ML041170047
| ML041170047 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/09/2004 |
| From: | Rosalyn Jones Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML041170047 (118) | |
Text
Duke R. A.
JONES litPowere Vice President A Duke Energy Company Duke Power 29672 / Oconee Nuclear Site 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax April 9, 2004 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Duke Energy Oconee Nuclear Station, Unit 2 Docket Nos. 50-270 Third Ten Year Inservice Inspection Interval Requests for Relief No. 04-ON-002 and 003 Pursuant to 10 CFR 50.55a(g)(5)(iii), attached is a Request 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 04-ON-002 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.
Request for Relief 04-ON-003 is a similar request but addresses twelve (12) limited ultrasonic examinations on welds specifically associated with the Reactor Vessel as described in the attached request.
During examination of the subject Unit 2 welds, the ultrasonic examination coverage 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 request.
Achievement of 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. duke-energy. corn
U. S. Nuclear Regulatory Commission April 9, 2004 Page 2 If there are any questions or further information is needed you may contact R. P. Todd at (864) 885-3418.
Very y yours, R.
es Sit e President Attachment xc wlatt: L. A. Reyes, Regional Administrator U.S. Nuclear Regulatory Commission, Region II 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 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 April 9, 2004 Page 3 bxc w/att: R. K. Nader 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
Relief Request 04-ON.002 Page 1 of 9 Proposed Relief in Accordance with 10 CFR 50.55a(g)(5)(iii)
Inservice Inspection Impracticality Duke Energy Corporation Oconee Nuclear Station - Unit 2 (EOC-19)
Third 10-Year Interval - Inservice Inspection Plan Interval Start Date= 12-16-1994 Interval End Date=9-9-2004 ASME Section XI Code - 1989 Edition with No Addenda I.
II. & III.
IV.
V.
VI.
VII.
Limited System/
Code Requirement from WVhich Basis for Relief Alternate Justifieation Implementation Area/Weld Component for Which Relief Is Requested:
Examinations or for Granting Schedule I.D.
Relief is Requested:
100% Exam Volume Coverage Testing Relief Number Area or Weld to be Exam Category Examined Item No.
Fig. No.
Limitation Percentage 2-PZR-WP45 Reactor Coolant System Exam Category B-F See Paragraph See Paragraph See Paragraph See Paragraph Pressurizer Spray Item No. B05.040.002A "A"
4J" "K"
"S" Nozzle to Safe-End Section XI, Appendix III, III-Weld 4420 Fig. IWB-2500-8(c) 75% Volume Coverage Limited Scan of Examination Volume C-D-E-F 2LP-189-15 Low Pressure Injection Exam Category B-J See Paragraph See Paragraph See Paragraph See Paragraph System Item No. B09.011.005 "B"
"J"9 "L"
"S" Valve 2LP-47 to Pipe Fig. IWB-2500-8(c) 62.5% Volume Coverage Limited Scan of Examination Volume C-D-E-F 2-SGA-NC System Exam Category C-B See Paragraph See Paragraph See Paragraph See Paragraph WG23-1 Steam Generator A Item No. C02.021.001 "C"
J"i "N"
"S" Main Steam Fig. IWC-2500-4 (b)
Outlet Nozzle to Shell 22.22% Volume Coverage Weld Limited Scan of Examination Volume C-D-E-F
Relief Request 04-ON-002 Page 2 of 9 II. & III.
IV.
V.
VI.
VIl.
Limited System /
Code Requirement from Which Basis for Relief Alternate Justification Implementation Area/Weld Component for Which Relief Is Requested:
Examinations or for Granting Schedule I.D.
Relief is Requested:
100% Exam Volume Coverage Testing Relief Number Area or Weld to be Exam Category Examined Item No.
Fig. No.
Limitation Percentage 2-SGA-NC System Exam Category C-B See Paragraph See Paragraph See Paragraph See Paragraph WG23-2 Steam Generator A Item No. C02.021.002 "C"
&GJi" "N"
"S" Main Steam Fig. IWC-2500-4 (b)
Outlet Nozzle to Shell 22.22% Volume Coverage Weld Limited Scan of Examination Volume C-D-E-F 2-SGA-NC System Exam Category C-B See Paragraph See Paragraph See Paragraph See Paragraph WG23-1 Steam Generator A Item No. C02.022.001 "D"
"r'
."N, "S"
Main Steam Fig. IWC-2500-4 (b)
Outlet Nozzle 88.11% Volume Coverage Inside Radius Section Limited Scan of Examination Volume G-H 2-SGA-NC System Exam Category C-B See Paragraph See Paragraph See Paragraph See Paragraph WG23-2 Steam Generator A Item No. C02.022.002 "D"
..J",
"N" "S"
Main Steam Fig. IWC-2500-4 (b)
Outlet Nozzle 88.11% Volume Coverage Inside Radius Section Limited Scan of Examination Volume G-H 2LP-150-70 Low Pressure Injection Exam Category C-F-I See Paragraph See Paragraph See Paragraph See Paragraph System Item No. C05.011.012 "E"
"1."1
".'T.
"S" Valve 2LP-17 to Fig. IWC-2500-7(a)
Reducer Weld 56.75% Volume Coverage Limited Scan of Examination Volume C-D-E-F 2HP-219-14 High Pressure Injection Exam Category C-F-I See Paragraph See Paragraph See Paragraph See Paragraph System Item No. C05.021.013 F
"J" P
"5" Valve 2HP-409 to Pipe Fig. IWC-2500-7(a)
Weld 37.5% Volume Coverage Limited Scan of Examination Volume C-D-E-F
Relief Request 04.ON-002 Page 3 of 9 I.
II. & III.
IV.
V.
VI.
VII.
Limited System
/
Code Requirement from Which Basis for Relief Alternate Justification Implementation Area/hVeld Component for Which Relief is Requested:
Examinations or for Granting Schedule I.D.
Relief is Requested:
100% Exam Volume Coverage Testing Relief Number Area or Weld to be Exam Category Examined Item No.
Fig. No.
Limitation Percentage 2HP-396-5 High Pressure Injection Exam Category C-F-i See Paragraph See Paragraph See Paragraph See Paragraph System Item No. C05.021.093 4G "i"
.Ps" Valve 2HP-140 to Pipe Fig. IWC-2500-7(a)
Weld 62.5% Volume Coverage Limited Scan of Examination Volume C-D-E-F 2HP-221-22 High Pressure Injection Exam Category C-F-i See Paragraph See Paragraph See Paragraph See Paragraph System Item No. C05.021.115
'p "S"
Valve 2HP-4i0 to Fig. IWC-2500-7(a)
Elbow Weld 62.5% Volume Coverage Limited Scan of Examination Volume C-D-E-F 2-BWST-Low Pressure Injection Exam Category C-F-2 See Paragraph See Paragraph See Paragraph See Paragraph OUT-2 System Item No. C05.070.001 "Irg" "5"
4 saw Pipe to Flange Weld Fig. IWC-2500-7 63.66% Area Coverage Exam Surface A-B See Attachment A for C05.070.001 area/weld locations.
See Attachment B for Steam Generator A Main Steam Outlet Nozzle area/weld locations.
See Attachment C for inspection data on all 11 items with limited coverage.
See Attachment D for Pressurizer Spray Nozzle to Safe-End area/weld locations.
Note: The C05.011, C05.021, and C05.070 welds were inspected in August of 2002 and the B05.040, B09.011, C02.021, and C02.022 items were inspected in October of 2002.
Relief Request 04-ON-002 Page 4 of 9 IV. Basis for Relief Paragraph A: (The Pressurizer Spray Nozzle material is SA508 CL. 1 and the Safe-End material is SB-166. The diameter of the Nozzle to Safe-End weld is 4 inches and it has a wall thickness of.75 inches.)
During the ultrasonic examination of dissimilar metal weld 2-PZR-WP45, 75% coverage of the required examination volume was obtained. Scanning limitations were caused by the taper of the nozzle which prevented scanning from both sides of the weld. The percent coverage reported represents the aggregate coverage from all scans performed on the weld. The examination volume was scanned in two circumferential and one axial direction using 450 shear wave and longitudinal wave search units. In order to scan all of the required surfaces for the inspection of this weld, the 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 valve and pipe material was stainless steel. Weld 2LP-189-15 has a diameter of 10 inches and a wall thickness of 1.0 inches.)
During the ultrasonic examination of weld 2LP-189-15, 62.5% coverage of the required examination volume was obtained. Scanning limitations were caused by the valve configuration which prevented scanning from both sides of the weld. The percent coverage reported represents the aggregate coverage from all scans performed on the weld.
The examination volume was scanned in two circumferential directions using 450 shear waves and in one axial direction using 600 shear and longitudinal waves. 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 was a recordable indication found during the inspection of this weld. It was determined to be a geometric reflector due to root geometry.
Paragraph C: (The Steam Generator shell material is SA212 GR. B and the nozzle material is SA 508 CL. 1. The diameter of the Nozzle to Steam Generator shell weld is 29 inches and it has a wall thickness of 6.75 inches.)
During the ultrasonic examination of welds 2-SGA-WG23-1 and 2-SGA-WG23-2, 100% coverage of the required examination volume could not be obtained. The examination coverage was limited to 22.22%. Limitations were caused by the nozzle configuration. The percent coverage reported represents the aggregate coverage from all scans performed on the weld. The examination volume was scanned with 450 and 600 shear waves from one axial direction. No coverage could be achieved in the circumferential direction or with the straight beam scan because of the interference caused by the nozzle blend radius. The percentage of coverage reported represents the aggregate coverage. In order to scan all of the required surfaces for the inspection of this weld, the nozzles 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 these welds.
Paragraph D:
During the ultrasonic examination of the inside radius sections for 2-SGA-WG23-1 and 2-SGA-WG23-2, 100%
coverage of the required examination volume was not obtained. The examination coverage was limited to 88.11%.
The percentage of coverage reported represents the aggregate coverage. The inner radius examination volume was scanned from the vessel shell side using 60° and 700 shear waves. Duke Energy Corporation had been investigating the use of computer modeling of the nozzles to develop ultrasonic techniques that would achieve 100% coverage of the examination volume. However, these techniques were not ready at the time these examinations were scheduled.
Therefore, a best effort examination was performed. The steam generators will be replaced in the spring of 2004.
There were no recordable indications found during these inspections.
Relief Request 04-ON-002 Page 5 of 9 Paragraph E: (The valve and reducer material was stainless steel. Weld 2LP-150-70 has a diameter of 12 inches and a wall thickness of 1.312 inches.)
During the ultrasonic examination of weld 2LP-150-70, 56.75% coverage of the required examination volume was obtained. Scanning limitations were caused by the valve configuration which prevented scanning from both sides of the weld. The percent coverage reported represents the aggregate coverage from all scans performed on the weld.
The examination volume was scanned using 450 shear waves in two circumferential directions covering 63.5% of the volume and in one axial direction using 60° shear and longitudinal waves covering 100% of the examination volume.
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 valve and pipe material was stainless steel. Weld 2HP-219-14 has a diameter of 4 inches and a wall thickness of.674 inches.)
During the ultrasonic examination of weld 2HP-219-14, 37.5% coverage of the required examination volume was obtained. Scanning limitations were caused by the valve configuration which prevented scanning from both sides of the weld. The percent coverage reported represents the aggregate coverage from all scans performed on the weld.
The examination volume was scanned using 450 shear waves in two circumferential directions covering 50% of the volume and in one axial direction using 600 shear and longitudinal waves covering 100% of the examination volume.
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 G: (The valve and pipe material was stainless steel. Weld 2HP-396-5 has a diameter of 4 inches and a wall thickness of.531 inches.)
During the ultrasonic examination of weld 2HP-396-5, 62.5% coverage of the required examination volume was obtained. Scanning limitations were caused by the valve configuration which prevented scanning from both sides of the weld. The percent coverage reported represents the aggregate coverage from all scans performed on the weld.
The examination volume was scanned using 450 shear waves in two circumferential directions covering 50% of the volume and in one axial direction using 60° shear and longitudinal waves covering 100% of the examination volume.
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 1I: (The valve and elbow material was stainless steel. Weld 2HP-221-22 has a diameter of 4 inches and a wall thickness of.531 inches.)
During the ultrasonic examination of weld 2HP-221-22, 62.5% coverage of the required examination volume was obtained. Scanning limitations were caused by the valve configuration which prevented scanning from both sides of the weld. The percent coverage reported represents the aggregate coverage from all scans performed on the weld.
The examination volume was scanned using 45° shear waves in two circumferential directions covering 100% of the volume and in one axial direction using 600 shear and longitudinal waves covering 100% of the examination volume.
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.
Relief Request 04-ON-002 Page 6 of 9 Paragraph 1: (The diameter of the pipe to flange weld is 14 inches and it has a wall thickness of.375 inches The material was carbon steel.)
During MT examination of welds 2BWST-OUT-2, 100% coverage of the required examination surface could not be obtained. The examination coverage was limited to 63.66%. Limitations were caused because the pipe has minimum clearance from steel support members; thus, access for the inspection of 100% of the weld is not possible. The percentage of coverage reported represents the aggregate coverage. There were no recordable indications found during the inspection of this weld. In order to achieve more coverage, the pipe would have to be relocated to allow full access to MT or PT 100% weld, which is impractical.
V. Alternate Examinations or Testing Paragraph J:
The scheduled 10-year code examination was performed on the referenced area/weld and it resulted in the noted limited coverage. No additional examinations are planned for the area/weld during the current inspection interval.
VI. Justification for Granting Relief Paragraph K:
Ultrasonic examination of areas/welds for item number B05.040 were conducted using personnel, equipment and procedures qualified in accordance with ASME Section XI, Appendix VIII Supplement 10 of the 1995 Edition with the 1996 Addenda as administered by the PDI. Although 100% of the required scanning could not be achieved, the amount of coverage of the examination volume obtained for this weld provides an acceptable level of quality and integrity. In addition to the volumetric examination with limited scan, Duke Energy performed a surface examination (code required) on the B05.040 item and achieved 100% coverage. The result from the surface examination was acceptable. (See Paragraph M for additional justification.)
Paragraph L:
Ultrasonic examination of areas/welds for item number B09.011 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% of the required scanning could not be achieved, the amount of coverage of the examination volume obtained for this weld provides an acceptable level of quality and integrity. In addition to the volumetric examination with limited scan, Duke Energy performed a surface examination (code required) on the B09.011 item and achieved 100% coverage. The result from the surface examination was acceptable. (See Paragraph M for additional justification.)
Paragraph M:
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/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 RCS mass balance calculation. A second 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
Relief Request 04-ON-002 Page 7 of 9 leakage. A third is the level indicator in the Reactor Building normal sump. A fourth is a loss of level in the Letdown Storage Tank. Based on the portions and results of the required volumetric, surface and VT-2 examinations performed during this outage, it's Duke's belief that this combination of examinations provides a reasonable assurance of component integrity.
Paragraph N:
Ultrasonic examination of welds for item numbers C02.021 and C02.022 were conducted using personnel, qualified in accordance with ASME Section XI, Appendix VII. Procedures were in compliance with ASME Section V, Article 4 and Section XI, Appendix I. Due to the design of the Steam Generator Shell and Steam Outlet Nozzle; it is not feasible to obtain the examination scanning and volume coverage required. Duke Energy has examined the weld/area to the maximum extent possible utilizing the latest in examination techniques and equipment. The weld was rigorously inspected by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects. Although 100% of the required scanning could not be achieved, the amount of coverage of the examination volume obtained for this weld provides an acceptable level of quality and integrity.
(See Paragraph 0 for additional justification.)
Paragraph 0:
Duke Energy will use Class 2, Examination Category C-H, pressure testing and VT-2 visual examination to compliment the limited scanning and examination volume 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 (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. The Steam Generator C2.21 Main Steam outlet nozzle welds are located in the reactor building and not accessible for routine inspection. However, Table IWB-2500-1 of ASME Section XI, Class 1, Examination Category B-P, requires that a pressure test be performed after each refueling outage for Class 1 systems. This test requires a VT-2 visual examination for evidence of leakage at normal operating conditions. A portion of this test is near the Class 2 shell to main steam nozzle welds and a leak from the Steam Generator shell to nozzle weld would be observed during this test. Once a leak is identified, its location needs to be determined and assessed. This would provide adequate assurance of pressure boundary integrity. Further, the level of the Reactor Building normal sump is monitored daily and any change in the level or pumping frequency must be evaluated to verify there is no RCS leakage. Due to the location of these nozzles, any leakage would eventually end up in the reactor building sump. All of these together will provide reasonable assurance that if the weld/component developed a leak during a fuel cycle the leakage would be identified.
Paragraph P:
Ultrasonic examination of areas/welds for the item numbers C05.011 and 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% of the required scanning could not be achieved, the amount of coverage of the examination volume obtained for each of these welds provides an acceptable level of quality and integrity. In addition to the volumetric examinations with limited scan, Duke Energy performed a surface examination (code required) on each of the C05.011 and C05.021 items and achieved 100% coverage. The results from the surface examinations were acceptable. (See Paragraph R for additional justification.)
In addition to C05.021 welds that relief is being requested for limited scanning and limited examination coverage, there were 23 additional C05.021 welds that surface and volumetric examinations were performed on. The examinations didn't identify any reportable indications and greater than 90% coverage was obtained on each of the 23 welds. The 23 additional welds were from the same system as the C05.021 welds of this request.
Relief Request 04-ON-002 Page 8 of 9 Duke Energy Corporation does not claim credit for coverage of the far side of austenitic piping 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 sound path leg.
Duke Energy Corporation uses a combination of shear waves and longitudinal waves to examine single sided austenitic piping welds.
The procedures, personnel and equipment have been qualified through the Performance Demonstration Initiative (PDI). However, although longitudinal wave search units were used in the qualification and cracks were detecting through the weld metal, PDI does not provide a qualification for single sided examination of similar metal austenitic piping welds.
Paragraph Q:
Liquid Penetrant examination of area/weld for item number C05.070 was conducted using personnel, equipment and procedures qualified in accordance with the1989 Edition with no Addenda of the ASME Section Xl Code. Although 100% coverage of the examination area could not be achieved, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity. (See Paragraph R for additional justification.)
Paragraph R:
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 (surface 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 activity is that leakage from this weld would be detected by Operations personnel during their regular rounds. The Nuclear Equipment Operator has been trained to look for any unusual conditions, such as leaks. The C05.011, C05.021, C05.070 items, and item C05.051.012 in this request are 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. All of these activities together will provide reasonable assurance of weld/component integrity.
Duke Energy has examined the weld/component referenced in this request to the maximum extent possible utilizing the latest in examination techniques and equipment. The welds/components 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 this outage and the additional pressure testing (VT-2) exams, it's our opinion that this combination of examinations provides a reasonable assurance of component integrity.
VII. Implementation Schedule Paragraph S The scheduled third 10-year interval plan code examination was performed on the referenced area/weld resulting in limited volumetric coverage. No additional examinations are planned for the area/weld during the current inspection interval. With the exception of welds on the Oconee Unit 2 Steam Generators (because the generators will be replaced in the spring of 2004), 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.
Relief Request 04-ON-002 Page 9 of 9 VIII. Other Information The following individuals contributed to the development of this relief request:
James J. McArdle (NDE Level III Examiner) provided Sections 1I through V and part of Section VI.
B. W. Carney, Jr. (Oconee Engineering) provided part of Section VI.
Larry C. Keith (Oconee ISI Plan Manager) compiled the remaining sections.
Sponsored By:
Co /*dP Date K (
6 Approved By:
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DUKE POWER COMPANY Exam Start:
1129 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish:
1146 Revision 4 Station:
Oconee Unit:
2 Component/Veld ID: 2-PZR-WP45 Date:
10/23/2002 Weld Length (in.):
14.1 Surface Condition:
FLUSH Lo: 9.1.1.1 Surface Temoerature:
84 0
F Examiner: James L. Panel/
A' Level: 11 Scans:
Pyrometer S/N:
MCNDE 27228
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Cal Due:
12/12/2002 Examiner: Marion T.Weae Level:
11 45 0 72 dB 70 °3 dB j
Configuration:
NOZZLE TO SAFE END Procedure: NDE-610 Rev: 4 FC:
45T ° dB 70T a dB Flow 60 dB NOZZLE to SAFE END Calibration Sheet No:
6Scan Surface: OD CbaoST dB Applies to NDE-680 only 0202068, 0202069 Other:
35 - 61 dB Skew Angle:
IND Max Max Max Li L2 WI MpF W2 Mp2
- Dir, Surf.
Scan Damps 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac DO 1OT W ITE HMA HMA HMA HMA HMA HMA D
NOT WRIT 50%dac 50%dac 50%dac 50%dac 50%dac 50%dac IN THIS SPACI.
IN T IS 100%dac 100%dac 100%dac 100%dac 100%dac 100%dac NRI 45
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I I
I Remarks: *FC 97-01, 98-20, 01-05, 02-10 HSBCT
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Limitations: (see NDE-UT-4) El 90% or greater coverage obtained: yes-a no M %h 25-ot Sheet__/
of3 Reviewed BLevel:
Date:
Authorized,nsector:
Date:
Item No:
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205.040.002A r
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DUKE POWER COMPANY FORM NDE-T-4 ISI LIMITATION REPORT Revision I Component/Weld ID: 2-PZR-WP45 Item No: B05.040.002A Remarks:
SURFACE BEAM DIRECTION TAPER OF NOZZLE 100% COVERAGE El NO SCAN BY 1 SCAN FROM SAFE END SIDE.
OLIMITEDSCAN 9 1 0 2 O 1 0 2 a cw o ccw FROM L N/A to L N/A INCHES FROM WO 0
to BEYOND ANGLE:
0 0 0 45 0 60 0 Other FROM 0
DEG to 360 DEG SURFACE BEAM DIRECTION 0
NO SCAN O LIMITEDSCAN 0 10 2 O3 1
2 a cw o ccw FROM L to L INCHES FROM WO to ANGLE:
0 0 0 45 0 60 0 Other FROM DEGto DEG SURFACE BEAM DIRECTION 0
NO SCAN 0
LIMITEDSCAN 0 1 0 2 0 1 O 2 0 cw O ccw FROM L to L INCHES FROM WO to ANGLE:
0 0 0 45 0 60 0 Other FROM DEGto DEG SURFACE BEAM DIRECTION O NO SCAN 0
LIMITEDSCAN 1 0- 2 0 1 0 2 0 cw a ccw FROM L to L INCHES FROM WO to ANGLE: 0 0 0 45 0 60 0 Other FROM DEG to Prepared By:
Level:
Z Date: /
o, Sketch(s) attached O yes 0 no Sheet Z of Reviewed By:
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Date:
Authorized Inspectop Date:sc/,i L mv _
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DUKE POWER COMPANY NDE-UT-5 UT PROFILE/PLOT SHEET Revision 1 EXAMINATION SURFACE 1 EXAMINATION SURFACE 2 4
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Date: /o-Zi-0L 5
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DUKE POWER COMPANY FORM NDE-UT-10 ULTRASONIC INDICATION RECORD FOR PIPING Revision 0 Station:
Oconee I Unit:
2 ComponentAWeld ID: 2LP-189-15 Date:
10/23/2002 Surface Condition:
Gl UND Item No: B09.011.005 Examiner Jay A. Eaton vel:
Ill Procedure:
NDE-600 Rev:
14 FC:
0z -I Examiner Gayle E. Hou~er Level:
IlIl Lo:
9.1.1.1 Configuration:
CIRC.
Calibration Sheet No:
0202066, 0202067 S2 VALVE to Si PIPE Scan Surface: OD Mp W
L LI L2 Beam Exam IND 4
FSH Max Max Max 20 % FSH 20 % FSH Dir.
Surf.
Scan Damps Remarks 1
60*
159 1.8 1.6 RT3 360 INT.
2 1
AXIAL NO 2
60L 141 2.0
.800 RT2 360 INT.
2 1
AXIAL NO
/1-I S
i DUKE POWER COMPANY NDE-UT-5 UT PROFILE/PLOT SHEET Revision 1 EXAMINATION SURFACE 1 49t-K 3
li IIIII 1111 111 11 WI:ELD EXAMINATION 4URFACE 2 3 VQ I'VE4 2
1 III I Il A1-1 2
I IIIIIIIIIIIIIIII I111
.5
%.I I
-2 I
- 21.
- *E~ 5,.2 % /.o f 7W e s 1 :
.d~
t 2.5 3
E
.i I
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Component ID/Weld No.,z2 C PE
- /r
- Remarks:
M W xc:
7k ek A
IR%
=
e=J Pen In00)
'I/
i Cr
--1 ~XProfile taken' 270 at:, 2a D 90 180 Sheet 2 of..L L&td I-
,c, 2 U) a)
I U.J L.4j VW J r
LxI1 r
_I
& L (111I V~.0-L
/s Examiner:
4k?--
4 Item No: fO9c. f)l (. OX0-Level: 4 Date: 6
-s i2-L
- IDate:
,,/S Reviewed By:' 'VA,
-A A t h e, e R
Authorizedd nspectorr.
7~7= '-
d 7,
C'
.I DUKE POWER COMPANY Form NDE-UT-8 ULTRASONIC INDICATION RESOLUTION SHEET Revision.1 Acceptance Standard:
s" 9h1 oj Q3l1Jo)
INDICATION #1 IS A 360° REFLECTOR DUE TO ROOT GEOMETRY. A 70'SHEAR WAVE AND WSY 70 WAS USED AS CONFIRMATION. ADDITIONAL REVIEW OF RT FILM REVEALED ROOT CONCAVITY.
INDICATION #2 IS A 360° GEOMETRIC REFLECTOR FROM THE ID TAPER DUE TO THE VALVE CONFIGURATION. MANUAL PLOTTING OF THE INDICATION SHOWS THAT IT IS ALSO OUT OF AREA OF INTEREST.
Initial o Final cSI ANII I DATE..I D-AT HSBCT Item No: 809.011.005 Acceptable Indications: IND. #1 & #2 Rejectable Indications: N/A These indications have been compared with previous ultrasonic data 0 Yes ° No previous data available Examiner:
f Level:
Date:
10/23/2002 Sheet to e.
Date:,
3 of (1:1 F..
Date:
Authorized Inspector
/ 0 Z-0 7-.
-311t13
'S I
DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2LP-189-15 Item No: B09.011.005 Remarks:
SURFACE BEAM DIRECTION NO SCAN DUE TO VALVE G NO SCAN CONFIGURATION BUT 100%
0 LIMITED SCAN 0 1 0 2 0 1 0 2 0 cw O ccw COVERAGE OBTAINED USING 0
LIITEDSCANMULTIPLE BEAM ANGLE FROM L 0
to L 33.57 INCHES FROM WO CL to BEYOND DIRECTIONS.
ANGLE:
0 0 0 45 El 60 0 Other FROM DEG to DEG SURFACE BEAM DIRECTION 0
NO SCAN 0
LIMITED SCAN 0 1 0 2 0 1 0 2 0 cw O ccw FROM L to L INCHES FROM WO to ANGLE:
0 0 10 45 0 60 0 Other FROM DEG to DEG SURFACE BEAM DIRECTION 0
NO SCAN 0
LIMITED SCAN 0 1 0 2 0 1 01 2 0 cw O ccw FROM L to L INCHES FROM WO to ANGLE:
O0 0 45 0 600 Other FROM _
DEG to DEG 0 NO SCAN 0
LIMITED SCAN SURFACE 0 1 0 2
BEAM DIRECTION 0 1 O 2 O cw O ccw FROM L to L INCHES FROM WO to ANGLE:
O o 0 45 0 Prepared By:
Reviewed By:
I f" Icm j; no Sheet Y -of 6
i r
3 Date:.,,
,S2
° =
/
I I
DUKE POWER COMPANYl D-5 UT PROFILE/PLOT SHEET Revision 1 EXAMINATION SURFACE 1 WI
[III.I 'III IIII III 2
1 1
Ibi wIII LLI] iiiibtu ELD 1
EXAMINATION SURFACE 2 2
111111 3Val>L-4 II 1111 1111 1111III.
I a
.5
\\ -x 1.5 2
jFgv X,'
oC d/
2.5 i
Y GC.kA k 3
7 0 7 Componer t ID/.g0/eld V~~Og(~(R~t Remarks.
-t/t 6? 9Th"A-()ia4 -
Q(U5us e
AT oL 6umA Item No:
.c6 Prfile taken 270 at:J/SD D 90 180 Sheet < of L "d E, z; 1 v
I Examiner L
k-e Level: 7:E I Date:'t/ ajb2. 1 Reviewed By:
4 A I Level: -
Date:,;zt, Authorized Inspector.
Date:
/
-W.--
y...
DUKE POWER COMPANY Form NDE-UT-9 ULTRASONIC BEAM ANGLE MEASUREMENT RECORD Revision 3 1<1 'I
- 1. Take thickness measurements between.
wedge locations.
- 2. Place search unit on straight turn of pipe, and peak the signal.
- 3. Measure distance (d) between exit points.
- 4. Calculate beam angle with formula as shown using measured wall thickness.
tan 0 =
(d/2) t
- 5. Use the measured beam angle to determine coverage and when plotting any indications.
Pipe Size:
10" Pipe Schedule:
1" THICK For thin wall pipe use 2nd Vee path tan o =
(d12) 2t Nominal 45 deg: d= __0 _; t= _ 0 _; measured angle=
0.00 deg Nominal 60 deg: d= _ 3.46
- t= _ 1_ _; measured angle" 59.97deg Nominal 70 deg
- d= __0 _ ; t= _ 0 _; measured angle=
0.00 deg Item No.
B09.01 1.005 Level Date i1-1 I7 C."
Date
C:1
)
S..
DUKE POWER COMPANY Exam Start:
1155 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish:
1221 Revision 4 Station:
Oconee Unit:
2 Component/Weld ID: 2-SGA-WG23-1 Date:
101161202 Weld Length (in.):
92.0 Surface Condition:
AS GROUND Lo:
9.2.3 Surface Temperature:
109
° F Examiner David Zimmerman b
Level: ill Scans:
Pyrometer S/N:
MCNDE 27227.
Level:Cal-Due:
12/12/2002 Examiner: Winfred C. Leepe vel: II 45 0 64.5 dB 70 D dB_._d f
,<d
_0.Configuration:
CIRC. EWLD Procedure: NDE-820 Rev: 0 FC:
45T 0 64.5 dB 70T ° dB S2 Flow Si N/A 60 El 73.0 dB NOZZLE to SHELL Calibration Sheet No:
60T 0 73.0 dB Scan Surface: OD 022340023 Applies to NDE-680 only 0202034, 0202035 Other dB Skew Angle:
N/A Max Mp W
L Beam Exam IND X Max Max Max LI L2 WI MpI W2 Mp2 Dir.
Surf.
Scan Damps Ref 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac 0
NOT WRIT DO NOT WRITE HMA HMA HMA HMA HMA HMA 50%dac 50%dac 50%dac 50%dac 50%dac 50%dac IN THIS SPACI.
IN T IS 100%dac 100%dac 100%dac 100%dac 100%dac 100%dac NRI Remarks:
Limitations: (see NDE-UT-4) 0 90% or greater coverage obtained: yes 0 no 0 4.
Date:
Sheet L/ of K l
Item No:
C02.021.001 1
-3
- E o :.
o 2.!n (I
311403Initial 0,
Final 3111 IANI
~DATE.
C J
FORM NDE-IJT-4 DUKE POWER COMPANY ISI LIMITATION REPORT Revision 1 ComponentNWeld ID: 2-SGA-WG23-1 Item No: C02.021.001 Remarks:
SURFACE BEAM DIRECTION NOZZLE CONFIGURATION 0E NO SCAN.
OLIMITEDSCAN 1 E 2 2
El cw ccw FROM L N/A to L N/A INCHES FROM WO TOE to BEYOND ANGLE:
0 0 0 45 G 60 0 Other FROM 0
DEG to 360 DEG SURFACE BEAM DIRECTION 0
NO SCAN O LIMITED SCAN 0 10 0
2 2
cw o ccw FROM L to L INCHES FROM WO to ANGLE:
0 0 0 45 0 60 0 Other FROM DEG to DEG SURFACE BEAM DIRECTION 0
NO SCAN O LIMITEDSCAN 0 1 0 2
2O cw l
ccw FROM L to L INCHES FROM WO to ANGLE:
0 0 0 45 0 60 0 Other FROM DEG to DEG SURFACE BEAM DIRECTION 0
NO SCAN O LIMITEDSCAN 03 1 0 2
O 1 O 2 Oc Cw O ccw FROM L to L INCHES FROMWO to ANGLE:
0 0 0J 45 0 60 0 Other FROM DEG to It
_m Prepared By:
DvId K. Zimi Level:
III Date: 10/16/2002 Sketch(s) attached 0l yes
- no Sh Reviewed By
Authorized Inspect or<~~"
leet 2 of 6 R
M _
I
Attachment C Page /z of SI DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0 Examination Volume/Area Defined 0 Base Metal 0
° Near Surface 0 Boltinq El Inner Radius Area Calculation Volume Calculation 2.25 IN. X 4.0 IN. = 9.0 SQ.IN.
9.0 SQ.IN. X 92 IN. = 828 CU.IN.
Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Percent Coverage Scan # Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.in.)
tL 1
45160 2
45/60 3
45160 4
45160 2
1 Cw CCw
/J A 9.0 0.0 0.0 0.0 0.0 92 92 92 92 0
828 0
0 0
828 828 828 828 828 3312 8s n S
0
,?,Z ~
o
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CP4 31(4 13 7hty 3Mv CLAED ( 0%)-.
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DUKE POWER COMPA.
Y Ultrasonic Beam Spread Measurement Sheet I
NDE-4)6 I
I Revision I I
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Oz g e-I Examiner.
Level:
Date:'
ReviewedBy:
Level:
Date:
Authorizedppector:
Date AA
/o m/all"
- E
_ 5 r^ =1 5
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5 DP Z
DUKE POWER COMP..AY Ultrasonic Beam Spread Measurement Sheet NDE-%_.016.
Revision 1..
I I'
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,3 W2 /°.Y Mp2
/. Y Calibration Sheet No:
/
Examiner.
Level:
Date:
Reviewed By:
Level:
Date:
Authorized Inspector.
Date:
I?
iv
- o. g.-t16tl3 1 d/
a. /y1 I
I
C.
..-J DUKE POWER COMPANY Exam Start:
1225 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish:
1250 Revision 4 Station:
Oconee Unit:
2 Component/Weld ID: 2-SGA-WG23-2 Date:
10116/202 Weld Length (in.):
92.0 Surface Condition:
AS GROUND Lo:
9.2.3 Surface Temoerature:
109
° F Examiner: Larry Mauldin
&.Level:
11 Scans:
Pyrometer S/N:
MCNDE 27227 Cal Due:
12/12/2002 Examiner: James L. Panel,,Level:
II 45 E 64.5 dB 70 °3 dB Configuration:
CIRC. WELD Procedure: NDE-820 Rev: 0 FC:
45T 0 64.5 dB 70T 2 dB S2 Flow Si N/A 60 0 73.0 dB NOZZLE to SHELL Calibration Sheet No:
60T 0 73.0 dB Scan Surface: OD 0202037, 0202038 Applies to NDE-680 only Other dB Skew Angle:
N/A Max MP W
L Beam Exam IND #
Max Max Max LI L2 WI MpI W2 Mp2 Dir.
Surf.
Scan Damps Ref 4
O 5
20%dac 20%dac 20%dac 20%dac 20%dac 20%dac D
NOT WRIT
)PW I
DO IOT W ITE HMA HMA HMA HMA HMA HMA D,
W b
N b
IS SPaCE 50%dac 50%dac 50%dac 50%dac 50%dac 50%dac IN THIS SPACE I
T -II S1kE100%Mdac 1100%dac 1100%dacl 00%dac 100%dac 100%dacl1 Remarks:
Limitations: (see NDE-UT-4) 0 90% or greater coverage obtained: yes Cl no E Sheet/
o f e
Reviewed By:
Level:
Date:
Authorized Insoector:
Date:
Item No:
,."C.2
<4/
C02.021.002 c41xj1/2,-
Initial 1; Final ANFI DATE T 'I I
C
!I DUKE POWER COMPANY FORMNDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2-SGA-WG23-2 Item No: C02.021.002 Remarks:
SURFACE BEAM DIRECTION NOZZLE CONFIGURATION El NO SCAN O LIMITEDSCAN
° 1 ID 2 E
O1 13 2 a cw E ccw FROM L N/A to L N/A INCHES FROM WO TOE to -
BEYOND ANGLE:
0 0 El 45 0E 650 0 Other FROM 0
DEG to 360 DEG SURFACE BEAM DIRECTION O
NO SCAN O LIMITED SCAN
° 1 0 2 O 1 0 2 a cw a ccw FROM L to L INCHES FROM WO to ANGLE:
0 0 0 45 0 60 0 Other FROM DEG to DEG SURFACE BEAM DIRECTION 0
NO SCAN O LIMITEDSCAN 0 1 ° 2 O 1 O 2 O cw O ccw FROM L to L INCHES FROM WO to ANGLE:
0 0 0 45 0 60 0 Other FROM DEG to DEG SURFACE BEAM DIRECTION 0
NO SCAN 0
LIMITED SCAN 0 1 0 2
0 1 a 2 O cw O ccw FROM L to L INCHES FROM WO to I.
ANGLE:
0 0
0 45 0 60 0 Other_
FROM____ DEGto Prepared By: Larry E. Mauldi vel:
11 Date: 10116/2002 Sketch(s) attached El yes 0 no Sheet 2 of___
Reviewed By: J',/)
A Date:
O?lAuthorized Inspector Date:,.A Initial q Final Bl ANQ II 4 DA7TE-T-11-l UCRT
I I
AttachmentC Page 8 °ofS DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination VolumelArea Defined 0 Base Metal 0
Weld 0 Near Surface
° Boltinq
° Inner Radius Area Calculation Volume Calculation 2.25 IN. X 4.0 IN. = 9.0 SQ.IN.
9.0 SQ.IN. X 92 IN. = 828 CU.IN.
Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Scan # Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.in.)
Percent Coverage W%
1 L§'4(a 3 4e6c, z
c.ic bZ23 I
0.0 Ciz 0
0.0 L4 Lj4S4 CCM IKUNCD Kii A0IA WA I
f-0.0 5/L103 o.C
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,CLAIMED (0%)-
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a 0
99 o c-5-oy initial 0 Final a ANII -
DATE HSBCT
/IIItem No:
C02.021.002 Prepared By: Larry Mauldlin Level:
II Date: 10/16/2002 Reviewed By:
C5 Level:
Date:
l Vi7
a-asw c.
-/
0 No z z iLF cde AiS S OIoS' I1
.5CAL4-
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Ultrasonic Beam Spread Measurement Sheet NDE-IJ J..
I Revislon 1 I
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Calibration Sheet No:
a 037 Exa aner.
Level:
Date:
Reviowed By:
Level:
Date:
Authorized Inspector.
Date:
_72
~
A i T / / 0 t 'a /1) 72
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DUKE POWER COMPA*'-'
Ultrasonic Beam Spread Measurement Sheet.
NDE-FI Revision 1
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1.0 Callbration Sheet No:
0 3
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Level:
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Reviewec, By:
Level:
Date:
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Date:
h/ia.
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DUKE POWER COMPANY Exam Start:
1211 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish:
1239 Revision 4 Station:
Oconee Unit:
2 Component/Weld ID: 2-SGA-WG23-1 Date:
1011612002 Weld Length (in.):
N/A Surface Condition:
AS GROUND La:
9.2.3 Surface TemPerature:
109 F
Examiner: David Zimmerman Level: ii Scans:
Pyrometer S/N:
MCNDE 27227
,,y PsCal Due:
12/12/2002 Examiner Winfred C. Leeper evel:
II 45 ° dB 70 E 75.0 dB JC
.Configuration, INNER RADIUS Procedure: NDE-680 Wv: 2 FC:
45T ° dB 70T E 75.0 dB N/A Flow N/A 60 0 73.0 dB N/A to NIA Scan Surface: OD Calibration Sheet No:
60T E 73.0 dB Apples to NDE-680 only 0202036, 0202040ApletoNE60ny 0 Other dB Skew Angle:
Max Mp W
L Beam Exam IND # 2$
Max Max Max LI L2 WI MpI "a
Mp2 Dir.
Surf.
Scan Damps Ref 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac DO 14OT W ITE HMA HMA HMA HMA HMA HMA D
NOT WRI IN T IS SP CE 50%dac 50%dac 50%dac 50%dac 50%dac 50%dac IN THIS SPAC 100%dac 100%dac 100%dac 100%dac 100%dac 100%dac NRI Remarks:
- 02-03, 02-08 Limitations: (see NDE-UT-4) 10 90% or greater coverage obtained. yes
- no 0 SheetL/
of 4 Reviewed Bv:
Level:
Date:
Authorized Insoector:
Date:
Item No:
(
//a-'B
/0 a C02.022.001 I gj >
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Attachment C Page l3 of 5?>
DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0 Examination Volume/Area Defined 0 Base Metal
° Weld
° Near Surface
° Bolting 0 Inner Radius Area Calculation Volume Calculation SEE DRWG.
18.5 SQ.IN.
18.5 SQ.IN. X 92 IN. = 1702 CU.IN.
Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Scan # Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.in.)
Percent Coverage 1
6017O CW 16.3 92 1499.6 1702 2
60170 CCW 16.3 92 1499.6 1702 2999.2 3404 88.11 Item No:
C02.022.001 Prepared By: Larry Mauldin Level:
II Date:10/16/200, Reviewed By:
Level:
A, Date: lo l51MZ
@okll:7&2 Jlt'%i O-rLL.sr A/0o77, Z.9 BALD soA -Wd Zs-I SLYY A.
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AItamnmentU Stcck Code No. 89203 Page 2Sof S'?7i Station.J.2t 1i,
____Unit ___ Rev.
File No.
Sheet Of Subject ex 42ak scwf I.
4 Date _
- Prob No.
Checked by D.ate
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DUKE POWER COMPANY Exam Start:
1208 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish:
1237 Revision 4 Station:
Oconee Unit:
2 Component/Weld ID: 2-SGA-WG23-2 Date:
10/16/2002 Weld Length (in.):
N/A Surface Condition:
AS GROUND Lo:
9.2.3 Surface Temrerature:
109 F
Examiner: Larry Mauldin i
Level: II Scans:
Pyrometer S/N:
MCNDE 27227
~&
ACal Due:
12/12/2002 Examiner: James L. Panel Level: II 45 a dB 70 0 75.0 dB
, aConfiguration:
INNRE RADIUS Procedure: NDE-680 Rev: 2 FC:
45T ° dB 70T El 75.0 dB N/A Flow N/A
_El_
6 73.0 dB N/A to N/A Scan Surface: OD Calibration Sheet No:
60T a 73.0 dB Aple to On 020239,00204 Applies to NDE-680 only 0202039, 0202041 Other:
dB Skew Angle:
Max Mp W
L Beam Exam IND #
e Max Max Max Li L2 W1 Mp1 W2 Mp2 DIr.
Surf.
Scan Damps R ef 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac DO NOT W ITE HMA HMA HMA HMA HMA HMA D
NOT WRIT IN T IS SP CE 50%dac 50%dac 50%dac 50%dac 50%dac 50%dac IN THIS SPACE.
IOO%dac 100%dac 100%dac 100%dac 100%dac i00%dac Remarks:
- 02-03, 02-08 Limitations: (see NDE-UT-4) 0 90% or greater coverage obtained: yes ° no 0 Sheetj
_ of Y
Reviewed Bv:y
,K, Level:
Date:
Authorized Inspectorr Date!
Item No:
4/
C02.022.002 I
_ g oo.
I%
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Attachment C i Page a-of s, DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0 Examination VolumelArea Defined
°3 Base Metal
° Weld 0 Near Surface a Boltinjq 0 Inner Radius Area Calculation Volume Calculation SEE DRWG.
18.5 SQ.IN.
18.5 SQ.IN. X 92 IN. = 1702 CUN.
Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Percent Coverage Scan # Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.1n.)
Item No:
C02.022.002 Prepared By: Larry Mauldin Level:
II Date: 10116/200,l Reviewed By:
Level:
n Date: lo olzl
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1054 Revision 2 Station:
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2 Component/Weld ID: 2LP-150-70 Date:
8/5/2002 Nominal Material Thickness (in):
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93 Deg F Measured Material Thickness (in):
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MCNDE 27228 Surface Condition:
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0920 NDE-UT-3A ULTRASONIC EXAMINATION DATA SHEET FOR LAMINAR REFLECTORS Exam Finish:
0923 Revision 2 Station:
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Component/Weld ID: 2HP-219-14 Date:
8/7/2002 Nominal Material Thickness (in):
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14.1 Surface Temperature:
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1428 Revision 2 Station:
Oconee Unit 2
Component/Weld ID: 2HP-396-5 Date:
8/7/2002 Nominal Material Thickness (in):
0.531 Weld Length (in.):
14.1 Surface Temperature:
107 Deg F Measured Material Thickness (in):
.559.
Lo:
9.1.1.2 Pyrometer S/N:
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AS GROUND Calibration Sheet No:
Cal Due:
12/10/2002 Examiner Marion T. Weave Level:
II 0202023 Configuration:
Circ. Weld Examiner Winfred C. Leeperl /-
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II S2 Flow 51 Valve to Pipe Procedure:
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SURFACE BEAM DIRECTION VALVE CONFIGURATION El NO SCAN O LIMITElSCAN
° 1 2 2 1 0 2 0 cw o ccw FROM L N/A to L N/A INCHES FROM WO C/L to BEYOND ANGLE:
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1004 NDE-UT-3A ULTRASONIC EXAMINATION DATA SHEET FOR LAMINAR REFLECTORS Exam Finish:
1008 Revision 2 Station:
Oconee Unit:
2 Component/Weld ID: 2HP-221-22 Date:
81712002 Nominal Material Thickness (in):
0.531 Weld Length (in.):
14.1 Surface Temperature:
92 Deg F Measured Material Thickness (in):
0.540.
Lo:
9.1.1.2 Pyrometer S/N:
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II S2 Flow Si Procedure:
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DUKE POWER COMPANY FORMNDE-UT-ISI LIMITATION REPORT Revision 1 ComponentN/eld ID: 2HP-221-22 Item No: C05.021.115 Remarks:
SURFACE BEAM DIRECTION VALVE CONFIGURATION G NO SCAN O LIMITEDSCAN 0 1 0 2 0 1 0 2 0 cw ° ccw FROM L to L -
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0 0 0 45 0 60 O Other FROM 0
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Attachment C l Page si of Si.
DUKE POWER COMPANY Limited Examination Coverage Worksheet NDE-91-1 Revision 0 Examination Volume/Area Defined E Base Metal 0
° Near Surface
° Boltinq 0 Inner Radius Area Calculation Volume Calculation SEE DRWG.
SEE DRWG.
Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required C
Scan # Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.in.)
Percent overage V1r4 ALL 457/60 AXIALICIRC.
.285 14.1 a.y2
.tw t3 I 423 i95.4
(- ;
o7-2 0
07--7./b Cy
?t47/
I Item No:
C05.021.115 Prepared By: David K. Zimmerman 0 - r, Level:
III Date: 1O/281200 Reviewed By: P a4 7
6 Level:
'15 Date: /0.-i.O
I I
DUKE POWER COMPANY DE-UT-5 UT PROFILE/PLOT SHEET Revision 1 EXAMINATION SURFACE 1 EXAMINATION SURFACE 2 WELD 4
3
- 2 1I iii liii liiilii 1111 11111
.1 L
1 2
3
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- 7
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- Remarks:
I Item No: Cn5 cs2. I u
Profile taken 270 t atJ L
90 180 SheetL of-L.
I CM 3 i
O.
Examiner. 19J.gA*l
-?--
_ILevel:
I Date:,e)/lz/oz Reviewed By:
b
,,Sg/
I Leve-:
Date:
3-.o IFAtoiedSseto.
~Date:, 3z Authorized Inspectors Date: 3
(
DUKE POWER COMPANY ND-5 UT PROFILE/PLOT SHEETr Revision l EXAMINATION SURFACE 1 WELD EXAMINATION SURFACE 2 4
3 2
1 I
.I 1' 11 1.1 1 III I.II I
1 2
3 4
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. 3 Component ID/Weld No. 7-Eg-Z
?7Z l Remarks:
Item.
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U Profile taken 0
270 at:-- -- kA 90 180 Sheet.Lof L I,>~
i 4 -6 l -n Examiner.
I Level: iZ I Date: tA/rtA/oz Reviewed By:
)
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ILevelf-.V I Date: s-sbz I uhrze n:Wor(c-7 Date: ; r/<
jAuthorized Inspector!
c'".
Date: 03
rX"1 C
DUKE POWER COMPANY NDE-US.
UT PROFILE/PLOT SHEET Revislon 1 EXAMINATION SURFACE 1 EXAMINATION SURFACE 2 WELD 4
3 2
1 I
II.11.1 111 1 1 111 1 h A I
i.
1 2
3
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Component ID/Weld No.._-aP Z7
- 7 u
- Remarks:
Item No: c c oeite
.115 Eviewe B Level: -,
Date:
.e,0a Reviewed By.:
< /
Level:
Date: 3-50 270 90
.0.
. M M
! LI =
- I NQ:
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180 Sheet-LofLL Authorized Inspectod / e_--r,.
Date: 3 Date: 3 -//l_&
Attachment C, Page r8of 5?
I Form NDE-35A I Revision 3 DUKE POWER COMPANY STATION Oconee UNIT 2
LIQUID PENETRANT EXAMINATION REPORT Weld/ID No. 2-BWST-OUT-2 Material Type: 0 SS f CS 0 Inconel Diameter 14 Schedule/Thickness L.375 1l ISI 0 PSI 0 Other Procedure Rev. No.
19 Field Change No.(s) N/A W/O No.
98473656 SKETCH OF ITEM EXAMINED Surface Temperature 840 M&TE S/N:
MCNDE 27227 Penetrant Materials Category:
A E3 A(SE) O B O C O D O3 A(SE) Approved Penetrant Materials Data:
Batch Numbers Cleaner 01B07K Penetrant OOJ07K Developer 98J07K Emulsifier Fluorescent 0
Nonfluorescent w Black Light Intensity Verified Acceptance Standard:
A 0
D 0 G 0 K 0 Time
\\p, Date ez\\N Other.
B O E Q H O L 0 Light Meter S/N: t5 I P.
C 0 F E J ° M 0 Ind.
T Indication Reference Documents Recordable Reportable No.
Type/Dirnensions IeItI PIP S/N:
Rejectable O Acceptable E Exam Limitations:
[ Yes (p3. G, 4p % Examined 0
No (100% Examined)
Comments:
Examiner: Daryl L. Robinson
-&g,_
Level:
II Date:
8/2/2002 Examiner:
Level:
Date:
Reviewed By:
c Level:
25Date:
,-o_
Finalejw V/
Date ANII Bview Date Item No.
2SLv9
.cJ 4
C05.070.001 6X f
Attachment C Page s of. ?
DUKE POWER COMPANY l
NDE-91-1 Limited Examination Coverage Worksheet I
Revision O Examination Volume/Area Defined Base Metal N?
Weld 0 Near Surface E Bolting
° Inner Radius Area Calculation Volume Calculation
- Surface Examination( NDE-35)
Required area - 1.375 in.(w) X 43.98 in.(l) = 60.47 in.
sq.
Area inspected - 1.375 in.(w) X 28.0 in.(i) = 38.5 in.
sq.
Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Scan #Angle Direction (sq.in.)
(in.)
(cu.in.)
.,eu.in.)
Percent Coverage N/A N/A N/A 38.5/60.47
- q.
63.66 Item No:
C05.070.001 Prepared By: Daryl L Robinson
'az1 Level:
II Date: 8/2/2002 Reviewed By:
- 77j73, Level:
_ZZ7r.
Date: ?/13/OZ-
L s
. -- jm'.
,d I
IDENT PIECE D AM.
THICK.
C.
NO.
DNo.,THCK.
QT
'WP2-2 I TO I N/A 6.188 I
i 1vPi-2 2 TO 2 N/A 6.188 2
I WPI-3 3 TO 3 N/A 6.188 3 t 1
WP3-1 I TO 2 84'I, D.
6.188 4 3 WP3-2 2 TO 3 84!' 1. D.
6.188 5
I
,WP4 3TO4841 84" I.D.
6.188 6
WP6 40 TO 41 84 1.D.
13.563 8
I WP7-1 4TO4Oa41 N/A 6.188 9
WP7-2 4TO 4Oa4 N/A 6.188 30 6
WP15 6 TO 8 4.750 331 3
NTI.
Attachment D Page I of 1 F
v vP WP23 8 TO 37 101*' NPS 1.063 32 3
P 63-4(W-X QUADY P63-Y-Z UDAT 82 \\TOP VIEW
\\
\\WP63-4 (W-X QUADRANT)
.\\
oWP63-5 (Y-Z oUADRANT)
WP63-6 (Z-W QUADRANT)
WP26-4 (W-X QUADRANT)
WP26-5 (Y-Z QUADRANT)
WP26-6 (Z-W QUADRANT)
-1 1
1 WP26-1 30 TO 4 6.186 37 I
WP26-2 30 TO 4 6.188 40 WP26-3 30 TO 4 6.188 41 2 WP26-4 30 TO I 6.188 42 6
WP26-5 30 TO I 6.188 45 1L WP26-6 30 TO I 6.188 110 81 VWP26-7 30 TO 4 6.188 WP28 TO 4 a 40 84 1. D.
4.750 WP33-1 31 TO 5 4.750 WP33-2 31 TO 5 4.750 WP33-3 31 TO 5 4.750 WP34 9 TO 5 4.750 WP45 45TO 9 4"NPS 0.750 WP63-1 42 TO 30 1.1875 WP63-2 42 TO 30
- 1.1875 WP63-3 42 TO 30 1.1875 WP63-4 42 T0 30 1.1875 WP63-5 42 TO 30 1.1875 WP63-6 42 TO 30 1.1875 WP7 6 I TO5 84" 1. D.
4.750 WP82-X I20 TO 3 N/A 3.500 v2Pez-XY 110 TO 3 N/A 3.500 WEI WP82-Y 110 TO 3 N/A 3.500
- 1. D. NO-I.r AV_
0 01 -
-WP7-2 (W-X QUADRANT)
\\-, ~
REF. DRAUIINGS r
A--
WI OM 1201-456
-to II :f,?
.. i WP82-YZ 110 TO 3 N/A 3.500 Wp9i-tI
,Ca I
4 1
r r
- l.
, J I)C
- e.
L I
I I
.WP82--Z I 220 TO 3 1 N/A 3.500 WP9I -2,11 7 I
I HI-I -I IIILt WP82-ZW I 0TO 3 N/A 3.500 IWP9I 4. 4 I IjC8 PRESSURIZER WELD OUTLINE WP82-W 110 TO 3 N/A 3.500 7-/14g-%-l 7-2-3-i wP6-7'.-
.f_.
V_
VWD
- 1. D\\l
.Nh Fwn WP82-WX 110 TO 3 N/A 3.500 DATE APPD DATE DWG NO.
REV ISI-OCN2-002 1I........
Request for Relief 04-ON-003 Limited Examinations Associated With Reactor Vessel Welds 2EOC 19
Relief Request 04-ON-003 Page 1 of 7 Proposed Relief in Accordance with 10 CFR 50.55a(g)(5)(iii)
Inservice Inspection Impracticality Duke Energy Corporation Oconee Nuclear Station - Unit 2 (EOC-19)
Third 10-Year Interval - Inservice Inspection Plan Interval Start Date= 12-16-1994 Interval End Date=9-9-2004 ASME Section XI Code - 1989 Edition with No Addenda I. L1. & Ill.
IV.
V.
VI.
VIl.
Limited System I Code Requirement from Which Basis for Relief Alternate Justification.
Implementation Area/Weld Component for Which Relief is Requested:
Examinations or for Granting Schedule I.D.
Relief is Requested:
100% Exam Volume Coverage Testing Relief Number Area or Weld to be Exam Category Examined Item No.
Fig. No.
Limitation Percentage 2-RPV-WR34 NC System Exam Category B-A See Paragraph See Paragraph See Paragraph See Paragraph Reactor Vessel Item No. B01.01 1.004 "A"
"F'
.G" Lower Shell to Lower Fig. IWB-2500-1 Head Ring 36% Volume Coverage due to Circumferential Weld limited scanning.
2-RPV-WR35 NC System Exam Category B-A See Paragraph See Paragraph See Paragraph See Paragraph Reactor Vessel Item No. B01.021.003 "A"
6"FtG' "G"
Lower Head Cap to Fig. IWB-2500-3 Lower Head Ring 42% Volume Coverage due to Circumferential Weld limited scanning.
2-RPV-WRI3 NC System Exam Category B-D See Paragraph See Paragraph See Paragraph See Paragraph Reactor Vessel Item No. B03.090.001 "B"
"F' "H"
Outlet Nozzle-to-Vessel Fig. IWB-2500-7(a)
Weld @ 900 82% Volume Coverage due to limited scanning.
(UT from vessel I.D.)
2-RPV-NC System Exam Category B-D See Paragraph See Paragraph See Paragraph See Paragraph WR13A Reactor Vessel Item No. B03.090.002 "B"
"Fs "H""
1 Outlet Nozzle-to-Vessel Fig. IWB-2500-7(a)
Weld @ 270° 82% Volume Coverage due to limited scanning.
(UT from vessel I.D.)
Relief Request 04-ON-003 Page 2 of 7 II. & III.
IV.
V.
VI.
VII.
Limited System /
Code Requirement from Which Basis for Relief Alternate Justification Implementation Area/Weld Component for Which Relief Is Requested:
Examinations or for Granting Schedule I.D.
Relief is Requested:
100% Exam Volume Coverage Testing Relief Number Area or Weld to be Exam Category Examined Item No.
Fig. No.
Limitation Percentage 2-RPV-WR54 NC System Exam Category B-D See Paragraph See Paragraph See Paragraph See Paragraph Reactor Vessel Fig. IWB-2500-7(a)
"C" "F"
"H" Core Flood Item No. B03.090.007 Nozzle-to-Vessel Weld (UT from vessel I.D.)
@ 00 81 % Volume Coverage due to limited scanning.
2-RPV-NC System Exam Category B-D See Paragraph See Paragraph See Paragraph See Paragraph WR54A Reactor Vessel Fig. IWB-2500-7(a)
"C" "F'
"H1" Core Flood Item No. B03.090.008 Nozzle-to-Vessel Weld (UT from vessel ID)
@ 180° 81 % Volume Coverage due to limited scanning.
2-RPV-WR54 NC System Exam Category B-D See Paragraph See Paragraph See Paragraph See Paragraph Reactor Vessel Item No. B03.100.007 "D"
"OF'H' "H"
Core Flood Nozzle Fig. IWB-2500-7(a)
Inside Radius Section 52% Volume Coverage due to
_@ 00 limited scanning.
2-RPV-NC System Exam Category B-D See Paragraph See Paragraph See Paragraph See Paragraph WR54A Reactor Vessel Item No. B03.100.008 "D"
"F' "H"
"3" Core Flood Nozzle Fig. IWB-2500-7(a)
Inside Radius Section 52% Volume Coverage due to
@ 1800 limited scanning.
2-53A-8-63 NC System Exam Category B-J See Paragraph See Paragraph See Paragraph See Paragraph Reactor Vessel Item No. B09.01 1.011 IE""F' "H""3" Core Flood Fig. IWB-2500-8(c)
Safe-End to Pipe 76% Volume Coverage due to Circumferential Weld limited scanning.
@ 00
Relief Request 04-ON.003 Page 3 of 7 II. & III.
IV.
V.
VI.
VII.
Limited System I Code Requirement from Which Basis for Relief Alternate Justification Implementation Area/Weld Component for Which Relief is Requested:
Examinations or for Granting Schedule I.D.
Relief is Requested:
100% Exam Volume Coverage Testing Relief Number Area or Weld to be Exam Category Examined Item No.
Fig. No.
Limitation Percentage 2-53A-8-63 NC System Exam Category B-J See Paragraph See Paragraph See Paragraph See Paragraph Reactor Vessel Item No. B09.01 1.01 1A "E"
M FF "H"" J Core Flood Fig. IWB-2500-8(c)
Safe-End to Pipe 76% Volume Coverage due to Circumferential Weld limited scanning.
@ 00 (UT from nozzle I.D. in lieu of PT from O.D.)
2-53A-8-64 NC System Exam Category B-J See Paragraph See Paragraph See Paragraph See Paragraph Reactor Vessel Item No. B09.011.013 "E"
M I"F" "H"
Core Flood Fig. IWB-2500-8(c)
Safe-End to Pipe 71% Volume Coverage due to Circumferential Weld limited scanning.
@ 1800 2-53A-8-64 NC System Exam Category B-J See Paragraph See Paragraph See Paragraph See Paragraph Reactor Vessel Item No. B09.011.013A "E"
"F" "H
1,,
Core Flood Fig. IWB-2500-8(c)
Safe-End to Pipe 71 % Volume Coverage due to Circumferential Weld limited scanning.
@ 1800 (UT from nozzle I.D. in lieu of PT from O.D.)
Note: The welds in the above table were inspected in October of 2002.
Note: See Attachment A for a drawing on all the welds listed above.
Relief Request 04-ON-003 Page 4 of 7 IV. Basis for Relief (See Attachment A for area/weld locations.)
Paragraph A:
During the ultrasonic examination of welds 2-RPV-WR34 and 2-RPV-WR35, 100% coverage of the required examination volume could not be obtained. The examination coverage was limited to 36% and 42% respectively.
Limitations were caused by the core guide lugs & flow stabilizers for WR34 and incore nozzles & flow stabilizers for WR35 that restrict the scanning surface as shown on the Attachment A, B, and C drawings. The percentage of coverage reported represents the aggregate coverage from all scans. Some areas received no coverage at all while some areas were completely covered from four directions. 13.3% of the near surface (inner 15 % of wall thickness) volume of the weld and base material was covered in four scan directions using a 70° beam angle. 76.6% of the near surface volume of the weld and base material was covered with a 700 beam angle from one axial and circumferential direction. Only 10.1% of the near surface volume of the weld and base material received no coverage. There were no recordable indications found in the areas that were examined for either of these two welds. In order to achieve more coverage the core guide lugs, incore nozzles and flow stabilizers would have to be moved to allow greater access for scanning, which is impractical.
(See Attachment B for drawings on Weld 1-RPV-WR34)
(See Attachment C for a drawing on Weld 1-RPV-WR35)
Paragraph B:
During the ultrasonic examination of welds 2-RPV-WR13 and 2-RPV-WR13A, 100% coverage of the required examination volume could not be obtained. The examination coverage was limited to 82%. Limitations were caused by the outlet nozzle boss that restricts the scanning surface both from the nozzle I.D. and the vessel I.D. The percentage of coverage reported represents the aggregate coverage from all scans. The weld and adjacent base material received 100% coverage from the nozzle bore with 15° and 450 beam angles. Scans from the vessel shell side resulted in 42% coverage of the weld and base material with a 450 beam angle of the outer 85% of the vessel wall and coverage of the inner 15% with a 700 beam angle. There were no recordable indications found in the areas that were examined for item number B03.090.001. There were 21 recordable indications found during examination of item number B03.090.002. All of the indications were detected from the nozzle bore and were determined to be acceptable, sub-surface flaws. In order to achieve more coverage, the outlet nozzle boss would have to be moved to allow greater access for scanning, which is impractical.
(See Attachment D for drawing on both welds)
Paragraph C:
During the ultrasonic examination of welds 2-RPV-WRR54 and 2-RPV-WR54A, 100% coverage of the required examination volume could not be obtained. The examination coverage was limited to 81% 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:
Relief Request 04-ON-003 Page 5 of 7 Weld and adjacent base material = 81% scanned parallel to the weld centerline in two directions and perpendicular to the weld centerline from one direction.
Inner 15% from the vessel ID = 97%, in four orthogonal directions.
There were no recordable indications found in the areas that were examined for item number B03.090.007. There was one recordable indication found during examination of item number B03.090.008. This indication was detected from the vessel ID and was determined to be an acceptable, sub-surface flaw. 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 no scanning was performed from the nozzle I.D. (0% examination coverage). 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 a drawing on the core flood nozzle)
Paragraph D:
During the ultrasonic examination of inside radius sections 2-RPV-WR54 and 2-RPV-WR54A, 100% coverage of the required examination volume could not be obtained. The examination coverage was limited to 52%. Limitations were caused by the flow restrictor that prevents scanning from the nozzle bore surface. The percentage of coverage reported represents the aggregate coverage from all scans. There were no recordable indications found in the areas that were examined for either of these inside radius sections. In order to achieve more coverage, the flow restrictor would have to be moved to allow greater access for scanning, which is impractical.
(See Attachment E for a drawing on the core flood nozzle)
Paragraph E:
During the ultrasonic examination of welds 2-53A-8-63 and 2-53A-8-64, 100% coverage of the required examination volume could not be obtained. The examination coverage was limited to 76% and 71%, respectively.
Limitations were caused by air at the top of nozzle that prevented the transducer from making contact for scanning the surface. The reactor vessel inspection services vendor made two attempts to evacuate the air with equipment made for the purpose but additional air was reintroduced from an unknown source. After the second attempt was unsuccessful and the source for the air could not be determined, a decision was made to perform the scan and obtain as much coverage as possible (the percentages shown above). The vendor noted that similar problems with eliminating trapped air have been experienced on other reactor vessels with small diameter piping.
Alternatively, it is impractical to perform this exam from the outside nozzle surface due to the excessive personnel radiation exposure. Approximately 40 man-hours would be required to prepare each safe-end to pipe weld for examination from the outside surface. The preparation involves removing the refueling canal seal plate, shielding bricks, shielding supports in the nozzle area and insulation. The radiation levels in this area are expected to be 0.51 R/hr. An alternative path would be to enter from the bottom of the reactor vessel and build scaffolding approximately 30 feet high to reach the core flood nozzles. This activity would require approximately 80 man-hours. 40 man-hours in a 0.51/hr radiation field and 40 man-hours in a 1-2 R/hr radiation field. Total estimated exposure would be 80-140 man-rem. shielding in this area is impractical. Any remote inspection would require the same preparatory work.
The percentage of coverage reported represents the aggregate coverage. There were no recordable indications found in the volumes that were examined for either of these two welds. In order to achieve more coverage, the air would have to be eliminated which proved to be impractical during the subject inspection.
(See Attachment F for a drawing on safe-end to pipe welds)
Relief Request 04-ON-003 Page 6 of 7 V. Alternate Examinations or Testine Paragraph F:
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.
VI. Justification for Granting Relief Paragraph G:
Ultrasonic examination of welds for item numbers B01.011 and B01.021 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.)
In addition to the Category B-A welds that relief is being sought for, there were 4 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, B03.100, and B09.011 were conducted using personnel, equipment and procedures qualified in accordance with ASME Section XI, Appendix I, 1989 Edition with no Addenda. Inspection of B09.011 welds from the outside diameter is not a viable alternate due to the dose that would be received to prepare and perform the inspections. Relief Requests ONS-001 and ONS-002 were written to perform UT from the ID surface in lieu of a surface exam from the OD surface of all reactor vessel nozzles to pipe welds due to the radiation exposure that is involved with performing inspections from the OD surface. Relief for ONS-001 and ONS-002 was granted on an SER dated 11-15-95. 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 (referenceTable lWB-2500-1, item numbers B15.010 and B15.050) 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 B15.011 and B15.051) is required once during each 10-year inspection interval. 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 IWB-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
Relief Request 04-ON-003 Page 7 of 7 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 RCS mass balance calculation. A second 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 third is the level indicator in the Reactor Building normal sump. A fourth 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 portions 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.
VII.Implementation Schedule Paragraph J 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. Other Information The following individuals contributed to the development of this relief request:
James J. McArdle (Principal NDE Level III Inspector) provided Sections II through V and part of Section VI.
B. W. Carney, Jr. (Oconee Engineering) provided part of Section VI.
Larry C. Keith (Oconee ISI Plan Manager) compiled the remaining sections.
Sponsored By:
gc Ufl_ C.
Date 3-_
____e Approved By:
k D
__________Date__________
Attachment A pagef of I
'DEEP END OF W CPS TAMCLT 12
SFOW
'~
INOZW__X CPS TMRCE IS INOZOZ-.,
..Z-2-5M OXAA1LS1U Z-f1Pv-ontoo801 011.001 WastA 1oIAI W23 a001.01 1.501 I
a.2-,
O 00"l0 so~aa 2-fy-C0
I I Attachment B g
Pages of 7 OCONEE-2 APPENDIX VIII EXAMINATION COVERAGE FOR WELD:
2-RPV-WR34 B01.0110.004 SCAN PLAN DWG NO.: 6014932E-02 AGGREGATE COVERAGE OBTAINED:
W09 36%
Zone Coverage Obtained Weld: 30%
Adjacent Base Metal: 38%
~~uitiftii ID Weld Length:
536.03 In.
Area Measurement Volume Calculation Weld: Near Surface 4.12 sq. In.
Weld: Near Surface 2208.4 cu. in.
Weld: Balance of Volume 7.17 sq. In.
Weld: Balance of Volume 3843.3 cu.
h n.
Base Metal: NearSurface 8.05 sq.iIn.
Base Metal: NearSurface 4315.0 cu.In.
Base Metal: Balance of Volume 39.54 sq. In.
Base Metal: Balance of Volume 21194.6 cu. In.
WELD Weld (Near Surfacegiegoon B.C--It)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined. Required Percent Entry (deg.)
Direction (sq. In.)
(on.)
(cu. In.)
(cu. in.)
Examined I
70L 1 1 4.12 71.47 294.5 294.5 100%
2 70L 12 4.12 71.7 294.5 294.5 100%
3 70L 3
4.12 71.47 294.5 294.5 100%
4 70L 4
4.12 71.47 294.5 294.5 100%
5 5 70L 11 4.12 205.48 846.6 846.6 100%
6 70L 12 0.00 205.48 0.0 846.6 0%
7 70L 3
.4.12 205.48 846.6 846.6 100%
8 70L 4
0.00 205.48 0.0 846.6 0%
9 70L 11 0.00 259.08 0.0 1067.4 0%
10 70L 12 0.00 259.08 0.0 1067A 0%
11 70L 3
0.00 259.08 0.0 1067A 0%
12 70L 4
0.00 259.08 0.0 1067.4 0%
Totals:
2871.0 8833.8 33%
Weld (Balance of Volume Region G-HI-i J)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry (deg.)
Direction (sq. In.)
in.)
(cu. in.)
(cu. In.)
Examined 1
45L 11 7.17 71A7 512.4 512.4 100%
2 45L 12 7.17 71.47 512.4 512.4 100%
3 45L 3
7.17 71A7 512.4 512.4 100%
4 45L 4
7.17 71.47 512.4 512.4 100%
5 45L 11 3.03 205.48 622.6 1473.3 42%
6 45L 12 0.00 205.48 0.0 1473.3 0%
7 45L 3
0.00 205.48 0.0 1473.3 0%
8 45L 4
7.17 205.48 1473.3 1473.3 100%
9 45L 11 0.00.
259.08 0.0 1857.6 0%
10 45L 12 0.00 259.08 0.0 1857.6 0%
11 45L 3
0.00 259.08 0.0 1857.6 0%
12 45L 4
0.00 259.08 0.0 1857.6 0%
13 45S 11 7.17 71.47 512.4 512.4 100%
14 45S 12 7.17 71.47 512.4 512.4 100%
15 45S 3
7.17 71.47 52 512.4 100%
16 45S 4
7.17 71.47 512.4 512.4 100%
17 45S 11 6.42 205.48 1319.2 1473.3 90%
18 45S 12 0.00 205.48 0.0 1473.3 0%
19 45S 3
0.00 205A8 0.0 1473.3 0%
20 45S 4
7.17 205.48 1473.3 1473.3 100%
21 45S 11 0.00 259.08 0.0 1857.6 0%
22 45S 12 0.00 259.08 0.0 1857.6 0%
23 45S 3
0.00 259.08 0.0 1857.6 0%
24 45S 4
0.00 259.08 0.0 1857.6 0%
Totals:
8988.0 30746.7 29%
' Attachment B Page3 of 7 BASE METAL SHEET - 2 Adjacent Base Metal (Near Surface Region A-84-L and C-D-E-H)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. In.)
(in.)
(cu. In.)
(cu. in.)
Examined I
70L 11 8.05 71.47.
575.3 575.3 100%
2 70L 3
8.05 71A7 575.3 575.3 100%
3 70L 11 7.31 205.48 1502.1 1654.1 91%
4 70L 3
5.62 205.48 1154.8 1654.1 70%
5 70L 11 0.00 259.08 0.0 2085.6 0%
6 70L 3
0.00 259.08 0.0 2085.6 0%
Totals:
3807.5 8630.1 44%
Adjacent Base Metal (Balance of Volume Region E-F-G-t and IJ-K-L)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry#
(deg.)
Direction (sq. In.)
(On.)
(cu. In.)
(cu. In.)
Examined 1
45L 11 39.54 71.47 2825.9 2825.9 100%
2 45L 3
39.54 71.47 2825.9 2825.9 100%
3 45S 11 39.54 71A7 2825.9 2825.9 100%
4 45S 3
39.54 71A7 2825.9 2825.9 100%
5 45L 11 22.67 205A8 46582 8124.7 57%
6 45L 3
26.88 205.48 5523.3 8124.7 68%
7 45S 11 32.19 205.48 6614.4 8124.7 81%
8 45S 3
18.25 205.48 3750.0 8124.7 46%
9 45L 11 0.00 259.08 0.0,.10244.0 0%
10 45L 3
0.00 259.08 0.0 10244.0 0%
11 45S 11 0.00 259.08 0.0 10244.0 0%
12 45S 3
0.00 259.08 0.0 10244.0 0%
Totals.
31849.7 84778.5 38%
I Attachment B Page q. of 7 WELD <NEAR SURFACE)t 4.12 SQ IN. (70tL)
WELD (BALANCE OF VOLUME),
3.03 SQ IN. (45*L) 6.42 SQ IN. (45'S)
-BASE METAL (NEAR SURFACE)i 7.31 SQ IN. (70'L)
BASE METAL (BALANCE OF VOLUME)'
22.67 SQ IN. (45'L) 32.19 SQ IN.
<45.S)
CORE GUIDE LUG L1 QUAN: 12 450L
_ i 45°S 701L THIS VIEW DEPICTS ALPHA (AXIAL) SCANS FIRING DOWNWARD (DIRECTION 11)
PARTIAL SCANS LUGS AND FLOW REMNANTS DUE TO GUIDE STABILIZER W09 2-RPV-WR34 B01.011.004
I Attachment B Page 5 of 7 WELD (NEAR SURFACE):
0.00 SQ IN.
WELD (BALANCE OF VOLUME):
0.00 SQ IN..
-BASE METAL (NEAR SURFACE),
0.00 SQ IN.
BASE METAL (BALANCE OF VOLUME)t 0.00 SQ IN.
CORE GUIDE LUG QUAN: 12 70 0L 45 0S 45*L THIS VIEW DEPICTS ALPHA (AXIAL)
SCANS FIRING UPWARD (DIRECTION 12)
FLOW STABILIZER REMNANT QUAN: 12 PARTIAL SCANS LUGS AND FLOW REMNANTS DUE TO GUIDE STABILIZER W09 2-RPV-WR34 B01.011.004
I
_.I tahment B Page 6 of 7 WELD (NEAR SURFACE)I 4.12 SQ IN. (70t)
WELD (BALANCE OF VOLUME),
7.17 SQ IN. (45tL & 45*S)
'BASE METAL (NEAR SURFACE):
5.62 SQ IN. (70*L)
BASE METAL. (BALANCE OF VOLUME)t 18.25 SQ IN. <45*L) 26.88 SQ IN.
(45*S)
CORE GUIDE LUG QUANI 12 THIS VIEW DEPICTS THETA (CIRC) SCANS (DIRECTION 3 & 4)
FLOW STABILIZER REMNANT QUAN: 12 PARTIAL SCANS LUGS AND FLOW REMNANTS DUE TO GUIDE STABILIZER W09 2-RPV-WR34 B01.011.004
a a
I Attachment B I Page 7 of 7 W09 2-RPV-WR34 B01.011.004
Attachment C I Page
. of 4q OCONEE-2 APPENDIX Vill EXAMINATION COVERAGE FOR WELD:
WIG 2-RPV-WR35 130I.021.003 SCAN PLAN DWG NO.: 6014933E-02 AGGREGATE COVERAGE OBTAINED:
42%/
Zone Cover-age Qbtalned Weld: 40%
Adjacent Base Metal: 43%
Wee d Length:
448.12 In.
Area Measurement Volume Calculaion Weld: Near Surface 0.99 sq. In.
Weld: Near Surface 443.6 cu. In.
lad: Balance of Volume 6.21 sq. In.
Weld: Balance of Volume 27828 cu. In.
Base Metal: Near Surface 6.02 sq. In.
Base Metal: Near Surface 2697.7 cu. in.
Base Metal: Balance of Volume 24.78 sq. In.
Base Metal: Balance of Volume 11104.4 cu. In.
WELD Weld (Near Surface Regionn BC--I)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry (deg.)
Direction (sq. In.)
fin.)
(cu. In.) (cu. in.)
Examined 1
70L 11 0.99 168.05 166.4 166.A - 100%
FULL 2
70L 1t I
0.0 56.01 0.0 55.4 0%
PARTIAL 3
70L 11 0.00 224.06 0.0 221.8 0%
NONE 4
70L 12 0.99 168.05 166.4 166.4 100%
FULL 5
70L 12 0.00 56.01 0.0 55.4 0%
PARTIAL 6
70L 12 0.00 224.06 0.0 221.8 0%
NONE 7
70L 3
0.99 168.05 166.4 166.4 100%
FULL 8
70L 3
0.00 56.01 0.0 55.4 0%
PARTIAL 9
70L 3
0.00 224.06 0.0 221.8 0%
NONE 10 701 4
0.99 168.05 166.4 166.4 100%
FULL 11 701 4
0.00 56.01 0.0 55.4 0%
PARTIAL 12 70L 4
0.00 224.06 0.0 221.8 0%
NONE Totals:
665.5 1774.5 38%
Weld (Balance of Volume Region G44-4J)
Exam.
Area Length Volume Volurne Angle Beam Examined Examined Examined Required Percent Entry#
(deg.)
Direction (sq. In.)
(in.)
(cu. In.)
(cu. in.)
Examined 1
45L 11 6.21 168.05 1043.6 1043.6 100%
FULL 2
45L 11 5.70 56.01 319.3 347.8 92%
PARTIAL 3
45L 11 0.00 224.06 0.0 1391.4 0%
NONE 4
45L 12 6.21 168.05 1043.6 1043.6 100%
FULL 5
45L 12 0.00 56.01 0.0 347.8 0%
PARTIAL 6
45L 12 0.00 224.06 0.0 1391.4 0%
NONE 7
45L 3
6.21 168.05 1043.6 1043.6 100%
FULL 8
45L 3
0.00 56.01 0.0 347.8 0%
PARTIAL 9
45L 3
0.00 224.06 0.0 1391.4 0%
NONE 10 45L 4
6.21 168.05 1043.6 1043.6 100°% FULL 11 45L 4
0.00 56.01 0.0 347.8 0%
PARTIAL 12 45L 4
0.00 224.06 0.0 1391.4 0%
NONE 13 45S 11 6.21 168.05 1043.6 1043.6 100%
FULL 14 45S 11 5.70 56.01 319.3 347.8 92%
PARTIAL 15 45S 11 0.00 224.06 0.0 1391.4 0%
NONE 16 45S 12 6.21 168.05 1043.6 1043.6 100%
FULL 17 455 12 0.00 56.01 0.0 347.8 0%
PARTIAL 18 45S 12 0.00 224.06 0.0 1391.4 0%
NONE 19 45S 3
6.21 168.05 1043.6 1043.6 100%
FULL 20 45S 3
0.00 56.01 0.0 347.8 0%
PARTIAL 21 45S 3
0.00 224.06 0.0 1391.4 0%
NONE 22 45S 4
6.21 168.05 1043.6 1043.6 100%
FULL 23 45S 4
0.00 56.01 0.0 347.8 0%
PARTIAL 24 45S 4
0.00 224.06 0.0 1391.4 0%
NONE Totals:
8987.0 2226Z4 40%
Attachment C I Page 3 of L(
BASE METAL SHEET-2 Adjacent Base Metal (Near Surface Region A-84-L and C-D-E.H)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. In.)
(in.)
(cu. In.)
(cu. in.)
Examined I
70L 11 6.02 168.05 1011.6 1011.6 100%
FULL 2
70L 11 2.50 56.01 140.0 337.2 42%
PARTIAL 3
70L 11 0.00 224.06 0.0 1348.8 0%
NONE 4
70L 3
6.02 168.05 1011.6 1011.6 100%
FULL 5
70L 3
1,82 56.01 101.9 337.2 30%
PARTIAL 6
70L 3
0.00 224.06 0.0 1348.8 0%
NONE Total 2265.2 5395.3 42Y%
Adjacent Base Metal (Balance of Volume Region E-F-G4-and.J.K-L)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. In.)
fin.)
(cu. In.)
(cu. in.)
Examined 1
45L 11 24.78 168.05 4164.2 4164.2 100%
FULL 2
45L 11 16.95 56.01 949.4 1387.9 68%
PARTIAL 3
45L 11 0.00 224.06 0.0 5552.2 0%
NONE 4
45S 3
24.78 168.05 4164.2 4164.2 100/
FULL 5
4SS 3
8.19 56.01 458.7 1387.9 33%
PARTIAL 6
45S 3
0.00 224.06 0.0 5552.2 0%
NONE Toals:
9736.4 2220&.6 44%
.F-r ;,
Attachment C
? Page L of 4 FLOW STABILIZER-z W10 OCONEE-2 2-RPV-WR35 B01.021.003
II Attachment D Page :2 of 6 OCONEE-2 W15 2-RPV-WR13 803.090.001 803.090.001 A 803.1 00.001 W16 2-PHB-1 809.011.021 809.011.021 A W23 2-RPV-WR13A B03.090.002 B03.090.002A B03.100.002 W24 2-PHA-1 809.011.019 809.011.019A T,
1--1/~
3TIIE 7
ECTION VIEW f 5.18 sq 'in.
HORIZONTAL SE VERTICAL SECTION VIEW X
j I WEl BAS NOz
-D & ADJACENT
- E METAL FROM ZZLE BORE I
45/15' 63.74-sq in.
I Attachment D t Page :3 of 6
OCONEE-2 W15 2-RPV-WR13 B03.090.001 B03.090.001 A B03.1 00.001 W16 2-PHB-1 809.011.021 B09.011.021A W23 2-RPV-WR 13A B03.090.002 803.090.002A 803.100.002 W24 2-PHA-1 B09.011.019 B09.01 1.019A I. I ;-.
/
/
7 HORIZONTAL SECTION VIEW VERTICAL SECTION VIEW 45S/45L/70L shell/7 1.71 sq in.
shell/8 0.00 sq in.
45-S/45-L/70 L shell/7 7.64 sq in.
shell/8 2.69 sq in.
INNER 15% T SHELL/7/8 FROM VESSEL SHELL i
Attachment D I i Page 4 of 4
, I OCONEE-2 W15 2-RPV-WR I' 803.090.001 803.090.001A B03.100.001 W16 2-PHB-1 809.011.021 B09.011.021A W23 2-RPV-WR13A 803.090.002 803.090.002A B03.100.002 W24 2-PHA-1 809.011.019 809.011.019A
/
I MION VIEW HORIZONTAL SEC 0.45 sq in 5.68 sq in.
VERTICAL SECTION VIEW INNER 157=-
SHELL/9 FROM VESSEL SHELLl
I Attachment D Page 5 of 6i OCONEE-2 W15 2-RPV-WR13 803.090.001 603.090.001 A B03.100.001 W16 2-PHB-1 809.011.021 609.011.021A W23 2-RPV-WR 13A B03.090.002 B03.090.002A 803.100.002 W24 2-PHA-1 809.011.019 B09.011.019A t
i HORIZONTAL SECTION VIEW VERTICAL SECTION VIEW 45S/45L/70L 1.97 SO IN.
45S/45L/70L 7.09 SQ IN.
f
\\LI I
INNER 15% T SHELL/10 FROM VESSEL SHELL
X Attachment D Page 6 of 6 OCONEE-2 W15 2-RPV-WR 13 B03.090.001 803.090.001 A B03.100.001 W16 2-PHB-1 809.011.021 B09.011.021A W23 2-RPV-WR13A B03.090.002 B03.090.002A 803.100.002 W24 2-PHA-1 B09.011.019 B09.011.019A f
/
/
/
TION VIEW f HORIZONTAL SEC 70' 7.61 sq in.
70 7.10 sq in.
VERTICAL SECTION VIEW gL INNE CIRC cOv
-ER RADIUS d
V ERAGE l
I I
]
I
- as.-
lAttachment E
Page p, offal Oconee-2 Explanation of Limited Coverage for Core Flood Nozzle to Shell Weld The Core Flood Nozzle of a B&W 177 plant has several obstructions which limits UT inspection of the nozzle-to-shell weld. In order of magnitude of impact these include:
The Flow Restrictor located in the bore of the Core Flood Nozzle.
The Inlet Nozzles located 30 degrees on either side of the Core Flood Nozzles The taper above the Core Flood Nozzle associated with the Core Support Ledge.
The radius blend between the shell and the bore of the nozzle itself.
Despite these obstructions, Framatome ANP has gone to great lengths to get the maximum practical coverage ofthis weld. The coverage, which is described bythe following spread sheet output and graphic figures, totals up as follows:
Weld &Adjacent Base Metal = 81%
Near Surface (Vessel ID) = 97%
Inside Radius = 52%
"Ursula", the robotic system which will perform this inspection, uses several abbreviations to describe a coordinate system for scan and index purposes. There are four major classes of scans in the "Ursula" system:
("S") Shell used for the cylindrical vessel ID
("N") Nozzle used for the nozzle to shell from the vessel ID
("P") Pipe used for scans in the nozzle ID
("M") Meridional used for the lower head In addition, several axes of motion are labeled:
("Z") which is the majorcenterline axis of the vessel, with the positive sense down into the vessel ("R") which is a radial distance measured perpendicular to the "Z" axis, with the positive sense away from the "Z" axis
(""T) Theta which is an angular displacement, in the plane "R" is measured in, between 0 degrees and 720 degrees from vessel 0 (The B&W "NV" axis of the vessel)
("A") Alpha which is an angular displacement of the spherical radius (sr) of the lowerhead as measured from the reference 0 point when this sr is perpendicular to the "Z" axis, such that positive angles increase from 0 to 90 from the shell to the centerline of the vessel at the bottom of the lower head.
In addition to these major axes, each nozzle has an axis system associated with its centerline. Axes of nozzle motion are:
("R") units are measurements off the vessel centerline along the nozzle centerline
("`W") is a radial measurement, perpendicular to the nozzle centerline, with the positive sense away from the nozzle centerline
("B") Beta is an angular displacement, in the plane "W" is measured in, from a reference 0 at "top dead center" of the nozzle.
Scans are denoted by the class, axis, and the positive or negative sense with which a reference axis on the
Attachment E Page 3 of 15 "Ursula" contact head aligns: For example, the scans we are interested in are within the Nozzle, or "N" scan class. The contact head reference axis (and in his case the beam direction of the transducers) will align with either the "W' radial direction-trom the nozzle centerline, or the Beta (VB")
angular sense about the nozzle centerline with positive being clockwise rotation when viewing the nozzle from the vessel centerline.
Since the bore of the Core Flood Nozzle is obstructed by the Flow Restrictor all scans for the nozzle to shell weld are scanned from the vessel ID and will be either.
NWP NWN NBP NBN with the final "P" or '"' denoting positive or negative sense.
Because no scans are performed from the nozzle bore, scans must be performed on the shell perpendicular to the nozzle'to shell weld centerline, in addition to the scans parallel to the weld centerline on the vessel ID.
Figure 1,2 & 3 indicates zones of coverage in which different limitations and scan directions apply. The subsequent figures and spread sheet output are based on this coverage. Zones I thru 3 are all NWN scans with the beam direction perpendicular to the weld centerline towards the center of the nozzle. Zone 4 is a NWP scan with the beam direction perpendicular to the centerline of the weld away from the center of the nozzle.
Zone 5 is scanned in both NBP & NBN with the beam direction paralfel to the weld centerline.
The spread sheet entries are as follows:
Beam Direction I comes from NWN scans Beam Direction 2 comes from NWP scans Beam Direction 3 comes from NBP scans Beam Direction 4 comes from NBN scans To calculate % coverage the spread sheet uses the volume acquired by a given angle divided by the true unobstructed inspection volume required to be examined. For a given angle and beam direction the sum of the degrees for which the various coverages were obtained must equal 180 degrees.
This is because the total nozzle inspection volume is broken into a horizontal inspection volume (and subsequent coverage) and a vertical inspection volume (and subsequent coverage). Each area and coverage is considered to represent 180 degrees of the nozzle. After the horizontal and vertical sections are calculated separatelytheyare combined to provide aggregate coverage numbers.
I' Attachment E
..Page if of I r; -
I
I..
I 1s I Attachment E
. Page S of IS START OF CORE SUPPORT LEDGE TAPER @ Z = 27' I
NWP LIMITS SHELL/9 = NWP SCANS Figure-2
I IlAttachment E Page 6 of of START OF CORE SUPPORT LEDGE TAPER C Z = 27' NBR & NBL SCAN LIMITS SHELL/7=
SHELL/8 NBR SCANS
= NBL SCANS Figure-3
l Attachment E I
ge 7 of iS OCONEE-2 wil 2-RPV-WR54 B03.090.007 B03.100.007 W19 2-RPV--WR54A B03.090.008 B03.100.008 W-31.44 ULMTED COVERAGE DUE TO CORE SUPPORT LEDGE TAPER F
W-8.75 ALL I
1,\\
II II WELD: 18.79 SQ IN.
ADJACENT BASE METAL 156.50 SQ IN.
INNER 15% BMT: 23.26 SQ IN.
INNER RADIUS: 6.25 SQ IN.
I.-
BEAM DIRECTION 1-ZONE 1
Attachment E Page s of 15 OCONEE-2 Wil 2-RPV-WE,54 B03.090.007 B03. 100.007 W19 2-RPV-WR54A B03.090.008 B03. 100.008 WELD: 18.79 SQ IN.
ADJACENT BASE METAL-158.00 SQ IN.
INNER 15% BMT: 23.26 SO IN.
INNER RADIUS: 6.25 SQ IN.
BEAM DIRECTION 1-ZONE 3 60- OF 90- (66.6% OF SCAN)
I Attachment E I Page '7 of 15 OCONEEI-2 wi 1 2-RPV-WR54 B03.090.007 B03.100.007 W19 2-RPV-WR54A B03.090.008 B03.100.008 WELD: 15.81 SO IN.
ADJACENT BASE METAL 120.91 SO IN.
INNER 1 5' BMT. 23.26 SQ IN.
INNER RADIUS: 6.25 SO IN.
BEAM DIRECTION 1-ZONE 3 30- OF 90- (33.3% OF SCAN)
I Attachment E Page / 6 of I5-OCONEE-2 Wil 2-RPV-WR54 B03.090.007 B03.1 00.007 W19 2-RPV-WR54A B03.090.008 B03. 100.008 WELD: 19.16 SQ IN.
ADJACENT BASE METAL 177.52 SQ IN.
INNER 15% BMT: 24.13 SO IN.
INNER RADIUS: 6.26 SQ IN.
BEAM DIRECTION 1-ZONE 2 45 OF 90 (50.00% OF SCAN)
I Attachment E I Page II of i5 I
UUUNEE-22 Wil1 2-RPV-WR54 B03.090.007 B03.100.007 W19 2-RPV-WR54A B03.090.008 B03.100.008 WEID: 19.16 SQ IN.
ADJACENT BASE METAL 151.72 SO IN.
INNER 15Z BMT: 24.13 SO IN.
INNER RADIUS: 6.26 SQ IN.
BEAM DIRECTION 1 -ZONE 2 45-OF 90- (50.00% OF SCAN)
Attachment E Page lIt of is OCONEE-2 Wil 2-RPV-WR54 B03.090.007 B03. 100.007 W19 2-RPV-WR54A B03.090.008 B03. 100.008 WELD: 4.59 SO IN.
BEAM DIRECTION 2-ZONE 4
l Attachment E i Page /,3 of 15 OCONEE-2 wi1 2-RPV-WR54 B03.090.007 B03.1 00.007 W19 2-RPV-WR54A B03.090.008 I
B03. 100.008 WELD: 4.71 SQ IN.
BEAM DIRECTION 2-ZONE 4
AttachmentE Page IeY of /ST OCONEE-2 wi1 2-RPV-WR54 B03.090.007 B03. 100.007 W19 2-RPV-WR54A B03.090.008 B03.1 00.008 WELD: 18.79 SO IN.
ADJACENT BASE METAL SHELL/3: 142.41 SO IN.
SHELL/4:
97.90 SQ IN.
INNER 15% SWT: 22.00 SQ IN.
INNER RADIUS: 0.26 SQ IN.
I_
W-8.75 ALL SCANI BEAM DIRECTION 3 & 4-ZONE 5
I49 I Attachment E
- Page as of
/5 OCONEE-2 Wil 2-RPV-WR54 B03.090.007 B03.100.007 w19 2-RPV-WR54A B03.090.008 B03.100.008 WELD: 19.16 SQ IN.
ADJACENT BASE METAL SHELL/3: 148.97 SO IN.
SHELL/4: 105.98 SO IN.
INNER 15X BMT: 22.61 SQ IN.
INNER RADIUS: 0.21 SO IN.
BEAM DIRECTION 3 & 4-ZONE 5