC-20-0030, RR-A42 | |
| Download: ML20121A132 (46) | |
Text
April 30, 2020 NRC-20-0030 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Fermi 2 Power Plant NRC Docket No. 50-341 NRC License No. NPF-43 Peter Dietrich Senior Vice President and Chief Nuclear Officer DTE Energy Company 6400 N. Dixie Highway, Newport, Ml 48166 Tel: 734.586.4153 Fax: 734.586.1431 Email: peter.dietrich@dteenergy.com DTE IO CFR 50.55a
Subject:
Submittal of Relief Request RR-A42 for Inservice Inspection Impracticality During the Third Ten-Year Inservi?e Inspection Interval Pursuant to 10 CFR 50.55a(g)(5)(iii), the basis for the determination of impracticality is being submitted to the NRC no later than 12 months after the expiration of the 120-month Inservice Inspection (ISI) Interval. The Third Ten-Year ISI interval ended on May 1, 2019, and complied with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC),Section XI, 2001 Edition through the 2003 Addenda.
The enclosed relief request RR-A42 identifies weld locations for which less than the required examination coverage was obtained due to interference or geometry. The information provided in the enclosure demonstrates the impracticality when attempting to comply with the Code required examination coverage.
No new commitments are being made in this submittal.
DTE requests approval within one year of the date of this submittal.
Should you have any questions or require additional information, please contact Ms. Margaret (Peg) M. Offerle, Manager - Nuclear Licensing, at (734) 586-5076.
Peter Dietrich Senior Vice President and Chief Nuclear Officer
USNRC NRC-20-0030 Page 2
Enclosure:
Fermi 2 Relief Request RR-A42 for Inservice Inspection Impracticality During the Third Ten-Year Inservice Inspection Interval cc: NRC Project Manager NRC Resident Office Regional Administrator, Region III
Enclosure to NRC-20-0030 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 Fermi 2 Relief Request RR-A42 for Inservice Inspection Impracticality During the Third Ten-Year Inservice Inspection Interval
Enclosure to NRC-20-0030 Page 1 Relief Request RR-A42 Impractical ISI Code Requirements for Third Ten-Year Interval In Accordance with 10 CFR 50.55a(g)(5)(iii)
Code Class 1
References:
ASME Section XI, Tables IWB-2500-1 and IWC-2500-1 Examination Category:
B-A, B-D, B-G-1, C-B, R-A Item Numbers:
B1.21, B1.22, B1.40, B3.90, B6.40, C2.21, RA-1.16
==
Description:==
Essentially full volumetric examination coverage of some Code items is impractical with the current exam technology based on configuration of the Fermi 2 Reactor Pressure Vessel (RPV) and piping.
Components:
See Limited Exam Tables - Table 1 - RPV Welds, Table 2 -
Nozzle Welds, and Table 3 - Piping Welds
2. Applicable Code Edition and Addenda
The Code of Record for the Third Ten-Year Inservice Inspection (ISI) Interval at Fermi 2 Nuclear Power Plant, Unit 2 was the 2001 Edition through the 2003 Addenda of the ASME Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, as modified by 10 CFR 50.55a. The Appendix VIII requirements and use of the Performance Demonstration Initiative (PDI) requirements for Fermi 2 are in accordance with the 2001 Edition of Section XI through the 2003 Addenda as conditioned by 10 CFR 50.55a(b)(2)(xv) and 10 CFR 50.55a(b)(2)(xxiv).
3. Applicable Code Requirements
ASME Section XI Inspection Category Tables IWB-2500-1 and IWC-2500-1 specify essentially 100% of the weld length for the full volume specified in the applicable coverage figure. NRC approved ASME Code Case N-460 allows reduction of the Code specified volume when due to component configuration or geometry to not less than 90% of the specified volume. This code case was incorporated into ASME Section XI and is currently in IWA-2200(c) of the 2013 Code Edition in use at Fermi 2 for the Fourth Ten-Year Interval which began on May 2, 2019. All exams were performed with PDI qualified procedures, equipment and personnel.
4. Reason for Request
In accordance with 10 CFR 50.55a(g)(5)(iii), if the licensee has determined that conformance with Code requirement is impractical for its facility the licensee must notify the NRC and
Enclosure to NRC-20-0030 Page 2 submit, as specified in 10 CFR 50.4, information to support the determinations.
Determinations of impracticality in accordance with this section must be based on the demonstrated limitations experienced when attempting to comply with the Code requirements during the inservice inspection interval for which the request is being submitted.
Pursuant to 10 CFR 50.55a(g)(5)(iii), DTE Electric (DTE) is requesting relief from ASME Section XI requirements to examine essentially 100% of specified weld length / volume, because within the limits of RPV design and configuration it was impractical to do so with currently available inspection technology. This relief request is based on actual demonstrated limitations based on geometric configuration of components and welds when attempting to comply with the Code requirements in the performance of the examinations.
Coverage plots provide a conservative estimate of the required volume covered based on a simple average of the combined number of scans required when complete coverage is not possible.
- 5. Proposed Alternative and Basis for Relief The proposed alternative is that exams as performed for the Third Ten-Year ISI Interval provide an acceptable level of safety and no further attempts to meet the ASME Section XI coverage requirements for the listed welds is necessary due to impracticality. Further basis is provided as follows:
- 1) DTE performed required ultrasonic and surface examinations to the maximum extent possible based on weld, component, or item configuration.
- 2) The ASME Section XI Inservice Inspection Program is a sample-based program designed to detect the onset of degradation for components and welds subject to operating environment and stresses. For the RPV welds including nozzles, the missed area is relatively small when compared to the overall population of welds. There is no type of weld, material or degradation mechanism that is not represented in the population examined for the operating conditions (1030-1055 psi at approximately 575°F). For the RPV materials of construction (low alloy carbon steel) and service environment, there is no known degradation mechanism that applies to the missed areas that is different or would increase overall risk due to the missed coverage.
- 3) The RPV shell-to-flange weld and head-to-flange welds were excluded by ASME Section XI, Appendix VIII. However, DTE examined these welds using procedures, personnel, and equipment that have been demonstrated and qualified in accordance with ASME Section XI, 2001 Edition, 2003 Addenda, Appendix VIII, Supplements 4 and 6 as amended by 10 CFR 50.55a and the PDI Program. Since the examinations were performed from a single side due to the weld configuration, all procedures and personnel were qualified for single sided access for examination of these welds.
Appendix VIII requirements were developed and adopted to ensure the effectiveness of ultrasonic examinations within the nuclear industry by means of a rigorous, item specific performance demonstration containing flaws of various sizes, locations, and orientations.
The PDI process has established, with a high degree of confidence, the capability of
Enclosure to NRC-20-0030 Page 3 personnel, procedures, and equipment to detect and characterize flaws that could be detrimental to the structural integrity of the RPV. The PDI approach has demonstrated that, for detection and characterization of flaws in the RPV, the ultrasonic examination techniques are equal to, or surpass the requirements of the ASME Section V, Article 4 ultrasonic examination requirements. Though Appendix VIII is not specified for the RPV flange weld ultrasonic testing (UT) examinations, the use of Appendix VIII, Supplements 4 and 6 criteria for detection and sizing of flaws in these welds is equal to, or exceeds the requirements of ASME Section V, Article 4.
- 4) For austenitic stainless-steel piping welds subject to intergranular stress corrosion cracking (IGSCC), whenever the component is limited to one single side scanning due to configuration, the weld volume cannot be credited to be greater than 50% coverage based on the limitations of ASME Section XI, Appendix VIII ultrasonic procedure demonstrations. All ASME Class 1 welds at Fermi 2 subject to IGSCC were mitigated with some type of stress improvement (i.e., solution annealing, induction heat stress improvement, or mechanical stress improvement) prior to 2 years of service.
Consequently, all Fermi 2 welds in the reactor coolant pressure boundary are Category A (resistant to cracking) or B (not resistant but treated for stress mitigation). Additionally, DTE has implemented an effective hydrogen water chemistry and noble metal chemical addition program. DTE did not credit this for the 3rd interval and the Category B welds were inspected at a 25% selection rate (27 of 106 welds) in accordance with BWRVIP-75A. Therefore, the percentage of welds that were inspected is more than twice the specified 10% target population specified in the risk-based ISI inspection program. Since this selection rate is equivalent to the ASME Section XI Category B-J rate and the population is targeted to welds with potential degradation (IGSCC), the reduction in coverage from configuration limited exams does not impact the ability of the program to detect degradation and does not increase core damage probability. Due to the actions taken to address IGSCC mitigation during construction, there have been no cracks detected to date.
- 5) Periodic system pressure tests and visual examinations are performed in accordance with ASME Section XI, Examination Category B-P, for Class 1 pressure retaining welds and items each refueling outage.
DTE believes that no significant increase in coverage was possible with the available equipment and procedures based on component configuration. Therefore, it has been determined that further attempts to meet the ASME Section XI coverage requirements for the listed welds was impractical until the next scheduled performance of the exam when newer techniques may become available. Furthermore, the exams as performed for the Third Ten-Year ISI Interval provide an acceptable level of safety.
6. Duration of Proposed Alternative
This relief is requested for the Third Ten-Year ISI Interval, which began on May 2, 2009 and ended on May 1, 2019.
Enclosure to NRC-20-0030 Page 4 In accordance with 10 CFR 50.55a(g)(5)(iii), this relief is being requested no later than 12 months after the expiration of the 120-month inspection interval for which relief is sought.
- 7. Precedent Industry requests for relief due to impracticality associated with limited examinations due to configuration limitations are common and are filed by licensees following the end of an interval after exams have been attempted. Examples of recent NRC relief request authorizations that are in accordance with the regulation are:
- 1. NRC Letter to Entergy Nuclear Operations, Inc., Palisades Nuclear Plant - Relief Request No. RR 4-25 Limited Coverage Examinations during the Fourth 10-Year lnservice Inspection Interval, (CAC No. MF8886), dated August 14, 2017 (ADAMS Accession Number ML17194A807).
- 2. NRC Letter to Nebraska Public Power District, Cooper Nuclear Station - Request No.
RI-21, Revision 1 - Request for Relief Concerning Examinations for the Fourth 10-Year Inservice Inspection Interval (CAC No. MF9623; EPID L-2017-LLR-0026), dated March 22, 2018 (ADAMS Accession Number ML18064A102).
- 3. NRC Letter to Duke Energy Carolinas, LLC, Oconee Nuclear Station, Units 1, 2, and 3
- Relief from the Requirements of the ASME Code (Relief Request Nos. 15-ON-002 and 15-ON-003, Fourth 10-Year lnservice Inspection Interval) (CAC Nos. MF6506, MF6507, and MF6511), dated July 22, 2016 (ADAMS Accession Number ML16197A011).
- 4. NRC Letter to Exelon Generation Company, LLC, Dresden Nuclear Power Station, Units 2 and 3 - Request I4R-17 Relief from the Requirements of the ASME Code (CAC Nos. MF3352 AND MF3353), dated October 30, 2015 (ADAMS Accession Number ML15265A164).
- 8. References
- 1) American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section XI, Codes Case N-578, Risk-Informed Requirements for Class 1, 2, and 3 Piping, Method B,Section XI, Division 1.
- 2) American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section XI, Codes Case N-716, Alternative Piping Classification and Examination Requirements,Section XI, Division 1.
- 3) NRC Presentation, Coverage Relief Requests NDEIC-January 13-15, 2015, dated January 13, 2015 (ADAMS Accession Number ML15013A266).
- 4) BWRVIP-75-A: BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules, dated October 2005. EPRI Report 1012621.
to NRC-20-0030 Page 5 Table 1 - Reactor Pressure Vessel Welds and Components Component
/ Weld ID Cat. /
Item Description Material Percent Coverage Geometric or Configuration Limitation And Exam Result 1-319A B-A B1.21 RPV Head Meridional Weld SA-533 Grade B 78.8%
volumetric Top Head Lifting Lug welded over meridional weld. No recordable indications. (See Attachment 1) 1-319C B-A B1.21 RPV Head Meridional Weld SA-533 Grade B 78.8%
volumetric Top Head Lifting Lug welded over meridional weld. No recordable indications. (See Attachment 1) 1-319E B-A B1.21 RPV Head Meridional Weld SA-533 Grade B 78.8%
volumetric Top Head Lifting Lug welded over meridional weld. No recordable indications. (See Attachment 1) 1-319G B-A B1.21 RPV Head Meridional Weld SA-533 Grade B 78.8%
volumetric Top Head Lifting Lug welded over meridional weld. No recordable indications. (See Attachment 1) 2-306A B-A B1.21 RPV Head Meridional Weld SA-533 Grade B 0%
volumetric Inaccessible Bottom Head Welds - Control Rod Drive (CRD)
Penetrations and Skirt Attachment Welds encompass the weld area.
(See Attachment 2) 2-306B B-A B1.21 RPV Head Meridional Weld SA-533 Grade B 0%
volumetric Inaccessible Bottom Head Welds - CRD Penetrations and Skirt Attachment Welds encompass the weld area. (See Attachment 2) 2-306C B-A B1.21 RPV Head Meridional Weld SA-533 Grade B 0%
volumetric Inaccessible Bottom Head Welds - CRD Penetrations and Skirt Attachment Welds encompass the weld area. (See Attachment 2) 2-306D B-A B1.21 RPV Head Meridional Weld SA-533 Grade B 0%
volumetric Inaccessible Bottom Head Welds - CRD Penetrations and Skirt Attachment Welds encompass the weld area. (See Attachment 2) 2-306E B-A B1.22 RPV Head Meridional Weld SA-533 Grade B 0%
volumetric Inaccessible Bottom Head Welds - CRD Penetrations and Skirt Attachment Welds encompass the weld area. (See Attachment 2) 2-306F B-A B1.22 RPV Head Meridional Weld SA-533 Grade B 0%
volumetric Inaccessible Bottom Head Welds - CRD Penetrations and Skirt Attachment Welds encompass the weld area. (See Attachment 2) 2-306G B-A B1.22 RPV Head Meridional Weld SA-533 Grade B 0%
volumetric Inaccessible Bottom Head Welds - CRD Penetrations and Skirt Attachment Welds encompass the weld area. (See Attachment 2) 5-306 B-A B1.21 RPV Head Circumferential Weld SA-533 Grade B 0%
volumetric Bottom head CRD (control rod drive) penetrations and skirt attachment weld. (See Attachment 2) 2-308B B-A B1.12 RPV Longitudinal Shell Weld SA-533 Grade B 74%
volumetric Vessel Insulation Package clearance for outer diameter (OD) scanning and Guide Rod for inner diameter (ID) scanning. No recordable indications. (See Attachment 3) to NRC-20-0030 Page 6 Component
/ Weld ID Cat. /
Item Description Material Percent Coverage Geometric or Configuration Limitation And Exam Result 3-319 B-A B1.40 RPV Head to flange SA-533 Grade B to SA-508 Class 2 100%
surface 74%
volumetric RPV Flange configuration and proximity to the weld. No recordable indications. (See Attachment 4) 6-306 B-A B1.21 RPV Head Circumferential Weld SA-533 Grade B 68.9%
volumetric RPV Skirt attachment proximity to the Bottom Head circumferential weld. No recordable indications. (See Attachment 5)
Threads in RPV Flange B-G-1 B6.40 Stud Holes 1-68 SA-508 Class 2 with 309 Clad 87.55%
volumetric Raised cladding on scanning surface limits ultrasonic examination coverage. No recordable indications. (See Attachment 6) to NRC-20-0030 Page 7 Table 2 - Nozzle Welds Component /
Weld ID Cat./
Item Description Material Percent Coverage Geometric or Configuration Limitation And Exam Result 2-318 B-D B3.90 RPV Head Vent Nozzle SA-508 Class 2 to SA-533 Gr. B 81%
volumetric Configuration of the nozzle. No recordable indications. (See Attachment 7) 4-316A B-D B3.90 Feedwater (FW) Nozzle-to-Vessel Weld SA-508 Class 2 to SA-533 Gr. B 68.06%
volumetric Configuration of the nozzle and proximity of the instrument nozzle pad. No recordable indications.
(See Attachment 8) 4-316B B-D B3.90 FW Nozzle-to-Vessel Weld SA-508 Class 2 to SA-533 Gr. B 76.68%
volumetric Configuration of the nozzle. No recordable indications. (See Attachment 9) 4-316E B-D B3.90 FW Nozzle-to-Vessel Weld SA-508 Class 2 to SA-533 Gr. B 76.68%
volumetric Configuration of the nozzle. No recordable indications. (See Attachment 9) 4-316F B-D B3.90 FW Nozzle-to-Vessel Weld SA-508 Class 2 to SA-533 Gr. B 76.68%
volumetric Configuration of the nozzle. No recordable indications. (See Attachment 9) 5-314B B-D B3.90 Reactor Recirculation System (RRS) Nozzle-to-Vessel Weld SA-508 Class 2 to SA-533 Gr. B 84.3%
volumetric Configuration of the nozzle. No recordable indications. (See Attachment 10) 13-314A B-D B3.90 RRS Nozzle-to-Vessel Weld SA-508 Class 2 to SA-533 Gr. B 87.76%
volumetric Configuration of the nozzle. No recordable indications. (See Attachment 11) 13-314B B-D B3.90 RRS Nozzle-to-Vessel Weld SA-508 Class 2 to SA-533 Gr. B 87.76%
volumetric Configuration of the nozzle. No recordable indications. (See Attachment 11)
SW-E11-D2-HX-01 CB C2.21 Residual Heat Removal (RHR)
Heat Exchanger Nozzle-to-Shell (or Head Weld)
SA-105 to SA-516 Gr. 70 100%
surface 73.86%
volumetric Nozzle to shell weld face angle limits direct scanning of the inner 1/3 code volume. No recordable indications. (See Attachment 12) to NRC-20-0030 Page 8 Table 3 - Piping Welds Component /
Weld ID Cat./
Item Description Material Percent Coverage Geometric or Configuration Limitation And Exam Result FW-E11-2327-6W0 R-A R1.16 RHR Return Pipe to Tee Weld SA403WP 304 to SA358 G304 308 weld 50%
volumetric No credit for scanning tee side. No recordable indications. (See Attachment 13)
FW-G33-3096-12WF3 R-A R1.16 Sweepolet to Tee SA182F304 to SA403WP304 308 weld 50%
volumetric No credit for scanning tee side. No recordable indications. (See Attachment 13)
FW-RD-2-A11 R-A R1.16 Sweepolet to Pipe SA182F304 to SA358 G304 308 weld 50%
volumetric No credit for scanning sweepolet side. No recordable indications. (See Attachment 13)
SW-RD-2-A3-W7 R-A R1.16 Cross to Pipe SA403WP304 to SA358 G304 308 weld 50%
volumetric No credit for scanning cross side. No recordable indications. (See Attachment 13)
SW-RS-2-A3-W4 R-A R1.16 Sweepolet to Pipe SA182F304 to SA376 Type 304 308 weld 50%
volumetric No credit for scanning sweepolet side. No recordable indications. (See Attachment 13)
SW-RS-2-A3-W5 R-A R1.16 Pipe to Flange SA182F316 to SA376 Type 304 308 weld 50%
volumetric No credit for scanning the flange side. No recordable indications. (See Attachment 13)
SW-RS-2-B3-W4 R-A R1.16 Sweepolet to Pipe SA182F304 to SA376 Type 304 308 weld 50%
volumetric No credit for scanning sweepolet side. No recordable indications. (See Attachment 13)
SW-RS-2-B3-W5 R-A R1.16 Pipe to Flange SA182F304 to SA376 Type 304 308 weld 50%
volumetric No credit for scanning the flange side. No recordable indications. (See Attachment 13) to NRC-20-0030 Page 9
- Welds 1-319 A, C, E, G Manual ultrasonic examinations were performed from the RPV closure head OD surface. The examination was limited due to the lifting lug position. Total coverage of each weld was calculated to be 78.8%. No flaw indications were recorded.
RPV Head lifting lugs sit on top of meridional welds (typical of 4).
11.1 in.
60°T PUii YIIEW TOP' ttltAD ADltlllM.Y 60° Sup. 6 NS Exam Volume= 5.7 Sq. In.
60° Sup. 6 FV Exam Volume= 15.1 Sq. In.
60° Sup. 4 Inner 15%T Exam Volume= 3.6 Sq. In.
60° Sup. 6 NS T-Scan Achieved= 5.7 Sq. In.
60° Sup. 6 FV T-Scan Achieved = 15.1 Sq. In.
60° Sup. 4 Inner 15% TT-Scan Achieved = 3.6 Sq. In.
60° Sup. 6 NS P-Scan Achieved= 5.7 Sq. In.
60° Sup. 6 FV P-Scan Achieved = 15.1 Sq. In.
60° Sup. 4 Inner 15%T P-Scan Achieved= 3.6 Sq. In.
4.7 in. 2.9 in.
5o*r Go0 T/P 2.9 in.
4.7 in.
G0° TIP G0°T Coverage was unrestricted.
11.1 in.
60°T to NRC-20-0030 Page 10 60° Sup. 6 NS Exam Volume = 5.7 Sq. In.
60° Sup. 6 FV Exam Volume = 15.1 Sq. In.
60° Sup. 4 Inner 15%T Exam Volume = 3.6 Sq. In.
60° Sup. 6 NS T-Scon Achieved= 0.9 Sq. In.
60° Sup. 6 FV T-Scan Achieved= 13.7 Sq. In.
60° Sup. 4 Inner 15% TT-Scan Achieved = 3.6 Sq. In.
60° Sup. 6 NS P-Scan Achieved = 0.0 Sq. In.
60° Sup. 6 FV P-Scon Achieved = 0.0 Sq. In.
60° Sup. 4 Inner 15%T P-Scon Achieved = 0.0 Sq. In.
60°T I
ml Coverage not achieved Coverage was restricted for T-scan and P-scan due to a lifting lug.
60°T to NRC-20-0030 Page 11 Typical of 4 I HITACHI SP2000 RPV Examination Coverage Calculation Sheet Fermi 2 l2RF181 Weld 1-319A !Meridional Weldl CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length =
68.1 Required El(om Percent Exam Volume =
24.4 Area Sq. in.
Area Scanned of Area Weld Length Percent 60' T-Scan 156 N51 A
5.7 5.7 23.4%
45.1 7.7%
60'T-5can 156 FVl A
15.1 15.1 61.9%
45.1 20.5%
60' T-Scon ON 1541 A
3.6 3.6 14.8%
45.1 2.4%
60' T-Scon UP 1541 A
3.6 3.6 14.8%
45.1 2.4%
60' P-Scon 156 NSI A
5.7 5.7 23.4%
45.1 7.7%
60' P-Scon 156 FVI A
15.1 15.1 61.9%
45.1 20.5%
60' P-Scon ON 1541 A
3.6 3.6 14.8%
45.1 2.4%
60' P-5can CCW 1541 A
3.6 3.6 14.8%
45.1 2.4%
60' T-5con 156 NSI 8
5.7 0.9 3.6%
23.0 0.6%
60' T-Scon 156 FVI 8
15.1 13.7 56.1%
23.0 9.5%
60' T-Scan ON 1541 8
3.6 3.6 14.8%
23.0 1.2%
60'T-5can CC 1541 B
3.6 3.6 14.8%
23.0 1.2%
60' P-Scan 156 NSI 8
5.7 0.0 0.0%
23.0 0.0%
60' P-Scon 156 FVl 8
15.1 0.0 0.0%
23.0 0.0%
600 P*Scon UP 1541 8
3.6 0.0 0.0%
23.0 0.0%
60' P-5con ON 1541 8
3.6 0.0 0.0%
23.0 0.0%
60' T-5can 156 NSI 60' T-Scon 156 FVl 60' T-Scon CW 1541 60'T-5canCCl541 60' P-Scon 156 NSI 60' P-Scan 156 FVl 60' P-Scon UP 1541 60' P-Scan ON 1541
% Total Composite Coverage=
78.8%
Comments:
A -Manual scanning was not limited to single side access for T-scon.
B -Manual scanning was limited due to a lifting lug.
Note -Rounding methods may affect calculated values. UC-Underclad, FV-Full volume, NS-Near Surface. Weld length in inches.
RevOI/WS ferrn2,Rfl8 Summary No.: FNP2-Bl.12-0006 Poge 5 of 9 to NRC-20-0030 Page 12
- RPV Bottom Head Welds 2-306A, B, C, D, E, F, G and Circumferential Weld 5-306 Meridional welds 2-306A-G and circumferential weld 5-306 are inside the RPV Skirt Access Cover provided for visual leakage inspection and access to the peripheral CRDs. The CRDs and incore monitoring tubes prevent access for ultrasonic examination of these welds.
SKIRT to NRC-20-0030 Page 13
- RPV Longitudinal Seam Weld 2-308B Longitudinal seam weld 2-308B is on the upper intermediate shell course. Automated ultrasonic examination is performed from the OD surface between the mirror insulation and the vessel wall. The ultrasonic scanner mechanism is mounted to the vessel wall by magnetic wheels and a small electric motor must pull the scanner, transducer package, UT cables, camera, and couplant tube approximately 36 up the vessel. The weight of the package and limited space between the mirror make full coverage from the OD extremely difficult. All welds on this shell course were limited in similar manner from the OD due to an indeterminate cause. The other 2-308 shell course welds were supplemented by automated scanning from the ID of the vessel to obtain full volume coverage. Weld 2-308B could not completed from the ID due the location of the internal 180-degree guide rod. Coverage is limited to the length of weld that could be scanned from the OD.
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lN(ltt I) to NRC-20-0030 Page 14 Scanner mechanism looking up from Bioshield Annulus Site:
Fermi System:
Bidirectional coverage for Up & Down skews shown with cross hatching.
COVERAGE SKETCH Sheet Unit: 2 Outage#:
RFO15 Procedure# __
IIUX~~-P-'D_l_-2_5_4 __
RPV Weld#: ____
2*-'3-'-0-'-8_8'----
MAX EXAM AREA: 6.751n X l36.7Sln
- 923,053 in~
0.5 X 6.75in X ll.69in
- 39.-45 lnl 6.75in x 92.671n
- 625.52 in1 6.75 n--::.:.:.:.::.:.:.~::~Po:gg 11.69
~!i:1-----+sos.Jo Report#
GFRM2-RF15-04 Revision:
3 FCN:
N/A Scan Limitation 360° 13.75 92 67 Level
~
Pg
'-/ of t./
Level Date ANII Review b to NRC-20-0030 Page 15
~ W.~~.~ync AW* *U*ujlwv** (i.<1,k.Cln,iwt, Ultrasonic Examination SCAN LIMITATION Sheet Report #
GFRM2-RF15-04 Page_:2__of 3/
Weld Number:
2-308 B Interfering Condition:
Undetermined Scan Limitation Size of Interfering Condition:
Full 360° just above 520"
~-------------
Distance from Weld Centerline:
NIA Distance from Datum Point 0.0: ___
F_u_ll_c_i~_cu_m_fe_re_n_c_e--'@=-5_2_0_" __
Reference Drawing Number: ___________
E_-2_3_2_-9_0_2 __________ _
Comments and Sketches: (include extent of bidirectional exam coverage achieved):
Code Coverage Calculations CW= 76%
CCW= 76%
UP= 72%
Down= 72%
Total Code Coverage
+
+
+
296/4 =
74%
Exam Volume= 136. 75 x 6. 75 = 923 SQ. IN.
CW Sound Propagation UP Weld Length Examined= 104.37" Weld Volume Examined= 104.37 X 6. 75 = 704 Percent Examined = 704 I 923 = 76%
(See Coverage Sketch Sheet)
Weld Volume Examined = 626 +39 = 665 Percent Examined = 665 I 923 = 72%
EXAMINER:a=~-<-~....;..
./....;::
_,. '---~---
REVIEWER: 1/2:°"-ef-;:7(2'~
Authorized Inspection Agency: ~ ~
ccw Weld Length Examined= 104.37" Weld Volume Examined = 104. 37 X 6. 75 = 704 Percent Examined= 704 I 923 = 76%
Down (See Coverage Sketch Sheet)
Weld Volume Examined = 626 +39 = 665 Percent Examined = 665 I 923 = 72%
LEVEL ::zzr DATE
~-/...?-/ 2 LEVEL
_:t:t::t::-
DATE
'i/,?!2..
I Date:..,_,!-/ 9- / Z-to NRC-20-0030 Page 16
- Weld 3-319 Manual ultrasonic examinations were performed from the RPV closure head OD surface. The examination was limited due to the RPV Flange configuration limiting scanning direction from one side only.
to NRC-20-0030 Page 17 Total Area of Interest: 34.92 sq. in.
Circumferential ScanTotal Area of Coverage: 31.07 sq. in.
Circumferential Scan Coverage: 88.97%
Axial Scan Total Area of Coverage: 19.50 sq. in.
Axial Scan Total Coverage: 55.84%
Total Scan Coverage: 55.84 + 88.97 + 2 = 72.40%
Limited Scan Area (Axial)
Weld: 3-319 Limited Scan Area (Circ) to NRC-20-0030 Page 18
- Weld 6-306 Manual ultrasonic examinations were performed from the RPV closure head OD surface. The examination was limited due to the proximity of the vessel skirt limiting scanning direction from one side only with the transducer exit point reaching just past the centerline of the weld.
1iiH"--- ~---..-----r....i..--i--,,----&;;~--...-l----'--..------l-...----..1----1 -----Nr M..,_ __ 5UPPOll'T SKIR'T
"'",._ __,.. ~,~*.:~*h COVER to NRC-20-0030 Page 19 Dn l!nef9Y' Supplemental Report Report No.:
UT-514-024 Page:
3 of 8
Summary No.: FNP2-B1.21-0003 Sketch or Photo: S:11S1-IST Programsllddeal_ServerlRF16 WesDyne\\RF16 lddeal Attachments\\RF16 Report Plctures\\Serth Coverage 6-306.Jpg Total exam volume: "H"+"I" = (4.2x6.1)+(1.7x6.1/2) = 30.8in2 Inner 15% exam volume: "J" 0.63x6.1 = 3.8in2 Outer 85% exam volume: 30.8-3.8 = 27in2 Inner 15% Area examined
= CW : Area "B" 0.63x4.1 = 2.6
= CCW : Area "B" 0.63x4.1 = 2.6
- 1. LK UP: 0
- 1. LK ON : 0.63x6.1 = 3.8 2.6+2.6+0+3.8 = 9 9/4=2.25 2.25/3.8 = x/100 = 59% Coverage of the inner 15%
59/100 = x/15 = 8.9% of total exam volume.
Outer 85% Area examined 1.: Area "C" and "D" (6.lx3.6) + (6.lx0.65/2) = 24in2
= : Area "E" "F" & "G" (3x3.6) + (3x0.6/2) + (4.9xl.3/2) = 14in2 24+14=38 38/ 2 = 19in2 19/27 = x/100 = 70.4% of Coverage of the outer 85%
70.4/100 = x/100 = 60% ofTotal exam volume Inner 15% + Outer 85%
to NRC-20-0030 Page 20
~
- DTE Energr Summary No.: FNP2-B1.21-0003 Examiner. Blecha, Paul Other: N/A ----------
Comments: Area not covered in Circ scan.
Supplemental Report Level: 11-PDI Reviewer. Linden, Randy. Level Ill Level: 111-PDI Site Review: Brooks, Marc A.
- Level Ill Level: N/A ANII Review: Wilson, Mark* HSB CT Sketch or Photo: S:USI-IST ProgramsUddeal_Server\\RF16 Wes0yne\\RF16 lddeal AltachmenlslRF16 Report Pictures\\6-306 Circ Sketch.jpg I
~
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Report No.:
UT-S14-024 Page:
4 of 8
Date~v Date: 3-/-/(j Date: 3 -:f:/f tL.
1, -,, I to NRC-20-0030 Page 21 i
- DREnergr Summary No.: FNP2-B1.21.0003 Examiner: Serth, Joseph P.
Examiner. Blecha, Paul Other. NIA ---------
Comments: Area not covered in A1. scan.
Supplemental Report Level:
11-PDI Reviewer. Linden, Randy. Level Ill Level: 111-PDI Site Review: Brooks, Marc A.* Level Ill Level: N/A ANII Revie1*r. Wilson, Mark* HSB CT Sketch or Photo: S:USI-IST Programs\\lddeal_$erver\\RF16 WesDyne\\RF16 lddeal AtlachmentslRF16 Report Pictures\\6-306 A,, Ske1ch.jpg Report No.:
UT-514-024 Page:
5 of 8
Date: a!l]J.L/
Date: 3./~/~
Date: 3 -S*lf to NRC-20-0030 Page 22 DTEEnorgr Summa,y No.: FNP2-B1.21-0003 Examiner: Serth, Joseph P.
Examiner: Blecha, Paul Other: N/A ----------
Comments: Used to calculate coverage.
Supplemental Report Level: 11-PDI Reviewer: Linden, Randy. Level Ill Level:
111-PDI S~e Review: Brooks, Marc A.
- Level Ill Level: N/A ANII Review: Wilson, Mark* HSB CT Sketch or Photo: S:USI-IST ProgramsUddeal_SeNerlRF16 WesDynelRF16 lddeal Attachmenls\\RF16 Report Pictures\\6-306 Skelch 2.jpg r
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Report No.:
UT.S14-024 Page:
7 of 8
(@)
Date.q97 /C/
,,!//JC/;
Dale: ]-/-/(/
~
Dale: 3~5-/y to NRC-20-0030 Page 23 Summary No.: FNP2-B1.21-0003 Examiner: Blecha, Paul Other: N/A ----------
Comments: Used to calculate coverage in Circ direction.
Supplemental Report Level: 11-PDI Level: 111-PDI Level: N/A Reviewer: Linden, Randy
- Level Ill Sile Review: Brooks, Marc A.
- Level Ill ANII Review: Wilson, Mark* HSB CT Sketch or Photo: S:USI-IST ProgramsUddeal_ServerlRF16 Wes0yne\\RF16 lddeal Attachmenls\\RFl6 Report Pidures\\6-306 Skelch 1.jpg v I I
E
' <1' j'
,I V
Report No.:
UT-514-024 Page:
6 of 8
Date:~J7N Date: 3./-II/
Date: 3--5"-ly to NRC-20-0030 Page 24 i
DTEEnergy Examiner. Blecha, Pa Other. N/A ----------
Comments: Used to calculate coverae in A1. scans.
Supplemental Report Level:
11-PDI Reviewer. Linden, Randy -Level Ill Level: 111-PDI Sile Review: Brooks, Marc A. -Level Ill Level: N/A ANII Review: Wilson, Mark -HSB CT Sketch or Photo: S:USI-IST ProgramsUddeal_ServerlRF16 WesDynelRFt6 lddeal Attachments\\RF16 Report Pidures\\6-306 Sketch 3.jpg
'
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-~
I Report No.:
UT-S14-024 Page:
8 of 8
Da1eJd1J_~
Date:.J:li!j_
Date: 3*5*;/
to NRC-20-0030 Page 25
- Threads in RPV Flange Manual ultrasonic examinations were performed from the RPV flange surface. The examination was limited due to the proximity of the raised clad flange seal surface.
Supplemental Report Rep011 No.:
UT-F10.Q06 Page:
of 5
Summary No.: FNP2-B6.40-0001 Examiner. Scruggs, Jonathan T. 'fl Level: ___!!_
R~ Morton, Victor. Level Ill @
Dace: 111212010 Examiner.-""~'*------ Level: ~
Site Review: Broob, Marc A ** Level 111 Date:
0 11..c. -""cc'*~----- Level: ~
ANII Revlew: ~* 1~*------
Date:
Comments; RPV S!od Hole Limited ArH 1 Skelchor Pholo: S.IISMST Pr(9'amtllOdHI_Sa!Ye!'IAFl* ARE\\IA\\RF1* lclclealAllachmenl1\\Repol1 Plchn11RPV Stud hole anittd -**' )pg to NRC-20-0030 Page 26 DTEEnergy-Supplemental Report Report No.:
UT-F10-006 Page:
3 of 5
Summary No.: FNP2-B6.40-0001 Sketch or Photo: S:I1S1-IST Programsllddeal_Server\\RF14 AREVAIRF14 lddeal Attachments\\Report Pictures\\RPV Stud Hole Coverage doc1.jpg Fermi RF14 - Fall 2010 Reactor Vessel Stud Hole Ultrasonic Examination Coverage Total Arca: 24.8 1 Sq. In.
. 7854 X (8.90' -6.90') = 24.81 Limited Arca: 3.09 Sq. In.
1.8 X.35 =.63 4.45' + 2 X ({1t X 67° + I 80)- (sin 67°)) = 2.46 Total Coverage: 2 1. 7 Sq. In.
% Total Covcnigc: 87.55%
I
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11/4/4 to NRC-20-0030 Page 27
- Weld 2-318 Manual ultrasonic examinations were performed on the RPV Head Vent Nozzle from the closure head OD surface. The examination was limited due to the configuration of the nozzle radius preventing the transducer centerline from scanning across the full volume required by ASME Section XI, Figure IWB-2500-7(a).
SPARE W/'BL lND _.
~r,i;?'--...~~
3-3]88 to NRC-20-0030 Page 28
/
I
/
I P-Scans I
60° NS P I
60' FV P I
Fermi Unit-2 Top Head Vent 60° NS Exam Volume= 7.2 Sq. In.
60° FV Exam Volume = 16.8 Sq. In.
60° NS T-Scan achieved = 3.6 Sq. In.
60° FV T-Scan achieved= 13.6 Sq. In.
60° NS P-Scan achieved = 3.0 Sq. In.
60° FV P-Scan achieved = 12.1 Sq. In.
Inner 15% T-Scan achieved= 3.2 Sq. In.
Fermi Unit-2 Top Head Vent 60° NS Exam Volume= 7.2 Sq. In.
60° FV Exam Volume = 16.8 Sq. In.
60° NS T-Scan achieved = 3.6 Sq. In.
60° FV T-Scan achieved= 13.6 Sq. In.
60° NS P-Scan achieved = 3.0 Sq. In.
60° FV P-Scan achieved = 12.1 Sq. In.
Inner 15% T-Scan achieved = 3.2 Sq. In.
T-S~ans eo* NS T-Scan r
- r---:--:::::::?l--------~6~0'~FVT-Scan I
I I
I I
7 Nominal T = 4.25" Nominal Clad T = N/A to NRC-20-0030 Page 29 CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length = 360.
Required Exam Area Scanned of Area Weld Length Percent Exam Volume = 24.
Area Sq. In.
Manual Manual Manual Manual 60° NS T-Scan A
7.2 3.6 15.0%
360 7.5%
60° S6 T-Scan A
13.6 13.6 56.7%
360 28.3%
so* S4 / IRS Scan A
3.2 3.2 13.3%
360 6.7%
60° NS P-Scan A
7.2 3.0 12.5%
360 6.3%
60° S6 P-Scan A
13.6 12.1 50.4%
360 25.2%
60° IRS P-Scan A
3.2 3.2 13.3%
360 6.7%
60° NS T-Scan 60° S6 T-Scan 60° S4 T-Scan 60°.NS P-Scan 60°-S6 P-Scan 60°1 S4 P-Scan f
i I
% Total Composite Coverage=
81 %
to NRC-20-0030 Page 30
- Weld 4-316A Manual ultrasonic examinations were performed on the Feedwater Nozzle from the RPV shell OD surface. The examination was reported to be limited due to the configuration of the nozzle radius preventing the transducer centerline from scanning across the full volume required by ASME Section XI, Figure IWB-2500-7(b) as well as location of the 2-315C instrumentation nozzle limiting scanning of a portion of the circumference.
i i
10*
' o*
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T411a-- **.+----------+---------+----------+-------- - --t, nsr--~===::;::====~===::::;;======l====:,::=====l===:::;=====r NOff 'l
... -.* ~.. ----*Yo- -
- --+-- M.AHII t'Tl!AM
---t--- l Nl'TaJMDITATiOii
-f- _ -r------0----+--'T"".._o ____ -+-___._0_-r __ -+-___,_o ___ --t 6 17" --
- -&::..:,,- --+--------+---+----....;;'-e;;;;..---t--- 1N,"""'IIENTATION
- 1*-11li,;-----,; -
,K:;~- -jl--- ~ro>w:ATI*
&40'*1});--,---*; --
- _1:
-+ti-+t-~==--t-- COM --.v 6J1' "'*~*----44'*'.i -
--+----=~=
.,... ___,..,._.;:.;=------+-..--..... --,~_....,-.! _____..... __ +,,---------'I TDC 13" Inst. Nozzle Pad 0
14" Weld Nozzle Boss 4" From Weld CL N4A Nozzle OD Radius N4 N4
~,,,
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i I
AXIAL COVERAGE CIRCUMFERENTIAL COVERAGE to NRC-20-0030 Page 31 N4A Examination Coverage Angle / Coverage
- 1) 60° (Axial) From Vessel:
Total Exam Area (100%):
.7854 x ((37' - 32') x (6.44)) = 1745 Cu. In.
Exam Area Not Covered:
.7854 x ((37' - 35.4') x (1.234)) + 2 = 87.25 Cu. In.
2.5 x 16.25 x 6.44 = 261.62 Cu. In.
87.25 + 261.62 = 348.87 Cu. In.
Exam Area Covered :
1745-348.87 = 1396.13 Cu. In.
(1396.13 + 1747) X 100 = 80.01 Total Axial Scan Coverage= 80.01%
- 2) 60" (Circumferential) From Vessel Upper 85%:
Total Exam Area (100%):
. 7854 x ((37' - 32') x (5.474)) = 1483.25 Cu. In.
Exam Area Not Covered:
.7854 x ((33.5' - 32') x (5.474)) = 422.40 Cu. In.
.7854 x ((35' - 33.5') x (5.474)) + 2 = 220.87 Cu. In.
Exam Area Covered:
(1483.25 - 839.98) = 643.27 + 1483.25 X 100 = 43.37 Total Circumferential Scan Coverage= 43.37%
Utility: DTE Energy I Plant: FERMI I Unit: 2 I Outage: RF14 N4A Inner 15% Circumferential Examination Coverage Nozzle to Shell Weld Lower 15%
- 1) 50° (+/- 66' ) From Vessel: 85.01% Coverage 7854 x ((37' - 32') x (.966)) = 261.75 Cu. In.
2.5 x.966 x 16.25 = 39.24 Cu. In.
(261.75 - 39.24) + 261.75 X (100) = 85.01 Total Coverage= 85.01%
I Weld ID: 4-316A I Work Sheet Number:
Axial scans were performed with a procedure qualified for the examination of vessel shell welds (54-ISl-805-07). This procedure has been demonstrated for detection of flaws located throughout the entire weld thickness. Coverage obtained during axial scans was limited due to the nozzle configuration.
In the circumferential scan direction the outer 85%-t is examined with the same vessel procedure as above and coverage was also limited due to nozzle configuration. To achieve additional coverage in the circumferential scan direction a second examination is performed with a procedure qualified for nozzle inside-radius examinations (54-ISl-850-007). This procedure has been demonstrated for detection of flaws in the inner 15%-t only. The nozzle inside-radius techniques were performed in accordance with the parameters identified in EPRI modeling report IR-2007-287.
60' RL Axial Scan (54-151-805-07) 100% ts volume 60' RL Circ Scan (54-ISl-805-07) upper 85% ts volume SO'S Circ Scan (54-151-850-007) inner 15% ts volume Thickness (ts) Inches 6.44 Thickness (ts) Inches 6.44 Thickness (ts) Inches 6.44 Weld Widlh Inches 1.5 Weld Width Inches 1.5 Weld Width Inches 1.5 Exam Volume (A D E H) Cu. Inches 1745 Exam Volume (A D E H) Cu. Inches 1745 Exam Volume (A D E H) Cu. Inches 1745 Area of no Coverage Cu. Inches 348.87 Upper 85% Volume Cu. Inches 1483.25 Inner 15% Volume Cu. Inches 261.75 Percentage of Area Scanned 80.01%
Area of no Coverage Cu. Inches 839.98 Area of no Coverage Cu. Inches 39.24 Percentage of Area Scanned 43.37%
Percentage of Area Scanned 85.01%
Coverage Axial Scan 100% ts volume 80.01%
Coveraae Circ Scan uooer 85% ts volume 43.37%
Coveraae Circ Scan inner 15°/o ts volume 12.75%
Total Coverage Axial and Circ Scans:
68.06%
Scanning was performed to the maximum extent possible. The total coverage achieved for scans performed in accordance with procedure 54-ISl-805-07 is a conservative estimate derived from the physical limitation caused by the nozzle configuration at the vertical sections of the nozzle and does not include additional volume obtained at the horizontal sections of the nozzle. See coverage diagrams for further information.
to NRC-20-0030 Page 32
- Welds 4-316B, 4-316E, 4-316F Manual ultrasonic examinations were performed on the Feedwater Nozzle from the RPV shell OD surface. The examination was reported to be limited due to the configuration of the nozzle radius preventing the transducer centerline from scanning across the full volume required by ASME Section XI, Figure IWB-2500-7(b). These nozzles are identical to 4-316A except there is no circumferential scan limitation from close proximity instrumentation.
N4B Examination Coverage Angle I Coverage
- 1) 60° (Axial) From Vessel:
Total Exam Area (100%):
.7854 x ((37 1
- 321} x (6.44)): 1745 Cu. In.
Exam Area Not Covered:
.7854 x ((371 - 35.41) x (1.234)) + 2 = 87.25 Cu. In.
Exam Arca Covered:
(1745
- 87.25) + 1745 *.95
.95 X 100
- 95 Total Ax/al Scan Coverage a: 95.00%
- 2) so* (Circumforontiat) From Vessel Upper 85%:
Total Exam Area (100%):
.7854 x ((JP - 321) x (5.474))"' 1483.25 Cu. In.
Exam Area Not Covered:
.7854 x ((33.5 1
- 32") x (5.474)) = 422.40 Cu. In,
.7854 x ((351 - 33.51) x (5.474)) + 2 = 220.87 Cu. In.
Eum Area Covered:
(1483.25-839.98)
- 643.27 + 1483.25 X 100
- 43.37 Total Circumferential Scan Coverage= 43.37%
N4B Inner 15% Circumferential Examination Coverage Nozzle to Shell Weld Lower 15%
- 1) so* (+/- 66' ) From Vessel: 100% Coverage
.7854 x ((37' - 32') x (.966)) = 261.75 Cu. In.
261.75 + 261.75 X (1 00) = 100 T otal Coverage= 100%
Utility: DTE Energy I Plant; FERMI Unit: 2 I Outage: RF14 I Weld lD: 4-3168 f Work Sheet Number:
Axial scans were performed with a procedure qualified for the examination of vessel shell welds (54-ISI-805-07). This procedure has been demonstrated for detection of Raws located throughout the entire weld thickness. Coverage obtained during axial scans was limited due to lhe nozzle configuration.
In lhe oircumfereotial scan direction the outer 85%-t is examined wilh the same vessel procedure as above and coverage was also limited due to nozzle configuration. To achieve additional coverage in the circumferential scan direction a second examinalion i.s performed with a procedure qualified for nozzle inside-radius examinations (54-ISI-850*007). This procedure has been demonstrated for detection of flaws in the Inner 15%-t only. The nozzle inside-radius techniques were performed in accordance with the parameters idendfied in EPRI modeling report IR-2007-287.
SO'R.L A;dol Scan [S4~S1-80S.07) 1001/4 ts volume 60"R.L Clrc Scan (54~Sl-80S-071 upPor 85% Is volumo so*s C.rc Soon (54-ISl-85N1071 lnncr 15'14 ts volumo ThickneH (t>) lnehe*
6.4.
Thickness (ts) Inches 6.44 Thict<Mss (IS) lnc!W!S 6.44 Weld W\\dlh lncl,es 1.5 Weld Widlh lnd>M 1.5 Weld Width Inches 1,5 Exam VolUme (A D E H) Cu. Inches 1745 Exilm VolUme (AD e H) Cu. lncl>es 1745 Exam Volume (AO e H) Cu. lncheo 1745 Area of no Coverage Cu. Inches 37.25 u_, 8S% VOiume Cu. 1nehes
- 83.25 Inner 15% Volume Cu. Inches 261.75 Percentage of Area Scanned 95.00%
Aroa of no Coverage Cu. Inches 339.98 Aseo of no Cove,oge Ou. Inell**
0.00 P,eentage of Atea Seaone<I 43.37%
Pe:rcellt;age of Area Scanned 1001/4 Coverage Axial Scan 100% ts volume 95.0%
Cover.,go Clrc Scan uft-r 85% IS volume 43.37%
Coverane Cfrc Sc.an [nner 15% ts volume 15.00%
Total Co'alerage.AlClal and Clrc Sc:a.ns:
76.68%
Scanning was performed to the maximum extent possible. The tolal ooverage achieved ror scans performed in accordance with procedure 54-ISI-805-07 is a conservative estimate derived rrom the physical limitation caused by the nozzle configuration at the vertical sections of the nozzle and does not include additional volume obtained at lhe horizontal sections or the nozzle. See coverage diagrams for rurther infom,ation.
to NRC-20-0030 Page 33 0: Weld 5-314B Manual ultrasonic examinations were performed on the Reactor Recirculation Suction Nozzle from the RPV shell OD surface. The examination was reported to be limited due to the proximity and configuration of bottom head shell taper and shell mirror insulation flange.
- i"---I-'-------~-+
...... --------+......... ------+-~---..... ---
11,'-e'",; ___ -111*
---fi9-lHH-ffi+- -W-- %.
113'-* V,6 --- !:ti~ -
- 1~8-=-- 13-314A
- 'a,,~---111* -
121/i-HITACHI 4F Fermi Unit 2 RF18 5-314B Coverage Plot 5-314B r32° 96 Drawing showng imitobOn of wsseJ toper.
13-
"l9rl0olll to NRC-20-0030 Page 34 Fermi 2 N 1 Rec ire. Outlet
~
~~~: i ~ i~~ iii~::: f 3:a5~~1n.
60' Sup. 4 Inner 15%1 Exam Volume= 2.9 Sq. In.
Inner 15%1 P*Scon 8<am Volume= 2.9 Sq. In.
~
~~K ~ ~ ~~;~'3: rN~ii'?.
fZ.~"fi~f "t-Wc~~9ii~~~r.'I'.c.i 0ii \\~ i~Y Modeling!
Coverage restricted area Coverage was limned due to nozzle configuration and insulation around nozzle.
Proposed monuol UT W-T-scori exom1no110n OrOl~ng shO'l.ing scon distance bock to limitation caused by the insulation.
Fermi 2 l2RF18l Weld 5-314B (Recirc. Outletl CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld length=
360.
Required Exom Area Sconned of Area
\\Veld length Percent Exam Volume=
19.2 Area Sq. in.
Manually Manually Manual~
Manual~
70T Scan 156 NSI A
2.5 2.4 12.5%
264
~.6%
45' T-Scon 156 FVI A
13.8 11.9 62.0%
264 22.796 60' T-Scan 1541 A
2.9 0.0 0.0%
264 0.0%
IRS P*Scan 1551 A
2.9 2.9 100.0%
264 36.7%
70'T-Scon 1S6 NS)
B 2.5 2.4 12.5%
96 1.7%
45'T-Scan 156 fv1 B
13.8 7.6 39.6%
96 5.3%
60'T-Scan 1541 B
2.9 0.0 0.0%
96 0.0%
IRS P-Scan ~5l B
2.9 2.9 100.0%
96 133~
70' T-Scan 1S6 NS) 45' T*Scon 156 fli1 60'T-Sconl541 IRS P*Scan ~SI 70' T*Scon 156 NS!
45' T*Scon !S6 FVI 60' T-Scon 1541 IRS P-Scon 1551
% Total Com osite Cevera e =
p g
81.Jill.i to NRC-20-0030 Page 35 1: Welds 13-314A and 13-314B Manual ultrasonic examinations were performed on the Reactor Recirculation Inlet Nozzle from the RPV shell OD surface. The examination was reported to be limited due to nozzle configuration.
Typical N2 Recirc Inlet Nozzle z<<f---1--1--------1--L-------.1-'---,------.l-'----....------1 e,5*-0'\\; ___.Jll ' ---
_4:i)..._-.<<=)+-+-ff* -
113'a* Vii --- ~,.. - - -
I~
[ -
C 111'
- 11 1511~-- -IM* ---
- ---+--- -::,:uu::NTATIOH
..,,_ - - l---~--~--1::....::,:.;:..--4"-,.--l,-~l--'-,---.-_;_;1-1--.-----,...... --,,....,
~o,.;- --
13-314A AxialCove,aEeDiaeram Thi.s diag,.am idcn1ifies the limitalions caused by the noHle radius.
Notto Scale This diagram klcntifies the limitation1 caused by the nozdc ~dius.
Not to Scale 13-314A Circumferential Cow.-rage Diagram 13-314B Circumferential Coverage Diagram CORE.lt.P/STAM0- 8Y LIQUl'D CONTftOl.
to NRC-20-0030 Page 36 Axial scans were performed with a procedure qualified for the examination of vessel shell welds (54-ISI-805-07). This procedure has been demonstrated for detection of flaws located throughout the entire weld thickness. Coverage obtained during axial scans was limited due to the nozzle configuration.
In the circumferential scan direction the outer 8~%-t Is examined with the same vessel procedu1e a:s alx.lve amJ wv~*ay~ wa~ also limited t.Jue to nozzle configuration. To achieve additional coverage in the circumferential scan direction a second examination is performed with a procedure qualified for nozzle inside-radius examinations (54-1$1-850-07). This procedure has been demonstrated for detection of flaws in the inner 15%-1 only. The nozzle inside-radius techniques were perlormed in accordance with the parameters identified in EPRI modeling report IR-2007-287.
so*RL Axial Scan l S4-ISl-805-07) 100% ts volume
&0*RL Circ Scan {54-ISl-805--07) upper 85% ts volume so*s Clrc Scan (54-ISl-850~7) Inner 15% ts volume ThlCkneu {ts) Inches 7.69 Thidtnen (ts) Inches 7.69 Th!Ckneu {ts) Inches 7.69 Weld Width Inches 15 Wetd Width Inches 1.5 Weld Width Inches 15 Exam Volume (ADE H) Sq. Inches 19 23 Ex.am Volume (ADE H) Sq Inches 19.23 Exam Voltme (ADE H) Sq Inches 19 23 AIU Scanned Sq. Inches 188405 Upper 85% voeunie Sq Inches 16.34 Inner 15% voeun,e Sq Inches P~cenrage of ArH Scanned Area Scanned Sq Inches 11.634 Area Scanned Sq Inches Percentaoe ol Area Scanned 71.20%
Percentage ot Area Scanned Coveraoe Axial Scan 100% ts volume Coveraae Clrc Scan u ooer 85% ts volume 60.52%
coveraoe Aidal Scan lnl'lef 15% ts volume Total Coverage Axial and Circ Scans:
87.76%
Scanning was performed to the maximum extent possible. The total coverage achieved for scans performed in accordance with procedure 54-ISI-805-07 ls a conservative estimate derived from the physical limitation caused by the nozzle configuration at the vertical sections of the nozzle and does not include additional volume obtained at the horizontal sections of the nozzle.
Component Number 13-314 A to NRC-20-0030 Page 37 Axial scans were performed with a procedure qualified for the examination of vessel shell welds (54-1$1-805-07). This procedure has been demonstrated for detection of flaws located throughout lhe entire weld thickness. Coverage obtained during axial scans was limited due to the nozzle configuration.
In the circumferential scan directio, the outer 85%-t is examined with the same vessel procedure as above and coverage was also limited due to nozzle configuration. To achieve additional coverage in the circumferential scan direction a second examination is performed wlth a procedure qualified for nozzle inside-radius examinations (54-ISI-650-07). This procedure has been demonstrated for detection of flaws in the inner 15%-t only. The nozzle inside-radius techniques were performed in accordance with the parameters identified in EPRI modeling report IR-2007-267.
60"RL Axial Scan (54-ISl-805-07) 100o/, ts volume 60"RL Clrc Scan (54-151-805-07) upper 85o/. lS volume so*s Circ Scan (54-151-850-07) inner 15°/o ts volume Thiekness (ts) Inches 7.69 Thiekness (ts) Inches 7.69 Thiekness (ts) Inches 1.69 Weld Wiellh Inches 1.5 Weld Width Inches 1.5 Weld Width Inches 1.5 Exam Volume (ADE H) Sq. Inches 19.23 Exam Volume (A D E H) Sq. Inches 19.23 Exam Volume (A D E HJ Sq. Inches 19,23 Area Scanned Sq. Inches 18.8405 Upper 85% Volume Sq. Inches 16.34 Inner 15% Volume Sq. Inches 2.88 Percentage of Area Scanned 98%
Area Scanned Sq. Inches 11.634 Area Scanned SQ. Inches 2.88 Percentage of Area Scanned 71.20%
Percentage of Area Scanned 100%
Coverage Axial Scan 100% ts volume 98%
Coverage Circ Scan upper 85°/. ts volume 60.52%
Coveraae Axial Scan inner 15°4 ts volume 15"/o Total Coverage Axial and Circ Scans:
87.76'Yo Scanning was performed to the maximum extent possible. The total coverage achieved for scans performed in accordance with procedure 54-ISI-805-07 is a conservative estimate derived from the physical limitation caused by the nozzle configuration at the vertical sections of lhe nozzle and does not include additional volume obtained at the horizontal sections of the nozzle.
Component Number 13-314 B to NRC-20-0030 Page 38 2: Weld SW-E11-D2-HX-01 Manual ultrasonic examinations were performed on the Residual Heat Removal Heat Exchanger Inlet Nozzle from the shell OD surface. The examination for reflectors perpendicular to the weld was limited due to nozzle to vessel weld face angle preventing effective scanning of the inner 1/3 volume as shown in ASME Section XI, Figure IWC-2500-4(a). Scanning for reflectors parallel to the weld was 100%
complete. The 4th Interval ISI Program review for this vessel performed in accordance with NRC accepted ASME Code Case N-716-1 has determined this weld was a low safety significance (LSS) and therefore will no longer require examination.
t
- TH~RMAL RELIEF VALVE SW-EII-D2.-HX-02
- f LEVEL GAUGE CONNECTION SW-Ell-02-HX-04 SW-Ell*DZ-HX*06 CONT. ON DWG.
&M721-3177 sw-El t-02-HX - OI-IRS
'-------r TOP SUPPORT FUNG (4 -90, i* t':'~:.MS;~~::}RING Total Area:.507 sq. in.
Weld Coverage SW-E11-D2-HX-01 Axial Scan Coverage:.507 sq. in. = 100% Coverage Circumferential Scan Coverage:.242 sq. in.= 47.73%
Scan Area Covered:.242 sq. in.
Scan Area Not Covered:.265 sq. in.
Total Coverage: 100 + 47.73 + 2 = 73.86%
to NRC-20-0030 Page 39 SW-E11-D2-HX--01 45 11111111' /
,111111, 70 45 70 45 I' SW-E11-D2-HX-01 11 11111
,1/11,"
CIRCUMFERENTIAL DIRECTION AX IAL DIRECTION to NRC-20-0030 Page 40 3: R-A, R1.16 Welds For R-A, R1.16 welds (potentially subject to IGSCC) when limited to single side access due to external configuration and/or potential non-parallel inside surfaces that could substantially change the assumed beam angle at a flaw, the coverage is a simple 50% assumption. This is because ASME Section XI, Appendix VIII Supplement 2 procedures are only qualified for detection when scanning is performed from both sides of the weld. The following coverage sketches are provided to demonstrate the limitation.
FW-E11-2327-6W0 RHR Return Pipe to Tee Weld FW-G33-3096-12WF3 Sweepolet to Tee Comments:
WELD SIZE FW-Ell-2327-6W0 Weld Crown Height Flush Crown Width 1.4~
Sketch or Photo:
NQm..Qla...
24.0" Weld Length 75.6"
~Cf C/L Pipe FLOW Tee 0
- t",< 17 r/
P/..r 0
oO 1-50
/-t:J L t?
/*t7 tl*oV (l -,s?,?
tl* f/o<
/ }y-f.33 - 3ll76' -/./? l'Y'F.3 to NRC-20-0030 Page 41 FW-RD-2-A11 Sweepolet to Pipe SW-RD-2-A3-W7 Cross to Pipe Comments:
WELD SIZE FW-RD-2-All Weld Crown Height Flush Crown Width 1.1*
Sketch or Photo:
Nom Dia.
12.0*
Weld Length 40.0" C/L
,o*
I I
~0*1
'ISO I: I Sweep-O-Let FLOW Pipe Contours Thickness Data From C/L of Weld
-1.5 I
-Toe I
C/L I
+Toe I
+1.5 N/A I
.737" I
.716" I
.590" I
.675" Comments:
WELD SIZE SW-RD-2-A3-W7 Weld Crown Height Flush Crown Width 2.0" Norn Dia.
22.0"
,ketch or Photo:
Weld Length 71.0" C/L Thickness and Contours validated from previous data.
Cross FLOW Pipe Contours Thickness Data From C/L of Weld
-1.5 I
-Toe I
C/L I
+Toe I
+1.5 N/A I
1.550" I 1.280" I 1.170" I 1.100" to NRC-20-0030 Page 42 SW-RS-2-A3-W4 Sweepolet to Pipe SW-RS-2-A3-W5 Pipe to Flange WELDSIZI SW-RS-Z-A3-W4 Weld crown Helcht Flush Crown Width
.so*
Sketch or Photo:
b'2m..Q1L 4.o*
Weld Length JS.l" Sweep-0-let FLOW Pipe Contours Thickness Data From C/L of Weld
-1.5 C/L
+Toe
+1.5 N/A 0.39 0.34" 0.36" 0.36"
\\1/EtDSIZE SW-RS-Z-A3-WS Weld Crown Height Flush Crown Width
.50" Sketch or Photo:
NQm.l!ii..
4.0" Weld bench 15.J" C/ L Pipe FLOW Flange Contours Thickness Data From C/l of Weld
-1.5
- Toe C/L
+Toe
+1.5 0.36" 0.35" 0.39" 0.43" N/A to NRC-20-0030 Page 43 SW-RS-2-B3-W4 Sweepolet to Pipe SW-RS-2-B3-W5 Pipe to Flange WELD SIZE SW-RS-2-83-W4 Weld Crown Height Flush Crown Width
.sou Sketch or Photo:
Norn Dia.
4.0" Weld Length 14.1" Sweep-0-let FLOW Pipe Contours Thickness Data From C/l of Weld
-1.5 C/L
+ Toe
+l.S N/A 0.323" 0.313" 0.316" 0.321" WELD SIZE SW-RS-2-83-WS Weld Crown Height Flush Crown Width
.so*
Norn Dia.
4.0" Sketch or Photo:
Weld Length 14.J" C/L Pipe FLOW Flange Contours Thickness Data From C/L of Weld
-1.5
-Toe C/L
+Toe
+1.5 0.316" 0.308" 0.330" 0.340" N/A