ML051790245
| ML051790245 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/24/2005 |
| From: | Rosalyn Jones Duke Energy Corp, Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML051790245 (134) | |
Text
{{#Wiki_filter:RONALD A JONES Duke -7 Vice President Power, II Oconee Nuclear Site Duke Power ONOI VP / 7800 Rochester Hwy. Seneca, SC 29672 864 885 3158 864 885 3564 fax June 24, 2005 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Duke Energy Oconee Nuclear Station, Unit 3 Docket Nos. 50-270 Third Ten Year Insprvice Inspection Interval Requests for Relief No. 05-ON-001 and 002 Pursuant to 10 CFR 5O.5'5a(g) (5)(iii), attached are two Requests for Relief from the requirement to examine 100% of the volume specified by the ASME Boiler and Pressure Vessel Code, Section XI, 1989 Edition with no Addenda (as modified by Code Case N-460). Request for Relief 05-ON-001 is to allow Duke Energy to take credit for eleven (11) limited ultrasonic examinations on welds associated with various systems and components described in the attached request (Attachment A). Request for Relief 05-ON-002 is a similar request but addresses seven (7) limited ultrasonic examinations on welds specifically associated 'with the Reactor Vessel as described in the attached request (Attachment B). During the recent Unit 3 EOC-21 refueling outage, from 10-9-04 through 1-2-05, numerous ultrasonic examinations were conducted on various welds. The ultrasonic examination coverage of the subject Unit 3 welds did not meet the 90% examination requirements of Code Case N-460. The obtainable volume coverage for each weld examination is indicated on the attached requests. Achievementlof greater examination coverage for these welds is impractical due to piping/valve geometry, interferences, and existing examination technology-. Therefore, Duke Energy requests that the NRC grant relief as authorized under 10 CFR 50.55a(g)(6)(i). www.dukepower.corn
U. S. Nuclear Regulatory Commission June 24, 2005 Page 2 If there are any questions or further information is needed you may tact R. P. Todd at (864) 885-3418. Vera yt R. A. o s Site ice President Attachments A and B
U. S. Nuclear Regulatory Commission June 24, 2005 Page 3 xc w/att: Mr. William D. Travers Administrator, Region II U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St., SWW, Suite 23T85 Atlanta, GA 30303 L. N. Olshan, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 S. E. Peters, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 xc(w/o attch): M. C. Shannon Senior NRC Resident Inspector Oconee Nuclear Station Mr. Henry Porter Division of Radioactive Waste Management Bureau of Land and Waste Management SC Dept. of Health & Environmental Control 2600 Bull St. Columbia, SC 29201
U. S. Nuclear Regulatory Commission June 24, 2005 Page 4 bxc w/att: R. L. Gill, Jr. T. J. Coleman V. B. Dixon B. W. Carney, Jr. R. P. Todd L. C. Keith G. L. Brouette (ANII) J. J. Mc Ardle III ISI Relief Request File NRIA File/ELL ECO50 Document Control
Attachment A Request for Relief 05-ON-001 Limited Examinations Associated With Various Systems and Components 3EOC 21
Relief Request 05-ONO001 Page 1 of 8 Proposed Relief in Accordance with 10 CFR 50.55a(g)(5)(iii) Inservice Inspection Impracticality Duke Energy Corporation Oconee Nuclear Station - Unit 3 (EOC-21) Third 10-Year Interval - Inservice Inspection Plan Interval Start Date= 12-16-1994 Interval End Date=1-2-2005 ASME Section XI Code - 1989 Edition with No Addenda Code Case N-460 is applicable I. II. III. IV. &V. VI. VII. VIII. List Limited System / Code Requirement from Impracticality/ Proposed Implementation Justification for Number Area/hVeld I.D. Component for Which Which Relief is Requested: Burden Caused by Alternate Schedule and Granting Relief Number Relief is Requested: 100% Exam Volume Coverage Compliance Examinations or Duration Area or Weld to be Exam Category Testing Examined Item No. Fig. No. __ Limitation Percentage
- 1. 3-PZR-WP26-1 Reactor Coolant System Exam Category B-D See Paragraph "A" See Paragraph "H" See Paragraph "I" See Paragraph "J" Pressurizer Sensing Item Number B03.110.009 Sample Nozzle to Fig. IWB-2500-7(a)
Heater Belt Weld 25.92% Volume Coverage Limited Scan of Examination Volume A-B-C-D-E-F-G-H-I
- 2. 3-PZR-WP26-2 Reactor Coolant System Exam Category B-D See Paragraph "A" See Paragraph "H" See Paragraph "I" See Paragraph "J" Pressurizer Sensing Item Number B03.1 10.010 Sample Nozzle to Fig. IWB-2500-7(a)
Heater Belt Weld 25.92% Volume Coverage Limited Scan of Examination Volume A-B-C-D-E-F-G-H-I
- 3. 3-PZR-WP26-3 Reactor Coolant System Exam Category B-D See Paragraph "A" See Paragraph "H" See Paragraph "I" See Paragraph "J" Pressurizer Sensing Item Number B03.1 10.011 Sample Nozzle to Fig. IWB-2500-7(a)
Heater Belt Weld 25.92% Volume Coverage Limited Scan of Examination Volume A-B-C-D-E-F-G-H-I
Relief Request 05.ON-001 Page 2 of 8 l l I1. IIl.IV. &V. VI. VII. Vill. List Limited System Code Requirement from Impracticality/ Proposed Implementation Justification for Number Area/\Veld I.D. Component for Which Which Relief is Requested: Burden Caused by Alternate Schedule and Granting Relief Number Relief is Requested: 100% Exam Volume Coverage Compliance Examinations or Duration Area or Weld to be Exam Category Testing Examined Item No. Fig. No. Limitation Percentage
- 4. 3-PZR-WP26-7 Reactor Coolant System Exam Category B-D See Paragraph "A" See Paragraph "H" See Paragraph "I" See Paragraph "J" Pressurizer Sensing Item Number B03.110.012 Sample Nozzle to Fig. IWB-2500-7(a)
Heater Belt Weld 25.92% Volume Coverage Limited Scan of Examination Volume A-B-C-D-E-F-G-H-I
- 5. 3-LDCB-IN-VI High Pressure Injection Exam Category B-D See Paragraph "B" See Paragraph "H" See Paragraph "I" See Paragraph "J" System Item Number B03.150.003 Letdown Cooler 3B Fig. IWB-2500-7(a)
Inlet Nozzle to Channel 29.26% Volume Coverage Head Weld Limited Scan of Examination Volume A-B-C-D-E-F-G-H-I-J
- 6. 3-LDCB-OUT- High Pressure Injection Exam Category B-D See Paragraph "B" See Paragraph "IT' See Paragraph "I" See Paragraph "J" V2 System Item Number B03.150.004 Letdown Cooler 3B Fig. IWB-2500-7(a)
Outlet Nozzle to 29.26% Volume Coverage Channel Head Weld Limited Scan of Examination Volume A-B-C-D-E-F-G-H-I-J
- 7. 3-14B-H20A Low Pressure Service Exam Category C-C See Paragraph "C" See Paragraph "H" See Paragraph "I" See Paragraph "K" Water System Item Number C03.020.017 Component Support Fig. IWC-2500-5(a)
Attachment to Pipe 50% Surface Coverage Weld Limited Coverage of Examination Surfaces A-B and C-D
- 8. 3-51A-67-3 High Pressure Injection Exam Category C-F-I See Paragraph "D" See Paragraph "H" See Paragraph "I" See Paragraph "L" System Item Number C05.021.049 Pipe to Elbow Weld Fig. IWC-2500-7(a)
(circumferential weld) 87.38% Volume Coverage Limited Scan of Examination Volume C-D-E-F
Relief Request 05-ON-001 Page 3 of 8 Il I 11. H. I III. I IV. &v. I VI. I Vil. I Vill. List Limited System / Code Requirement from Impracticality/ Proposed Implementation Justification for Number Area/Weld I.D. Component for Which Which Relief is Requested: Burden Caused by Alternate Schedule and Granting Relief Number Relief is Requested: 100% Exam Volume Coverage Compliance Examinations or Duration Area or Weld to be Exam Category Testing Examined Item No. Fig. No. 4 4 Limitation Percentage 4 4 4 + High Pressure Injection Exam Category C-F-I See Paragraph "E" I See Paragraph "H" I See Paragraph "I" I See Paragraph "L" System Item Number C05.021.051 Pipe to Valve 3HP-194 Fig. IWC-2500-7(a) Weld 35.55% Volume Coverage (circumferential weld) Limited Scan of Examination Volume C-D-E-F High Pressure Injection Exam Category C-F-I See Paragraph "F' See Paragraph "H" See Paragraph "I" See Paragraph "L" System Item Number C05.021.076 Flange to Pipe Weld Fig. IWC-2500-7(a) (circumferential weld) 58% Volume Coverage Limited Scan of Examination Volume C-D-E-F _ High Pressure Injection Exam Category C-F-I See Paragraph "G" See Paragraph "H" See Paragraph "I" See Paragraph "L" System Item Number C05.021.091 Elbow to Pipe Weld Fig. IWC-2500-7(a) (circumferential weld) 87.38% Volume Coverage Limited Scan of Examination Volume C-D-E-F See Attachment A for B03.110 area/weld locations. See Attachment B for B03.150 area/weld locations. See Attachment C for inspection data on all items listed in the above table for this Relief Request. Note: Items in this relief request were inspected during one of the following months: July, October, or November of 2004.
Relief Request 05-ON-001 Page 4 of 8 IV. & V. Impracticalitv/Burden Caused by Code Compliance Paragraph A: (The Pressurizer Sensing Sampling Nozzle material is SA508 Grade B and the Pressurizer Heater Belt material is SA516 Grade 70. This weld has a diameter of 5.75 inches and a wall thickness of 6.187 inches.) During the ultrasonic examination of the Sensing Sampling Nozzle to Heater Belt weld, 25% coverage of the required examination volume was obtained for this weld. The percentage of coverage reported represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 scan perpendicular and parallel to the weld covered 28% of the weld and base material; 600 scan perpendicular and parallel to the weld covered, 30% of the weld and base material. The weld joint geometry, which is essentially a branch connection arrangement using a set-in nozzle, prevented scanning from both sides of the weld. In order to scan all of the required volume for these welds, the sensing sampling nozzle would have to be redesigned to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld. Paragraph B: (The Letdown Cooler Inlet/Outlet Nozzles and Channel Head material is SA182 Grade T316L. These welds have a diameter of 3.0 inches and a wall thickness of .875 inches.) During the ultrasonic examination of the Inlet/Outlet Nozzles to Channel Head welds, 29% coverage of the required examination volume was obtained for each of the welds. The percentage of coverage reported represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 scan perpendicular and parallel to the weld covered 28% of the weld and base material; 600 scan perpendicular and parallel to the weld covered, 29% of the weld and base material. The weld joint geometry, which is essentially a branch connection arrangement using a set-on nozzle, prevented scanning from both sides of the welds. In order to scan all of the required surfaces for the inspection of these welds, the inlet/outlet nozzles would have to be redesigned to allow scanning from both sides of the welds, which is impractical. There were no recordable indications found during the inspection of theses welds. Paragraph C: (The Pipe and Lug material is carbon steel. This pipe has a diameter of 8.0 inches and a wall thickness of .500 inches. The four lugs are 1.5 inches thick and the welds are 1/4 inch fillet welds.) During the MT examination of the attachment welds on lugs for the component support, 50% coverage of the required examination surfaces was obtained. The percentage of coverage represents the aggregate coverage for all the examinations surfaces required to be examined. The limitations were due to limited access space that would not allow 2 of the attachment lugs to be examined. In order to examine all of the required surfaces for the inspection of these attachment lugs, the support would have to be redesigned to allow access for examining the attachment lugs or the piping rerouted to allow access, which is impractical. There were no recordable indications found during the inspection of the accessible lug welds. Paragraph D: (The pipe and elbow material is stainless steel. This weld has a diameter of 2.5 inches and a wall thickness of .375 inches.) During the ultrasonic examination of this weld, 87% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The 45° shear wave circumferential scans, both clockwise and counter-clockwise covered 100% of the examination volume and the 60° shear wave axial scan covered 48% from the pipe side of the weld. A supplemental 700 shear wave scan covered 22% of the examination volume in one axial direction from the pipe side of the weld. Limitations were caused by elbow configuration which prevented scanning from that side. In order to scan all of the required volume for this weld, the elbow would have to be redesigned to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld. Paragraph E: (The valve and pipe material is stainless steel. This weld has a diameter of 4.0 inches and a wall thickness of .674 inches.) During the ultrasonic examination of this weld, 35% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 47% of the examination volume and the 600 shear wave axial scan covered 47% of the examination volume from one direction.
Relief Request 05-ON-001 Page 5 of 8 A supplemental scan using a 600 refracted longitudinal wave search unit covered 52.6% of the examination volume including 100% of the inside surface within the area of interest. The limitation was caused by the taper on the valve side of the weld which prevented scanning from that side. In order to scan all of the required surfaces for the inspection of this weld, the valve would have to be redesigned to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld. Paragraph F: (The flange and pipe material is stainless steel. This weld has a diameter of 4.0 inches and a wall thickness of .531 inches.) During the ultrasonic examination of this weld, 58% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 100% of the examination volume and the 60° shear wave axial scan covered 32% of the examination volume from the elbow side. The limitation was caused by the taper on the flange side of the weld which prevented scanning from that side. In order to scan all of the required surfaces for the inspection of this weld, the flange would have to be redesigned to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld. Paragraph G: (The pipe and elbow material is stainless steel. This weld has a diameter of 2.5 inches and a wall thickness of .375 inches.) During the ultrasonic examination of this weld, 87% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The 45° shear wave circumferential scans, both clockwise and counter-clockwise covered 100% of the examination volume and the 600 shear wave axial scan covered 48%. A supplemental 70° shear wive scan covered 22% of the examination volume in one axial direction from the pipe side. Limitations were caused by elbow configuration which prevented scanning from that side. In order to scan all of the required surfaces for the inspection of this weld, the elbow would have to be redesigned to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld. VI. Proposed Alternate Examinations or Testing Paragraph II: The scheduled 10-year code examination was performed on the referenced area/weld and it resulted in the noted limited coverage of the required ultrasonic volume. These inspections were performed during the last inspection outage of the interval; no additional examinations are planned for the area/weld during the current inspection interval. VII. Implementation Schedule and Duration Paragraph I The scheduled third 10-year interval plan code examination was performed on the referenced areas/welds resulting in limited scan and volumetric coverage. No additional examinations are planned for the areas/welds during the current inspection interval. The same areas/welds may be examined again as part of the next (fourth) 10-year interval plan, depending on the applicable code year edition and addenda requirements adopted in the future. VIll. Justification for Granting Relief Paragraph J: Ultrasonic examination of areas/welds for item number B03.1 10 and B03.150 were conducted using personnel, qualified in accordance with ASME Section XI, Appendix VII of the 1995 Edition with the 1996 Addenda. The ultrasonic procedures used complied with the requirements of ASME Section V, Article 4, 1989 Edition with no addenda. Although 100% coverage of the examination volume could not be achieved, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity.
Relief Request 05-ON-001 Page 6 of 8 Duke Energy will use Class 1, Examination Category B-P, pressure testing and VT-2 visual examination to compliment the limited scan examinations. The Code requires that a pressure test be performed after each refueling outage for Class 1. These tests require a VT-2 visual examination for evidence of leakage. This testing provides adequate assurance of pressure boundary integrity. In addition to the above Code required examinations (volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through these welds, it would be detected and isolated. Specifically, leakage from these welds would be detected by monitoring of the Reactor Coolant System (RCS), which is performed once each shift under procedure PT/31A/0600/10, "RCS Leakage". This RCS leakage monitoring is a requirement of Technical Specification 3.4.13, "Reactor Coolant System Leakage". Any leakage is also evaluated in accordance with this Technical Specification. The leakage could also be detected through several other methods. One method is the Reactor Building air particulate monitor. This monitor is sensitive to low leak rates; the iodine monitor, gaseous monitor and area monitor are capable of detecting any fission products in the coolant and will make these monitors sensitive to coolant leakage. A second is the level indicator in the Reactor Building normal sump. A third is a loss of level in the Letdown Storage Tank. Based on the results of the required volumetric, surface and VT-2 examinations performed during this outage, it is Duke's belief that this combination of examinations provides a reasonable assurance of component integrity. Paragraph K: MT examination of the support attachment welds for item number C03.020.017 were conducted using personnel, qualified in accordance with paragraph IVA-2300 of the 1989 Edition with no addenda, ASME Section XI Code. The examination procedure was demonstrated using the remote camera equipment and the 1/32 inch black line on an 18% neutral gray card. Although 100% of the required examination surfaces could not be examined, the amount of surface that was examined provides an acceptable level of quality and integrity. In addition to the MT examinations with limited coverage, Duke Energy performed a supplemental Visual VT-1 examination on the welds of the 2 lugs that were not accessible for MT and achieved 100% coverage. The results from the Visual VT-1 examinations were acceptable. (See Paragraph M for additional justification.) Duke Energy has examined the support referenced in this request to the maximum extent possible utilizing the latest in examination techniques and equipment. Based on the inspections coverage and results of the required MT exam this outage and the supplemental VT-1 exam on the inaccessible lugs, it is Duke's belief that this examination provides a reasonable assurance of component integrity. Paragraph L: Ultrasonic examination of areas/welds for the item numbers C05.021 were conducted using personnel, equipment and procedures qualified in accordance with ASME Section XI, Appendix VIII Supplement 2 of the 1995 Edition with the 1996 Addenda as administered by the PDI. Although 100% coverage of the examination volume could not be achieved, the amount of coverage obtained for each of these welds provides an acceptable level of quality and integrity. In addition to the volumetric examinations with limited coverage, Duke Energy performed a surface examination (code required) on each of the C05.021 items and achieved 100% coverage. The results from the surface examinations were acceptable. (See Paragraph M for additional justification for all C05.021 items except for C05.021.076.) (For item C05.021.076 see Paragraph N for additional justification) In addition to the C05.021 welds that relief is being requested for limited scanning, there were 13 additional C05.021 welds that surface and volumetric examinations were performed on. The examinations didn't identify any recordable indications and 100% coverage was obtained on each of the 13 welds. The 13 additional welds were from the same system as the C05.021 welds of this request.
Relief Request 05-ON-001 Page 7 of 8 Duke Energy Corporation does not claim credit for coverage of the far side of austenitic welds. The characteristics of austenitic weld metal attenuate and distort the sound beam when shear waves pass through the weld. Refracted longitudinal waves provide better penetration but cannot be used beyond the first path leg. Duke Energy Corporation uses a combination of shear waves and longitudinal waves to examine single sided austenitic welds when the nominal material thickness exceeds 0.5 inch. A 70° shear wave angle beam is used to interrogate the far side of the weld when the nominal material thickness is equal to or less than 0.5 inch and a 600 refracted longitudinal wave is used to interrogate the far side of the weld when the nominal material thickness is greater than 0.5 inch. Paragraph M: Duke Energy will use Class 2, Examination Category C-H, pressure testing and VT-2 visual examination to compliment the limited examination coverage. The Code requires that a pressure test be performed once each period for Class 2 items. These tests require a VT-2 visual examination for evidence of leakage. This testing provides adequate assurance of pressure boundary integrity. In addition to the above Code required examinations (volumetric, surface and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through these welds, it would be detected and isolated. Specifically, leakage from these welds would be detected by monitoring of the Reactor Coolant System (RCS), which is performed once each shift under procedure PT/3/A/0600/10, "RCS Leakage". This RCS leakage monitoring is a requirement of Technical Specification 3.4.13, "Reactor Coolant System Leakage". Any leakage is also evaluaited in accordance with this Technical Specification. The leakage could also be detected through several other methods. One method is the Reactor Building air particulate monitor. This monitor is sensitive to low leak rates; the iodine monitor, gaseous monitor and area monitor are capable of detecting any fission products in the coolant and will make these monitors sensitive to coolant leakage. A second is the level indicator in the Reactor Building normal sump. A third is a loss of level in the Letdown Storage Tank. Based on the results of the required volumetric, surface and VT-2 examinations performed during this outage, it is Duke's belief that this combination of examinations provides a reasonable assurance of component integrity. Paragraph N: Duke Energy will use Class 2, Examination Category C-H, pressure testing and VT-2 visual examination to compliment the limited examination coverage. The Code requires that a pressure test be performed once each period for Class 2 items. These tests require a VT-2 visual examination for evidence of leakage. This testing provides adequate assurance of pressure boundary integrity. In addition to the above Code required examinations (volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely case that leakage did occur through this weld, it would be detected and isolated. One is that leakage from these welds would be detected by Operations personnel during their regular rounds (reference procedure OP/3/A/1 102/020A "Primary Rounds"). The Nuclear Equipment Operator has been trained to look for any unusual conditions, such as leaks. In addition, the procedure addresses leaks as being an item to consider during rounds. The C05.021 item in this request is located in an area where operations personnel will be walking through as part of their rounds; therefore, any leak would be identified by visual observation. Duke Energy has examined the welds/components referenced in this request to the maximum extent possible utilizing the latest in examination techniques and equipment. The welds/components identified in Section II of this request were rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the coverage and results of the required volumetric exams and surface exams this outage and the pressure testing (VT-2) exams, it is Duke's belief that this combination of examinations provides a reasonable assurance of component integrity.
Relief Request 05-ON-001 Page 8 of 8 IX. Other Information The following individuals contributed to the development of this relief request: James J. McArdle (Principal UT NDE Level III Examiner) provided Sections III., IV., V., and part of Section VIII. B. W. Carney, Jr. (Oconee Engineering) provided part of Section VIII. Larry C. Keith (Oconee ISI Plan Manager) compiled the remaining sections. Sponsored By: (4Co)a Date f~ 3 - -aoo5 Approved By: of-fe- t.. -- Date
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ATTACHMEN] C UT Vessel Examination PAGE ( OF 76 Site/Unit: Oconee / 03 Procedure: NDE-640 Outage No.: ONS3EOC21 Summary No.: Bo3.110.009 Procedure Rev.: 2 Report No.: UT-04-470 Workscope: ISI Work Order No.: 98641456 Page: 1 of 1 Code: Asme Section XI 1989 Cat./ltem: B-D-/B3.110.9 Location: N/A Drawing No.: ISI-OCN3-002
Description:
Nozzle to To Shell System ID: 50 Component ID: B03.110.009 /3-PZR-WP26-1 Size/Length: N/A Thickness/Diameter: 6.187'/5.75" Limitations: See limitation calculations on report UT-04471. Start Time: 1115 Finish Time: 1120 Examination Surface: Inside a Outside R Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 72 OF Cal. Report No.: CAL-04-735 Angle Used l 0 45 l45Tl 60 60T l Scanning dB 39 Indication(s): Yes a No i Scan Coverage: Upstream i Downstream i CW i CCW i Comments: FC 03-20 Results: Accept R Reject E] Info _ Percent Of Coverage Obtained > 90%: No - 25.927% Reviewed Previous Data: Yes Examiner Level Il-N g r Date Reviewer 1 Signature Date Mauldin, Larry E. 11/1(2004 , iq Og Examiner Level III Signature Date Site Review Signature Date Eaton, Jay A. 11/1/2004 'I Other Level N/A U' Signature Date ANII Review Signature A D Date N/A I7Af/ ii 44V
/ I
A11ACHMENT C PAGE x OF 16 UT Vessel Examination Site/Unit: Oconee I 03 Procedure: NDE-820 Outage No.: ONS3EOC21 Summary No.: s0 3.110.009 Procedure Rev.: 1 Report No.: UT-04-471 Workscope: iSI Work Order No.: 98641456 Page: I of 3 Code: Asme Section XI 1989 Cat/item: B-D-/B3.110.9 Location: N/A Drawing No.: ISI-OCN3-002
Description:
Nozzle to To Shell System ID: 50 Component ID: B03.110.009 /3-PZR-WP26.1 SizelLength: N/A Thickness/Diameter: 6.187"/5.75" Limitations: See attached limitation report. Start Time: 1121 Finish Time: 1131 Examination Surface: Inside z Outside j Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centeriine of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 72 OF Cal. Report No.: CAL-04-736, CAL-04-737 AngleUsed l0 45 l45T 60 l60T l l Scanning dB 70.2 70.2 84.6 84.6 Indication(s): YesE Nos Scan Coverage: Upstream DownstreamM3 CWR CCWlR Comments: FC 03-29, 03-31 Results: Accept i Reject a Info I_ Percent Of Coverage Obtained > 90%: No - 25.927% Reviewed Previous Data: Yes Examiner Level Il-N ture Date Reviewer Signature Date Mauldin, Larry E. 11/1/2004 Examiner Level IlIl / Signature Date Site Review Signature Date Eaton, Jay A. ( .l 11/1/2004 Other Level N/A Signature Date ANiI Review ' Signature Date N /A _ _ _ _ _ _ _ _ _ _ _ __
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PABE 3 DF 76 C AlEACIHMENT Nuke Limitation Record Site/Unit: Oconee / 03 Procedure: NDE-820 Outage No.: ONS3EOC21 ummary No.: B03.110.009 Procedure Rev.: 1 Report No.: UT.04-471 Workscope: ISI Work Order No.: 98641456 Page: 2 of 3 Description of Limitation: Limited 3600 from the weld edge and beyond due to blend radius and nozzle configuration. Aggregrate Coverage Angle Beam Dir. Base Metal Weld Agaregate 0 N/A 37.42% 0% 18.71% 45 Si 61.77% 44.14% 52.96% 45 S2 0% 0% 0% 45 CW 47.28% 13.1% 30.19% 45 CCW 47.28% 13.1% 30.19% 60 Si 72.03% 53.1% 62.57% 60 S2 0% 0% 0% 60 Cw 47.28% 13.1% 30.19% 60 CCW 47.28% 13.1% 30.19% Umitations removal requirements: N/A Radiation field: N/A
AT IACHMENr C PA6E BF 96 tbP1neuke Determination of Percent Coverage for V OWrg UT Examinations - Vessels Site/Unit: Oconee / 03 Procedure: NDE-820 Outage No.: ONS3EOC21 Summary No.: B03.110.009 Procedure Rev.: 1 Report No.: UT-04-471 Workscope: IS1 Work Order No.: 98641456 Page: 3 of 3 0 deg Planar Scan 100.000 % Length X 18.710 % volume of length /100 = 18.710 % total for 0 deg 45 deg Scan 1 100.000 % Length X 52.960 % volume of length / 100 = 52.960 % total for Scan 1 Scan 2 100.000 % Length X 0.000 % volume of length / 100 = 0.000 % total for Scan 2 Scan 3 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 3 Scan 4 100.000 % Length X 30.190 % volume of length /100 = 30.190 % total for Scan 4 Add totals and divide by # scans = 28.335 % total for 45 deg Other den 60 Scan 1 100.000 % Length X 62.570 % volume of length / 100 = 62.570 % total for Scan 1 Scan 2 100.000 % Length X 0.000 % volume of length / 100 = 0.000 % total for Scan 2 Scan 3 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 3 Scan 4 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 4 Add totals and divide by # scans = 30.738 % total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 25.927 % Total for complete exam Note: Supplemental coverage may be achieved by us of other angles / methods. When used, the coverage for volume not obtained with angles as noted above shall be c Iculated and added to the total to provide the percent total for the complete examination. Site Field Supervisor: ... _ Date: \ IJ. l
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AITACHMENT C PAGE IOQF '76 UT Vessel Examination Site/Unit: Oconee I 03 Procedure: NDE-640 Outage No.: ONS3EOC21 Summary No.: 80: 3.110.010 Procedure Rev.: 2 Report No.: _ UT-04-472 Workscope: 'SI Work Order No.: 98641456 Page: 1 of 1 Code: Asme Section XI 1989 Cat./Item: B-D-/B3.110.10 Location: N/A Drawing No.: ISI-OCN3-002
Description:
Nozzle to To Shell System ID: 50 Component ID: B03.110.010 13-PZR-WP26-2 Size/Length: N/A Thickness/Diameter: 6.187"/5.75" Limitations: See limitation calculations on report UT.04-473. Start Time: 1137 Finish Time: 1142 Examination Surface: Inside a Outside i Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 72 °F Cal. Report No.: CAL-04-735 Angle Used l0 45 45T 60 60T l Scanning dB 39 Indication(s): Yes E1 No i Scan Coverage: Upstream i Downstream id CWI CCWRJ Comments: FC 03-20 Results: Accept E Reject a Info __ Percent Of Coverage Obtained > 90%: No - 25.927% Reviewed Previous Data: Yes Examiner Level Il-N Si ature Date Reviewer Signature Date Mauldin, Larry E. 017,? 11/112004
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Examiner Level III Sig ature Date Site Review r Signature Date Eaton, Jay A. Tl.-k 1/1/2004 _ Other Level N/A Signature Date ANII Review Signature N/A ____________________________
A11ACHMENT C PAGE It DF ¶'7 An,. ke UT Vessel Examination 4Vr:eW Site/Unit: Oconee / 03 Procedure: NDE-820 Outage No.: ONS3EOC21 Summary No.: 803.110.010 Procedure Rev.: I Report No.: UT-04-473 Workscope: ISI Work Order No.: 98641456 Page: 1 of 3 Code: Asme Section Xi 1989 Cat./Item: B.D-183.110.10 Location: N/A Drawing No.: ISI-OCN3-002
Description:
Nozzle to To Shell System ID: 50 Component ID: B03.110.010 /3-PZR-WP26-2 Size/Length: N/A Thickness/Diameter: 3.187"/5.75" Limitations: See attached limitation report. Start Time: 1143 Finish Time: 1154 Examination Surface: Inside ] Outside i Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplai int: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 72 -F Cal. Report No.: CAL-04-736, CAL-04-737 Angle Used 0 1 45 1 45T 1 60 1 60T l Scanning dB l70.2 1 70.2 1 84.6 l 84.6 Indication(s): Yes E No i Scan Coverage: Upstream R) Downstream i CW i CCW 1R Comments: FC 03-29, 03-31 Results: Accept i Reject a Info Q] Percent Of Coverage Obtained > 90%: No - 25.927% Reviewed Previous Data: Yes
Al ALHMeENT C PAGE fALF 16 Dukie Limitation Record Site/Unit: Oconee / 03 Procedure: NDE-820 Outage No.: ONS3EOC21 Summary No.: B03.110.010 Procedure Rev.: 1 Report No.: UT-04-473 Workscope: ISt Work Order No.: 98641456 Page: 2 of 3 Description of Limitation: Limited 360 from the weld edge and beyond due to blend radius and nozzle configuration. Aggregrate Coverage Angle Beam Dir. Base Metal Weld Aggregate 0 N/A 37.42% 0% 18.71% 45 Si 61.77% 44.14% 52.96% 45 S2 0% 0% 0% 45 CW 47.28% 13.1% 30.19% 45 CCW 47.28% 13.1% 30.19% 60 SI 72.03% 53.1% 62.57% 60 S2 0% 0% 0% 60 CW 47.28% 13.1% 30.19% 60 CCW 47.28% 13.1% 30.19% Limitations removal requirements: NIA Radiation field: NIA
A11ACHMENT C P011Lukej~ Determination of Percent Coverage for PAGE /3 OF 76 UT Examinations - Vessels Site/Unit: Oconee / 03 Procedure: NDE-820 Outage No.: ONS3EOC21 Summary No.: B03.110.010 Procedure Rev.: 1 Report No.: UT-04-473 Workscope: [Si Work Order No.: 98641456 Page: 3 of 3 0 den Planar Scan 100.000 % Length X 18.710 % volume of length /100 = 18.710 % total for 0 deg 45 deg Scan 1 100.000 % Length X 52.960 % volume of length /100 = 52.960 % total for Scan 1 Scan 2 100.000 % Length X 0.000 % volume of length / 100 = 0.000 % total for Scan 2 Scan 3 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 3 Scan 4 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 4 Add totals and divide by # scans = 28.335 % total for 45 deg Other deg 60 Scan 1 100.000 % Length X 62.570 % volume of length / 100 = 62.570 % total for Scan 1 Scan 2 100.000 % Length X 0.000 % volume of length / 100 = 0.000 % total for Scan 2 Scan 3 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 3 Scan 4 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 4 Add totals and divide by # scans = 30.738 % total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 25.927 % Total for complete exam Note: Supplemental coverage may be achieved by yse of other angles / methods. When used, the coverage for volume not obtained with angles as noted above shall be alculated and added to the total to provide the percent total for the complete examination. Site Field Supervisor: :M.- Date: \\ \ I I lOS
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AITACHMENT C PAGE /7If F 9'6 UT Vessel Examination Site/Unit: Oconee / 03 Procbdure: NDE-640 Outage No.: ONS3EOC21 Summary No.: B03.110.011 Procedure Rev.: 2 Report No.: UT-04-474 Workscope: ISI Work Order No.: 98641456 Page: 1 of I Code: Asme Section Xl 1989 Cat./ltem: B-D-/B3.110.11 Location: N/A Drawing No.: ISI-OCN3-002
Description:
Nozzle to To Shell System ID: 50 Component ID: B03.110.011 /3-PZR-WP26-3 Size/Length: N/A Thickness/Diameter: 6.187"/5.75" Limitations: See limitation calculations on report UT-04-475. Start Time: 1204 Finish Time: 1208 Examination Surface: Inside a Outside Mv Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 72 OF Cal. Report No.: CAL-04-735 Angle Used l45 1 45T1 601 60T I I Scanning dB E I I I I Indication(s): Yes [-1 No Ail Scan Coverage: Upstream 6Z Downstream 0 CW2 CCWg Comments: FC 03-20 Results: Accept i Reject C Info al Percent Of Coverage Obtained > 90%: No - 25.927% Reviewed Previous Data: Yes
A11ACHMENT C PAGEaO OF 76
*,irke UT Vessel Examination .WrneW Site/Unit: Oconee / 03 Procedure: NDE-820 Outage No.: ONS3EOC21 Summary No.: B0 3.110.011 Procedure Rev.: 1 Report No.: UT-04-475 Workscope: 'SI Work Order No.: 98641456 Page: 1 of 3 Code: Asme Section Xl 1989 Cat./Item: B-D-/B3.110.11 Location: N/A Drawing No.: ISI-OCN3-002
Description:
Nozzle to To Shell System ID: 50 Component ID: B03.110.011 /3-PZR.WP26.3 Size/Length: N/A Thickness/Diameter. 6.1887"/5.75" Limitations: See attached limitation report. Start Time: 1213 Finish Time: 1233 Examination Surface: Inside Q Outside r3 Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 72 *F Cal. Report No.: CAL.04-736, CAL-04-737 AngleUsed l0 45 l45T 60 l60T l l Scanning dB 70.2 70.2 84.6 84.6 Indication(s): YesE No } Scan Coverage: Upstream 2 Downstreami CWR CCWR Comments: FC 03-29, 03-31 Results: Accept i Reject IInfo a Percent Of Coverage Obtained > 90%: No - 25.927% Reviewed Previous Data: Yes Examiner Level Il.N S aJre Date Review Signature Date Mauldin, Larry E. rZ W!' & 1111/2004 -O Examiner Level IlIl Signature Date Site Review y / Signature Date Eaton, Jay A. 11/1/2004 I Other Level N/A Signature Date ANII Revi Signature Date N/AR e i v
AT 1AL1 j1L19i C PA6E ;/ JJF 76 Limitation Record Site/Unit: Oconee 1 03 Procedure: NDE-820 Outage No.: ONS3EOC21 Summary No.: B03.110.011 Procedure Rev.: 1 Report No.: UT-04-475 Workscope: ISI Work Order No.: 98641456 Page: 2 of 3 Description of Limitation: Limited 360° from the weld edge and beyond due to blend radius and nozzle configuration. Aggregrate Coverage Angle Beam Dir. Base Metal Weld Aggregate 0 N/A 37.42% 0% 18.71% 45 SI 61.77% 44.14% 52.96% 45 S2 0% 0% 0% 45 CW 47.28% 13.1% 30.19% 45 CCW 47.28% 13.1% 30.19% 60 Si 72.03% 53.1% 62.57% 60 S2 0% 0% 0% 60 CW 47.28% 13.1% 30.19% 60 CCW 47.28% 13.1% 30.19% Limitations removal requirements: NIA Radiation field: NIA Examiner Level ii. ig e Date Review A Signature Date Mauldin, Larry E. 11112004 Q //- 0-ot Examiner Level l l ignature Date Site Review ) Signature Date Eaton, Jay A. F 11/112004 ONtAer Level NIA ' Signature Date ANII l Signature Date N/A d~ITE
Determination of Percent Coverage for PAGE 1aa OF 9rEnergy. UT Examinations - Vessels Site/Unit: Oconee / 03 Procedure: NDE-820 Outage No.: ONS3EOC21 Summary No.: B03.110.011 Procedure Rev.: 1 Report No.: UT-04*475 Workscope: ISI Work Order No.: 98641456 Page: 3 of 3 0 deg Planar Scan 100.000 % Length X 18.710 % volume of length / 100 = 18.710 % total for 0 deg 45 deg Scan 1 100.000 % Length X 52.960 % volume of length /100 = 52.960 % total for Scan 1 Scan 2 100.000 % Length X 0.000 % volume of length / 100 = 0.000 % total for Scan 2 Scan 3 100.000 % Length X 30.190 % volume of length /100 = 30.190 % total for Scan 3 Scan 4 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 4 Add totals and divide by # scans = 28.335 % total for 45 deg Other deg 60 Scan 1 100.000 % Length X 62.570 % volume of length / 100 = 62.570 % total for Scan 1 Scan 2 100.000 % Length X 0.000 % volume of length I 100 = 0.000 % total for Scan 2 Scan 3 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 3 Scan 4 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 4 Add totals and divide by # scans = 30.738 % total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 25.927 % Total for complete exam Note: Supplemental coverage may be achieved by use of other angles / methods. When used, the coverage for volume not obtained with angles as noted above shall be alculated and added to the total to provide the percent total for the complete examination. I Site Field Supervisor: __ Date: Cll
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*D, ke UT Vessel Examination Inew.
Site/Unit: Oconee / 03 Procedure: NDE-640 Outage No.: ONS3EOC21 Summary No.: BO3.110.012 Procedure Rev.: 2 Report No.: UT-04-476 Workscope: ISI Work Order No.: 98641456 Page: 1 of I Code: Asme Section Xl 1989 Cat/Item: B-D-/B3.110.12 Location: N/A Drawing No.: ISI-OCN3-002
Description:
Nozzle to To Shell System ID: 50 Component ID: B03.110.012 /3-PZR-WP26-7 Size/Length: N/A Thickness/Diameter: 6.187'/5.75' Limitations: See limitation calculations on report UT.04-477. Start Time: 1209 Finish Time: 1212 Examination Surface: Inside a Outside i Surface Condition: AS GROUND Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 72 OF Cal. Report No.: CAL.04-735 Angle Used l 0l 45 45T 60 60T l Scanning dB 39 Indication(s): Yes 5 No W Scan Coverage: Upstream i Downstream 2 CW i CCW i Comments: FC 03-20 Results: Accept i Reject a Info a_ Percent Of Coverage Obtained > 90%: No - 25.927% Reviewed Previous Data: Yes Examiner Level Il-N CS.ari r Date Reviewer 1,,.ao Signature Date Mauldin, Larry E. 11/1/2004 / //. 9.-O Examiner Level ill Signature Date Site Review Signature Date Eaton, Jay A. (By11/1/2004 Other Level N/A I Signature Date ANII Review . Signature Date N/A _ _ _ _ _ _ _ _ _ _ __ __ __ _ 7 /1
AtIACHMENT C PAGE k7OF % UT Vessel Examination Site/Unit: Oconee / 03 Procedure: NDE-820 Outage No.: ONS3EOC21 Summary No.: B03.110.012 Procedure Rev.: - 1 Report No.: UT-04-477 Workscope: ISI Work Order No.: 98641456 Page: 1 of 3 Code: Asme Section XI 1989 Cat./Item: B-D- /B3.110.12 Location: N/A Drawing No.: ISI-OCN3-002
Description:
Nozzle to To Shell System ID: 50 Component ID: B03.110.012 /3-PZR-WP26-7 Size/Length: N/A Thickness/Diameter: 6.187"/5.75" Limitations: See attached limitation report. Start Time: 1219 Finish Time: 1240 Examination Surface: Inside L Outside 0 Surface Condition: Lo Location: 9.2.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 72 °F Cal. Report No.: CAL-04-736. CAL-04-737 Angle Used 45 145T1 60 160T I { Scanning dB 70.2 70.2 84.6 84.6 1 Indication(s): Yes [] NoR Scan Coverage: Upstream i] Downstream i CWRI CCWqJ Comments: FC 03-29, 03-31 Results: Accept 0 Reject z Info E Percent Of Coverage Obtained > 90%: No - 25.927% Reviewed Previous Data: Yes
ATTACHMENT C PAGE ad OOF 76 Limitation Record Site/Unit: Oconee / 03 Procedure: NDE-820 Outage No.: ONS3EOC21 summary No.: 803.110.012 Procedure Rev.: 1 Report No.: UT-04-477 Workscope: ISI Work Order No.: 98641456 Page: 2 of 3 Description of Limitation: Limited 360° from the weld edge and beyond due to blend radius and nozzle configuration. Aggregrate Coverage Angle Beam Dir. Base Metal Weld Aggregate 0 N/A 37.42% 0% 18.71% 45 SI 61.77% 44.14% 52.96% 45 S2 0% 0% 0% 45 CW 47.28% 13.1% 30.19% 45 CCW 47.28% 13.1% 30.19% 60 SI 72.03% 53.1% 62.57% 60 S2 0% 0% 0% 60 CW 47.28% 13.1% 30.19% 60 CCW 47.28% 13.1% 30.19% Limitations removal requirements: WA Radiation field: N/A Examiner Level Il-N i re Date Review Signature Date Mauldin, Larry E. 1111/2004 0 1// 9 Examiner Level iI Signature Date Site Review Signature Date Eaton, Jay A. 11/112004
'ther Level N/A Signature Date ANI Revie Signature Date
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AIIACHMENT C PAGE 310F (7(. Determination of Percent Coverage for
&guy. UT Examinations - Vessels Site/Unit: Oconee / 03 Procedure: NDE-820 Outage No.: ONS3EOC21 Summary No.: B03.110.012 Procedure Rev.: 1 Report No.: UT-04-477 Workscope: ISI Work Order No.: 98641456 Page: 3 of 3 0 deg Planar Scan 100.000 % Length X 18.710 % volume of length / 100 = 18.710 % total for 0 deg 45 deg Scan 1 100.000 % Length X 52.960 % volume of length / 100 = 52.960 % total for Scan 1 Scan 2 100.000 % Length X 0.000 % volume of length /100 = 0.000 % total for Scan 2 Scan 3 100.000 % Length X 30.190 % volume of length /100 = 30.190 %total for Scan 3 Scan 4 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 4 Add totals and divide by # scans = 28.335 % total for 45 deg Other deg 60 Scan 1 100.000 % Length X 62.570 % volume of length / 100 = 62.570 % total for Scan 1 Scan 2 100.000 % Length X 0.000 % volume of length / 100 = 0.000 % total for Scan 2 Scan 3 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 3 Scan 4 100.000 % Length X 30.190 % volume of length / 100 = 30.190 % total for Scan 4 Add totals and divide by # scans = 30.738 % total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 25.927 % Total for complete exam Note:
Supplemental coverage may be achieved by us of other angles I methods. When used, the coverage for volume not obtained with angles as noted above shall be c culated and added to the total to provide the percent total for the complete examination. Site Field Supervisor: -L D Date: It I I I OI I-- I I
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ATtACHMENT C PAGE 37UF 96 1^ ftk UT Vessel Examination adw. Site/Unit: Oconee / 03 Procedure: NDE-630 Outage No.: ONS3EOC21 Summary No.: BO:3.150.003 Procedure Rev.: 2 Report No.: UT-04-487 Workscope: 'SI Work Order No.: 98641451 Page: I of 2 Code: Asme Section XI 1989 Cat./item: B-D- /B3.150.3 Location: NIA Drawing No.: 1-44773-1
Description:
Nozzle to Channel Body System ID: 51A 3.0or Component ID: B03.150.003 /3-LDCB-IN-V1 Size/Length: N/A Thickness/Diameter: .875"48.e2 "I 4 Limitations: None Start Time: 0815 Finish Time: 0847 Examination Surface: Inside El Outside W Surface Condition: AS GROUND Lo Location: 9.2.2 Wo Location: Centerline of Weld Coupla:nt: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE 27220 Surface Temp.: 74 OF Cal. Report No.: CAL-04-741, CAL-04-742, CAL-04-743 Angle Used 0 45 l 45T 1 60 l 60T 7 45RL l Scanning dB 45.0 45.0 7 70.5 1 , 66.5 Indication(s): Yes El NoR Scan Coverage: Upstream i Downstream EJ CWR CCWP1 Comments: Results: Accept i Reject E] Info C Scanning dB's less than ref +14 to obtain 2:1 signal to noise ratio. Percent Of Coverage Obtained > 90%: No - 29.263% Reviewed Previous Data: Yes Examiner Level I ature Date Reviewers 4 A Signature Date Resor, James H. 11/4/2004 //(c/,aa -/ Examiner Level Il-N nature Date SiteReview 61l Signature Date Jones, Russel 11/4/2004 _ Other Level N/A Signature Date ANII Re iew , Sig.p)ture Date N/A t6 / I///f /0
AlTIACHMENT C rDPuke Determination of Percent Coverage for PASE3S OF I7 rEnergy4 UT Examinations - Vessels Site/Unit: Oconee / 03 Procedure: NDE-630 Outage No.: ONS3EOC21 Summary No.: B03.150.003 Procedure Rev.: 2 Report No.: UT-04-487 Workscope: ISI Work Order No.: 98641451 Page: 2 of 2 0 deg Planar Scan % Length X % volume of length 100 = % total for 0 deg 45 deg Scan 1 100.000 % Length X 35.900 % volume of length /100 = 35.900 % total for Scan 1 Scan 2 100.000 % Length X 15.600 % volume of length / 100 = 15.600 % total for Scan 2 Scan 3 100.000 % I Length X 31.400 % volume of length / 100 = 31.400 % total for Scan 3 Scan 4 100.000 % I Length X 31.400 % volume of length / 100 = 31.400 % total for Scan 4 Add totals and divide by # scans = 28.575 % total for 45 deg Other deg 60 Scan 1 100.000 % Length X 46.600 % volume of length / 100 = 46.600 % total for Scan 1 Scan 2 100.000 % Length X 10.400 % volume of length /100 = 10.400 % total for Scan 2 Scan 3 100.000 % Length X 31.400 % volume of length / 100 = 31.400 % total for Scan 3 Scan 4 100.000 % Length X 31.400 % volume of length / 100 = 31.400 % total for Scan 4 Add totals and divide by # scans = 29.950 % total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 29.263 % Total for complete exam Note: Supplemental coverage may be achieved b use of other angles / methods. When used, the coverage for volume not obtained with angles as noted above shall b calculated and added to the total to provide the percent total for the complete examination. Site Field Supervisor: XDate:llgjot
A1IACHMENII C PA6E31 OF 96 DUKE POWER COMPANY I ULTRASONIC BEAM ANGLE MEASUREMENT RECORD I 1?>O5Z'. 1'o. O3
- 1. Take thickness measurements between wedge locations.
- 2. Place search unit on straight run of pipe, and peak the signal.
- 3. Measure distance (d) between exit t points.
. I
- 4. Calculate beam angle with formula tan + = (d/2) as shown using measured wall t thickness.
- 5. Use the measured beam angle to determine coverage and when plotting any indications.
Pipe size: - .OG troz) For thin wall pipe use 2nd Vee path Pipe -Schedule: tan = (d/2 2t Nominal 45 deg: d=_' .70;t- .. ;875.; measured angle= 44.1deg Nominal 60 deg: d= A__; t= ; measured angle= SIM deg Nominal 70 deg: d=-_ _; t=-..; measured angle=--deg Examiner Level Date Examiner Level Date Aw 4o lz //--/-et Reviewe Level Date AuthpzedInspector Date (1 AHeXB/ j/ - Ad, Lt,evel
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A1tACHMENT C PAGE s0OF 96 DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID: 3-LDCB-INLET-VI Item No: B03.150.003 remarks: E NO SCAN SURFACE BEAM DIRECTION Due to branch conn. config. E LIMITED SCAN E 1 E 2 Z 1 0 2 E cw E cow FROM L N/A to L N/A INCHES FROM WO .5" to Beyond ANGLE: E 0 E 45 0 60 other FROM 0 DEG to 360 DEG l NO SCAN SURFACE BEAM DIRECTION Due to branch conn. config. E LIMITED SCAN E 1 E2 l 2 0 cw c w cow FROM L _ to L INCHES FROM WO .5" to Beyond ANGLE: E 0 El 45 ED 60 other FROM 0 DEG to 360 DEG El NO SCAN SURFACE BEAM DIRECTION E LIMITED SCAN E 1 2 E 1 E 2 E cw E ccw FROM L to L INCHES FROM WO to _ ANGLE: El 0 E 45 a 60 other FROM DEG to DEG E NO SCAN SURFPXCE BEAM DIRECTION El LIMITED SCAN 0 1 Ij~2 E 1 2 2E cw E cCw to LoE_ INCHES FROM WO to Sketch(s) attached FROM L other FROM DEG to DEC2 E yes E No ANGLE: MO El 445 F 60
,red By: James H. Resor C I
AIIALJnMtnU L PAGE 1 OF 76 Supplem :al Report Report No.: pokrtergy Page: 2_ of -14 S10I Summary No.: 03 . 16D . oc3 Level: , Reviewer: Date:, I\ .Ž4 Examiner: Date: Level: Site Review: Examiner: Level: ANII Review: a ~Date: 2E//O Other: -,C - AA /. CLL-U<QZ Ut-=D rD DE.fEZNM¶U-Comments: AJP2tARt^E OF5 tzvA AE.AS ODP
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ATTACHMENT C PAGE4qaF 76 Supplemr .al Report Report No.: PEk 'g Page: _5 of IL Summary No.: 3 (D) - k5-0. C)0 3 - Examiner: Level: - Reviewer: - Date:It)o f
-11, 911L-1 Site Review:
4 11L Examiner: Level: Date: Other: Level: - ANII Review - Date: /1////by 6 /L. p Comments:
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AtIACHMENT C Supplemi al Report Report No.: PAGE ZA30F 16 pVk01eer *y Page: 4 of Iv4 Summary No.: YI.V5D. L-3 /, I Examiner: Level: Reviewer: ( hL;= \ - Date: ' C Examiner: Level: Site Review: l Date: Other: - Level: ANII Review: djc 'Date: /1/A $,, Comments: )i5° 4aLIAI5C2AN0 +/- 3 - LbC, - T eV -VI laQrer 0alAs6 Sketch or Photo: g pe~ (. - ~s n;), 7\-( 7
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AtIACHMENT C Pk k Supplem al Report PAGE 4CGF '76 Udkhnerg Report No.: Page: .5 of 1t4 Summary No.: $O3.t03.O-oo3 Examiner: Level: 2 Reviewer: Lg Date: _________ Examiner: Level: Site Review: 11 VDate: Other: Level: ANII Review: zjt acf 7C -/ f~ Date: A///// Comments: 3- LDCZ - :r LEr-V1 45D A v~t, amt ZL Sketch or Photo: AmC' (1 A. :)3 ).-
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ATTACHMENT C
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PAGE cfl~f 96 Vk11Lasergy Page: (p of I Summary No.: Go~DL. LC6. b D-n Examiner: !<~ 6124(7 Level: ef Reviewer: -ib~ Date: ____ _ Examiner: Level: . Site Review: V/ Date: Other: Level: ANII Review: 1V* Date: 2t//1/OC C, Comments: 3 - LID C- - En LET - V 1 (DOC e4 Gust4 i Sketch or Photo: (-) I ,3 _ $r elpl A: (,S t t-'~ i-')S-75 " A 2=
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ATIACHMENT C PABE /6 OF 6 SupplemL at Report oew. Report No.: Page: *7 of 1 Summary No.: 1303.15-6. D6.3 /,-A I Examiner: Level: %7 Reviewer: ( BU = Date: 4' Examiner: (11 r--I Level: Site Review: I Date: Other: Level: ANII Review: Date: Comments: 3-L-bC - hLEtr -V l (0o0, AfhwLt 62spJ L-AQA Cg GiQ-Ai, Sketch or Photo:
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G 4As Examiner: - Level: Site Review: VI Date: Other: Level: ANII Review: C." Date: / /: z/ C-Comments: - LDO-C-fJL.t-VX QCY2Zct CvJEA6E ClabXa' 667ssol .;~~se-Sketch or Photo: I1.o
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AT TACHMENI Supplem( al Report PA6E %70aF 76 Report No.: FVbie, Page: I( of IA Summary No.: JZo3. P6 . 6D-3 Examiner: Level: A Reviewer: Date: 1lill.DIQ I L--1-1 0 1 A I Examiner: L Level: Site Review. Date: Other: Level: ANII Review: 6/(- - Date: Comments: 3 - L DC4Z - Lk.Fr - V I d 65°OtY £P I. Agev riP&,JeCQM1i Sketch or Photo: A P.)': *-" V-' 1- , 2-7 .n SC'D I ?-t - .1 5 1z% ES.F z * =.{ i 16 Aa~rsk . S5(o, I
ATTACHMENT C PAES6 OF q6 ike Supplem, gal Report Report No.: FVEnergy Page: I Iof 14! Summary No.: iio05 igb .on3 Examiner: i -- Level: ff Reviewer: M-IZ I: Date: Il_ _v_ 4 Examiner: Level: Site Review: Date: Other: Level: ANII Review: Date: =///ay 6' Comments: 45* 0 mU<ePrAr L 41atrC-: I -I Y .$J = . adTs L t Sketch or Photo: AZ: I it)
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AttACHMENT C Supplemr 'al Report PAS E SI OF ?6 Report No.: Co-VkWW *0 Page: 12, of 14 Summary No.: Bo3. 5IO. c03 Examiner: Level: Reviewer: liTc Date: C'2 Examiner: - Level: Site Review: 9 Date: Other: Level: ANII Review: I j{4 4 ZE Date: ____ C,. - Comments: 3 -L o - ZrLeri -V/ 0,00l fhl-m 6CAIJ -i i- 2= of~ Ad Sketch or Photo: 6:'A I<,F I- 0 42 L.t LI ;(f_
AllAME1 TC Supplemn al Report PAGE S1QF?6 V~nergy0 Report No.: Page: 13 of lj Summary No.: BO0 . tL5, 03 Examiner: Level: Z!: Reviewer: Date: I Examiner: Is-t'/ %K Level: Site Review: a ly Date: Other: Level: ANII Review: A ate: /_ __ 61 -' - , -X Comments: 3- LbCIS-27~r- V I (o0 A- i DL tA12
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AtItACHMENT C Supplem' al Report Report No.: PA 6E5O3 F 70 Vk*erg Page: Lv of ELF Summary No.: 5 0 3. iE . oo3 Examiner: Level: g_ Reviewer: Date: 1 C,7'-1-1 Examiner: Level: Site Review: I I Date: Other: Level: ANII Review: N c V Date: Ag//4z Comments: 5 - LIxc - TKLr -V I 44G6 C(O C0,,CtKZpG, Sketch or Photo: A W D-~- I' ( .4t -e3) =-412-5 IL. 2LIA.- .31C . 5 .. QZV)z5 En 1q3 5 ,;n Ic s " EgO (co fs - ,,, En
AttACHMENI C D>ke UT Vessel Examination PAGESq OF 16 PtF4 neW . Site/Unit: Oconee / 03 Procedure: NDE-630 Outage No.: ONS3EOC21 Summary No.: BO:3.150.004 Procedure Rev.: 2 Report No.: UT-04-486 Workscope: 'SI Work Order No.: 98641451 Page: 1 of 2 Code: Asme Section Xi 1989 Cat./Item: B-D- /B3.150.4 Location: NIA Drawing No.: 1-44773-1
Description:
Nozzle to Channel Body System ID: 51A 3.0 Component ID: B03.150.004 /3-LDCB-OUT-V2 Size/Length: N/A Thickness/Diameter: .875 8_B ' OT Limitations: See attached documents. Start Time: 0815 Finish Time: 0847 Examination Surface: Inside n Outside 3 Surface Condition: AS GROUND Lo Location: 9.2.2 . Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE 27220 Surface Temp.: 74 -F Cal. Report No.: CAL-04-741, CAL-04-742, CAL-04-743 Angle Used 0 45 1 45T 60 j 60T 145 RL Scanning dB 45.0 1 45.0 70.6 66.5 Indication(s): Yes a No Mv Scan Coverage: Upstream E Downstream 23 CWRJ CCWRJ Comments: Results: Accept i Reject Q Info a Scanning dB's less than ref +14 to obtain 2:1 signal to noise ratio. Percent Of Coverage Obtained > 90%: No - 29.263% Reviewed Previous Data: Yes Examiner Level II Signatwre Date Reviewer, A, 7 Signature Date Resor, James H. 4 WZ, 11/4/2004 // A/(tq //-/O-d Examiner Level 11-N ure Date Site Review t / Signature Date Jones, Russel .#' 11/4/2004 Other Level N/A 7 Signature Date ANII Rev)e.y Ad < Signayre Date N/A /UL- C/< /'(//
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Al ACHhMMA C JLDuke Determination of Percent Coverage for PAGES-Sr 96 (oDEnergy. UT Examinations - Vessels Site/Unit: Oconee / 03 Procedure: NDE-630 Outage No.: ONS3EOC21 Summary No.: B03.150.004 Procedure Rev.: 2 Report No.: UT-04-486 Workscope: ISI Work Order No.: 98641451 Page: 2 of 2 0 deg Planar Scan % Length X % volume of length / 100 = % total for 0 deg 45 deg Scan 1 100.000 % Length X 35.900 % volume of length / 100 = 35.900 % total for Scan 1 Scan 2 100.000 % Length X 15.600 % volume of length /100 = 15.600 % total for Scan 2 Scan 3 100.000 % Length X 31.400 % volume of length / 100 = 31.400 _ % total for Scan 3 Scan 4 100.000 % Length X 31.400 % volume of length / 100 = 31.400 _ % total for Scan 4 Add totals and divide by # scans = 28.575 % total for 45 deg Other deg 60 Scan 1 100.000 % Length X 46.600 % volume of length /100 = 46.600 %o total for Scan 1 Scan 2 100.000 % Length X 10.400 % volume of length / 100 = 10.400 Yototal for Scan 2 Scan 3 100.000 % Length X 31.400 % volume of length / 100 = 31.400 Yo total for Scan 3 Scan 4 100.000 % Length X 31.400 % volume of length / 100 = 31.400 Y.total for Scan 4 Add totals and divide by # scans = 29.950 % total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 29.263 % Total for complete exam Note: Supplemental coverage may be achieved by use of other angles / methods. When used, the coverage for volume not obtained with angles as noted above shall be alculated and added to the total to provide the percent total for the complete examination. Site Field Supervisor: M. Date: \ tO o4
ATTACHMENT C uwS oF 76, DUKE POWER COMPANY I lI ULTRASONIC BEAM ANGLE MEASUREMENT RECORD I io3,ls.co4
- 1. Take thickness measurements between wedge locations.
- 2. Place search unit on straight run of pipe, and peak the signal.
- 3. Measure distance (d) between exit 3I points.
- 4. Calculate beam angle with formula tan 0 = (d/2) as shown using measured wall t thickness.
- 5. Use the measured beam angle to A Us x determine coverage and when plotting any indications.
Pipe size:-
- For thin wall pipe use 2nd Vee path Pipe -Schedule:_ ./ .
tan 0= td/2) 2t Nominal 45 deg: d=_'.-70; t=- i875.; measured angle=+/-LL'1deg Nominal 60 deg: d=_.&_; t= 576' ; measured angle= 51-AQ deg Nominal 70 deg: d=_._; t=.._; measured angle=--deg V Examiner Level Date 4 Authorized Inspector Date
'A JkW, A%4,7L / 11'17y
AtItACHMENI C PASES70Ft 6 DUKE POWER COMPANY ISI LIMITATION REPORT Component/Weld ID: 3-LDCB-OUTLET-V2 Item No: B03.150.004 remarks: 13 NO SCAN SURFACE BEAM DIRECTION Due to branch conn. config. 0 LIMITED SCAN I1 2 31 0 2 Z cw E cow FROM L N/A to L N/A INCHES FROM WO .5" to Beyond ANGLE: El 0 Z 45 13 60 other FROM 0 DEG to 360 DEG
' NO SCAN SURFACE BEAM DIRECTION E LIMITED SCAN E1 1 2 E 1 E 2 a cw 13 ccw Due to branch conn. config.
FROM L N/A to L N/A INCHES FROM WO .5" to Beyond ANGLE: Ea 0 01 45 0 60 other FROM 0 DEG to 360 DEG 1 NO SCAN SURFACE BEAM DIRECTION E LIMITED SCAN l 1 1 2 1 1 0 2 1 cw M cCw FROM L to L INCHES FROM WO to . ANGLE: 0 [3 45 El 60 other FROM DEG to DEG 13 NO SCAN SURFACE BEAM DIRECTION E3 LIMITED SCAN R 31 2 1 1 1 2 D cw n Ccw INCHES FROM WO to Sketch(s) attached FROM L to L ANGLE: n ° a 45 n 60 other FROM DEG to DEG Z yes 1 No
A11 AUH14th z; i PAGE SgUF '7' Suppler. ital Report Report No.: Page: 2. of 1t r;gy
-N\ I1 Summary No.: . t_~n*., , O.OoLI D
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ATTACHMENT C Supplern tal Report dco y Report No.: PAGES70F f6 Page: _5 of IL4 Summary No.: i-3o5.l5Oej-ooY A/ I Examiner: Level: Reviewer Date: l_\__l____ Examiner: Level: Site Review: Date: Other: _ _ _ Level: ANII Review /tJ,4<Date: _Y6//Z/0 C Comments: 3 - LD c- - 0 0 -re-i-- 2 Cb : A9 o- .:z - 2ss:-. z7 Sketch Pr Photo:
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AtTACHMENT C I Lk Supplem Lal Report PAGE G0 OF ?6 Report No.: Htneg. _ . . ... vage: :_ of I_ Summary No.: t& D.. 16D. b b 4 Examiner: Level: 27 Reviewer: -TT- Date:
- 0 Examiner: GC4°w/ Level: Site Review: p - Date:
Other: Level: ANII Review: 0 ItZb %- - Date: /e/uzy L/ Comments: q50 4vAL5c i 3- L-oCZ - u-re-PE- VaI Sketch or Photo: AstD (X- \-t) e; %(4 of% 5,.is C (* -d n;). 1\- .8.
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ATTACHMEHt C Supplem "aI Report Report No.: PAGE aOF s6 VOnergy Page: ,5 of1L4 Summary No.: 50 .c0.0oo(
-d6 Examiner: Level: ; Reviewer: , hlb , 7TL Date: q Examiner: Level: Site Revfew: UI z Date:
Other: Level: ANII Review
- H '- 7 9 Date: 4//i Comments:
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Supplems al Report ATTACHMENT C Report No.: PA GE Ca O 96 Ph6n* Page: : of IL Summary No.: 1.73 () ?3. 15,6. b 2). L4 Examiner: Level: Reviewer: olD'qll L eLC-11
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Date: Examiner: Level: Site Review: J' C# Date: Other: Level: ANII Review: Date: / Comments: i L - OULEf- v Z (PO /J-%A L, 6CA i Sketch or Photo: prt, :( Z. ,)3~33E 2 1) 3 3t
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Supplem( ATTACHMENT C Pb ke al Report V0ieg Report No.: PAGE 63 OF 76 Page: 7 of t4 Summary No.: So3.i5Zb. D 4 - Examiner: Level: - Reviewer: 13 g ;Date: 1Df Examiner: C- Level: Site Review: Date: Other: Level: ANII Review: Date: /// Y Comments: 3 vD-(PC), AYIPL eD / rj2 Ah~r e.: 6N6Q-Atj - Sketch or Photo: Pr~~-D 1.25t = 3 -67
ATTACHMENT C Supplem ial Report PAGE C+OF: ¶6 P0ikezy Report No.: Page: '3 of , I Summary No.: GD)3.15D. bOD Examiner: Level: -f Reviewer: n/1 b e ef
--UrDate: I44cD /0 Examiner: Level: Site Review: I , Date:
Other: Level: ANII Review: e-(I a--Z~Date: ~/ Comments: 3 - LDtC - 0&r - \/2-A mt) .S;r w -I-. 13o7s' ;s1 Sketch or Photo: 945K6V-= 1.tID W.1 1.le -in GtfJ-11!'- I 4 q`. 5 - 8e ;,r I IIzq 7-eC = aII &4Gl Ck
ATTACHMENT u Supplemr al Report PONVergy Report No.: PA6E 6SO F 176
^ Page: : q' o 14 Summary No.: 18 D3. 16b . Ot: LF Examiner:
Examiner: GI, :>- Level: Level:
-9Z Reviewer:
Site Review: W1"v Date: lI llolo Date: Other: Level: ANII Review:
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ATtACHMENT C Supplem. al Report P01kbey Report No.: PAGE ;6 DF 6 Page: I 0 of I' Summary No.: Examiner: Level: ,z Reviewer: Date: Examiner: Level: Site Review: Date: Other: Level: ANII Review: Date: ///_ //_ _/ Comments:
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AtTACHMENT C Supplem 'al Report Report No.: PAGE 67 OF 76 Vbao Page: II of 14 Summary No.: 30,515o onq Examiner: Sa Level: _7 Reviewer: Date: L44o'l Examiner: Level: Site Review: I4, Date: Other: Level: ANII Review: I I Date: It //// A Comments: 3- L - ruar.- \/ 45AAINL<e L A-':I- = . 275 Sketch or Photo:
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ATTACHMENT C Supplem .al Report Obnergy. ReportNo.: PAGE6B 0 '7( g Page: 1:- of 14 Summary No.: bo3. 10, q 0 Examiner: Level: _; Reviewer: A , Date: -I44pq Examiner: Level: Site Review: I Date: Other: Level: ANII Review: Date: ////j /1 Comments: 3 Lbl - O ) -Vit Gd, A Mcrj-drlm A,- 1-DA = .05 Ad\ Sketch or Photo: Aie D: ).b K .S S... .IL5 pa Ar '0 *5s_
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Pk - , Supplem' 'al Report ATTACHMENT C Report No.: PAGE 176 OL-iew. 9? _U Page: 13 of 14 Summary No.: Examiner:
'653.t~b,o04 Level: /,j Reviewer:
n Date: * , q Examiner: Level: Site Review: U Date: Other: Level: ANII Review: A
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,o Date: /Zr L..,
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Al AtAhME~r C Supplem, .al Report PAGE 70 GF?6 Report No.: o. Page: j I V of A/+. Summary No.: ' 0 3.1W ., 4 - - Examiner:
,7sFac Level: _zZ Reviewer: Date: Oq Examiner: Level: Site Review: M-,^-
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Magnetic Particle Examination ATTACHMENT C
*1b6&1kO PAGE 71 fF 96 Site/Unit: Oconee / 03 Procedure: NDE-25 Outage No.: ONS3EOC21 Summary No.: C03 .020.017 Procedure Rev.: 21 Report No.: MT-04-094 Workscope: IS' Work Order No.: 98642593 Page: 1 of 3 Code: Asme Section Xi 1989 CatJltem: C-C- /C3.20.17 Location: N/A Drawing No.: 0-2479A
Description:
Rigid Restraint System ID: 14B Component ID: C03.020.017 /3-14B-H20A Size/Length: 8.0"/1.5" Limitations: Yes - see attached limitation reports. Light Meter Mfg.: NWA Serial No.: N/A Illumination: NWA Temp. Tool Mfg.: NWA Serial No.: N/A Surface Temp.: N/A OF Resolution: N/A Lift Block Serial No.: N/A Surface Condition: As Welded Lo/Wo Location: N/A Field Orientation: Two Perpendicular Magnetic Particle Material Brand: OCTAGON Wet E] Mixed: Yes E] Applied By: Dusting i Type: ND8-YELLOW Dry El No Nl Spraying [1 Batch No.: F-21 011 Fluorescent El With: Flooding Li Equipment: MAGNAFLUX Serial No.: NDE-UT-3 Head Shot N/A W Amperes Fixed Spacing L AC i DC El Adj. Spacing i 3-6 inches Encircling Coils N/A W Tums Prods. Spacing N/A W inches Current (machine setting) N/A W Amperes Indication Loc Loc Diameter Length Type Remarks No. L W R/L NRI Comments: Technique B, Acceptance Standard J, PIP 0-04-07725, VT-1 performed on limited area. Results: Accept i Reject E Info E Initial Section XI Examination Percent Of Coverage Obtained > 90 : No - 50% Reviewed Previous Data: No Examiner Level I /ature Date Review A Signature Date Eaton, Jay A. (_/4 11/8/2004 / -hl-dt Examiner Level N/A Signature Date Site Review Signature Date NIWA -/ //%//& Other Level WA Signature Date AN[[ Rpview Signalure Date WA / I 7/6It U or
ATIACHMENT C imitation Record PAGE 7D OF 76 SitelUnit: Oconee / 03 Procedure: NDE-25 Outage No.: ONS3EOC21
.ummary No.: C03.020.017 Procedure Rev.: 21 Report No.: MT-04-094 Workscope: ISI Work Order No.: 98642593 Page: 2 of 3 Description of Limitation:
Bottom 2 lugs not examined due to limited access. Sketch of Umitation: I- , IZY,
-Zw (634'2-4 12 W 4SC:CT S
Limitations removal requirements:
AIlIACHMENT c Duke Determination of Percent Coverage for PAGE 73 DF 96 repEnerg". Surface Examinations Site/Unit: Oconee / 03 Procedure: NDE-25 Outage No.: ONS3EOC21 Summary No.: C03.020.017 Procedure Rev.: 21 Report No.: MT-04-094 Workscope: IsI Work Order No.: 98642593 Page: 3 of 3 Area Required (as shown in applicable code reference drawing) Length 18.000
- Width 1.250
= Total Area required 22.500 square inches Coverage Achieved Area examined 11.250 sq. in. /Total area required (100%) 22.500 sq. in.
= Percent coverage 50.000 % (area required - area of limitations = area examined)
To determine length of a circumferential weld Note - Diameter refers to actual external diameter not pipe size (see table below) Diameter * (Pi) 3.1416
= Length inches Pipe Actual (Length) Pipe Actual (Length)
Size Diameter Circumference Size Diameter Circumference 2 2.375 7.46 12 12.75 40.06 2.5 2.875 9.03 14 14.0 43.98 3 3.5 11.0 16 16.0 50.27 3.5 4.0 12.57 18 18.0 56.55 4 4.5 14.14 20 20.0 62.83 5 5.563 17.48 22 22.0 69.12 6 6.625 20.81 24 24.0 75.40 8 8.625 27.10 30 30.0 94.25 10 10.75 33.77 Site Field Supervisor: SeFe Sp r iMe rD Date: t q//^_
ATTACHMENT C PAGE 7f OF f6 L x^9 st Xcc -s5fi6l r-a
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ATTACHMENT C t k>e UT Base l\ :ILamination PAGE 75 OF 6 a;aetrg .. Site/Unit: Oconee / 03 Procedure: NDE-640 Outage No.: ONS3EOC21 Summary No.: C05.021.049 Procedure Rev.: 2 Report No.: UT-04-488 Workscope: 'SI Work Order No.: 98643243 Page: 1 of 2 Code: Asme Section Xl 1989 Cat./ltem: C-F-11C5.21.49 Location: N/A Drawing No.: 3-51 A-67
Description:
Elbow to Pipe System ID: 51 A Component ID: C05.021.049 /3-51A-67-3 Size/Length: N/A Thickness/Diameter .375"/2.5" Limitations: None Start Time: 0954 Finish Time: 0958 Examination Surface: Inside z Outside i Surface Condition: AS GROUND Lo Location: 9.1.1.2 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 62 °F Scanning dB: 66 Cal. Report No.: CAL-04-744 Ind. % Amplitude Position One Position Max Position Two Loss Remarks No. Back Wan Full Screen Li WI W2 MP IM WI W2 MP L2 WI W2 MP NRI Comments: FO 03-20 Results: Accept i Reject E Info J Initial Section Xi Examination Percent Of Coverage Obtained > 90%: Yes /100% Reviewed Previous Data: No Examiner Level li-N Si nat Date Reviewer Signature ate Tucker, David K. 11/5/2004 ( ai\r z 0 Examiner Level II Si ture Date Site Review Signature Date Jordan, Joey 11/5/2004 Other Level NI5k Signature Date ANII Review Signature Date N/A
AIIANHMENT C PAGE 76 OP Ot Lcuke Supple. ;ntal Report Report No.: UT-04.488 F"Enery. Page: 2 of 2 Summary No.: C05.021.049 Examiner: Tucker, David K. ,z Level: Il-N Reviewer: 131 Date: Examiner: Jordan, Joey Level: II Site Review: 11 J I / , - Date: Other: N/A Level: N/A ANII Review: Date:
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PAGE 77 OF 976 UT Pipe Weid Examination Site/Unit: Oconee / 03 Procedure: NDE-600 Outage No.: ONS3EOC21 Summary No.: Co5.021.049 Procedure Rev.: 15 Report No.: UT-04-490 Workscope: iSI Work Order No.: 98643243 Page: 1 of 3 Code: Asme Section Xi 1989 Cat~ltem: C-F-1/C5.21.49 Location: WA Drawing No.: 3-51A-67
Description:
Elbow to Pipe System ID: 51A Component ID: C05.021.049 /3-51 A-67-3 Size/Length: NWA Thickness/Diameter .375"/2.5* Umitations: Yes - see attached limitation report. Start Time: 1005 Finish Time: 1026 Examination Surface: Inside E Outside i Surface Condition: AS GROUND Lo Location: 9.1.1.2 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 62 OF Cal. Report No.: CAL-04-745, CAL-04-746, CAL-04-747 Angle Used 0 145 145T 60 70 i l Scanning dB 45.0 48.0 55 Indication(s): Yes j No i Scan Coverage: Upstream R Downstream Wj CW 0 CCW i Comments: Results: Accept i Reject 2 Info Iinitial Section Xi Examination Percent Of Coverage Obtained > 90%: No/ 87.388% Reviewed Previous Data: No _~~~ ____a__ __ _ _ _ _ _ _ _ _ _ _ Examiner Level I i re 7 Date Reviewer Signature Date Jordan,Joey 11/5/2004 1ag 2_lct A_ 9 2__(O //- 14 -a_ Examiner Level N/A napfe Date Site Review v Signature Date W/A Other Level N/A Signature Date ANiI R Signature Date N/A I-o"-
AIIACHMENT C PAGE 78 OF 96 0W&uke Limitation Record ri~ofnergy. Site/Unit: Oconee / 03 Procedure: NDE-600 Outage No.: ONS3EOC21 Mammary No.: C05.021.049 Procedure Rev.: 15 Report No.: UT-04-490 Vorkscope: ISt Work Order No.: 98643243 Page: 2 of 3 Description of Limitation: Limited at the Intrados on the elbow side of the weld. Limitation dimension Is the Inner third of the elbow (Lo + 3.0" to Lo + 6.0"). Sketch of Limitation: 2// Limitations removal requirements: Radiation field:
AIIACHMENT C Determination of Percent Coverage for PAGE *7' OF 96 RIVuAXe UT Examinations - Pipe Site/Unit: Oconee / 03 Procedure: NDE-600 Outage No.: ONS3EOC21 immary No.: C05.021.049 Procedure Rev.: 15 Report No.: UT-04-490 Workscope: ISf Work Order No.: 98643243 Page: 3 of 3 45 deg Scan 1 % Length X % volume of length / 100 = % total for Scan 1 Scan 2 % Length X % volume of length / 100 = % total for Scan 2 Scan 3 100.000 % Length X 100.000 % volume of length /100 = 100.000 % total for Scan 3 Scan 4 100.000 % Length X 100.000 % volume of length / 100 = 100.000 % total for Scan 4 Add totals and divide by # scans = 100.000 % total for 45 deg Other deg - 60 (to be used for supplemental scans) The data to be listed below is for coverage that was not obtained with the 45 deg scans. Scan 1 66.700 % Length X 100.000 % volume of length / 100 = 66.700 % total for Scan 1 Scan 2 66.700 % Length X 100.000 % volume of length / 100 = 66.700 % total for Scan 2 Scan/i 33.300 % Length X 48.500 % volume of length / 100 = 16.150 % total for Scan 3 Scan fZ 33.300 % Length X 0.000 % volume of length / 100 = 0.000 % total for Scan 4 Percent complete coverage Add totals for each scan required and divide by # of scans to determine; 87.388 % Total for complete exam Site Field Supervisor: A~t*t. v Date: I II z? fo ti A/'Ar ,/kr 4VAO, 7-t4d J ; PaWCe7r v -ir 70 Z*er> ag7 g /6(f,62%X % 74( ) /Yerr &reAcr Act4 jurs/
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ATIACHMENT U PA6E8O OF I(,
,ItUT Base MetL. .amination ..*' .ySw Site/Unit: Oconee / 03 Procedure: NDE-640 Outage No.: ONS3EOC21 Summary No.: CO! 5.021.051 Procedure Rev.: 2 Report No.: UT-04-393 Workscope: IS, Work Order No.: 98642953 Page: 1 of 2 Code: Asme Section XI 1989 Cat./Item: C-F-1/C5.21.51 Location: N/A Drawing No.: 3HP-241
Description:
Pipe to Vaive (3HP-194) System ID: 51A Component ID: C05.021.051 /3HP-241-2 Size/Length: NWA Thickness/Diameter 0.674"1/4.0" Limitations: None Start Time: 1102 Finish Time: 1105 Examination Surface: Inside E Outside i Surface Condition: AS GROUND Lo Location: 9.1.1.1 Wo Location: Centeriine of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE 27220 Surface Temp.: 74 OF Scanning dB: 65.6 Cal. Report No.: CAL-04-643 Id. % Amplitude Position One Position Max Position Two Loss % - - - - -- -- -Remarks N.BackWafl FullScreen LI7 WI W2 MP IM WI IW2 MP 12 WI W2 MP NRI Comments: FC 03-20 Results: Accept i Reject E] Info E Initial Section XI Examination Percent Of Coverage Obtained > 90%: Yes /100% Reviewed Previous Data: No
A1IACHMENT C PA6E81 8F 76 k Duke Supplemenmal Report Report No.: UT-04-393
.VEnergy.
Page: 2 of 2 Summary No.: C05.021.051 Examiner: Zimmerman, David K. , Level: IlIl Reviewer: Date: .21 Examiner: Jones, Russel _ j za Level: II-N Site Review: _/ L e-._ Date: Other: N/A Level: NIA ANII Review: - Date: A0VW Comments: Thickness/Profile sheet. Sketch or Photo: \\ngofsl\ndeess\UT\IDDEAL\ProfileLine2.jpg 0D r©3 I I I I I I I I I I I
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ATTACHMENT C PAGE SA OF 06 aMyEnergy. Doke UT Pipe Weld Examination Site/Unit: Oconee / 03 Procedure: NDE-600 Outage No.: ONS3EOC21 Summary No.: CO5.021.051 Procedure Rev.: 15 Report No.: UT-04-394 Workscope: ISI Work Order No.: 98642953 Page: 1 of 3 Code: Asme Section XI 1989 Cat./Item: C-F-1/C5.21.51 Location: N/A Drawing No.: 3HP-241
Description:
Pipe to Valve (3HP-194) System ID: 51A Component ID: C05.021.051 /3HP-241-2 Size/Length: N/A Thickness/Diameter: 0.674" / 4" Limitations: Yes - See 1SI Limitation Report Attachment StartTime: 1107 Finish Time: 1125 Examination Surface: Inside E Outside i Surface Condition: AS GROUND Lo Location: N/A Wo Location: Centerline of Weld Couplant: ULTRAGEL It Batch No.: 03125 Temp. Toot Mfg.: FISHER Serial No.: MCNDE 27220 Surface Temp.: 74 OF Cal. Report No.: CAL-04-644, CAL-04-645, CAL-04-646 Angle Used I 0 45 45T l 60 l 38° 6ORL l Scanning dB 49.6r 49.6 54.1 Indication(s): Yes 2 No i Scan Coverage: Upstream i Downstream E CW i CCW i Comments: None Results: Accept 3 Reject ° Info E Initial Section XI Exam Percent Of Coverage Obtained > 90%: No / 35.55% Reviewed Previous Data: No Examiner Level Ill Signature _ Date Reviewer A Signature Date Zimmerman, David K. 10/20/2004 t Hak /A / o '- Examiner Level II-N a signatur-, S- Date Site Review Signature Date Jones, Russel . 10/20/2004 Other Level N/A Signature Date ANII Review Signature Date N /A_ _ _ _ _ _ _ ______
FAtIA DFNT E Determination of Percent Coverage for PAGE e3 QfiF6 [w nrW. UT Examinations - Pipe Site/Unit: Oconee I 03 Procedure: NDE-600 Outage No.: ONS3EOC21 Summary No.: C05.021.051 Procedure Rev.: 15 Report No.: UT-04-394 Workscope: [Si Work Order No.: 98642953 Page: 2 of 3 45 deg Scan 1 % Length X % volume of length / 100 = % total for Scan 1 Scan 2 % Length X % volume of length / 100 = % total for Scan 2 Scan 3 100.000 % Length X 47.400 % volume of length / 100 = 47.400 % total for Scan 3 Scan 4 100.000 % Length X 47.400 % volume of length / 100 = 47.400 % total for Scan 4 Add totals and divide by # scans = 47.400 % total for 45 deg Other deg - 60 (to be used for supplemental scans) The data to be listed below is for coverage that was not obtained with the 45 deg scans. Scan 1 100.000 % Length X 0.000 % volume of length / 100 = 0.000 % total for Scan 1 Scan 2 100.000 % Length X 47.400 % volume of length / 100 = 47.400 % total for Scan 2 Scan 3 % Length X % volume of length / 100 = % total for Scan 3 Scan 4 % Length X % volume of length / 100 = % total for Scan 4 Percent complete coverage Add totals for each scan required and divide by # of scans to determine; 35.550 %Total for complete exam Site Field Supervisor
. -I . Date: IC) 0o /
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AItACHMENT C PA6E8 OF 76 Supplemi1 ,tal Report IM6"W. Report No.: Page: 3 UT-04-394 of 3 Summary No.: C05.021.051 Examiner: Zimmerman, David K.,, Level: IlIl Reviewer: Date: Examiner: Jones, Russel 1, Level: l-N Site Review: - I / , 1., , Date: Other N/A " Level: N/A ANII Review: - V/EI'
;4 Date: AQO2,)- W/
Comments: Scan 2, 3, 4 coverage. Sketch or Photo:
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ATIACHMENI C PA6E OS OFr DUKE POWER COMPANY UT-04-394 ISI LIMITATION REPORT Attachment Component/Weld ID: C05.021.051 Item No: 3HP-241-2 remarks: 1 NO SCAN SURFACE BEAM DIRECTION Valve Conf. ZLIMITED SCAN l1 0i 2 0J 1 Z 2 a cw o ccw FROM L N/A to L N/A INCHES FROM WO C/L to Beyond ANGLE: El 0 E] 45 Z 60 other FROM 0 DEG to 360 DEG E NO SCAN SURFACE BEAM DIRECTION Valve Conf. E LIMITED SCAN .l 1 E22l 1 M22 cw Z ccw FROM L N/A to L N/A INCHES FROM WO C/L to Beyond ANGLE: El 0 Z 45 El 60 other FROM 0 DEG to 360 DEG El NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN l1 0 2 E I E 2 0 cw El ccw FROM L to L INCHES FROM WO to _ ANGLE: El 0 El 45 E 60 other FROM DEG to DEG El NO SCAN SURFACE BEAM DIRECTION E LIMITED SCAN El1 E 2 El1 0 2 0 cw l ccw FROM L to L _ INCHES FROM WO to Sketch(s) attached ANGLE: El 0 E] 45 E 60 other FROM DEG to DEG El yes Q No Prepared By: David Zimmerman - Level: III Date: 10/20/2004 Attachment 1 of 1 Reviewed By: ,K Date: Author o.f Date: I .
'I
ATIACHMENT PAGE 86 OF 76U UT Base Metk .amination i.-.bWS Site/Unit: Oconee / 03 Procedure: NDE-640 Outage No.: ONS3EOC21 Summary No.: Co5.021.076 Procedure Rev.: 2 Report No.: UT-04-181 Workscope: Is, Work Order No.: 98645068 Page: 1 of 2 Code: Asme Section XI 1989 Cat./Item: C-F-1/C5.21.76 Location: N/A Drawing No.: 3-51 A-119
Description:
Flange to Pipe System ID: 51A Component ID: C05.021.076 /3-51A-119-11 Size/Length: N/A Thickness/Diameter 4.0" /.531 Limitations: None Start Time: 1109 Finish Time: 1113 Examination Surface: Inside 2 Outside i Surface Condition: AS GROUND Lo Location: 9.1.1.1 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 88 °F Scanning dB: 50 Cal. Report No.: CAL-04-433 Ind. % Amplitude Position One Position Max Position Two No. Loss % Remarks BackWag Full Screen Li WI W2 MP LM W1 W2 MP L2 WI W2 MP NRI Comments: FC 03-20 Results: Accept n3 Reject ° Info E Initial Section XI Inspection Percent Of Coverage Obtained > 90%: Yes-1 00% Reviewed Previous Data: No Examiner Level II Signature Date Reviewer A o Signature Date Resor, James H. 7/12/2004 /1~A /(- 7-/4 o' Examiner Level II a Date Site Review Signature Date Jordan, Joey 7/12/2004 Other Level N/A n/Siliature Date ANII Review Signature Date N/A __ _ _ _ _ _ _ _ __
ATTACHMENT C PAGE g 7 OF 76 PL Duke Supplemetical Report Report No.: UT-04-1 81 OvEnergy. Page: 2 of 2 Summary No.: C05.021.076 Examiner: Resor, James H. -7 Level: II Reviewer: Date: Examiner: Jordan, Joey (g, 4;j~ Level: II Site Review: fl" Date: Other: N/A Level: N/A ANII Review: Date: 1&46/oE Comments: Sketch or Photo: Z:\UT\IDDEAL\ProfileLine2.jpg St1,1 / AR
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At IACHMENT C PAGE R8 OF 76 b Dime UT Pipe Weed Examination 16MEnergy. Site/Unit: Oconee / 03 Procedure: NDE-600 Outage No.: ONS3EOC21 Summary No.: Co5.021.076 Procedure Rev.: 15 Report No.: UT-04-182 Workscope: iSI Work Order No.: 98645068 Page: 1 of 3 Code: Asme Section Xl 1989 Catiitem: C-F-1/C5.21.76 Location: N/A Drawing No.: 3-51A-119
Description:
Flange to Pipe System ID: 51A Component ID: C05.021.076 /3-51A-119-11 Size/Length: N/A Thickness/Diameter: 4.00 /.531 Limitations: Yes - See Attached Limitation Report Start Time: 1116 Finish Time: 1131 Examination Surface: Inside E Outside Ea Surface Condition: AS GROUND Lo Location: 9.1.1.1 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 88 OF Cal. Report No.: CAL-04-434, CAL-04-435, CAL-04-436 Angle Used 0 45 45T 60 60L l l Scanning dB 42 45 60 Indication(s): Yes J No i Scan Coverage: Upstream E] Downstream i CW i CCW i Comments: See attached calculation sheets Results: Accept i Reject 2 Info ] Initial Section XI Inspection Percent Of Coverage Obtained > 90%: No Reviewed Previous Data: No Examiner Level II Signa Date Reviewer A x Signature Date Resor, James H. 7/12/2004 /JjT /l / //7 d,-t Examiner Level Ii - ur Date Site Review / 1 Signature Date Jordan,Joey ( 7/12/2004 Other Level N/A ,<-/ Signature Date ANII Review Signature Date N/A
ATtACHMENI C PACE 89 OF 16 Limitation Record Site/Unit: Oconee / 03 Procedure: NDE-600 Outage No.: ONS3EOC21 Summary No.: C05.021.076 Procedure Rev.: 15 Report No.: UT-04-182 Workscope: ISI Work Order No.: 98645068 Page: 3 of 3 Description of Limitation: See attached sketch for calculations of aggregate coverage. Sketch of Umitation: Limitations removal requirements: Radiation field:
AIIACHMENT C M-Puk Determination of Percent Coverage for PAGE 170 OF 96 rwa-new. UT Examinations - Pipe Site/Unit: Oconee / 03 Procedure: NDE-600 Outage No.: ONS3EOC21 Summary No.: C05.021.076 Procedure Rev.: 15 Report No.: UT-04-182 Workscope: ISI Work Order No.: 98645068 Page: 2 of 3 45 deg Scan 1 % Length X % volume of length /1 00 = % total for Scan 1 Scan 2 % Length X % volume of length / 100 = % total for Scan 2 Scan 3 100.000 % Length X 100.000 % volume of length / 100 = 100.000 % total for Scan 3 Scan 4 100.000 % Length X 100.000 % volume of length /100 = 100.000 % total for Scan 4 Add totals and divide by # scans = 100.000 % total for 45 deg Other deg - 60 (to be used for supplemental scans) The data to be listed below is for coverage that was not obtained with the 45 deg scans. Scan 1 100.000 % Length X 32.000 % volume of length / 100 = 32.000 % total for Scan 1 Scan 2 0.000 % Length X 0.000 % volume of length / 100 = 0.000 % total for Scan 2 Scan 3 % Length X % volume of length / 100 = % total for Scan 3 Scan 4 % Length X % volume of length / 100 = % total for Scan 4 Percent complete coverage Add totals for each scan required and divide by # of scans to determine; 58.000 % Total for complete exam Site Field Supervisor: _____ Date: (3.d 7, C-t'j
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ATTACNMEHNT C PAE St OF T76 Ald" UT Base N I Lamination
..ergy.
Site/Unit: Oconee / 03 Procedure: NDE-640 Outage No.: ONS3EOC21 Summary No.: Co5.021.091 Procedure Rev.: 2 Report No.: UT-04-489 Workscope: ISI Work Order No.: 98643243 Page: 1 of 2 Code: Asme Section XI 1989 Cat./ltem: C-F-1/C5.21.91 Location: WA Drawing No.: 3-51 A-67
Description:
Pipe to Elbow System ID: 51A Component ID: C05.021.091 /3-51A-67-4 Size/Length: WA Thickness/Diameter .375'/2.5" Limitations: None Start Time: 0958 Finish Time: 1002 Examination Surface: Inside E Outside i Surface Condition: AS GROUND Lo Location: 9.1.1.2 Wo Location: Centerline of Weld Couplant: ULTRAGEL 11 Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 62 OF Scanning dB: 66 Cal. Report No.: CAL-04-744 Ind % Amplitude Position One Position Max Position Two Loss Remarks No Back Wan Full Screen Li WI W2 MP LM W1 W2 MP L2 WI W2 MP NRI Comments: FC 03-20 Results: Accept i Reject 2 Info n Initial Section XI Examination Percent Of Coverage Obtained > 90%: Yes / 100% Reviewed Previous Data: No I Examiner Level Il-N - Date Reviewer Signaturo Date Tucker, David K. XC 11/5/2004 c_ V __ _ __ X __ _ __ _ __ _ __ _ Examiner Level II ture Date Site Review Signature Jordan, Joey 1115/2004 Other Level NIAX / / Signature Date ANII Review Signature Pate N/AI LZ I
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ATTACHMENT C PAGE 93 OF 76
&I .Juke Suppkl mntal Report Report No.: UT-04-489 d Energy.
Page: 2 of 2 Summary No.: C05.021.091 Examiner: Tucker, David K. Level: II N Reviewer: Date: -\ 1aI. . 04 i Examiner: Jordan, Joey (' Level: II Site Review: v, .- 4 / 1 4 _-; 1 Date: Other: N/A Level: N/A ANII Review: r W&&AW Date: ,/,V Comments: Sketch or Photo: \\Ngofsl\ndeess\UT\IDDEAL\ProfiteLine2.jpg
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AtItACHMENT C PAGE -7Sc UF '76 Mulker UT Pipe aid Examination MV energy. Site/Unit: Oconee / 03 Procedure: NDE-600 Outage No.: ONS3EOC21 Summary No.: C05.021.091 Procedure Rev.: 15 Report No.: UT-04-491 Workscope: ISI Work Order No.: 98643243 Page: 1 of 3 Code: Asme Section Xi 1989 Cat./Item: C-F-1/C5.21.91 Location: N/A Drawing No.: 3-51A-67
Description:
Pipe to Elbow System ID: 51A Component ID: C05.021.091 /3-51A-67-4 Size/Length: N/A Thickness/Diameter: .375"/2.5" Limitations: Yes - see attached limitation report. Start Time: 1009 Finish Time: 1030 Examination Surface: Inside j Outside i Surface Condition: AS GROUND Lo Location: 9.1.1.1 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 03125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE32768 Surface Temp.: 62 OF Cal. Report No.: CAL-04-745, CAL-04-746, CAL-04-747 Angle Used 0l 45 l45Tl 60 70 l l Scanning dB 45 48 55 Indication(s): Yes I No i Scan Coverage: Upstream i Downstream i CW i CCW i Comments: Results: Accept i Reject R Info Iinitial Section Xl Examination Percent Of Coverage Obtained > 90%: No / 87.388% Reviewed Previous Data: No
A11ACHMENT C PAGE q'5 OF fi PLQke Limitation Record Site/Unit: Oconee 1 03 Procedure: NDE-600 Outage No.: ONS3EOC21 Summary No.: C05.021.091 Procedure Rev.: 15 Report No.: UT.04-491 Workscope: IS! Work Order No.: 98643243 Page: 2 of 3 Description of Limitation: Limited at the Intrados on the elbow side of the weld. Limitation dimension Is the Inner third of the elbow (Lo + 3.0" to Lo + 6.0"). Sketch of Limitation: 2Z4A; 2S mos " v Limitations removal requirements: Radiation field:
ATIACHMENT C ReDuke Determination of Percent Coverage for PAGE 76 OF 16 ravp esY UT Examinations - Pipe Site/Unit: Oconee / 03 Procedure: NDE-600 Outage No.: ONS3EOC21 immary No.: C05.021.091 Procedure Rev.: 15 Report No.: UT-04-491 Workscope: ISI Work Order No.: 98643243 Page: 3 of 3 45 deg Scan 1 % Length X % volume of length / 100 = % total for Scan 1 Scan 2 % Length X % volume of length /100 = % total for Scan 2 Scan 3 100.000 % Length X 100.000 % volume of length / 100 = 100.000 % total for Scan 3 Scan 4 100.000 % Length X 100.000 % volume of length / 100 = 100.000 % total for Scan 4 Add totals and divide by # scans = 100.000 %total for 45 deg Other deg - 60 (to be used for supplemental scans) The data to be listed below is for coverage that was not obtained with the 45 deg scans. Scan 1 66.700 % Length X 100.000 % volume of length /100 = 66.700 % total for Scan 1 Scan 2 66.700 % Length X 100.000 % volume of length / 100 = 66.700 % total for Scan 2 Scan.9 1 33.300 % Length X 48.500 % volume of length / 100 = 16.150 % total for Scan 3 Scan/o. 33.300 % Length X 0.000 % volume of length / 100 = 0.000 % total for Scan 4 Percent complete coverage Add totals for each scan required and divide by # of scans to determine; 87.388 %Total for complete exam Site Field Supervisor: Date: I I& V
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Attachment B Request for Relief 05-ON-002 Limited Examinations on Reactor Vessel 3EOC 21
Relief Request 05-ON-C02 Page 1 of 6 Proposed Relief in Accordance with 10 CFR 50.55a(g)(5)(iii) Inservice Inspection Impracticality Duke Energy Corporation Oconee Nuclear Station - Unit 3 (EOC-21) Third 10-Year Interval - Inservice Inspection Plan Interval Start Date = 12-16-1994 Interval End Date = 1-2-2005 ASME Section XI Code - 1989 Edition with No Addenda Code Case N-460 is applicable MI. l IV. &V. lVI. l Vll. l VIll. List Limited System / Code Requirement from Impracticality/ Proposed Alternate Implementation Justification for Number Area/Weld I.D. Component for Which Which Relief is Requested: Burden Caused by Examinations or Schedule and Granting Relief Number Relief is Requested: 100% Exam Volume Coverage Compliance Testing Duration Area or Weld to be Exam Category Examined Item No. Fig. No. Limitation Percentage
- 1. 3-RPV-WR34 NC System Exam Category B-A See Paragraph "A" See Paragraph "E" See Paragraph "F' See Paragraph "G" Reactor Vessel Item No. B01.01 1.004 Lower Shell to Lower Fig. IWB-2500-1 Head Ring 44.5% Volume Coverage Circumferential Weld
- 2. 3-RPV-WR35 NC System Exam Category B-A See Paragraph "B" See Paragraph "E" See Paragraph "F' See Paragraph "G" Reactor Vessel Item No. B01.021.003 Lower Head Cap to Fig. IWB-2500-3 Lower Head Ring 50% Volume Coverage Circumferential Weld 3 3-RPV-WR19 NC System Exam Category B-A See Paragraph "C" See Paragraph "E" See Paragraph "F' See Paragraph "G' Reactor Vessel Item No. B01.030.001 Upper Shell to Flange Fig. IWB-2500-4 Circumferential Weld 85.8% Volume Coverage
- 4. 3-RPV-WR54 NC System Exam Category B-D See Paragraph "D" See Paragraph "E" See Paragraph "F' See Paragraph "H" Reactor Vessel Item No. B03.090.007 Core Flood (UT from vessel I.D.)
Nozzle-to-Vessel Weld Fig. IWB-2500-7(a)
@00 84.2% Volume Coverage
Relief Request 05-ON-002 Page 2of 6 111.IV. &V. VI. Vll. Vill. - . List Limited System Code Requirement from Impracticality/ Proposed Alternate Implementation Justification for Number Area/Weld I.D. Component for Which Which Relief Is Requested: Burden Caused by Examinations or Schedule and Granting Relief Number Relief is Requested: 100% Exam Volume Coverage Compliance Testing Duration Area or Weld to be Exam Category Examined Item No. Fig. No. Limitation Percentage
- 5. 3-RPV-WR54 NC System Exam Category B-D See Paragraph "D" See Paragraph "E" See Paragraph "F' See Paragraph "H" Reactor Vessel Item No. B03.090.007A Core Flood (UT from nozzle bore.)
Nozzle-to-Vessel Weld Fig. IWB-2500-7(a)
@ 00 84.2% Volume Coverage
- 6. 3-RPV-WR54A NC System Exam Category B-D See Paragraph "D" See Paragraph "E" See Paragraph "F' See Paragraph "H" Reactor Vessel Item No. B03.090.008 Core Flood (UT from vessel ID)
Nozzle-to-Vessel Weld Fig. IWB-2500-7(a)
@ 1800 84.2% Volume Coverage _
- 7. 3-RPV-WR54A NC System Exam Category B-D See Paragraph "D" See Paragraph "E" See Paragraph "F" See Paragraph "H" Reactor Vessel Item No. B03.090.008A Core Flood (UT from nozzle bore)
Nozzle-to-Vessel Weld Fig. IWB-2500-7(a)
@ 1800 84.2% Volume Coverage See Attachment A for area/weld locations.
Note: The welds listed in the table above were inspected in December of 2004.
Relief Request 05-ON-002 Page 3 of 6 IV. & V. Impracticalitv/ Burden Caused by Code Compliance Paragraph A: (The Lower Shell and Lower Head Ring material is SA508 CL2. This weld has a diameter of 170.250 inches and a wall thickness of 5.5 inches.) During ultrasonic examination, 100% coverage of the required examination volume could not be obtained. Twelve core guide lugs restrict the scanning surface, as shown on the Attachment B drawing, causing limitations that resulted in 44.5% coverage. The percentage of coverage reported represents the aggregate coverage from all scans parallel and perpendicular to the weld. The weld and adjacent base material were examined using 450 refracted shear waves and 45° refracted longitudinal waves. Examination volumes directly below the core guide lugs received no coverage when scanned parallel to the weld. Additionally no scans were performed perpendicular to the weld directly below the core guide lugs. Scans parallel to the weld were restricted to 7.6 inches on either side of each core guide lug and scans perpendicular to the weld were restricted to 4.7 inches on either side of each core guide lug. In order to achieve more coverage, the core guide lugs would have to be moved to allow greater access, which is impractical. There were no recordable indications found in the areas that were examined. 54% of the weld and base material volume received coverage in two directions perpendicular to the weld. 35% of the weld and base material volume received coverage in two directions parallel to the weld. 55.50% of the weld and base material volume received no coverage. (See Attachment B for exam information) Paragraph B: (The Lower Head Cap material is SA533 CLI GRB and Lower Head Ring material is SA508 CL2. This weld has a diameter of 143.00 inches and a wall thickness of 5.375 inches.) During ultrasonic examination, 100% coverage of the required examination volume could not be obtained. The examination coverage was limited to 50%. The percentage of coverage reported represents the aggregate coverage from all scans parallel and perpendicular to the weld. The flow stabilizers, core guide lugs and in-core nozzles that restrict the scanning surface, as shown on the Attachment C drawing, caused the limitations. The weld and adjacent base material were examined using 45° refracted shear waves and 45° refracted longitudinal waves. There were no recordable indications found in the areas that were examined. In order to achieve more coverage the flow stabilizers, core guide lugs and in-core nozzles would have to be moved to allow greater access for scanning, which is impractical. 53.33% of the weld and base material volume received coverage in two directions perpendicular to the weld. 46.66% of the weld and base material volume received coverage in two directions parallel to the weld. 50% of the weld and base material received no coverage. (See Attachment C for exam information) Paragraph C: (The Upper Shell and Flange material is SA508 CL2. This weld has a diameter of 167.630 inches and a wall thickness of 12.00 inches.) During ultrasonic examination, 100% coverage of the required examination volume could not be obtained. The examination coverage was limited to 85.8%. The percentage of coverage reported represents the aggregate coverage from all scans parallel and perpendicular to the weld. Limitations were caused by inside surface taper and the ledge shown in Attachment D. The percentage of coverage reported represents the aggregate coverage from all scans. The weld and adjacent base material were examined using 450 refracted shear waves and 450 refracted longitudinal waves. There were no recordable indications found in the areas that were examined. In order to achieve more coverage, the weld would have to be redesigned which is impractical. (See Attachment D for exam information)
Relief Request 05-ON-002 Page 4 of 6 Paragraph D: (The Upper Shell and Core Flood Nozzle material is SA508 CL2. This weld has a diameter of 25.00 inches and a wall thickness of 12.00 inches.) During ultrasonic examination, 100% coverage of the required examination volume could not be obtained. The examination coverage was limited to 84.2% of the required volume. The Core Flood Nozzles of a B&W 177 plant have several obstructions which limit ultrasonic examination coverage. In order of significance these are:
- The flow restrictor which is welded to the inner bore of the nozzle;
- The inlet nozzles located 300 on either side of each core flood nozzle;
- The taper above the core flood nozzles associated with the Core Support Ledge.
The percentage of exam volume coverage reported represents the aggregate coverage as follows: Weld and adjacent base material = 87.6% scanned parallel to the weld in two opposite directions and 72.9% scanned perpendicular to the weld centerline from the nozzle bore and the vessel inside surface. There were no recordable indications found in the areas that were examined for either of these welds. In order to achieve more coverage, the inlet nozzles would have to be moved. and the taper on the flange would have to be redesigned to allow greater access for scanning, which is impractical. In addition, because of the proximity of the flow restrictors limited scanning was performed from the nozzle I.D as shown in Attachment E. In order to achieve more coverage, the flow restrictor would have to be moved to allow access for scanning, which is impractical. (See Attachment E for exam information) VI. Proposed Alternate Examinations or Testing Paragraph E: The scheduled 10-year code examination was performed on the referenced area/weld and it resulted in the noted limited scanning and coverage of the required ultrasonic volume. No additional examinations are planned for the area/weld during the current inspection interval. VII. Implementation Schedule and Duration Paragraph F The scheduled third 10-year interval plan code examination was performed on the referenced area/weld resulting in limited scanning and volumetric coverage. No additional examinations are planned for the area/weld during the current inspection interval. The same area/weld may be examined again as part of the next (fourth) 10-year interval plan, depending on the applicable code year edition and addenda requirements adopted in the future. VIII. Justification for Granting Relief Paragraph G: Ultrasonic examination of welds for item numbers B01.011, B01.021 and B01.30 were conducted using personnel, equipment and procedures qualified in accordance with ASME Section XI, Appendix VIII, Supplements 4 and 6, 1995 Edition with the 1996 Addenda as administered through the Performance Demonstration Initiative (PDI) Program. Although limited scanning prevented 100% coverage of the examination volume, the amount of coverage obtained for these examinations along with the additional volumetric and visual examinations (listed in the next paragraph) provides an acceptable level of quality and integrity. (See Paragraph I for additional justification.)
Relief Request 05-ON-002 Page 5 of 6 In addition to the Category B-A welds that relief is being sought for, there were 3 circumferential Category B-A welds that were inspected and all obtained greater than 90 % coverage and there were no reportable indications found during the inspections. Visual examinations were also performed as part of the reactor vessel inspections (item number B 13.010.001 and B 13.050.001) and were found to be without any reportable indications. Paragraph H: Ultrasonic examination of areas/welds for item numbers B03.090 were conducted using personnel, equipment and procedures qualified in accordance with ASME Section XI, Appendix I, 1989 Edition with no Addenda. Although limited scanning prevented 100% coverage of the examination volume, the amount of coverage obtained for these examinations provides an acceptable level of quality and integrity. (See Paragraph I for additional justification.) Paragraph I: Duke Energy will use the Code required pressure testing and VT-2 visual examination to compliment the limited examination coverage. The Code requires (reference Table NVB-2500-1, item numbers B 15.010 and B 15.050) that a system leakage test be performed after each refueling outage for Class 1. Additionally a system hydrostatic test (reference Table IWB-2500-1, item numbers B 15.011 and B15.051) is required once during each 10-year inspection interval; however, Code Case N-498-1 was invoked in lieu of performing the hydrostatic test. These tests require a VT-2 visual examination for evidence of leakage. This testing provides adequate additional assurance of pressure boundary integrity. Duke Energy will use VT-3 visual examination to compliment the limited examination coverage. The Code requires (reference Table NVB-2500-1, item number B 13.010) that a VT-3 examination be performed after the first refueling outage and subsequent refueling outages at approximately 3 year periods. During the first and second periods of an interval a VT-3 examination is performed on areas above and below the reactor core that are made accessible for examination by removal of components during normal refueling outages. During the third period of an interval the VT-3 examination is performed on all of the reactor vessel interior surfaces at the same time that the automated UT exams are performed on the reactor vessel welds. These examinations provide adequate additional assurance of pressure boundary integrity. In addition to the above Code required examinations (volumetric, pressure test, and VT-3), there are other activities which provide a high level of confidence that, in the unlikely case that leakage did occur through these welds, it would be detected and isolated. Specifically, leakage from these welds would be detected by monitoring of the Reactor Coolant System (RCS), which is performed once each shift under procedure PT/1,2,3/A/0600/10, "RCS Leakage". This RCS leakage monitoring is a requirement of Technical Specification 3.4.13, "Reactor Coolant System Leakage". Leakage is also evaluated in accordance with this Technical Specification. The leakage could also be detected through several other methods. One is the Reactor Building air particulate monitor. This monitor is sensitive to low leak rates; the iodine monitor, gaseous monitor and area monitor are capable of detecting any fission products in the coolant and will be activated by coolant leakage. A second is the level indicator in the Reactor Building normal sump. A third is a loss of level in the Letdown Storage Tank. Duke Energy Corporation has examined the welds/components referenced in this request to the maximum extent possible utilizing the latest in examination techniques and equipment. These welds were rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Based on the coverage and results of the required volumetric and visual examinations performed during this outage, it is Duke's belief that this combination of elements provides a reasonable assurance of component integrity.
Relief Request 05-ON-002 Page 6 of 6 IX. Other Information The following individuals contributed to the development of this relief request: James J. McArdle (Principal NDE Level III Inspector) provided Sections III through V and part of Section VIII. B. W. Carney, Jr. (Oconee Engineering) provided part of Section VIII. Larry C. Keith (Oconee ISI Plan Manager) compiled the remaining sections. Sponsored By: C, Co7 C - Date 5 J (: ()5 a Approved By: - X ._ Date Sg/Z6/C S I f(
A .3 - . f-T fci 1-wj T '" " Westinghouse Proprietary Class 2C
- 0. G 90- 150' 180 210 270 330 360' VI 3-2RPV-VRI9 DO RPV-V X03090X3X 3-RPV-VR12A 32.RPVVI2fl V23 3-RPV-VRI.C (203.09(1003) CD3O3O- D~9OO4RPVVWRt3A 0IO2O90O6)
Ul~3RPV-VRlAIQ. V3 B010011.00 ] I IRPV-VRI .. _ -- -- 1N9 SCALED TO M: ID SUrAC.E OCONEE 3 BOC03 WesDyne Internationat TT= Vessel. Rotlout EXAMINATION PROGRAM PLAN 2004 Page 29 of 52 s~cnDrwWNVEJSET4 1 OF-? I
And 1 cr \ teAt 1Ait . -. K-) Wesilnghoum Proprietary Class 2C
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0o VIS 3RPV-VR12 3033.09.00 270' OCONEE 3 BOC03 too, WesDyne International mx Nozzle OrientQtion EXAMINATION PROGRAM PLAN 2004 Page 31 of 52 I.ND G4DDM NO= SHEET 3 OF 22
. . 11 A TTA rAtMA0 7 6 PO,$. 4-R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Oconee WesDyne WELD NO. W4 (3-RPV-WR34) International COMPONENT Transition to Lower Shell Circ. Weld BEAM ANGLE BREAK DOWN BEAM DIRECTION 45 Shear 45 L Single 45 L Dual WELD VOLUME WELD IVOLUME WELD I VOLUME WELD VOLUME Perpendicular 54.00 54.00 54.00 54.00 54.00 54.00 Parallel 35.00 35.00 35.00 35.00 35.00 35.00 _ AVERAGE 44.50 44.50 44.50 Comments: Combined Perp. 54.00 Combined Para. 35.00 Combined Average 44.50 Analyst I L Date l/z/el 7/ I k--111
A TI4CJ4cri-euT 1 WesUnghouse Proprietary Clasm 2C 289.50
- 291.94 8.56 _ Working Point Top Perp
- =
(82.56 ) 303.10- 301.39 <83.(;9*) Top Para((et (79.13') 308.43 - 1 )
- <- 309.50 313.06 (75.97") Bottom Paraotel (77.09') 312.64 313.35 (75.76') Bottom Perp R87.06 WP 5.38 (W4)
Scan Increment = 0.329 (0.5') for Paraltet Scans 3-RPV-WR34
- 0.329' (0.50') for Perp Scans B01.011.004 lVerify rokbot sequence list for Perp sledl rotationI OCONEE 3 BOC03 Parallel Scan Limits +/- 5.0* Either Slde of Core Guide Lugs WesDyne Internationac Perp Scan Limnits +/- 3.1' Either Side of Core Guide Lugs m2 Transition to Lower Shelt Circ Vetd No Scans Performeed Below Core Guide Lugs EXAMINATION PROGRAM PLAN 2004 AIL DISIONS ININISHEET 8 OF 22 UNLESS OTHERV NUlEM 1D PC Page 36 of 52
5Rs 3 +3 Zone of partial cover;age typical 12 locations IScone OLO,1E3 /u 9) I a, Tc,3,q I ONS-3 3-RPV-WR34
4 A tr-A Ch msT c-AOj l*43 _, R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Oconee WesDyne WELD NO. W5 (3-RPV-WR35) International COMPONENT Lower Head to Transition Circ. Weld BEAM ANGLE BREAK DOWN BEAM DIRECTION 45 Shear 45 L Single 45 L Dual WELD I VOLUME WELD I VOLUME WELD VOLUME WELD IVOLUME Perpendicular 53.33 53.33 53.33 53.33 53.33 53.33 _ _ Parallel 46.66 46.66 46.66 46.66 46.66 46.66 _ AVERAGE 50.00 50.00 50.00 Comments: I., N A COMBINED AVERAGE 50.00 Analyst /I Date I /C. (I
A T~j c -kP 7C Westinghouse Proprietary Class 2C
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-291.94 Tangent (worklno point)
Ctev tion
/-1 I 58.53' T
Paralltt op
\ 58.29 N 51.7 1 Perp top 51.47' Peep Bottom Poreolet Botton i
(WS) i 3-RPV-VWR35 B01.021.003 OCONEE .3 BOC03 Scan Increment = 0.329' MS') For Parallet Scans WesDyne Inter'rationat
= 0.329' (0.50') for Perp Scans L o Towresltlon Circ Veld fHead EXAMINATION PROGRAM PLAN 2004 J I UL WI SHMEE 9 OF 22
A ThAch m-eAT C P 9 R2 34 3 FLOW STABILIZER- INCORE NOZZLE LI 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 *1Our~5 e y OCONCE-3 3-RPV-WR35 B0 1.021.003
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/4-A TTACJ\ M4A/F v I1 R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME OCONEE WesDyne WELD NO. W1 (3-RPV-WR19)
International COMPONENT Shell to Flange Weld BEAM ANGLE BREAK DOWN BEAM DIRECTION 45 Shear 45 L Single 45 L Dual WELD JVOLUME WELD l VOLUME WELD IVOLUME WELD IVOLUME Perpendicular 86.66 86.66 86.66 86.66 86.66 86.66 Parallel 85.00 85.00 85.00 85.00 85.00 85.00 _ AVERAGE . 85.83 85.83 85.83 Comments: Combined Perp. 86.66 Combined Para. 85.00 Combined Average 85.83 Analyst w4- Date /a/'6,i' 77-I
AP.Tr /J\ ,vWki7- D 1-Westinghouse Piroprietary Class 2C
/
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- 82.44R to Clad I Top Perp
- 22.036 Taper 24.25 Parallel 27.058 T1aper 32.00 - 17.4*
39.75
- 41.460 Bottom, Parallel 48.23 Bottom Perp 12.00 - (W1)
.188 3-RPV--WR19 84.OR to Clad B01.030.001 OCONEE. 3 BOC03 Scan Increnent = 0.5' for Parallel Scans
= 0.341' for Perp Scans l VWesDyrve Internotionao Upper Shell to FlQnqe EXAHINATION PROGRAM PLAN 2004 UOiTiMW NOMISHEET 4 OF 22
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lo t -.. A d-oc-k m-epAT
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/ 6 R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Oconee WesDyne WELD NO. W1 I (3-RPV-WR54)
International COMPONENT Core Flood Nozzle to Shell @ 00 BEAM ANGLE BREAK DOWN BEAM DIRECTION 1 45 Shear" 45 L Single 45 L Dual Combined Bore/Star WELD VOLUMEJ WELD VOLUME WELD VOLUME WELD VOLUME TAN Scan Parallel 94.22 80.95 100.00 98.71 100.00 100.00 Combined Bore&Star Perpendicular 74.75 71.01 AVERAGE 87.59 99.35 100.00 72.88 Comments: Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Limitation is due to vessel saddle effect at 900 & 2700 and the flow restrictor located in the inside of the nozzle. Combined Perp. 72.88 Combined Para. 95.65 Combined Average 84.26 Analyst ./Ad 4~ Date / '/6'/ 4 / --
Po t x N4 6 R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Oconee WesDyne WELD NO. WI 9 (3-RPV-WR54A) International COMPONENT Core Flood Nozzle to Shell @ 1800 BEAM ANGLE BREAK DOWN BEAM DIRECTION 45 Shear 45 L Single 45 L Dual Combined Bore/Star WELD l VOLUME WELD l VOLUME I WELD I VOLUME I WELD I VOLUME TAN Scan Parallel 94.22 80.95 100.00 98.71 100.00 100.00 Combined Bore&Star . Perpendicular I __ 74.75 71.01 AVERAGE 87.59 99.35 100.00 72.88 Comments: Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Limitation is due to vessel saddle effect at 90° &270° and the flow restrictor located in the inside of the nozzle. Combined Perp. 72.88 . Combined Para. 95.65 Combined Average 84.26 Analyst Date Ie? 9/ I - I
- TTA-Ckr1tf =
.- Py Westinghouse Proprietary Class 2C I 84.OR to CMad
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'- 14.09
- 12.50
- 10.83 I - 0 r or 14 14 . 4' 0 a L4 U4 14 U 60.0 Ref.
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- 4. 6 U ]
Core Flood Nozzle to She( @e0' - 3RPV-WR54 (B03.090.007A) Core Flood Nozzle to Shell E 180' - 3RPV-WR54A (B03.090.008A) Core Flood Nozzle Safe End @ 0' - 3RPV-WR53 (BO5.010.OO1A, BO5.010.OOlB) Core Flood Nozzle Safe End @ 180' - 3RPV-WR53A (B05.010.002A, B05.010.002B) OCONEE 3 BOC03 Scan Increment: Axial Scans 1.15' Circ. Scans 0,080' WesDyne International
" Core rlood Nozzle to Stfit L Scife End Velds Page 48 of 52 EXAMINATION PROGRAM PLAN 2004 AMDONS INICM UNL=On=W=NO= SEE o 19 OF C22
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WexsUnghouse Proprietary Clas 2C A O 19 84-BR to Clad I 26.7 'Star Scon Mqx if a L-I t5.00 Thn Scon Max R6.00 11- 14.09 C.i t 2.SO0 M I- 10.83 0 9.00 Tan Scan Min 7.56 Star Scan Max Core Flood Nozzle to Shell 2- 0' Inner Radius VT-- 3RPV-WR54 (B03.100.007) Core Flood Nozzle to Shetl 2 180' Inner Radius VT- 3RPV-WR54A (B03.100.008) Core Flood Nozzle to Shell 0 - 3RPV-WR54 (B03.090.007) Core Flood Nozzle to Shell 180' - 3RPV-WR54A (B03.090.008) OCONEE 3 BOC03 Scan Increment, Star Scans r 2.29' (0.50' e Nozzle to Shell Weld Q WesDy2e Internationacl St n Scans = .'50' -cort rlood tzztte to Shvil TAN. Star tR CExam EXAMINATION PROGRAM PLAN 2004 --- AI SHEET 21 OF 22 v4uf 52
A p 6Jt 5T-c Poa5z S%-+ 6 START OF CORE SUPPORT LEDGE TAPER © Z = 27 t, g2 FIO5 gaL b
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