ML022200497
| ML022200497 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/29/2002 |
| From: | Gordon Peterson Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022200497 (71) | |
Text
PkDuke rPower A Duke Energy Company GARY R. PETERSON Vice President Catawba Nuclear Station Duke Power CNO1 VP / 4800 Concord Rd.
York, SC 29745 803 831 4251 803 831 3221 fax grpeters@duke-energy, corn July 29, 2002 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C.
20555
Subject:
Duke Energy Corporation Catawba Nuclear Station, Unit 2 Docket Number 50-414 Request for Relief Number 01-003, Revision 1 Limited Weld Examinations in End-of-Cycle 11 Refueling Outage
Reference:
Letter from Gary R. Peterson to NRC dated December 20, 2001 Please find attached, pursuant to 10 CFR 50.4 and 10 CFR 50.55a(g) (5) (iii),
Request for Relief Number 01-003, Revision
- 1. This request pertains to limited weld examinations during the Unit 2 End-of-Cycle 11 Refueling Outage and addresses issues discussed in a recent telephone conference call between Duke and NRC personnel.
Revision 1 of this Request for Relief supercedes Revision 0 in its entirety.
(Revision 0 was transmitted via the reference letter.)
Duke is requesting that NRC review and approve this Request for Relief at your earliest available opportunity.
There are no regulatory commitments contained in this letter or its attachment.
If you have any questions concerning this subject, please call L.J. Rudy at (803) 831-3084.
Very t
-u;yy Gary~ eterson Q
www. duke-energy. com
Document Control Desk Page 2 July 29, 2002 LJR/s Attachment xc (with attachment):
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 C.P. Patel, Senior Project Manager (addressee only)
U.S. Nuclear Regulatory Commission Mail Stop 08-H12 Washington, D.C.
20555-0001
Request for Relief Serial No.01-003 Revision 1 Page 1 of 20 DUKE ENERGY CORPORATION STATION: CATAWBA NUCLEAR STATION UNIT 2 10-YEAR INTERVAL REQUEST FOR RELIEF NO.01-003 Revision 1 Duke Energy Corporation has determined that conformance with certain ASME Section XI Code requirements is impractical.
Therefore, pursuant to 10CFR50.55a(g) (5) (iii),
Duke Energy requests relief from applicable portions of the code.
Reference Attachment 1 for welds addressed by this relief request.
There are six (6) welds in this request: one B-D, one B-J, three C-B, and one C-F-I.
ASME Section XI Code of Record: 1989 Edition with no addenda Interval: Second Ten-Year Interval; Second Inspection Period Applicable Code Case: N-460 I.
System/Component(s) for Which Relief is Requested:
ASME Section XI Code Class 1 Examination Category B-D Full Penetration Welds of Nozzles In Vessels ID Number 2PZR-Wl Item Number B03.110.001 Configuration Pressurizer Nozzle-to-Vessel Welds II.
Code Requirement:
ASME Section XI 1989 Edition with no addenda, Examination Category B-D, Item No. B03.110, Figure IWB 2500-7 (b),
Examination Volume A-B-C-D-E-F-G-H.
Request for Relief Serial No.01-003 Revision 1 Page 2 of 20 III.
Code Requirement from which Relief is Requested:
Relief is being sought from the requirement to examine 100% of the volume A-B-C-D-E-F-G-H shown in Figure IWB 2500-7(b).
IV.
Basis for Relief:
During the ultrasonic examination of the Pressurizer Surge Nozzle to Head Weld, 2PZR-Wl shown in Attachment 2,
100% coverage of the required examination volume could not be obtained.
The examination coverage was limited to 42.80%.
Limitations are caused by the weld geometry that restricts access to only one side of the weld, and the proximity of heater tubes that restrict the scanning surface.
The percentage of coverage reported represents the aggregate coverage obtained from one scan perpendicular to the weld axis and two
- scans, 1800 apart parallel to the weld.
V.
Alternate Examinations or Testing:
No additional examinations are planned during the current interval for 2PZR-Wl.
Radiography is not practical because of the geometry of the component, which prevents placement of the film and exposure source.
Duke Energy Corporation will continue to use the most effective ultrasonic techniques available to obtain maximum coverage for future examination of this weld.
VI.
Justification for the Granting of Relief:
Although the examination volume A-B-C-D-E-F-G-H in Figure IWB-2500-7(b) for ID Number 2PZR-Wl could not be covered, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity.
For results of the examination, reference.
Pressurizer Surge Nozzle to Head Weld, 2PZR-WI is located inside containment and is part of the reactor coolant system pressure boundary. General Design Criterion 30, "Quality of Reactor Coolant Pressure
Request for Relief Serial No.01-003 Revision 1 Page 3 of 20 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 this weld location, the instrumentation available to the operators for detection and monitoring of leakage would provide prompt and qualitative information necessary to permit them to take immediate corrective action.
If a leak should develop, the only corrective action would be to shutdown and depressurize the reactor coolant system, since the component is non isolable.
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. A 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:
Request for Relief Serial No.01-003 Revision 1 Page 4 of 20
"* 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.
VII. Implementation Schedule:
This examination will continue to be scheduled in accordance with the requirements of ASME Section XI for future inspection intervals.
Request for Relief Serial No.01-003 Revision 1 Page 5 of 20 I.
System/Component(s) for Which Relief is Requested:
ASME Section XI Code Class 1 Examination Category B-J Pressure Retaining Welds in Piping; Branch Pipe Connection Welds ID Number Item Number Configuration 2NC13-WN9 B09.031.003 Nozzle to Pipe II.
Code Requirement:
ASME Section XI 1989 Edition with no addenda, Examination Category B-J, Item No. B09.031, Figure IWB 2500-11.
ASME Section XI, Appendix III, Paragraph 111-4420, 1989 Edition with no addenda as modified by Code Case N-460.
"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."
III. Code Requirement from which Relief is Requested:
Relief is being sought from the requirement to examine the weld in two beam path directions, and to cover 100%
of the examination volume shown in Figure IWB-2500-11.
IV.
Basis for Relief:
During the ultrasonic examination of this branch pipe connection weld, 2NC13-WN9 shown in Attachment 3, greater than 90% of the required examination volume as allowed by Code Case N-460 could not be achieved.
The examination coverage was limited to 22.87% of the required examination volume. The percentage of coverage reported represents the aggregate coverage obtained from one scan parallel to the pipe axis and two scans, 1800 apart in the circumferential direction on the weld.
Although 22.87% is the coverage claimed for this
Request for Relief Serial No.01-003 Revision 1 Page 6 of 20 examination, 100% of the examination volume was covered with a 45 degree angle from one direction perpendicular to the weld axis.
This is an austenitic stainless steel branch connection weld where access is limited to the main run pipe side of the weld.
The main run of pipe is cast stainless steel. The weld design prevented any scan from the branch connection side.
In order to achieve coverage in the two beam path directions, and to cover greater than 90% of the examination volume, the weld would have to be re-designed to allow scanning from both sides.
Duke Energy Corporation does not claim credit for coverage of the far side of austenitic welds.
The characteristics of austenitic weld metal attenuate and distort the sound beam when shear waves pass through the weld.
Duke Energy Corporation uses dual element refracted longitudinal wave transducers, which provide superior penetration, to examine cast austenitic welds.
The refracted longitudinal wave transducers have a simulated focus effect which produces high sensitivity at a specific sound path distance. However, the sound beam diverges beyond this focal point and the sensitivity decreases by a factor of two at twice the focal sound path distance. The transducers used in this examination have focal distances from 3/4 T to T, where "T"
is the nominal thickness of the main run of pipe.
As a result, there is not enough sensitivity to calibrate the ultrasonic system for extended sound path distances beyond the pipe inside surface.
V.
Alternate Examinations or Testing:
No additional examinations are planned during the current interval for 2NC13-WN9.
Radiography is not practical because of the geometry of the component, which prevents placement of the film and exposure source.
Duke Energy Corporation will continue to use the most effective ultrasonic techniques available to obtain maximum coverage for future examination of this weld.
VI.
Justification for the Granting of Relief:
Although the examination requirements as defined in ASME Section XI 1989 Edition with No Addenda, Appendix III, Paragraph 111-4420, for ID Number 2NC13-WN9, could
Request for Relief Serial No.01-003 Revision 1 Page 7 of 20 not be covered, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity.
For results of the examination, reference Attachment 3.
2NC13-WN9 is located inside containment and is part of the reactor coolant system pressure boundary. General Design Criterion 30, "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 this weld location, the instrumentation available to the operators for detection and monitoring of leakage would provide prompt and qualitative information necessary to permit them to take immediate corrective action. If a leak should develop, the only corrective action would be to shutdown and depressurize the reactor coolant system, since the component is non isolable.
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. A 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;
Request for Relief Serial No.01-003 Revision 1 Page 8 of 20 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.
This weld is located on the 12" RHR suction line off the Loop 2C hot leg.
The nozzle material is SA182 F304N welded to the RCL hot leg piping which is SA351 CF8A.
There are no known degradation mechanisms associated with this material and no industry failure experience with this type of joint.
No effects from fatigue, corrosion, or stress corrosion cracking have ever been identified for this type of joint.
These stainless steel components are subjected to the primary water environment.
Water chemistry of primary systems is treated to minimize corrosion and periodically monitored to verify that the water quality meets the specifications.
Chlorides, fluorides, and particularly oxygen are controlled to very low limits.
The selected component materials in combination with the restricted limits of primary water chemistry preclude significant degradation of this joint.
VII. Implementation Schedule:
This examination will continue to be scheduled in accordance with the requirements of ASME Section XI for future inspection intervals.
Request for Relief Serial No.01-003 Revision 1 Page 9 of 20 I.
System/Component(s) for Which Relief is Requested:
ASME Section XI Code Class 2 Examination Category C-B Pressure Retaining Nozzle Welds in Vessels; Nozzle to Shell (or Head) Weld ID Number Item Number Configuration 2SGB-06A-18 C02.021.001 Nozzle to Shell Weld II.
Code Requirement:
ASME Section XI 1989 Editionwith no addenda, Examination Category C-B, Item No. C02.021, Figure IWC 2500-4 (a).
ASME Section V, Article 4, Paragraph T 424.1 states:
"The volume shall be examined by moving the search unit over the examination surface so as to scan the entire examination volume."
III.
Code Requirement from which Relief is Requested:
Relief is being sought from the requirement to scan the entire examination volume C-D-E-F shown in Figure IWC 2500-4(a).
IV.
Basis for Relief:
During the ultrasonic examination of Steam Generator 2B Auxiliary Feedwater Nozzle-to-Shell Weld 2SGB-06A-18, Item Number C02.021.001, greater than 90% coverage of the required examination volume could not be obtained.
The examination coverage was limited to 75.00% of the required examination volume.
This is a ferritic nozzle to shell weld where access is limited to the vessel shell side only.
The weld would have to be re-designed to allow scanning from both sides in order to achieve greater than 90% coverage.
The percentage of coverage reported represents the aggregate coverage obtained from one scan perpendicular to the weld axis and two
- scans, 1800 apart parallel to the weld as shown in.
Request for Relief Serial No.01-003 Revision 1 Page 10 of 20 V.
Alternate Examinations or Testing:
No additional examinations are planned during the current interval for ID Number 2SGB-06A-18.
Radiography is not an acceptable alternative because of access restrictions for source and film placement.
Duke Energy Corporation will continue to use the most effective ultrasonic techniques available to obtain maximum coverage for future examination of this weld.
VI.
Justification for the Granting of Relief:
Although the entire examination volume C-D-E-F in Figure IWC-2500-4(a) for ID Number 2SGB-06A-18 could not be covered, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity. For results of the examination, reference Attachment 4.
Steam Generator 2B Auxiliary Feedwater Nozzle-to-Shell Weld 2SGB-06A-18 is located inside containment and is part of the secondary system pressure boundary. If a
leak were to develop at this weld location, the instrumentation available to the operators for detection and monitoring of leakage would provide prompt and qualitative information necessary to permit them to take immediate corrective action. If a leak should develop, the probable corrective action would be shutdown and depressurize the steam generators, since the weld is non-isolable.
Other leakage detection systems available to the operator and dictated per plant technical specifications are:
" 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:
Request for Relief Serial No.01-003 Revision 1 Page 11 of 20
"* 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.
VII. Implementation Schedule:
This examination will continue to be scheduled in accordance with the requirements of ASME Section XI for future inspection intervals.
Request for Relief Serial No.01-003 Revision 1 Page 12 of 20 I.
System/Component(s) for Which Relief is Requested:
ASME Section XI Code Class 2 Examination Category C-B Pressure Retaining Nozzle Welds in Vessels; Nozzle to Shell (or Head) Weld ID Number Item Number Configuration 2BNSHX-3-NI C02.021.004 Nozzle to Channel Weld 2BNSHX-3-N2 C02.021.005 Nozzle to Channel Weld II.
Code Requirement:
ASME Section XI 1989 Edition with no addenda, Category C-B, Item No.
C02.021, Figure IWC-2500-4(a).
ASME Section XI, Appendix III, Paragraph 111-4420, 1989 Edition with no addenda as modified by Code Case N-460.
"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."
III.
Code Requirement from which Relief is Requested:
Relief is being sought from the requirement to perform the examination from two beam path directions, and to cover 100% of the examination volume shown in Figure IWC-2500-4(a).
IV.
Basis for Relief:
During the ultrasonic examination of the Containment Spray Heat Exchanger Inlet and Outlet Nozzle to Channel Welds 2BNSHX-3-Nl and 2BNSHX-3-N2 shown in Attachments 5 and 6, respectively, greater than 90% coverage of the required examination volume could not be obtained.
The examination coverage for both welds was limited to
Request for Relief Serial No.01-003 Revision 1 Page 13 of 20 49.03%.
The percentage of coverage reported represents the aggregate coverage obtained from one scan parallel to the nozzle axis and the two scans, 1800apart in the circumferential direction on the weld. Although 49.03%
is the coverage claimed for this examination, 100% of the inside surface within the examination volume was covered with a 700 angle from one direction perpendicular to the weld axis.
Austenitic weld metal characteristics and single sided access caused by the component geometry prevents two beam path direction coverage of the examination volume.
Obtaining coverage greater than 90% of the weld volume as defined in Code Case N-460 is not possible.
In order to achieve coverage in two beam path directions, and to cover greater than 90% of the examination volume, the welds would have to be re-designed to allow scanning from both sides.
Duke Energy Corporation uses refracted longitudinal waves, which provide superior penetration to examine austenitic welds.
The refracted longitudinal wave transducers have a simulated focus effect which produces high sensitivity at a specific sound path distance. However, the sound beam diverges beyond this focal point and the sensitivity decreases by a factor of two at twice the focal sound path distance.
The transducers used in this examination have focal distances from % T to T, where "T" is the nominal thickness of the nozzle.
As a result, there is not enough sensitivity to calibrate the ultrasonic system for extended sound path distances beyond the pipe inside surface.
V.
Alternate Examinations or Testing:
No additional examinations are planned during the current interval for weld Numbers 2BNSHX-3-Nl and 2BNSHX-3-N2.
Radiography is not an acceptable alternative because of access restrictions for source and film placement Duke Energy Corporation will continue to use the most effective ultrasonic techniques available to obtain maximum coverage for future examination of these welds.
VI.
Justification for the Granting of Relief:
Request for Relief Serial No.01-003 Revision 1 Page 14 of 20 Although the examination volume as defined in ASME Section XI 1989 Edition with no addenda, Figure IWC 2500-4 (a) could not be covered in two beam path directions, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity. These welds were examined using procedures and calibration blocks in accordance with ASME Section XI, Appendix III.
Containment Spray (NS) is used to control pressure inside the containment vessel during a safety injection with high containment pressure.
This system is not used for normal operation of the plant.
The area that contains the welds (Containment Spray Heat Exchanger Inlet and Outlet Nozzle to Channel) is surveyed twice a day by Operations during their routine rounds.
One of the items that must be checked off is for general condition of the room containing the heat exchanger.
It is reasonable to expect the operator making these rounds to detect any external leaks from these welds.
This same area is also surveyed once a week by a periodic test that is used to specifically look for radioactive leaks outside containment.
This area must be surveyed and signed off.
If a leak were encountered, it would be written up in a work request and a Problem Investigation Process form filled out.
The Fluid Leak Management Process then examines the leak.
The leak is either repaired or set up for periodic monitoring.
A leak in the NS system would also have to be entered into the Emergency Core Cooling System Leakage Program managed by Technical Specification 5.5.3.
These welds are located on the inlet and outlet nozzle connections to the NS heat exchangers.
These are 12" connections between the SA312 TP304 nozzles and the SA240 TP304 channel cylinder.
There are no known degradation mechanisms associated with this material and no industry failure experience with this type of joint.
No effects from fatigue, corrosion or stress corrosion cracking have ever been identified for these types of joints.
These stainless steel components are subjected to the primary water environment.
Water chemistry of primary systems is treated to minimize corrosion and periodically monitored to verify that the water quality meets the specifications.
Chlorides, fluorides, and particularly oxygen are controlled to very low limits.
The selected component materials in
Request for Relief Serial No.01-003 Revision 1 Page 15 of 20 combination with the restricted limits of primary water chemistry preclude significant degradation of these joints.
VII. Implementation Schedule:
These examinations will continue to be scheduled in accordance with the requirements of ASME Section XI for future inspection intervals.
Request for Relief Serial No.01-003 Revision 1 Page 16 of 20 I.
System/Component(s) for Which Relief is Requested:
ASME Section XI Examination Category C-F-I Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping; Circumferential Weld ID Number Item Number Configuration 2NV20-5 C05.021.232 Pipe to Valve II.
Code Requirement:
ASME Section XI 1989 Edition with no addenda, Examination Category C-F-l, Item No. C05.021, Figure IWC-2500-7 (a),
Examination Volume C-D-E-F.
III.
Code Requirement from which Relief is Requested:
Relief is being sought from the requirement to examine 100% of Volume C-D-E-F shown in Figure IWC-2500-7 (a).
IV.
Basis for Relief:
During the ultrasonic examination of this pipe to valve weld, 2NV20-5 shown in Attachment 7, greater than 90%
of the required examination volume as allowed by Code Case N-460 could not be achieved.
The examination coverage was limited to 61.09% of the required examination volume.
This is an austenitic stainless steel pipe to valve weld where access is limited to the pipe side of the weld only.
The percentage of coverage reported represents the aggregate coverage obtained from one scan parallel to the pipe axis and two scans, 1800 apart in the circumferential direction on each weld.
The weld design prevented any axial scan from the valve side. In order to achieve more coverage the weld would have to be re-designed to allow scanning from both sides.
Duke Energy Corporation does not claim credit for coverage of the far side of austenitic welds. The characteristics of austenitic weld metal attenuate and
Request for Relief Serial No.01-003 Revision 1 Page 17 of 20 distort the sound beam when shear waves pass through the weld.
Refracted longitudinal waves provide better penetration.
Duke Energy Corporation uses a combination of shear waves and longitudinal waves to examine single sided austenitic 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 detected through the weld metal, PDI does not provide a qualification for single sided examinations of austenitic welds.
V.
Alternate Examinations or Testing:
No additional examinations are planned during the current interval for ID Number 2NV20-5.
Because of the valve configuration, radiography would not provide any additional coverage.
Duke Energy Corporation will use the most effective ultrasonic techniques available to obtain maximum coverage for future examination of this weld.
VI.
Justification for the Granting of Relief:
Although the examination volume as defined in ASME Section XI 1989 Edition with no addenda, Figure IWC 2500-7 (a) could not be covered, the amount of coverage obtained for these examinations provides an acceptable level of quality and integrity. These welds were examined using procedures, personnel and equipment qualified through the Performance Demonstration Initiative (PDI).
This weld is located on the Seal Return Line from the Reactor Coolant Pumps.
This same line also provides mini-flow protection for the high head safety injection pumps.
The seal return line containing this weld is normally in service during power operations.
The Seal Return Line containing the weld is located in the Auxiliary Building.
During power operations and unit refueling outages, the Seal Return Line is accessible for visual inspections.
Request for Relief Serial No.01-003 Revision 1 Page 18 of 20 If a leak were to occur at the weld in question (at Valve 2NV-204),
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 Seal Return Line would be identified as a mass loss in the 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.
A 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 l-gpm limit.
If a leak were to occur at the subject weld, the water would spill on the floor in the Auxiliary Building and flow to a floor drain and then to the Floor Drain Tank.
Our Chemistry department periodically monitors the tank level and evaluates unidentified leakage for correction.
This same area is also surveyed once a week by a periodic test that is used to specifically look for radioactive leaks outside containment.
This area must be surveyed and signed off.
If a leak were encountered, it would be written up in a work request and a Problem Investigation Process form filled out.
The Fluid Leak Management Process then examines the leak.
The leak is either repaired or set up for periodic monitoring.
VII. Implementation Schedule:
This examination will continue to be scheduled in accordance with the requirements of ASME Section XI for future inspection intervals.
Request for Relief Serial No.01-003 Revision 1 Page 19 of 20 Finally, for all of the welds covered by this request for relief, in the event that a through wall leak were discovered, the affected component would be subjected to an operability determination as required by existing plant processes.
Should the affected component be determined to be inoperable, the applicable Technical Specification remedial actions would be followed.
The following individuals contributed to the development of this RFR:
Jim McArdle (NDE Level III) provided Sections II-V and part of Section VI David Goforth (Systems Engineer) and Bill Callaway (Civil Engineer) provided part of Section VI Andy Hogge (Sponsor) compiled the remaining sections Sponsored By:
Approved By:
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Request for Relief Serial No.01-003 Revision 1 Page 20 of 20 Description Table UT Examination Data B03.110.001 UT Examination Data B09.031.003 UT Examination Data C02.021.001 UT Examination Data C02.021.004 UT Examination Data C02.021.005 UT Examination Data C05.021.232
Request for Relief Serial No.01-003 Revision 1 Page 1 of 3 ASME Class 1 & 2 Inservice Inspection Request For Relief 01-003 Revision 1 For Catawba Unit 2 Based on ASME Section XI -
1989 Code Licensee Item No.
Exam System Or Area To Be
Reason for Request
Proposed Category/
Component Examined Alternate Figure No.
Examination B03.110.001 B-D Pressurizer Pressurizer Limited scan due to the IWB-2500-7 Surge weld geometry that None (b)
Nozzle to restricts access to only Lower Head one side of the weld, and the proximity of heater tubes that restricts the scanning surface.
Actual coverage obtained
= 42.80%
(See Attachment 2)
B09.031.003 B-J NC System Reactor Limited scan due to IWB-2500-Coolant access limited to the None 11 System main run pipe side of the Appendix Nozzle to weld.
- III, Pipe Actual coverage obtained Paragraph
= 22.87%
111-4420 (See Attachment 3)
Request for Relief Serial No.01-003 Revision 1 Page 2 of 3 ASME Class 1 & 2 Inservice Inspection Request For Relief 01-003 Revision 1 For Catawba Unit 2 Based on ASME Section XI -
1989 Code Licensee Item No.
Exam System Or Area To Be
Reason for Request
Proposed Category/
Component Examined Alternate Figure No.
Examination C02.021.001 C-B Steam Steam Limited scan due to IWC-2500-4 Generator Generator access limited to the None (a) 2B vessel shell side only.
Auxilliary Actual coverage obtained Feedwater
= 75%
Nozzle to (See Attachment 4)
Shell C02.021.004 C-B Containment Containment Limited scan due to IWC-2500-Spray Heat Spray Heat single-sided access None 4(a)
Exchanger Exchanger caused by the component Appendix Outlet geometry.
- III, Nozzle to Actual coverage obtained Paragraph Channel
= 49.03%
111-4420 (See Attachment 5)
I
Request for Relief Serial No.01-003 Revision 1 Page 3 of 3 ASME Class 1 & 2 Inservice Inspection Request For Relief 01-003 Revision 1 For Catawba Unit 2 Based on ASME Section XI - 1989 Code Licensee Item No.
Exam System Or Area To Be
Reason for Request
Proposed Category/
Component Examined Alternate Figure No.
Examination C02.021.005 C-B Containment Containment Limited scan due to IWC-2500-Spray Heat Spray Heat single-sided access None 4(a)
Exchanger Exchanger caused by the component Appendix Inlet geometry.
- III, Nozzle to Actual coverage obtained Paragraph Channel
= 49.03%
111-4420 (See Attachment 6)
C05.021.232 C-F-I NV System Chemical Limited scan due to IWC-2500-7 and Volume access limited to the None (a)
Control pipe side of the weld Valve 2NV-only.
204 to Pipe Actual coverage obtained
= 61.09%
(See Attachment 7)
DUKE POWER COMPANY Exam Start:
1433 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish:
1504 Revision 4 Station:
CNS Unit:
2 Component/Weld ID: 2PZR-W1 Date:
10/9/2001 Weld Length (in.):
77" Surface Condition:
AS GROUND Lo:
9.2.3 Surface Temperature:
71 0 F Examiner: David Zimmerman
/
Level:
III Scans:
Pyrometer S/N:
MCNDE 27010 l
Cal Due:
2/14/2002 Examiner: Larry Mauldin Level:
III 45 CD dB 70 14 59 dB P
r NConfiguration:
ZR Surge Nozzle to Lower Hea Procedure:
NDE-620 Rev:
8 FO:
45T [_
dB 70T []
59 dB S2 Flow S1 00-07 60 19 74/71.5 dB NOZZLE to HEAD Calibration Sheet No:
60T 10 74/71.5 dB Scan Surface: OD 0102054, 0102055, 0102056 Applies to NDE-680 only Other:
dB Skew Angle:
N/A Max Mp W
L Beam Exam IND #.*f Max Max Max Li L2 Wi Mpl W2 Mp2 Dir.
Surf.
Scan Damps Ref 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac
- DO 10T WRITE HMA HMA HMA HMA HMA HMA Do NOT WRIT:
IN T-IS SP CE 50%dac 50%dac 50%dac 50%dac 50%dac 50%dac IN THIS SPACf 100%dac 100%dac 100%dac 100%dac 100%dac 100%dac NRI 60/70 Remarks:
Limitations: (see NDE-UT-4) EQ 90% or greater coverage obtained: yes [
no Sheetj/
of_/
Reviewed Bv:
Level:
Date:
A tho/ized Inspector:
Date:
Item No:
/ *)
~
- Y/c~
10"-//-OI
//)
j Lo B03.110. 001 V I I
6LJr5TP 1 e6//CP 4 4A'AIJT 2 01ý#'
DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2PZR-W1 Item No: B03.110.001 Remarks:
SURFACE BEAM DIRECTION
- There are 20 (.75" Dia.@) Heater NO SCAN Tubes, 700 L loss-2.3" @ = 46 in. I
[
LIMITED SCAN E2 1
13 2 0
1 El 2
E2 cw 12 ccw 60'L loss-3.2"@=64 in.
FROM L to L INCHES FROM WO 3.0" to BEYOND ANGLE:
02 0 12 45 5L 60 10 Other 700 FROM N/A DEG to N/A DEG SURFACE BEAM DIRECTION DUE TO NOZZLE CONFIGURATION.
0]
NO SCAN 12 LIMITED SCAN 1521] 22 1
1 2
IS cw ccw FROM L
__-N/A to L
_N/A-INCHES FROM WO 3.0" to BEYOND ANGLE:
12 0 12 45 C& 60 (] Other 700 FROM 0
DEG to 360 DEG SURFACE BEAM DIRECTION 12 NO SCAN 12 LIMITED SCAN C 1 2 2 C3 1
21 2
21 cw El ccw FROM L to L INCHES FROM WO to ANGLE:
12 0 12 45 12 60 12 Other FROM DEG to DEG SURFACE BEAM DIRECTION 12 NO SCAN ID LIMITED SCAN 0
1 2112 121 2
1 2
cw 1 1 ccw FROM L to L INCHES FROM WO to ANGLE:
12 0 12 45 12 60 12 Other FROM DEG to Date:
I Sketch(s) attached 12 yes 12 no Authorized Inspector:2
/;
Sheet,
of /!.?
Date: 2,o i7 7
/
/
I Level:
DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined El Base Metal El Weld
[E Near Surface El Boltina El Inner Radius Area Calculation Volume Calculation See Drwg. For Calculations Zone I = 4.9 sq.in.X 78 in. = 382.2 cu.in.
Zone I = 4.9 sq. in.
Zone II & III 11.1 sq.in. X 78 in. = 865.8 cu.in.
Zone II & III = 11.1 sq-in.
Loss = 70' -- 46 in., 60' -- 64 in. for heater tubes Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Percent Coverage Scan #
Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.in.)
1 2
3 4
5 5
6 7
8 70 70 70 70 70 60 60 60 60 60 2
2 1
2 1
CW CCW 4.1 2.3 1.8 3.5 3.5 11 1.8
.3 5.9 5.9 32 46 78 78 78 14 64 78 78 78 131.2 105.8 140.4 273 273 154 1152 23 4 460.2 460.2 156.8 225.4 382.2 382.2 382.2 155.4 710.4 865.8 865.8 865.8
DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined E] Base Metal E]
Weld El Near Surface El Boltinq El Inner Radius Area Calculation Volume Calculation See Drwg. For Calculations Zone I = 4.9 sq.in.X 78 in. = 382.2 cu.in.
Zone I = 4.9 sq. in.
Zone II & Ill = 11.1 sq.in. X 78 in. = 865.8 cu.in.
Zone II & III = 11.1 sq. in.
Loss = 700 -- 46 in., 60' -- 64 in. for heater tubes Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Percent Coverage Scan #
Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.in.)
2136.4 4992 42.80
0
0 N
0
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DUKE POWER COMPANY Exam St ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Fi Station:
CNS Unit:
2 Component/Weld ID: 2NC13-WN9 Weld Length (in.):
38" Surface Condition:
AS GROUND Lo:
9.2.3 Examiner
David Zimmerman
-,,,Level:
III Scans:
Examiner: Gary -J. Moss *
/
Level:
11 45 63 dB 70 dB Procedure:
NDE-610 RWe*:
4 1FC:
45T 1 63 dB 70T H] P Calibration Sheet No:
0102008, 0102009 Max Mp W
Max Max Ref DO OT W ITE IN T-I IS SP CE L
Max L1 Dir.
Surf.
I 1
20%dac HMA 50%dac 100%dac 60 11 dB 60T E dB Other:
L2 20%dac HMA 50%dac 100%dac I......
I I
I W1 20%dac HMA 50%dac 100%dac Mpl 20%dac HMA 50%dac 100%dac dB W2 20%dac HMA 50%dac 100%dac art:
1040 4-nish:
1059 Revision 4 Form NDE-UT-2A Date:
9/19/2001 Surface Temperature:
70 0 F Pyrometer S/N:
MCNDE 27010 Cal Due:
2/14/2002 Configuration:
Branch to Pipe
$1 Flow S2 Pipe to Branch Scan Surface: OD Applies to NDE-680 only Skew Angle:
N/A
. Mp2 Beam
- Dir, 20%dac HMA 50%dac 1 00%dac D(
IN Exam Surf.
) NOT THIS Scan Damps WRIT SPACE NRI 450 AXIAL NRI 450 CIRC Remarks:
- FC 97-01, 98-20 Limitations: (see NDE-UT-4) [Z 90% or greater coverage obtained: yes no SheetL of Reviewed B':/
Level:
Date:
Awthorized Insrpector:
Date:
Item No:
,-/"
/~ d/
B09.031.003 Jl-'
7&&
6/
63
-~/~j I
I 1040 Form NDE-UT-2A nish:
1059 Revision 4 dB
DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2NC13-WN9 Item No: B09.031.003 Remarks:
0 NO SCAN SURFACE BEAM DIRECTION NOZZLE CONFIGURATION 11 LIMITED SCAN El 1 12 1
21 1
2 cw 2 ccw FROM L to L INCHES FROM WO 2.0" to BEYOND ANGLE:
01 0 0 45 01 60 0 Other FROM 0
DEG to 360 DEG E0 NO SCAN SURFACE BEAM DIRECTION E0 LIMITED SCAN 1
E0 2 0
1i 2 01 cw I]
ccw FROML toL INCHES FROMWO to ANGLE:
C] 0 0 45 E0 60 E0 Other FROM DEG to DEG "C NO SCAN SURFACE BEAM DIRECTION LIMITED SCAN 0] 1 0 2
F0 1 []
2 El cw 11 ccw FROM L.
to L INCHES FROM WO to ANGLE:
0 0 0 45 0 60 11 Other FROM DEG to DEG
[3 NO SCAN 03 LIMITED SCAN SURFACE 10 2
to L BEAM DIRECTION 1
1 11 2
11 cw 0 ccw INCHES FROM WO ANGLE:
0l 0 E0 45 0 60 0 Other FROM to DEG to 0
FROM L
DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined
[] Base Metal
[]
Weld El Near Surface El Boltinq El Inner Radius Area Calculation Volume Calculation PROFILE #1 63" DIA. /2 = 31.5" @ PROFILE 2.1" X.77" = 1.62 SQ. IN.
PROFILE 1 PROFILE #2 1.62 SQ. IN. X 31.5" = 51.03 CU. IN.
2.2" X.77" = 1.69 SQ. IN PROFILE 2 1.69 SQ. IN. X 31.5" = 53.24 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.)
1 1
2 3
3 4
4 450 450 450 450 450 45° 450 PROFILE #1 2
2 1
Cw Cw ccw CCw 1.62 0
0
.33 0
.33
.33 19 12.5 31.5 19 12.5 19 12.5 30.78 0
0 6.27 0
6.27 0
30.78 20.25 51.03 30.78 20.25 30.78 20.25
DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined 0 Base Metal R
Weld El Near Surface El Boltinq
[E Inner Radius Area Calculation Volume Calculation PROFILE #1 63" DIA. /2 = 31.5" @ PROFILE 2.1" X.77" = 1.62 SQ. IN.
PROFILE 1 PROFILE #2 1.62 SQ. IN. X 31.5" = 51.03 CU. IN.
2.2" X.77" = 1.69 SQ. IN PROFILE 2 1.69 SQ. IN. X 31.5" = 53.24 CU. IN.
Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Percent Coverage Scan #
Angle Direction (sq. in.)
(in.)
(cu.in.)
(cuin.)
PROFILE #2 1
1 2
3 3
4 4
450 450 450 450 450 45° 45' 2
2 1
Cw Cw CCw ccw 1.64 0
0
.10 0
.10 0
19 12.5 31.5 19 12.5 19 12.5 31.16 0
0 1.9 0
1.9 0
95.38 32.11 21.13 53.24 32.11 21.13 32.24 21.13 417.08 22.87
el
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DUKE POWER COMPANY Exam Start:
1210 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish:
1236 Revision 4 Station:
CNS Unit:
2 Component/Weld ID: 2SGB-06A-18 Date:
9/28/2001 Weld Length (in.):
18.8" Surface Condition:
AS GROUND Lo:
9.2.3 Surface Temperature:
69 0 F Examiner: Gary J. Moss
.Level*
1 Scans:
Pyrometer S/N:
MCNDE 27010 A P,*
1 s Cal Due:
2/14/2002 Examiner: David Zimmerma T-evel:
111 45 El d6 70 21 59.0 dB3 Configuration:
Nozzle to Shell Procedure:
NDE-620 Rev:-
FC:
45T C:
dB 70T []
59.0 dB S2 Flow Sl 00-07 60 0 72.5/71.5dB NOZZLE to SHELL Calibration Sheet No:
60T Z 72.5/71.,dB Scan Surface: OD 0102033, 0102034, 0102035 Applies to NDE-680 only Other:
dB Skew Angle:
N/A Max Mp W
L Beam Exam ND # 4.
Max Max Max Li L2 W1 Mpl W2 Mp2 Dir.
Surf.
Scan Damps Ref
_Dr Suf 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac DO NOT WRITE HMA HMA HMA HMA HMA HMA Do NOT WRIT:
IN TIIS SP CE 50%dac 50%dac 50%dac 50%dac 50%dac 50%dac IN THIS SPACE 100%dac 100%dac 100%dac 100%dac 100%dac 100%dac NRI Remarks:
Limitations: (see NDE-UT-4) 03 90% or greater coverage obtained: yes no I Sheetj_
ofjý Reviewed By:
Level:
Date:
A rizedI eor:
Date:
Item No:
/
2 p
C02,021.001 7-f)
~
2L64A3/4~T'
DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2SGB-06A-18 Item No: C02.021.001 Remarks:
SURFACE BEAM DIRECTION DUE TO NOZZLE CONFIGURATION
[]
NO SCAN 11 LIMITED SCAN ED 1 El 2 El1 12 2 El cw 0 ccw FROM L N/A to L
_ _N/A INCHES FROM WO 2.6" to BEYOND ANGLE:
El 0 C] 45 El 60 El Other FROM 0
DEG to 360 DEG SURFACE BEAM DIRECTION El NO SCAN C
LIMITED SCAN El 1 r2 El 1 3 2 E3 cw 11 ccw FROM L to L INCHES FROM WO to ANGLE:
El 0
[] 45 El 60 El Other FROM DEG to DEG SURFACE BEAM DIRECTION El NO SCAN El LIMITED SCAN El 1 E3 2 El I El 2 El cw 13 ccw FROM L to L INCHES FROM WO to ANGLE:
El 0 El 45 El 60 El Other FROM DEG to DEG SURFACE BEAM DIRECTION El NO SCAN E1 LIMITED SCAN El 1 E 2 E1 2 El cw 11 ccw FROM L to L INCHES FROM WO to ANGLE:
El 0 El 45 El 60 El Other FROM DEG to Prepared By:
David K.Zimmerman i.,,/,,Level:
III Date: 9/28/1901 Sketch(s) attached El yes
[
no Sheet of Reviewed By:
/ae Authorized Inspector:
Date:)o
- 6) LI
DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0 Examination Volume/Area Defined l
Base Metal 91 Weld El Near Surface El Boltina 11 Inner Radius Area Calculation Volume Calculation 1.375 IN. X 1.75 IN.= 2.4 SQ.IN.
2.4 SQ.IN. X 70 IN.= 168 CUIN.
Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Scan # Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.in.)
Percent Coverage 1
2 3
4 60°L 60°L 601L 600L 2
1 Cw CCW 2.4 0
2.4 2.4 70 70 70 70 168 0
168 168 504 168 168 168 168 672 100.00 75.00
AL\\4I ILL nP.,
6 (bM&
AJO1 6-6zZ-I-c.
-r 7D, i IK4I/()
(1 04 (
DUKE POWER COMPANY Exam Start:
1008 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish:
1028 Revision 4 Station:
CNS Unit:
2 Component/Weld ID: 2BNSHX-3-N1 Date:
9/11/2001 Weld Length (in.):
40.03 Surface Condition:
AS GROUND La:
9.2.3 Surface Temperature:
87 F
Examiner: Jay A. Eaton
_.Level:
III Scans:
Pyrometer S/N:
MCNDE 27008 SCal Due:
2/402 Examiner: Gayle E. Houser evel: II1 45 C3 dB 70 0
64 dB Configuration:
Nozzle to Shell Procedure:
NDE-630 Rev:
2 FC:
45T 0 34 dB 70T [
dB S2 Flow S1 99-02 60 0 62 dB NOZZLE to SHELL Calibration Sheet No:
60T dB Scan Surface: OD 0102001, 0102002, 0102003 Applies to NDE-680 only Other:
dB Skew Angle:
N/A Max Mp W
L Beam Exam ND Max Max Max LI L2 W1 Mpl W2 Mp2 Dir.
Surf.
Scan Damps Ref 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac DO 10T WIZITE HMA HMA HMA HMA HMA HMA Do NOT WRIT:
IN T IS SP)%CE 50%dac 50%dac 50%dac 50%dac 50%dac 50%dac IN THIS SPACE 100%dac 100%dac 100%dac 100%dac 100%dac 100%dac 1
60°L 200 1.5"
.5"-
10.0" 360° NT.
IND.
2 1
AXIAL NO Remarks: 600 &700 L WERE SCANNED @ LESS THAN SCANNING DB(REF. + 14 DB) DUE TO SIGNAL TO NOISE RATIO Limitations: (see NDE-UT-4) Z 90% or greater coverage obtained: yes C no Sheet
/
of 9 Reviewed By:
Level:
Date:
Autorized Inspector:
Dae:
Item No:
~ /f'*o JL74>f?';A
~
C02.021.004 V
A &Z-ý7A//
&* 3 a.
DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2BNSHX-3-N1 Item No: C02.021.004 Remarks:
09 NO SCAN SURFACE BEAM DIRECTION WELD TAPER 03 LIMITED SCAN 0I 1 10 2 0
1 0 20 cwO ccw FROM L.
to L INCHES FROM WO CL - 0.9" to BEYOND ANGLE:
0] 0 03 45 10 60 E0 Other 700 FROM 0
DEG to 360 DEG 0
NO SCAN SURFACE BEAM DIRECTION WELD TAPER EL LIMITED SCAN 01 0 2 01 1 0 2 0] cwO ccw FROM L to L INCHES FROM WO CL + 0.9" to BEYOND ANGLE:
0 0 0 45 0 60 01 Other 700 FROM 0
DEG to 360 DEG 0
NO SCAN SURFACE BEAM DIRECTION WELD TAPER SURF. 1 0
LIMITED SCAN 0
1 03 2 0l 1 0]
2 0M cw []
ccw FROM L.
to L INCHES FROM WO CL to C + 0.6" ANGLE:
03 0 13 45 0 60 01 Other FROM 0
DEG to 360 DEG 0l NO SCAN 01 LIMITED SCAN SURFACE 0
1 02 to L BEAM DIRECTION 0
1 2 0 cw 12 ccw INCHES FROM WO -
CL - 0.1 to BEYOND FROM.
0 DEG to 360 WELD TAPER SURF. 2 Date: o*Itjl I Sketch(s) attached 0 yes ono Sheet0 ? ofq Authorized Inspector:,*
- Date: /_/* 7//C)
FROM L U
L 11 no Sheet,*
ofq I
t-.
DUUE POWER COMPANY UT PROFILE/PLOT SHEET CAMM1NA I 1UN SURFACE~ 1 4
3 WE!
I
-f -,
'.D NDE-UT-5 1
2 DAMINAT1N$1JRFACE RevisIon.1 VEXAMNAIONURA4 II li (llI1I1IIlii ii I 2
3 Component ID/Weld No.
u Profile taken 27-0 (
t2
)
90 180 Sheet..+/-ofl._
.5 Exminer:
JLevel: 1-r Date: 01 11 Rviewed B :
Level:
Date:9.f-c Au thoed Inspector.
Wtý JP J2 Date:-L
- z Fý k I e--, ý4 )e -
-:z, -
k ý A
- KeMarks:
I
DUKE POWER COMPANY Form NDE-UIT-9 ULTRASONIC BEAM ANGLE MEASUREMENT RECORD Revision 3
- 1. Take thickness measurements between.
wedge locations.
- 2. Place search unit on straight turn of pipe, and peak the signal.
t
- 3. Measure distance (d) between exit
\\
points.
tan o =
(d/2)
- 4. Calculate beam angle with formula t
as shown using measured wall thickness.
- 5. Use the measured beam angle to determine coverage and when plotting any indications.
Pipe Size:
12 IN.
For thin wall pipe use 2nd Vee path ta
(/)Pipe Schedule:
N/A tan 0 =
(d/2) 2t Nominal 45 deg: d=
1.4
- t=
0.75 measured angle=
43.03 deg Nominal 60 deg: d= _0
- t=
_ 0 measured angle=
0.00 deg Item No.
Nominal 70 deg: d=
0 t=
0_
measured angle=
0.00 de C02.021.004 Examiner Level Date Examiner Level Date Gayle E. House III 9/11/2001 Jay A. Eaton.
Il 9/11/2001 Reviewed By Level Date Aut ispectOr Date A
DUKE POWER COMPANY Form NDE-UT-8 ULTRASONIC INDICATION RESOLUTION SHEET Revision 1 Acceptance Standard:
IND. #1 - 600L IS A GEOMETRIC REFLECTOR DUE TO WELD ROOT CONFIGURATION.
Item No: C02.021.004 Acceptable Indications: IND. #1 Rejectable Indications:
N/A These indications have been cd!mpared with previous ultrasonic data El Yes
[] No previous data available Examiner:-I Level:
Date:
t'--1 Jay A. Eaton 111 9/11/2001
-I~
.L he o
Reviewer:
/*
c (fD"Level:
Date:
Ait~orized I nspoector:
Datq:
U
DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined J Base Metal 0
Weld El Near Surface D Boltinci El Inner Radius Area Calculation Volume Calculation (0.25 in x 1.1 in) + (0.15 in x 0.05 in /2 ) = 0.283 sq.
0.283 sq. in. x 40in. = 11.32 cubic in.
in.
Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Percent Coverage Scan # Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.in.)
1 2
3 4
60&70 60&70 45 45
$1 S2 Cw CCw Total
.253 0
.151
.151 40 40 40 40 Aggregate Coverage 10.12 0
6.04 6.04 22.2 11.32 11.32 11.32 11.32 45.28 49.03
DUKE POWER C1 UT PROFILE/PLOT
- ýXAMINAT10N SURFACE1p(L 3
Ill I I I 2
II~
II I'1 1 11 1
C 55 /1o?Lc NDE-UT-5 Revislon.I I
I Vwtt 4 Ii EXAMINATION SURFACE 2 5-.3 4
I 1 1 1 1 1 1111 11111111 I III 1111 III 2
2.5 35 L
C..omponent IU/ Weld No.
V l~xaminer-
ýReylewed By:
~ %
ýAuthorzed Inspector.
Item No:
C,-c-z. cZI, 00*DL Level: T-7-T Date: G Level:
iD at e: 9 -4c0"
__Da t6:
b 7/
U Profile taken 270 (a t:________
90 189 Sheetl~of-2 A.
11' i4~~
.5
- Kemarks:
- /
I -
11111 11
DUKE POWER COMPANY Exam Start:
1008 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish:
1028 Revision 4 Station:
CNS Unit:
2 Component/Weld ID: 2BNSHX-3-N2 Date:
9/11/2001 Weld Length (in.):
40.03 Surface Condition:
AS GROUND Lo:
9.2.3 Surface Temperature:
87 0
F Examiner: Jay A. Eaton
ýevel:
III Scans:
Pyrometer S/N:
MCNDE 27008 Exmiera oser Le: 1Cal Due:
2/14/2002 Configuration:
Nozzle to Shell Procedure:
NDE-630 Rev:
2 FC:
45T 10 34 dB 70T El dB S2 Flow S1 99-02 60 []
62 dB NOZZLE to SHELL Calibration Sheet No:
60T []
dB Scan Surface: OD 0102001, 0102002, 0102003 Applies to NDE-680 only Other:
dB Skew Angle:
N/A Max Mp W
L Beam Exam IND #
e Max Max Max Li L2 W1 Mpl W2 Mp2 Dir.
Surf.
Scan Damps Ref 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac DO 1OT WMITE HMA HMA HMA HMA HMA HMA Do NOT WRIT IN TI1S SP %CE 50%dac 50%dac 50%dac 50%dac 50%dac 50%dac IN THIS SPACl 100%dac 100%dac 100%dac 100%dac 100%dac 100%dac 1
60'L 251 1.7"
.5"k 26" 360" INT.
IND.
2 1
AXIAL NO Remarks: 600 & 700 L WERE SCANNED @ LESS THAN SCANNING DB( REF. + 14DB) DUE TO SIGNAL TO NOISE RATIO Limitations: (see NDE-UT-4) 0 90% or greater coverage obtained: yes no 0Sheet I
of Reviewed Bv:
4 Level:
Date:
AuhorizedInspector:
Date:
Item No:
277 0
&1 C02.021.005 UI 7-f,
DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2BNSHX-3-N2 Item No: C02.021.005 Remarks:
SURFACE BEAM DIRECTION WELD TAPER
~
NO SCAN 0
LIMITED SCAN 03 1 10 2 10 2 03 cwO ccw FROM L to L INCHES FROM WO CL - 0.9" to BEYOND ANGLE:
0 0 0 45 0 60 03 Other 700 FROM 0
DEG to 360 DEG SURFACE BEAM DIRECTION WELD TAPER 0]
NO SCAN 91 LIMITED SCAN 0
1 01 2 0]
1 i 2 E0 cw ccw FROM L to L INCHES FROM WO CL + 0.9" to BEYOND ANGLE:
01 0 01 45 91 60 0l Other 700 FROM 0
DEG to 360 DEG SURFACE BEAM DIRECTION WELD TAPER SURF. 1 0]
NO SCAN
[
LIMITED SCAN 0
1 03 2 E0 1 E0 2
(Z cw []
ccw FROM L - -
to L INCHES FROM WO - -CL to C + 0.6" ANGLE:
0l 0
[] 45 0l 60 0 Other FROM 0
DEG to 360 DEG 0
NO SCAN
[
LIMITED SCAN FROM L toL ANGLE:
0l 0 ZI 45 0l 6010 Other SURFACE
.E0 1 Z 2 BEAM DIRECTION 01 1 0]
2 0
cw 12 ccw INCHES FROM WO CL -0.1 to BEYOND FROM 0
DEG to 360 WELD TAPER SURF. 2 ISketch(s) attached 91 yes 0 no Sheet*
of Authorized Inspector:
,,4
,,m Date:
N)[
Date:/0/7A
/m J *"I /
I I
DUKE POWER COMPANY Form NDE-UT-8 ULTRASONIC INDICATION RESOLUTION SHEET Revision 1 Acceptance Standard:
IND. #1 - 600L IS A GEOMETRIC REFLECTOR DUE TO WELD ROOT CONFIGURATION.
Item No: C02.021.005 Acceptable Indications: IND. #1 Rejectable Indications:
N/A These indications have been cornm ared with previous ultrasonic data El Yes 0 No previous data available E
i:vD**--**
I Level:
Date:
Seet of Jay A. Eaton I/
III 9/11/2001 Reviewer:V Level:
Date:
AutJ~orjized Insrpector:
Dat,,:
/
/
DUKE POWER COMPANY ULTRASONIC BEAM ANGLE MEASUREMENT RECORD Form NDE-UT-9 Revision 3 tan 0 =
(d/2) t For thin wall pipe tan o =
(d/2) 2t
- 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.
- 5. Use the measured beam angle to determine coverage and when plotting any indications.
Pipe Size:
12 IN.
use 2nd Vee path Pipe Schedule:
N/A Nominal 45 deg: d=
Nominal 60 deg: d=
1.4 0
Nominal 70 deg: d=
0
- t=
0.75
- t=
0
- t=
0 measured angle=
43.03 deg measured angle=
0.00 deg measured angle=
0.00 deg Item No.
C02.021.005 Examiner Level Date Examiner Level Date Gayle E. Houso C,6.w-III 9/11/2001 Jay A. Eaton-III 9/11/2001 Reviewed By 2)/
Level Date A
\\rorzed Inspector Date 21-/i'
/,4 2
t I,
I
DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined I
Base Metal L9-Weld El Near Surface El Boltincl El Inner Radius Area Calculation Volume Calculation (0.25 in x 1.1 in) + ( 0.15 in x 0.05 in / 2) = 0.283 sq.
0.283 sq. in. x 40in. = 11.32 cubic in.
in.
Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Scan # Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.in.)
Percent Coverage 60&70 60&70 45 45 S1 S2 Cw CCw TOTAL
.253 0
40 40
.151 40
.151 40 AGGREGATE COVERAGE 10.12 0
6.04 6.04 22.2 11.32 11.32 11.32 11.32 45.28 49.03 1
2 3
4
'A-.
DUKE POWER COMPANY N DE-UT-S UT PROFILE/PLOT SHEc-ET Revision.1 EXYAMINATION SURFACE I lfb&ý 4
'I~11'i I IIIII 3
R I II WE!
I1 1111111b AIVo a 1.1 EXAMINAT1ON SURFACE 2 2
4
- 1 l i i i1111
. III I I I III HIMiI 2
z___
2 3 z 3
Component 10/ Weld No.
- Remarks:
U Z->?J'ýA>,--
3- ~dz 270 ltemNo:CA1O os Eaminer.
Level: -Wi-Date:
- ý I 0 R evlewed By-E LIel Date:
Authorized rinspector.(
',$)
Date: !
/
1
.5 I
I III
DUKE POWER COMPANY Exam Start:
0952 NDE-UT-3A ULTRASONIC EXAMINATION DATA SHEET FOR LAMINAR REFLECTORS Exam Finish:
0955 Revision 2 Station:
CNS Unit:
2 Component/Weld ID: 2NV20-5 Date:
9/12/2001 Nominal Material Thickness (in):
0.237 Weld Length (in.):
14.25" Surface Temperature:
81° Deg F Measured Material Thickness (in):
.245 Lo:
9.1.1.1 Pyrometer S/N:
MCNDE 27010 Surface Condition:
AS GROUND Calibration Sheet No:
Cal Due:
2/14/2002 Examiner: Marion T. Weav.-
7
),"e Level:
11 0102005 Configuration:
Pipe to VLV 2NV-204 Examiner: Gary J. Moss Level:
11 S2 Flow 51 Procedure:
NDE-640 Rev:
1 FC:
VALVE to PIPE Ampl Li W1 Mpl W2 Mp2 L2 W1 Mp1 W2 Mp2 ND Brem a rem a rem a rem 2 Brem Brem
>rem
_rem
_rem a rem
_ Brem Exam Damps NO.
4 BW BW BW BW BW BW BW BW BW BW BW
- Surf, ap LOB LOB LOB LOB LOB LOB LOB LOB LOB LOB LOB 0° NRI Remarks:
95-18 & 95-19 Limitations:
see NDE-UT-4 03 None: 171 Sheet Jof Reviewed By:
Level:
Date:
Atutorized Inspector:
Date: 1 Item No:
ReviwedBy:J I
,id, 9.17(z-C05.021,232 j
fI 7 Ak &A7#/6613
'7 1-7
DUKE POWER COMPANY NDE-UT-5 UT PROFILE/PLOT SHEET RevIsIon.1 EXAMINATION SURFACE 1 4
3 Sl~
~ 2~l]j l
EXAMINATION SURFACE 2 2 -
WELD 212 2
3 4
'111
~
I/
I..*"
V #'
"t~* /
1,5 2
2.5 3
Component ID/Weld No, 0
.2.A/V/
2U 0 -
- Remarks:
270 Item No: 6o&. o,2_.
.3_
Examiner.,/
,.C-t-,
Level: / I Date: 9-/2.e/
Reviewed By:
ra2U Level:,_Z-..Date: 9./7, Autho-rzed Ins'pectod m, 'L,*
Date: Th/fl o)
(
I
.5 i
1111 I
1
Catawba Unit #2 BOCli1 NO ANGLE BEAM DATA CALIBRATION SHEET #.
COMPONENT I.D.#
ITEM #
6V09 2. 00 (
(U9§ OAJ. 3A
/02
/
0c (.
-,Z-Al V. c, o-S
(*o.
546
DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2NV20-5 Item No: C05.021.232 Remarks:
SURFACE BEAM DIRECTION DUE TO VALVE CONFIGURATION NO SCAN O1 LIMITED SCAN 01 1 fQ 2 El 1 C]
2 cw 01 ccw FROM L __-N/A to L N/A INCHES FROM WO CL -
to BEYOND ANGLE:
03 0 0] 45 0 60 0l Other FROM 0
DEG to 360 DEG SURFACE BEAM DIRECTION 0]
NO SCAN 03 LIMITED SCAN 0l 1 0 2 0l 1 0l 2 0l cw El ccw FROM L to L INCHES FROM WO to ANGLE:
0 0 0 45 01 60 0 Other FROM DEG to DEG SURFACE BEAM DIRECTION 0]
NO SCAN 0l LIMITED SCAN 0
1 0l 2 0D 1 El 2
El cw 0 ccw FROM L to L INCHES FROM WO to ANGLE:
0] 0 0l 45 0l 60 0 Other FROM DEG to DEG SURFACE BEAM DIRECTION 0]
NO SCAN El LIMITED SCAN 0 1 0l 2 13 1 []2 0
l 2
cw 0 ccw FROM L to L INCHES FROM WO to ANGLE:
E0 0 0 45 0] 60 0l Other FROM DEG to Prepared By:
Marion T. Weav_
Level:
II Date: 9/12/2001 Sketch(s) attached 0 yes 0 no Sheet of, of AI Reviewed By:
7/?_/c-*
- .Date:
/
Authorized Inspector:
Date:
/
E 7
2 Aggregate Supplemental 2
SUPPLEMENTAL COVERAGE 55.47 X 25% ( 1 SCAN ) = 13.87% OF TOTAL WELD DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0 Examination Volume/Area Defined
[] Base Metal 10 Weld 1l Near Surface El Boltina 11 Inner Radius Area Calculation Volume Calculation 0.1 IN. X 0.9 IN = 0.09 SQ. IN.
0.09 SQ. IN. X 14.2 IN. = 1.28 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
2 3
4 Shear RL 4
45 45 60 60 Wave Wave 60RL
.09
.09 0
.04 Coverage Coverage
.05 14.2 14.2 14.2 14.2 14.2 1.28 1.28 0
0.568 3.128 0.71 1.28 1.28 1.28 1.28 5.12 1.28 61.09 55.47
DUKE POWER COMPANY NDE-U'T-5 U`T PROFILE/PLOT SHEET Revision I EXAMINATION SURFACE 1 WELD V(Lv"-
EXAMINAT1ION SURFACE 2 g) !e_.
WEL 4
3 2
1 2
3 4
1 AA)
WAVW I
~oieA 2.5 S,
Component ID/Weld No.
Remaks:
Profile taken 270 2"_
90 I t e m N o :,C,,
- 3 7
Examiner.
,1Level:
7 Date:
o Reviewed By:
,,Level:-ý I Date: 9Y/7-o/
180 SheetLof C