ML20211B947
ML20211B947 | |
Person / Time | |
---|---|
Site: | Catawba ![]() |
Issue date: | 08/18/1999 |
From: | Gordon Peterson DUKE POWER CO. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 9908250128 | |
Download: ML20211B947 (101) | |
Text
.
3 Duke Power Catawba Nuclear Station 4800 Concord Road York, SC 29745 Cary R. Peterson (803) 83/4251 om y;,, y;g,,,,
(803) 831-3426nx August 18, 1999 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk ~
Washington, D.C..20555
Subject:
Duke Energy Corporation Catawba Nuclear Station, Unit 1 Docket Number 50-413 Request for Relief Number 99-02 Limited Weld Examinations Pursuant to 10 CFR 50.55a (g) (5) (iii), please find attached Request for Relief 99-02.
This request for relief is associated with limited' examination results for welds which were inspected during the Unit 1 End of Cycle 11 Refueling Outage.
The attachment to this letter contains all technical information necessary in support of this request for relief.
If you have any questions concerning this material, please call L.J.
Rudy at (803) 831-3084.
Very truly our,
pq a
Gary R.
Peterson-LJR/s Attachment I
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9908250128 990818 PDR ADOCK 05000413 p
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Document Control Desk
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Page 2 August 18, 1999 xc (with attachments):
L.A. Reyes, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St.,
SW, Suite 23T85 Atlanta, GA 30303 D.J. Roberts, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station P.S. Tam, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08-H12 Washington, D.C. 20555-0001
Request for Relief Serial No. 99-02 Page 1 of 16 1
DUKE ENERGY CORPORATION STATION: CATAWBA NUCLEAR STATION UNIT 1 10-YEAR INTERVAL REQUEST FOR RELIEF NO. 99-02 I. system / Component (s) for which Relief is Requested:
i ASME Section XI Code Class 1 Examination Category: B-D l
Full Penetration welds of Nozzles in Vessels, ASME Section XI Code Class 1
Examination Category:
B-F Pressure Retaining Dissimilar Metal Welds, ASME Section XI Code Class 1
Examination Category:
B-J Pressure Retaining Welds in Piping, ASME Section XI Code Class 2
Examination Category:
C-A Pressure Retaining Welds in Pressure Vessels, and ASME Section XI Code Class 2
Examination Category:
C-F-1 Pressure l
Retaining Welds in Austenitic Stainless Steel or High l
Alloy Piping l
ID Number Item Number 1SGB-INLET B03.140.003 l
1SGB-OUTLET B03.140.004 1SGD-INLET B03.140.007 ISGD-OUTLET B03.140.008 1SGB-INLET-W5SE B05.070.003 1SGB-OUT-W6SE B05.070.004 1SGD-INLET-W5SE B05.070.007 1SGD-OUT-W6SE B05.070.008 1NC22-02 B09.011.049 l
1NC22-03 B09.011.050 1NC23-02 B09.011.051 1NC23-03 B09.011.052 1NC22-WN7 B09.031.001 INC24-WN9 B09.031.003 1VCT-LH-SH C01.020.016 1CA66-35 C05.011.012
i Request for Relief Serial No. 99-02 Page 2 of 16 l
II. Code Requirement:
ASME Section XI 1989 Edition; Examination Category: B-D Full Penetration Welds of Nozzles in Vessels, Table IWB-2500-1, Item Number B03.140; Examination Category:
B-F Pressure Retaining Dissimilar Metal Welds, Table IWB-2500-1, Item Number B05.070; Examination Category:
B-J Pressure Retaining Welds in Piping, Table IWB-2500-1, Item Number B09.011 and B09.031, Examination Category C-A:
Pressure Retaining Welds in Pressure
- Vessels, Table IWC-2500-1, Item Number C01.020 and Examination Category C-F-1 Pressure Retaining Welds
)
in Austenitic Stainless Steel or High Alloy Piping, Table IWC-2500-1, Item Number C05.011 requires a
volumetric examination of essentially 100% of the weld volume.
Duke Energy Corporation, with NRC approval, has adopted Code Case N-460 which defines " essentially i
100%" as greater than 90% coverage.
l III. Code Requirement from which Relief is Requested:
Relief is requested for the above identified Weld ID Numbers:
- Class 1 Steam Generator 1B and 1D Inlet and Outlet Nozzle Inside Radius Sections, from meeting the coverage requirements as defined in ASME Section XI, 1989 Edition with no addenda, Figure IWB-2500-7(b),
Examination Volume M-N-O-P.
- Class 1 Steam Generator 1B and 1D Inlet and Outlet Nozzle-to-Safe-End Welds, from meeting the coverage requirements as defined in ASME Section XI, Appendix III, Paragraph III-4420, 1989 Edition with no addenda.
- The examination shall be performed using a sufficiently long examination beam path to provide coverage of the required examination volume in two-beam path directions.
The examination shall be performed from two sides of the weld where practicable, or from one side of the weld, as a minimum."
Request for Relief Serial No. 99-02 Page 3 of 16 Class 1 Piping Elbow-to-Nozzle Welds, Pipe-to-Safe-o End welds and Branch connection welds from meeting the coverage requirements as defined in ASME Section XI, Appendix III, Paragraph III-4420, 1989 Edition with no addenda.
The examination shall be performed using a sufficiently long examination beam path to provide coverage of the required examination volume in two-beam path directions.
The examination shall be performed from two sides of the weld where practicable, or from one side of the weld, as a minimum."
Class 2 Volume Control Tank Lower Head-to-Shell o
Weld, from meeting the coverage requirements as defined in ASME Section XI, Appendix III, Paragraph III-4420, 1989 Edition with no addenda.
" The examination shall be performed using a sufficiently long examination beam path to provide coverage of the required examination volume in two-beam path directions.
The examination shall be performed from two sides of the weld where practicable, or from one side of the weld, as a minimum."
Class 2 Steam Generator lA Auxiliary Feedwater Elbow-to-Nozzle Piping Weld, from meeting the coverage requirements as defined in ASME Section XI, Appendix III, Paragraph III-4420, 1989 Edition with no addenda.
The examination shall be performed using a sufficiently long examination beam path to provide coverage of the required examination volume in two-beam path directions.
The examination shall be performed from two sides of the weld where practicable, or from one side of the weld, as a minimum."
F Request for Relief Serial No. 99-02 Page 4 of 16 IV. Basis for Relief During the ultrasonic examination of the Steam Generator 1B and 1D Inlet and Outlet Nozzle Inside Radius Sections, 1SGB-Inlet,'1SGB-Outlet,-1SGD-Inlet and 1SGD-Outlet (Item Nos. B03.140.003, B03.140.004, B03.140.007 and B03.140.008 respectively) shown in Attachments 2, 3, 4 and 5, greater than 90% coverage of the required examination volume could not be obtained.
Limitations were caused by the ratio of the nozzle OD to the vessel thickness, which limits the ultrasonic coverage to 83.28% of the required examination volume.
When the nozzle OD is small in relation to the vessel thickness, more coverage can be obtained when scanning from the vessel side.
Nozzle inner radius sections were examined with the ultrasonic method to the maximum extent practical from the vessel wall.
Calibration blocks and procedures were in accordance with ASME Section V, Article 4.
I During the ultrasonic examination of the 1SGB and l
1SGD Inlet and Outlet Nozzle-to-Safe-End Welds, ISGB-INLET-W5SE, 1SGB-OUT-W6SE, ISGD-INLET-W5SE and 1SGD-OUT-W6SE (Item Nos. B05.070.003, B05.070.004, j
B05.070.007 and B05.070.008 respectively) shown in Attachments 6, 7,
8 and 9 respectively, greater than 90% coverage of the required examination volume l
could not be obtained.
Material characteristics and single sided access caused by component geometry prevents two-beam path direction coverage of the examination volume and limits the examination i
coverage to 75%.
The most effective ultrasonic i
technique for the examination of dissimilar metal i
l welds uses refracted longitudinal waves.
The longitudinal wave is preferred as the austenitic weld metal and buttering create highly attenuative barriers to shear wave ultrasound. The longitudinal wave is less affected by these difficulties.
l However, the longitudinal wave is affected by mode conversion when it strikes the inside surface of the safe end or pipe at any angle other than a right angle to the surface.
Request for Relief Serial No. 99-02 Page 5 of 16 The calculations below show that a 450 refracted longitudinal wave striking the inside surface of a 0
pipe will produce a 22.9 refracted shear wave in addition to the normally expected 45 reflected longitudinal' wave.
Sin-1= (sin 45 x V. )
+V, 0
t (0.707 x 0.123) + 0.223
=
Where; sin-1 is the shear wave angle V. is the shear wave velocity of the stainless steel safe end/ pipe material in inches / msec.
V,is the longitudinal wave velocity of the t
stainless steel safe / pipe end material in inches / msec.
As shown in the graph on page 6 of 16, the mode conversion process creates two sound beams of differing intensities reflecting off the inside 2
0 surface.
At incident angles greater than 30 the shear wave will predominate.
However, the shear wave is attenuated and scattered by the austenitic weld metal and the layer of buttering.
The examination sensitivity is degraded to such an extent that any examination using the second sound path leg is meaningless.
Therefore, the two-beam path direction coverage requirement is impractical.
l In order to'obtain the required two-beam path direction coverage, welds would have to be re-designed to allow scanning from both sides.
'Firestone, F.A.: Tricks with the Supersonic Reflectoscope, J. Soc. Nondestructive Testing, vol. 7, no. 2 Fall 1948.
Request for Relief Serial No. 99-02 Page 6 of 16 I
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L Waveinchient Angle During the ultrasonic examination of the Class 1 Piping: Elbow-to-Nozzle Weld 1NC22-02, Elbow-to-Nozzle Weld 1NC22-03, Pipe-to-Safe-End Weld 1NC23-02, Pipe-to-Safe-End Weld 1NC23-03, Branch Connection Weld 1NC-WN7 and Branch Connection Weld 1NC-WN9 (Item Nos. B09.011.049, B09.011.050, i
B09.011.051, B09.011.052, B09.031.001 and B09.031.003 respectively) shown in Attachments 10,11,12,13,14 and 15 respectively, greater than 90%
coverage of the required examination volume could not be obtained. Cast austenitic material characteristics and single-sided access caused by the component geometry prevents two-beam path direction coverage of the examination volume and limits the examination coverage to the percentages shown on Attachment 1.
In order to obtain the required two-beam path direction coverage, welds would have to be re-designed to allow scanning f;om both sides.
Ultrasonic techniques used for cast stainless steel i
are the same as those used for dissimilar metal welds.
l l
Request for Relief l
Serial No. 99-02 l
Page 7 of 16 During the ultrasonic examination of the Volume Control Tank Lower Head-to-Shell Weld IVCT-LH-SH i
(Item Number C01.020.016) shown in Attachment 16, greater than 90% coverage of the required examination volume could not be obtained.
Coverage was limited to 88.34% of the required examination volume because of the proximity of four support legs. In order to achieve greater than 90% coverage, more access would have to be provided by moving the support legs.
During the ultrasonic examination of the Class 2 Steam Generator 1A Auxiliary Feedwater Elbow-to Nozzle Weld 1CA66-35 (Item Number C05.011.012) shown in httachment 17, greater than 90% coverage of the required examination volume could not be obtained.
l Material characteristics and single sided access caused by component geometry prevents two-beam path direction coverage of the examination volume and limits the examination coverage to 75%.
The most effective ultrasonic technique for the examination of dissimilar metal welds uses refracted longitudinal waves.
The longitudinal wave is preferred as the austenitic weld metal and buttering create highly attenuative barriers to shear wave l
ultrasound. The longitudinal wave is less affected l
by these difficulties.
However, the longitudinal wave is affected by mode conversion when it strikes the inside surface of the safe end or pipe at any angle other than a right angle to the surface.
The calculations below show that a 45 refracted longitudinal wave striking the inside surface of a pipe will produce a 22.9 refracted shear wave in addition to the normally expected 45 reflected longitudinal wave.
Sin-l= (sin 45 xV.)
+V, 0
t (0.707 x 0.123) + 0.223
=
Where; sin ~1 is the shear wave angle l
V is the shear wave velocity of the I
stainless steel safe end/ pipe material in inches / msec.
f l
l
r Request for Relief Serial No. 99-02 Page 8 of 16 Vo is the longitudinal wave velocity of the stainless steel safe / pipe end material in inches / msec.
As shown in the graph on page 6 of 16, the mode conversion process creates two sound beams of differing intensities reflecting off the inside l
surface.
At incident angles greater than 30 the shear wave will predominate.
However, the shear wave is attenuated and scattered by the austenitic weld metal and the layer of buttering.
The examination sensitivity is degraded to such an extent that any examination using the second sound path leg is meaningless.
Therefore, the two-beam path direction coverage requirement is impractical.
In order to obtain the required two-beam path direction coverage, welds would have to be re-designed to allow scanning from both sides.
The use of radiography as an alternate volumetric examination method for is not practical due to component thickness and geometric configurations.
Other restrictions making radiography impractical are the necessity to use double wall techniques due to inaccessibility of the ID surface and physical barriers prohibiting access for placement of source, film, number bands, etc.
I IFirestone, F.A.: Tricks with the Supersonic Reflectoscope, J.
Soc. Nondestructive Testing, vol. 7, no. 2 Fall 1948.
I l
I
I l
Request for Relief Serial No. 99-02 Page 9 of 16 V.
Alternate Examinations or Testing:
No additional examinations are planned during the current interval for ID Numbers 1SGB-INLET, 1SGB-OUTLET, 1SGD-INLET, 1SGD-OUTLET, 1SGB-INLET-WSSE, ISGB-OUT-W6SE, ISGD-INLET-W5SE, 1SGD-OUT-W6SE, INC22-02, INC22-03, INC23-02, INC23-03, INC22-WN7, INC24-WN9, 1VCT-LH-SH and 1CA66-35.
Duke Energy Corporation will continue to use the most current ultrasonic techniques available to obtain maximum coverage for future 4
examinations of these ID Numbers.
VI. Justification for the Granting of Relief:
Steam Generators 1B and 1D Inlet and Outlet Nozzle Inner Radius Although the examination volume requirements as defined in ASME Section XI 1989 Edition with no addenda, Figure IWB-2500-7(b), Examination Volume M-N-O-P for ID Numbers 1SGB-Inlet, ISGB-Outlet, ISGD-Inlet and 1SGD-Outlet (Item Nos. B03.140.003, B03.140.004, B03.140.007 and B03.140.008 respectively) could not be met, the amount of coverage obtained for these examinations provides an acceptable level of quality and integrity.
For results of the examinations, reference Attachments 2, 3,4 and 5.
See additional comments below in the discussion of Class 1 Piping Welds, j
i j
1 l
l l
i i
Request for Relief Serial No. 99-02 Page 10 of 16 Steam Generators 1B and 1D Inlet and Outlet Nozzle-to Safe-End Welds Although the examination volume requirements as defined in ASME Section XI, Appendix III, Paragraph III-4420, 1989 Edition with no addenda, for ID Numbers ISGB-INLET-W5SE, ISGB-OUT-W6SE, 1SGD-INLET-W5SE and 1SGD-OUT-W6SE (Item Nos. B05.070.003, B05.070.004, B05.070.007 and B05.070.008 respectively) could not be met, the amount of coverage obtained provides an acceptable level of quality and integrity.
For results of the examinations, reference Attachments 6,7,8 and 9.
See additional comments below in the discussion of Class 1 Piping Welds.
Class 1 Piping Welds Although the examination volume requirements as defined in ASME Section XI, Appendix III, Paragraph III-4420, 1989 Edition with no addenda, for ID Numbers 1NC22-02, INC22-03, INC23-02, 1NC23-03, 1NC22-WN7 and 1NC24-WN9 (Item Nos. B09.011.049, B09.011.050, B09.011.051, B09.011.052, B09.031.001 and B09.031.003 respectively) could not be met, the amount of coverage obtained provides an acceptable level of quality and integrity.
For results of the examinations, reference Attachments 10, 11, 12, 13, 14 and 15.
The nozzle inner radius, nozzle to safe-end welds, and class 1 pipe welds on the Steam Generator Inlet and Outlet Nozzles are located inside containment and are part of the reactor coolant system pressure boundary.
" Quality of Reactor Coolant Pressure Boundary," of Appendix A to 10 CFR Part 50,
" General Design Criteria for Nuclear Power Plants," mandates that means be provided for detecting and, to the extent practical, identifying the location of the source of reactor coolant leakage. If a leak were to develop at these weld locations discussed in this relief request the instrumentation available to the operators for detection and monitoring of leakage would provide a prompt and qualitative information necessary to permit them to take immediate corrective action.
If a
leak should develop in these aforementioned locations the only corrective action
I l
Request for Relief Serial No. 99-02 4
Page 11 of 16 would be shutdown and depressurize the reactor coolant system since the welds are non-isolatable.
l Plant Technical Specifications dictate that a reactor coolant system water inventory balance be performed on a regular basis. A normal operating practice is to perform this computer based mass balance on a daily frequency and/or whenever the operators suspect any abnormal changes to other leakage detection systems.
Plant Technical Specification requires that if the leak rate cannot be reduced below 1 gpm unidentified that
{
the plant be put in hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Leakage as a result of a failed weld discussed in this section would show up as unidentified leakage and subject to the 1 gpm limit.
Other leakage detection systems available to the operator and dictated per plant technical specifications are:
- Containment Atmosphere Gaseous and Particulate Radioactivity Monitoring System (EMF monitors 38 &
39) which would detect airborne radiological activity;
- Containment Floor and Equipment Sump Level and Flow Monitoring Subsystem where unidentified accumulated water on the containment floor would be monitored and evaluated as sump level changes; Containment Ventilation Unit Condensate Drain Tank Level Monitoring Subsystem which collects and measures as unidentified leakage the moisture removed from the containment atmosphere.
Additionally, other indicators are also available to the operator that a leak exists or may be developing:
Containment Atmosphere Iodine Monitor (EMF 40)
Charging / Letdown system mismatches; Containment humidity indications; Pre-Cycle walkdowns performed each outage while system is at operating temperature and pressure prior to criticality; Post-Cycle walkdowns performed at operating temperature and pressure performed during unit shutdown.
Request for Relief Serial No. 99-02 Page 12 of 16 Volume Control Tank Lower Head-to-Shell Weld Although the examination volume requirements as defined in ASME Section XI, Appendix III, Paragraph III-4420, 1989 Edition with no addenda, for ID Number IVCT-LH-SH (Item Number C01.020.016) could not be met, the amount of coverage obtained provides an acceptable level of quality and integrity.
For results of the examination, reference Attachment 16.
The Volume Control Tank (VCT) is used in power operations.
The VCT is located in the Auxiliary Building adjacent to the unit mechanical penetration room on floor elevation 560 feet.
During power operations and unit refueling
- outages, the VCT is accessible for visual inspections.
If a leak were to occur at the welds in question (lower head to shell weld), there are several periodic tests and evaluations that are performed by established procedures that should identify the leakage for prompt OPS /ENG evaluation:
During power operation, any leakage from the VCT would be identified as a mass loss in reactor coolant system water inventory balance.
As described above, a normal operating practice is to perform this computer based mass balance on a daily frequency and/or whenever the operators suspect any abnormal changes to other leakage detection systems. Plant Technical Specification requires that if the leak rate cannot be reduced below 1 gpm unidentified that the plant be put in hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown j
within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Leakage as a result of a failed weld discussed in this section would show up as unidentified leakage and subject to the 1 gpm limit.
I
- If a leak were to occur at the subject welds, the water would spill on floor in VCT room and flow to l
floor drain and then to Floor Drain Tank.
Our Chemistry department periodically monitors the tank level and evaluates unidentified leakage for correction.
Request for Relief Serial No. 99-02 Page 13 of 16 Weekly visual inspections are made by Operations into the VCT Room per PT/l(2)/A/4150/02 (Visual Inspection of Radioactive Components Outside Containment).
Any leaks are required to be reported and evaluated per this Periodic Test.
Quarterly walkdowns by the System Engineer include a check of the VCT and related components.
Periodically, visual material condition inspections in accordance with NSD 104 are made in the VCT room by the site owner of the Aux Bldg Elev 560 area.
Identified leakage would be reported for evaluation.
- At a frequency of each refueling outage, visual leakage inspections of the VCT and charging system are made per PT procedure PT/1(2)/A/4202/06, " Leak Rate Determination for NV System."
Any NV components identified with external leakage are documented for evaluation, including the VCT.
Steam Generator lA Auxiliary Feedwater Nozzle Transition Ring-to-Elbow Weld Although the examination volume requirements as defined in ASME Section XI, Appendix III, Paragraph III-4420, j
1989 Edition with no addenda, for ID Number 1CA66-35
)
(Item Number C05.0ll.012) could not be met, the amount i
of coverage obtained provides an acceptable level of quality and integrity.
For results of the examination, reference Attachment 17.
If a leak were to occur at the weld in question (Steam Generator ID Auxiliary Feedwater (CA)
Nozzle to Transition Piece, Weld 1SGD-W261), there are methods by I
which the leak could be identified for prompt Engineering evaluation, i
l The CA nozzles are at final feedwater pressure and temperature.
In Modes 1 (Power </= approximately 17%),
2, and 3,
all feedwater is provided to the steam generators via the CA nozzle (CF-to-CA Bypass Fiow).
In Mode 1 (Power >/= approximately 17% power), a small amount of feedwater (Tempering Flow) is directed to the CA nozzle of the steam generators to keep the nozzles j
l at final feedwater temperature to reduce the thermal l
\\
Request for Relief Serial No. 99-02 Page 14 of 16 shock to the nozzles associated with CA system operation and transfer of feedwater flow to the nozzles during unit shutdowns.
A leak at the CA nozzle would result in the following:
- Increased S/G enclosure temperature.
This parameter -is monitored periodically by the Containment Ventilation System (VV)
Engineer per the associated
" Engineering Support Program".
- Increased input into the Ventilation Unit Condensate Drain Tank (VUCDT).
This parameter is monitored continuously by Operations via an OAC alarm and also periodically by the Liquid Radwaste System (WL)
Engineer and Reactor Coolant System (NC) Engineer per the associated
" Engineering Support Program".
Note:
The above parameters would be used to identify a
leak in the steam generator enclosure, but could not specifically identify the CA nozzle as the source of leakage.
A containment entry would be required to identify the exact source of the leakage, Also, a containment walkdown is performed when e
the unit reaches Mode 3 (full temperature /
pressure) during the unit shutdown for each refueling outage.
This walkdown should identify any leak at the weld in question.
Concerning the consequences of a leak at the CA nozzle (affects on CA system operation): Any leakage would result in a portion of the CA flow bypassing the steam generator, and therefore being unavailable to maintain steam generator levels.
Very small leaks
(<
1 gpm) would have no discernible effect on CA system operation.
Leaks that approach 5 gpm would need to be evaluated for system operability effects.
VII. Implementation Schedule:
These examinations will continue to be scheduled in accordance with the requirements of ASME Section XI for future Inspection Intervals at Catawba Nuclear Station, Unit 1.
Request for Relief Serial No. 99-02 Page 15 of 16 The following individuals contributed to the development of this RFR Jim McArdle (NDE Level'III) provided Sections 3-5 David Goforth, Mike Murdock and Steve Mays (System Engineers) provided Section 6 Andy Hogge and Jimmy Cherry (Sponsors) compiled the remaining sections
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i Request for Relief Serial No. 99-02
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Page 16 of 16 i
Description Table i
UT Examination Data B03.140.003 UT Examination Data B03.140.004 UT Examination Data B03.140.007 UT Examination Data B03.140.008 UT Examination Data B05.070.003 UT Examination Data B05.070.004 UT Examination Data B05.070.007 UT Examination Data B05.070.008 0 UT Examination Data B09.011.049 1 UT Examination Data B09.011.050 Attachmert 12 UT Examination Data B09.011.051 3 UT Examination Data B09.011.052 4 UT Examination Data B09.031.001 5 UT C'iamination Data B09. 031. 003 6 UT Examination Data C01.020.016 7 UT Examination Data C05.011.012 l
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,c Examination Volume / Area Defined O Base Metal O weld O Near Surface O Bolting El Inner Radius Area Calculation Volume Calculation Sin RTT - 4.51n RTT / 4 = 3.78in
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1 70/60 23.5/23* skew 4.98 94.25 469.37 563.6 83.28 l
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Examination Volume / Area Defined l
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DUKE POWER COMPANY NDE-91-1 b)
Limited Examination Coverage Worksheet i
Revision 0 Examination Volume / Area Defined O Base Metal O
Weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation D
Sin RTT - 4.5 in RTT / 4 = 3.76 in 5.98 in x 30in DIATT = 563.6 in3 4.5 x 0.5 in = 2.25 in Total = 5.98 in
- Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Scan # Angle Direction Percent Coverage (sq.in.)
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Revision 0 Examination Volume / Area Defined O Base Metal O
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Limited Examination Coverage Worksheet Revision 0 Examination Volume / Area Defined O Base Metal O Weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation 3.2" X 1.25" = 4 SQ. IN.
4 SQ. IN. X 121"(VELD LENGTH) = 484 CU. IN Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Scan # Angle Direction (sq.in.)
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DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0
.,,,.,...m Exarnination Volume / Area Defined B Base Metal B Weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation 3.2" X 1.25" = 4 SQ. IN.
4 SQ. IN. X 121"(WELD LENGTH) = 484 CU. IN.
Coverage Calculations 1
Area Length Volume Volume d
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1 33 1
4 121 484 484 100.00 2
45 2
0 121 0
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45 CW 4
121 484 484 100.00 TOTAL AGGREGATE COVERAGE 1452 1936 75.00 i
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7 DUKE POWER COMPA'NY NDE-91-1 O'
Limited Examination Coverage Worksheet Revision 0 l
Examination Volume / Area Defined 1
O Base Metal O Weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation AXIAL SCANS 1 & 2 AX1AL SCANS 1 & 2 2.9 X.83 = 2.407 2.9 X.83.114 = 274.398 I
CIRC SCAN 3 & 4 CIRC SCANS 3 & 4 2.65 X.83 = 2.199 2.9 X.83 X 114 = 250.68 Coverage Calculations Area Length Volume Volume i d
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1 45*L 1
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45*L CW 2.199 114 250.68 250.68 100.00 4
45'L CW 2.199 114 250.68 250.68 100.00 TOTAL AGGREGATE COVERAGE 683.475 1050.156 65.08 Item No:
B09.011.049 Date:#[u/g Prepared By:
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DUKE POWER COMPANY NDE-91-1
/
t Limited Examination Coverage Worksheet l
Examination Volume / Area Defined O Base Metal B Weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation
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AS GROUND CONDITION AX SCAN 1 & 2 TOP HALF OF WELD 1.4 X.83 X 114 = 132.468 AX SCAN 1 & 2: 1.4 X.83 = 1.162 CIRC SCAN 3 & 4 CIRC SCAN 3 & 4: 1.15 X.83 =.9545 1.15 X.83 X 114 = 108.81 Coverage Calculations Area Length Volume Volume d
eq Scan # Angle D rect on sq in.)
( n.
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eui Percent Coverage 1
45*L S2 1.162 57 66.23 66.23 100.00 2
45'L S1 0.0 0.0 0
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45*L CW
.9545 57 54.4 54.4 100.00 4
45*L CCW
.9545 57 54.4 54.4 100,00 j
TOP HALF COVERAGE 175.03 241.26 72.55 Item No:
B09.011.050 Prepared By:
Level: [
Date:
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Reviewed By:
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DUKE POWER COMPANY NDE-91-1
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Limited Examination Coverage Worksheet Revision 0 Examination Volume / Area Defined I
O Base Metal B Weld O Near Surface O Botting O Inner Radius Area Calculation Volume Calculation l
AS WELDED CONDITION AX SCAN 1 & 2 BOTTOM HALF OFWELD 1.4 X.83 X 114 = 132.468 AX SCAN 1 & 2: 1.4 X.83 = 1.162 CIF.C SCAN 3 & 4 CIRC SCAN 3 & 4: 1.15 X.83 =.9545 1.15 X.83 X 114 = 108.81 Coverage Calculations l
Area Length Volume Volume d
Examind Examjud Requjred Percent Coverage Scan # Angle D rec on (sq.in.)
(in.)
(cu.in.)
(cu.in.)
1 45*L S2 1.052 57~
59.964 66.234 90.53 2
45*L S1 0
0 0
66.234 0.00 3
45'L CW
.2075 57 11.827 54.4 21.74 4
45'L CCW
.2075 57 11.827 54.4 21.74 BOTTOM HALF COVERAGE 83.618 241.268 34.66 1
l l
Item No:
B09.011.050 Prepared By: [
Level: [
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DUKE POWER COMPANY NDE-91-1 i
Limited Examination Coverage Worksheet Revision 0 Examination Volume / Area Defined O Base Metal B Weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation TOTAL COVERAGE FOR ENTIRE WELD AX SCAN 1 & 2 AX SCAN 1 & 2 - 1.4 X.83 = 1.162 1.4 X.83 X 114 = 132.468 CIRC SCAN 3 & 4 - 1.15 X.83 =.9545 CIRC SCAN 3 & 4 1.15 X.83 X 114 = 108.81 Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Percent Coverage Scan # Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.in.)
BOTTOM 45*L alt.
83.618 241.26 34.66 TOP 45'L ALL 175.03 241.26 72.55 TOTAL AGGREGATE COVERAGE 258.648 482.52 53f4 i
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DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0 Examination Volume / Area Defined D Dase Metal O
Weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation AX SCAN 1 & 2 AX SCANS 1 & 2 1.7 X.83 = 1.411 1.7 X.83 X 114 = 160.85 CW/CCW SCAN 3 & 4 CW/CCW SCANS 3 & 4 1.45 X.83 = 1.2035 1.45 X.83 X 114 = 137.19 i
Coverage Calculations Area Length Volume Volume nd Examined Examined Required Scan # Angle D rec on m
Percent Coverage (sq..)
(in.)
(cu.in.)
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1 45*L 1
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45'L 2
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3 45'L LW
.2075 114 23.65 137.195 17.24 4
45'L CCW
.2075 114 23.65 137.195 17.24 168.026 506.09 28.19 Item No:
B09.011.051 Prepared By:
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DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0 Examination Volume / Area Defined O Base Metal O
Weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation AX Scans 1 & 2 AX Scan 1 & 2 2.3 x.83 = 1.909 2.3 x.83 x 114 = 217.626 CW/CCW Scans 3 & 4 CW/CCW Scans 3 & 4 2.05 x.83 = 1.708 2.05 x.83 x 114 = 193.97 Coverage Calculations Area Length Volume Volume d
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.2075 114 23.65 193.97 12.19 204.52 833.18 24.55 item No:
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DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0
..~........m Examination Volume / Area Defined O Base Metal O Weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation PROFILE 1 - SCAN 1-4 63" DIA. / 2 = 31.5" @ PROFILE 2.1" X.77" = 1.62 SQ. IN.
PROFILE 1 PROFILE 2 - SCAN 5 - 8 1.62 SQ. IN. X 31.5" = 51.03 CU. IN.
2 2" X.77" = 1.69 SQ. IN.
PROFILE 2 1.69SO. IN. X 31.5" = 53.24 CU. IN.
Coverage Calculations Area Length Volume Volume d
Examined harnined Requjred Percent Coverage Scan # Angle D rec on (sq.in.)
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1 45 2
1.62 19 30.78 30.78 100.00 i
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l f,
item No:
B09.031.001 Prepared By:
gg Level: 777 Date: y,y 99 j
Reviewed By:
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DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0 Examination Volume / Area Defined 8 Base Metal 8 Weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation PROFILE 1 - SCAN 1-4 63" DIA. / 2 = 31.5" @ PROFILE 2.1" X.77" = 1.62 SQ. IN.
PROFILE 1 PROFILE 2 - SCAN 5 - 8 1.62 SQ. IN. X 31.5" = 51.03 CU. IN.
2.2" X.77" = 1.69 SQ. IN.
PROFILE 2 1.69SO. IN. X 31.5" = 53.24 CU. IN.
Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Scan # Angle Direction (sq.in.)
(in.)
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(cu.in.)
Percent Coverage 7
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.10 19 1.9 32.11 5.92 7
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Item No:
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Limited Examination Coverage Worksheet Revision 0 l
..=
m Examination Volume / Area Defined
{
G Base Metal O Weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation PROFILE 1 SCAN 1 - 4 38" DIA. / 2 = 19" @ PROFILE 2 X.77 = 1.54 SQ. IN.
PROFILE 1 1.54 SQ. IN. X 19" = 29.26 CU. IN.
PROFILE 2 SCAN 5 -8 PROFILE 2 2.2 X.77 = 1.69 SQ. IN.
1.69 SQ. IN. X 19" = 32.11 CU. IN.
Coverage Calculations Area Length Volume Volume d
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.17 19 3.23 32.11 10.06 72.77 245.48 29.64 I
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DUKE POWER COMPANY NDE-91-1 i
Limited Examination Coverage Worksheet Revision 0 m
Examination Volume / Area Defined S Base Metal B Weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation 1.4 / 2 (.360 +.330) =.483 SQ. IN
.483 SO. IN. X 283 IN = 136.69 CU. IN.
Coverage Calculations Area Length Volume Volume nd Examined hamined i
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r-l DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0 Examination Volume / Area Defined B Base Metal O Weld O Near Surface O Bolting O Inner Radius 1
Area Calculation Volume Calculation
.24 X 1.5 +.55 X.4 / 2 =.47 SQ. IN.
.47 SQ. IN. X 20.8".= 9.776 = 9.776 = 9.78 CU. IN.
l Coverage Calculations Area Length Volume Volume nd
&amined Examined Required Scan # Angle D rec on Percent Coverage (sq. n.)
(in.)
(cu.in.)
(cu.,n.)
i i
1 45 1
.47 20.8 9.78 9.78 100.00 2
45 2
0 20.8 0
9.78 0.00 3
45 CW
.47 20.8 9.78 9.78 100.00 4
45 CCW
.47 20.8 9.78 9.78 100.00 29.34 39.12 75.00 l
l 1
l Item No:
C05.011.012 Prepared By:
Qgg Level: y Date: 3,6 O Reviewed By:
[
Level: 3 Date: f,N.97 YI~
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