ML020280368
| ML020280368 | |
| Person / Time | |
|---|---|
| Site: | Mcguire |
| Issue date: | 01/10/2002 |
| From: | Barron H Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML020280368 (63) | |
Text
SDuke Duke Energy Corporation McGuire Nuclear Station Energy.
12700 Hagers Ferry Road Hunrersville, NC 28078-9340 H. B. Barron (704) 875-4800 OFFICE Vice President (704) 875-4809 FAX January 10, 2002 U.
S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555-0001
Subject:
McGuire Nuclear Station Unit 2 Docket No.
50-370 Relief Request 01-009
Reference:
Letter from Mr.
H.B. Barron of Duke Energy Corporation to Nuclear Regulatory Commission, "Relief Request 01-001",
dated April 11, 2001 Pursuant to 10CFR50.55a(g) (5) (iii),
Duke Energy Corporation (Duke) requests relief from certain ASME Section XI requirements as described in the attached Relief Request 01 009.
This relief request addresses cases of limited examination coverage from inspections performed during end of fuel cycle (EOC) 13 for Unit 2.
This request is applicable to the Second 10-year Interval Inservice Inspection Program Plan.
The 1989 Edition of the ASME Section XI Code contains the applicable requirements.
This transmittal supercedes a previous submittal, addressing the same subject matter, from Duke Energy Corporation to the NRC, dated April 11, 2001.
Additional information is included in the attached relief request to address concerns raised by the NRC staff during a telephone conference call on October 18, 2001.
Duke requests that Relief Request 01 001 be withdrawn from consideration.
Questions on this matter should be directed to Norman T.
- Simms, McGuire Licensing and Compliance, at (704) 875-4685.
Sincerely, H.
B. Barron Attachment
U.S. Nuclear Regulatory Commission January 10, 2002 Page 2 cc:
Mr.
L.
A Reyes Regional Administrator, Region II U.
S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Mr.
R.E. Martin, Project Manager (addressee only)
Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission One White Flint North, Mail Stop O-8G9 11555 Rockville Pike Rockville, MD 20852-2738 S.
M. Shaeffer Senior NRC Resident Inspector McGuire Nuclear Station
U.S. Nuclear Regulatory Commission January 10, 2002 Page 3 bxc w/o att:
bxc w/
att:
N.T. Simms R.
Branch G.J. Underwood D.E. Caldwell R.K. Rhyne G.D. Scarboro R.D. Klein (MG01MM)
Master File # 1.3.2.13 RCG Files NRIA File/ELL
ATTACHMENT RELIEF REQUEST 01-009
Serial No.01-009 Page 1 of 24 Duke Energy Corporation McGuire Nuclear Station Unit 2 SECOND 10-YEAR INTERVAL REQUEST FOR RELIEF NO.01-009 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.
Included in the request are seven welds: four Examination Category B-J welds, one Examination Category C-B weld and two Examination Category C-F-I welds.
The McGuire Unit-2 Inservice Inspection Plan was written to the requirements of the 1989 Edition of ASME Section XI, no addenda.
The items in this Request for Relief were performed during EOC-13, the last outage in the second period of the second ten-year interval.
Code Case N-460 applies to the examinations performed during this outage.
I.
System / Components(s) for Which Relief is Requested:
Examination Category B-J:
Piping Circumferential Weld for the Reactor Coolant system.
ID Numbers Item Numbers End of Cycle 2NC2FW53-25 B09.011.032 13 II.
Code Requirement:
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition Table IWB-2500, lists the following requirements for the Examination Category as shown below:
Examination Category B-J: Figure IWB-2500-8 (c),
Examination Volume C-D-E-F.
Serial No.01-009 Page 2 of 24 III. Code Requirement from Which Relief Is Requested:
Examination Category B-J:
Relief is requested from the requirement to examine 100% of volume C-D-E-F.
IV.
Basis for Relief:
Examination Category B-J:
During the ultrasonic examination of this weld, greater than 90% of the required examination volume as allowed by Code Case N-460 could not be achieved.
As shown in Attachment 1, (Pages 1-4) the examination coverage was limited to 60.30% of the required examination volume.
This is an austenitic stainless steel elbow-to-flange 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.
The weld design prevented any axial scan from the flange 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 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.
Serial No.01-009 Page 3 of 24 V.
Alternate ExaminationS or Testing:
No additional examinations are planned during the current interval for this weld.
Because of the flange 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 examinations of this weld.
VI.
Justification for the Granting of Relief:
Examination Category B-J:
Although the examination volume as defined in ASME Section XI 1989 Edition with no addenda, Figure IWB 2500-8 (c) could not be covered, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity. This weld was examined using procedures, personnel and equipment qualified through the Performance Demonstration Initiative (PDI).
In addition, this weld was examined during installation using volumetric and surface NDE methods.
This weld is located within the reactor coolant loop.
This weld is not exposed to significant neutron fluence and not prone to negative material property changes (i.e.
embrittlement) associated with neutron bombardment.
This weld was rigorously inspected by radiography and dye penetrant examination during construction and verified to be free from unacceptable fabrication defects.
If a leak were to occur at the weld in question, the reactor coolant leakage calculation which is normally performed daily (and required by Technical Specifications to be performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) would provide an early indication of leakage.
The unidentified leakage specification in Technical Specification 3.4.13.1 is 1 gpm.
Several other indicators such as containment radiation monitors EMF-38, 39, and 40, the containment floor and equipment sump levels, containment humidity instruments and the ventilation unit condensate drain tank level would provide early indication of weld leakage for prompt Operations and Engineering evaluation.
Serial No.01-009 Page 4 of 24 VII. Implementation Schedule:
Duke Energy Corporation will continue to use ultrasonic examination procedures to obtain maximum coverage to the extent practical of the item number referenced in Section I of this Request for Relief.
No additional ultrasonic examination is planned during the current interval for this weld.
VIII.
References:
. Information for Examination Category B-J affected welds: Pages 1-4 cover this weld.
B09.011.032
Serial No.01-009 Page 5 of 24 I.
System / Components(s) for Which Relief is Requested:
Examination Category B-J:
Piping Circumferential Weld for the Reactor Coolant system.
ID Numbers Item Numbers End of Cycle 2NC2FW53-37 B09.011.039 13 II.
Code Requirement:
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition Table IWB-2500, lists the following requirements for the Examination Category as shown below:
Examination Category B-J: Figure IWB-2500-8 (c),
Examination Volume C-D-E-F.
III.
Code Requirement from Which Relief Is Requested:
Examination Category B-J:
Relief is requested from the requirement to examine 100% of volume C-D-E-F.
IV.
Basis for Relief:
Examination Category B-J:
During the ultrasonic examination of this weld, greater than 90% of the required examination volume as allowed by Code Case N-460 could not be achieved.
As shown in Attachment 1, (Pages 5-8) the examination coverage was limited to 60.30% of the required examination volume.
This is an austenitic stainless steel elbow-to-flange 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.
The weld design prevented any axial scan from the flange side. In order to achieve more coverage the weld would have to be re-designed to allow scanning from both sides.
Serial No.01-009 Page 6 of 24 Duke Energy Corporation does not claim credit for coverage of the far side of austenitic welds. The characteristics of austenitic weld metal attenuate and distort the sound beam when shear waves pass through the weld.
Refracted longitudinal waves provide better penetration.
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 this weld.
Because of the flange 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 examinations of this weld.
VI.
Justification for the Granting of Relief:
Examination Category B-J:
Although the examination volume as defined in ASME Section XI 1989 Edition with no addenda, Figure IWB 2500-8 (c) could not be covered, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity. This weld was examined using procedures, personnel and equipment qualified through the Performance Demonstration Initiative (PDI).
In addition, this weld was examined during installation using volumetric and surface NDE methods.
This weld is located within the reactor coolant loop.
This weld is not exposed to significant neutron fluence and is not prone to negative material property changes (i.e. embrittlement) associated with neutron bombardment.
This weld was rigorously inspected by radiography and dye penetrant examinations during
Serial No.01-009 Page 7 of 24 construction and verified to be free from unacceptable fabrication defects.
If a leak were to occur at the weld in question, the reactor coolant leakage calculation which is normally performed daily (and required by Technical Specifications to be performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) would provide an early indication of leakage.
The unidentified leakage specification in Technical Specification 3.4.13.1 is 1 gpm.
Several other indicators such as containment radiation monitors EMF-38, 39, and 40, the containment floor and equipment sump levels, containment humidity instruments and the ventilation unit condensate drain tank level would provide early indication of weld leakage for prompt Operations and Engineering evaluation.
VII. Implementation Schedule:
Duke Energy Corporation will continue to use ultrasonic examination procedures to obtain maximum coverage to the extent practical of the item number referenced in Section I of this Request for Relief.
No additional ultrasonic examination is planned during the current interval for this weld.
VIII.
References:
Information for Examination Category B-J affected welds: Pages 5-8 cover this weld.
B09.011.039
Serial No.01-009 Page 8 of 24 I.
System / Components(s) for Which Relief is Requested:
Examination Category B-J:
Piping Circumferential Weld for the Safety Injection system.
ID Numbers Item Numbers End of Cycle 2NI2F471 B09.011.162 13 II.
Code Requirement:
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition Table IWB-2500, lists the following requirements for each Examination Category as shown below:
Examination Category B-J: Figure IWB-2500-8 (c),
Examination Volume C-D-E-F.
III.
Code Requirement from Which Relief Is Requested:
Examination Category B-J:
Relief is requested from the requirement to examine 100% of volume C-D-E-F.
IV.
Basis for Relief:
Examination Category B-J:
During the ultrasonic examination of this weld, greater than 90% of the required examination volume as allowed by Code Case N-460 could not be achieved.
As shown in Attachment 1, (Pages 9-12) the examination coverage was limited to 59.70% of the required examination volume.
This is an austenitic stainless steel elbow-to-valve weld where access is limited to the elbow 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.
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.
Serial No.01-009 Page 9 of 24 Duke Energy Corporation does not claim credit for coverage of the far side of austenitic welds. The characteristics of austenitic weld metal attenuate and distort the sound beam when shear waves pass through the weld.
Refracted longitudinal waves provide better penetration.
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 this weld.
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 examinations of this weld.
VI.
Justification for the Granting of Relief:
Examination Category B-J:
Although the examination volume as defined in ASME Section XI 1989 Edition with no addenda, Figure IWB 2500-8 (c) could not be covered, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity.
This weld was examined using procedures, personnel and equipment qualified through the Performance Demonstration Initiative (PDI).
In addition, this weld was examined during installation using volumetric and surface NDE methods.
This weld is located within the Emergency Core Cooling System Cold Leg Injection lines.
This weld is not exposed to significant neutron fluence and is not prone to embrittlement associated with neutron
Serial No.01-009 Page 10 of 24 bombardment. This weld was rigorously inspected by radiography and dye penetrant examinations during construction and verified to be free from unacceptable fabrication defects.
If a leak were to occur at the weld in question, the reactor coolant leakage calculation which is normally performed daily (and required by Technical Specifications to be performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) would provide an early indication of leakage.
The unidentified leakage specification in Technical Specification 3.4.13.1 is 1 gpm.
Several other indicators such as containment radiation monitors EMF-38, 39, and 40, the containment floor and equipment sump levels, containment humidity instruments and the ventilation unit condensate drain tank level would provide early indication of weld leakage for prompt Operations and Engineering evaluation.
Check valves located downstream could however provide isolation from the reactor coolant system. In that case leakage from these welds would be indicated by outleakage from the associated Cold Leg Accumulator tanks.
Level in these tanks is continuously monitored and alarmed in the control room and is maintained within limits established in Technical Specification 3.5.1.2.
The fill frequency for these tanks is also trended by the Safety Injection System Engineer who would notice an increase in makeup to the tank should leakage occur from this weld.
Also containment floor and equipment sump level would provide early indication of weld leakage for prompt Operations and Engineering evaluation.
VII. Implementation Schedule:
Duke Energy Corporation will continue to use ultrasonic examination procedures to obtain maximum coverage to the extent practical of the item number referenced in Section I of this Request for Relief.
No additional ultrasonic examination is planned during the current interval for this weld.
VIII.
References:
Attachment
- 1.
Information for Examination Category B-J affected welds: Pages 9-12 cover this weld.
B09.011.162
Serial No.01-009 Page 11 of 24 I.
System / Components(s) for Which Relief is Requested:
Examination Category B-J:
Piping Circumferential Weld for the Safety Injection system.
ID Numbers Item Numbers End of Cycle 2NI2F494 B09.011.165 13 II.
Code Requirement:
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition Table IWB-2500, lists the following requirements for the Examination Category as shown below:
Examination Category B-J: Figure IWB-2500-8 (c),
Examination Volume C-D-E-F.
III.
Code Requirement from Which Relief Is Requested:
Examination Category B-J:
Relief is requested from the requirement to examine 100% of volume C-D-E-F.
IV.
Basis for Relief:
Examination Category B-J:
During the ultrasonic examination of this weld, greater than 90% of the required examination volume as allowed by Code Case N-460 could not be achieved.
As shown in Attachment 1, Pages 13-16, the examination coverage was limited to 59.61% of the required examination volume.
This is an austenitic stainless steel elbow-to-valve weld where access is limited to the elbow side of the weld bnly. 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.
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.
Serial No.01-009 Page 12 of 24 Duke Energy Corporation does not claim credit for coverage of the far side of austenitic welds. The characteristics of austenitic weld metal attenuate and distort the sound beam when shear waves pass through the weld.
Refracted longitudinal waves provide better penetration.
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 this weld.
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 examinations of this weld.
VI.
Justification for the Granting of Relief:
Examination Category B-J:
Although the examination volume as defined in ASME Section XI 1989 Edition with no addenda, Figure IWB 2500-8 (c) could not be covered, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity. This weld was examined using procedures, personnel and equipment qualified through the Performance Demonstration Initiative (PDI).
In addition, this weld was examined during installation using volumetric and surface NDE methods.
The weld is located within the Emergency Core Cooling System Cold Leg Injection lines.
This weld is not exposed to significant neutron fluence and is not
Serial No.01-009 Page 13 of 24 prone to embrittlement associated with neutron bombardment. This weld was rigorously inspected by radiography and dye penetrant examinations during construction and verified to be free from unacceptable fabrication defects. If a leak were to occur at the weld in question, the reactor coolant leakage calculation which is normally performed daily (and required by Technical Specifications to be performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) would provide an early indication of leakage.
The unidentified leakage specification in Technical Specification 3.4.13.1 is 1 gpm.
Several other indicators such as containment radiation monitors EMF-38, 39, and 40, the containment floor and equipment sump levels, containment humidity instruments and the ventilation unit condensate drain tank level would provide early indication of weld leakage for prompt Operations and Engineering evaluation.
Check valves located downstream could however provide isolation from the reactor coolant system. In that case leakage from these welds would be indicated by outleakage from the associated Cold Leg Accumulator tanks.
Level in these tanks is continuously monitored and alarmed in the control room and is maintained within limits established in Technical Specification 3.5.1.2.
The fill frequency for these tanks is also trended by the Safety Injection System Engineer who would notice an increase in makeup to the tank should leakage occur from this weld.
Also containment floor and equipment sump level would provide early indication of weld leakage for prompt Operations and Engineering evaluation.
VII. Implementation Schedule:
Duke Energy Corporation will continue to use ultrasonic examination procedures to obtain maximum coverage to the extent practical of the item number referenced in Section I of this Request for Relief.
No additional ultrasonic examination is planned during the current interval for this weld.
Serial No.01-009 Page 14 of 24 VIII.
References:
Information for Examination Category B-J affected welds: Pages 13-16 cover this weld.
B09.011.165
Serial No.01-009 Page 15 of 24 I.
System / Components(s) for Which Relief is Requested:
Examination Category C-B:
Nozzle-to-Shell (or Head) Weld for Steam Generator 2C Auxilliary Feedwater System (CA).
ID Numbers Item Numbers End of Cycle 2SGC-W259 C02.021.007 13 II.
Code Requirement:
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition Table IWC-2500, lists the following requirements for each Examination Category as shown below:
Examination Category C-B: Figure IWC-2500-4 (a),
Examination Volume C-D-E-F.
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:
Examination Category C-B:
Relief is requested from the requirement to examine 100% of volume C-D-E-F.
IV.
Basis for Relief:
Examination Category C-B:
During the ultrasonic examination of this weld, greater than 90% of the required examination volume as allowed by Code Case N-460 could not be obtained.
As shown in Attachment 2, the examination coverage was limited to 74.40% of the required examination volume.
This is a ferritic nozzle to shell weld where access is limited to the vessel shell side only.
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.
The weld design prevented any axial scan from the nozzle side.
In order to
Serial No.01-009 Page 16 of 24 achieve more coverage the weld would have to be re designed to allow scanning from both sides.
V.
Alternate Examinations or Testing:
No additional examinations are planned during the current interval for this weld.
Radiography is not an acceptable alternative because of access restrictions for source and film placement.
Duke Energy Corporation will use the most effective ultrasonic techniques available to obtain maximum coverage for future examinations of this weld.
VI.
Justification for the Granting of Relief:
Examination Category C-B:
Although the examination volume as defined in ASME Section XI 1989 Edition with no addenda, Figure IWC 2500-4 (a) could not be covered to the extent required, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity. This weld was examined using procedures, personnel and equipment qualified for the ultrasonic examination of ferritic pressure vessel welds through the Performance Demonstration Initiative (PDI).
The qualifications were conducted on samples with access to both sides of the weld.
Therefore, Duke Energy Corporation does not claim credit for the full volume when a single sided examination is performed.
If a leak were to occur at the weld in question [Steam Generator (CA) Nozzle],
there are methods by which the leak could be identified for prompt Engineering evaluation.
A leak at a CA nozzle would result in the following:
a) Increased containment humidity.
This parameter is indicated in the control room and is monitored periodically by Operations and also the Containment Ventilation System Engineer.
b) Increased S/G enclosure temperature.
This parameter is continuously monitored by the Operations via an OAC alarm, and is periodically monitored by the System Engineer.
Serial No.01-009 Page 17 of 24 c) 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 Engineer and Reactor Coolant System Engineer.
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 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.
McGuire has specific Safety Analyses for accidents where minor and major main feedwater system pipe breaks are postulated.
These Safety Analyses demonstrate compliance with requirements of 10CFRI00.
Replacement or re-design of any of these Class 1 or Class 2 nozzles is not a viable alternative.
Duke Energy believes the amount of coverage obtained for these examinations provides reasonable assurance of the continued structural integrity of the subject welds.
Also, the CA nozzles are equipped with thermal sleeves to limit thermal shock due to auxiliary feedwater injections.
McGuire operates the CA nozzles consistent with the stress and fatigue qualifications provided by the Manufacturer (BWI).
VII.
Implementation Schedule:
Duke Energy Corporation will continue to use ultrasonic examination procedures to obtain maximum coverage to the extent practical of the item number referenced in Section I of this Request for Relief.
Serial No.01-009 Page 18 of 24 No additional ultrasonic examinations are planned during the current interval for this weld.
VIII.
References:
Information for Examination Category C-B affected welds: Pages 1-9 cover this weld.
C02.021.007
Serial No.01-009 Page 19 of 24
- i.
System / Components(s) for Which Relief is Requested:
Examination Category C-F-i:
Piping Circumferential Weld for Safety Injection System.
ID Numbers Item Numbers End Of Cycle 2NI2F493 C05.011.129 13 II.
Code Requirement:
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition Table IWC-2500, lists the following requirements for the Examination Category as shown below:
Examination Category C-F-I: ASME Section XI, Figure IWC-2500-7 (a),
Examination Volume C-D-E-F.
III.
Code Requirement from Which Relief Is Requested:
Examination Category C-F-i:
Relief is requested from the requirement to examine 100% of Volume C-D-E-F.
IV.
Basis for Relief:
Examination Category C-F-i:
During the ultrasonic examination of this weld, greater than 90% of the required examination volume as allowed by Code Case N-460 could not be obtained.
As shown in Attachment 3, Pages 1-4 the examination coverage was limited to 59.86% of the required examination volume.
This is a stainless steel pipe to-valve weld where access is limited to the pipe side only.
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. 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.
Serial No.01-009 Page 20 of 24 Duke Energy Corporation does not claim credit for coverage of the far side of austenitic welds.
The characteristics of austenitic weld metal attenuate and distort the sound beam when shear waves pass through the weld.
Refracted longitudinal waves provide better penetration.
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 this weld.
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 examinations of this weld.
VI.
Justification for the Granting of Relief:
Examination Category C-F-I:
Although the examination volume as defined in ASME Section XI 1989 Edition with no addenda, Figure IWB 2500-7 (a) could not be covered, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity.
This weld was examined using procedures, personnel and equipment qualified through the Performance Demonstration Initiative (PDI).
In addition, this weld was examined during installation using volumetric and surface NDE methods.
This weld is located on the "D" Cold Leg ECCS line.
This weld is not exposed to significant neutron fluence and is not prone to embrittlement associated with neutron bombardment.
This weld was rigorously inspected by radiography and dye penetrant
Serial No.01-009 Page 21 of 24 examinations during construction and verified to be free from unacceptable fabrication defects.
Because there are two check valves between this weld and the reactor coolant loop, it is not likely that leakage through this weld would be exhibited as described previously for the Category B-J piping.
Likewise, a single check valve may also prevent outleakage from the "D" Cold Leg Accumulator (as described previously for Items B09.011.162 and B09.011.165 welds) from indicating weld leakage.
Leakage from this weld would likely be indicated by the containment floor and equipment sump level which is alarmed in the control room.
The inputs to this sump are also trended by the WL Liquid Radwaste system engineer and an upward trend or significant influent increase would prompt Operations and Engineering evaluation.
VII.
Implementation Schedule:
Duke Energy Corporation will continue to use ultrasonic examination procedures to obtain maximum coverage to the extent practical of the item number referenced in Section I of this Request for Relief.
No additional ultrasonic examination is planned during the current interval for this weld.
VIII.
References:
Information for Examination Category C-F-I affected welds: Pages 1-4 cover this weld.
C05.011.129
Serial No.01-009 Page 22 of 24 I.
System / Components(s) for Which Relief is Requested:
Examination Category C-F-l:
Piping Circumferential Weld for Chemical and Volume Control System.
ID Numbers Item Numbers End Of Cycle 2RCPA-TE C05.021.081 13 II.
Code Requirement:
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition Table IWC-2500, lists the following requirements for the Examination Category as shown below:
Examination Category C-F-I: ASME Section XI, Figure IWC-2500-7 (a),
Examination Volume C-D-E-F.
III.
Code Requirement from Which Relief Is Requested:
Examination Category C-F-i:
Relief is requested from the requirement to examine 100% of Volume C-D-E-F.
IV.
Basis for Relief:
Examination Category C-F-l:
During the ultrasonic examination of this weld, greater than 90% of the required examination volume could not be obtained.
As shown in Attachment 3 (Pages 5-10),
the examination coverage was limited to 58.17% of the required examination volume.
This is a
stainless steel flange-to-tee weld where access is limited to the flange side only.
The percentage of coverage reported represents the aggregate coverage obtained from one scan perpendicular to the weld axis and two scans, 180' apart parallel to the weld.
The weld design prevented any axial scan from the tee side.
In order to achieve more coverage the weld would have to be re-designed to allow scanning from both sides.
Serial No.01-009 Page 23 of 24 Duke Energy Corporation does not claim credit for coverage of the far side of austenitic welds. The characteristics of austenitic weld metal attenuate and distort the sound beam when shear waves pass through the weld.
Refracted longitudinal waves provide better penetration.
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 this weld.
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 examinations of this weld.
VI.
Justification for the Granting of Relief:
Examination Category C-F-I:
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 this examination provides an acceptable level of quality and integrity. This weld was examined using procedures, personnel and equipment qualified through the Performance Demonstration Initiative (PDI).
In addition, this weld was examined during installation using volumetric and surface NDE methods.
This weld is located on a portion of the Chemical and Volume Control system which is not credited nor is it required for accident mitigation.
A leak from this weld would not be considered an accident initiator.
Serial No.01-009 Page 24 of 24 This weld is located on the Discharge Accumulator for the Reciprocating Charging Pump.
Although this pump is not normally in operation, it is operated on a quarterly frequency at which time an operator is dispatched to observe the pump and would likely notice any leakage from the weld.
Since the pressure during the quarterly pump run is ten times more than the residual heat removal discharge pressure (accident condition),
a leak in the weld is more likely to occur during pump operation.
At other times, leakage from this weld would be noticed during operator rounds which are conducted in the pump room once each shift.
Unidentified reactor coolant leakage methods would also readily detect leakage from this piping.
A leak from this weld could easily be isolated leaving the Emergency Core Cooling System 100% functional.
VII.
Implementation Schedule:
Duke Energy Corporation will continue to use ultrasonic examination procedures to obtain maximum coverage to the extent practical of the item number referenced in Section I of this Request for Relief.
No additional ultrasonic examination is planned during the current interval for this weld.
VIII.
References:
Information for Examination Category C-F-I affected welds: Pages 5-10 cover this weld.
C05.021.081 The following individuals were involved in the development of this request for relief.
Edward Hyland, Bob Kirk, Bryan Meyer, Grant Cutri(McGuire Primary Systems Engineering) and Hoang V. Dinh (McGuire Civil Engineering) provided input to the engineering justification (Section VI) for granting relief. Jim McArdle (NDE Level III) provided Sections II, III, IV and V.
Gary Underwood (McGuire ISI Plan Manager) compiled and completed the request.
Sponsored Byy::
A Ný'
Date _-_________
Approved By:
Date e.
McGuire Unit #2 EOC13 Item #
All. 0//. o; Weld #
A
- A*Aczc).2 No Data Recorded. Reference Calibration Sheet #'s 6 00 Z 0 f6 REQUEST FOR RELIEF 01-001 ATFTACHMENT I PAGEs5 -
4
DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2NC2FW53-25 Item No: B09.011.032 Remarks:
SURFACE BEAM DIRECTION DUE TO FLANGE CONFIGURATION 0]
NO SCAN 03 LIMITED SCAN 12 1 0 2 0
1 0 2
cw El ccw FROM L N/A to L N/A INCHES FROM WO
.6" -
to
_ BEYOND ANGLE:
0 0]
45 12 60 03 Other FROM 0
DEG to 360 DEG SURFACE BEAM DIRECTION O' NO SCAN 11 LIMITED SCAN C 1 0l 2 Cl 1 0 2 0 cw E]
ccw FROM L to L INCHES FROM WO to ANGLE:
C0 0 45 0] 60 C3 Other FROM DEG to DEG SURFACE BEAM DIRECTION C]
NO SCAN CLIMITED SCAN 0 1 01 2 Cl 1 0 2 C cw 0 ccw FROM L to L INCHES FROM WO to ANGLE:
03 0 0] 45 E0 60 C] Other FROM DEG to DEG SURFACE BEAM DIRECTION 0]
NO SCAN EC LIMITED SCAN 0l 1 03 2 Ol 1 0 2 0 cw El ccw FROM L to L INCHES FROM WO to ANGLE:
0 0. 0 45 E0 60 E0 Other FROM DEG to Prepared By:
Level:
Date:
Sketch(s) attached 0 yes
" no Sheet.
of Reviewed By:
Date:
Authorized Inspector:
Date: q2,6
.312
.312
.127 0
AGGREGATE
.185 21 21 21 0
COVERAGE 21 6.6 6.6 2.7 0
3.9 6.6 6.6 66 6.6 6.6 100.00 100.00 40.91 0.00 60.30 0.00 59.09 59.1% OF 25% (SCAN 4) = 14.8%
Item No:
B09.011.032 Prepared By:
Level:
Date: 9-Zg# -,V Reviewed By:
Level: 7 Date: q-.9.5--0 C3 fi DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined 0 Base Metal 0
Weld 11 Near Surface
[] Bolting 0 Inner Radius Area Calculation Volume Calculation
.24 X 1.3=.312 SQ. IN.
.312 X 21.0 = 6.6 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 L-WAVE 4
45 45 60 60 60L
I DUKE POWER COMPANY UT PROFILE/PLOT SHEET EXAMINATION SURFACE 1 FLAA1,$
4 3
III I III' WELD 2
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I I
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-,&-37 No Data Recorded. Reference Calibration Sheet #'s 000 o2.L8 REQUEST FOR RELIEF 01--00 ATTACHMENT 1 PAGE__S
DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2NC2FW53-37 Item No: B09.011.039 Remarks:
0 NO SCAN SURFACE BEAM DIRECTION DUE TO FLANGE CONFIGURATION C]
LIMITED SCAN 12 1
Cl 2 1
1 C) 20 cw 0 ccw FROM L N/A to L N/A INCHES FROM WO
.6" to BEYOND ANGLE:
Cl 0 C3 45 0 60 C Other FROM.
-0 DEG to 360 DEG SURFACE BEAM DIRECTION oNO SCAN CLIMITED SCAN E 1 C3 2 C1 10 2 C cw 13 ccw FROM L to L INCHES FROM WO to ANGLE:
C3 0 Cl 45 Cl 60 Cl Other FROM DEG to DEG SURFACE BEAM DIRECTION C
NO SCAN C]
LIMITED SCAN C 1 C1 2 C 1 0 2 C cw 0 ccw FROM L to L INCHES FROM WO to ANGLE:
C1 0 C3 45 C1 60 C3 Other FROM DEG to DEG SURFACE BEAM DIRECTION Cl NO SCAN C
LIMITED SCAN C 1 C3 2 C] 1 El 2 0 cw 13 ccw FROM L to L INCHES FROM WO to ANGLE:
0 0 C 45 C] 60 C] Other FROM DEG to Prepared By:
Level:
z Date: -- 20 g o Sketch(s) attached 0 yes C no Sheet,Z-of Reviewed By:
Date:
-Authorized Inspector:
Date:
DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined 0 Base Metal 10 Weld 0 Near Surface 11 Bolting 0 Inner Radius Area Calculation Volume Calculation
.24 X 1.3 =.312 SQ. IN.
.312 X 21.0 = 6.6 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 45 45 60 60 L-WAVE 60L Cw CCw S2 S1 SHEAR WAVE S1
.312
.312
.127 21 21 21 0
0 AGGREGATE COVERAGE
.185 21 59.1% OF 25% (SCAN 4) = 14.8%
h-6.6 6.6 2.7 0
3.9 6.6 6.6 6.6 6.6 6.6 100.00 100.00 40.91 0.00 60.30 59.09
DUKE POWER COMPANY UT PROFILE/PLOT SHEET EXAMINATION SURFACE 1 FZ,,vc-4 3
2 2.5 3
2 III Component IU/welo NO.
SCAJ
1 II 1111.1 WELD NDE-UT-5 Revision 1 fa/-/3dj.. EXAMINATION SURFACE 2 1
2 3
11111111 liii liii liii*
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~~~Item No:
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'--Cc-z 180 Sheet.-of_
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V \\10 m
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- Reviewed By: *A*
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-2_
r No Data Recorded. Reference Calibration Sheet #'s i9)(0 :OZ O9 6000 cQ&?
REQUEST FOR RELIEF 01-00O ATTACHMENT 1 PAGE 2 -
)2.
DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2NI2F471 Item No: B09.011.162 Remarks:
0 NO SCAN SURFACE BEAM DIRECTION DUE TO VALVE CONFIGURATION O3 LIMITED SCAN 01 1 0 2 0
1 0 2 0 cw O ccw FROM L N/A_.
to L N/A INCHES FROM WO
.5" to BEYOND ANGLE: 00 0 11 45 0 60 01 Other FROM 0
DEG to 360 DEG "0 NO SCAN SURFACE BEAM DIRECTION "0 LIMITED SCAN 0 1 03 2
E0 10 20 cwO ccw FROM L.
to L INCHES FROM WO to ANGLE:
03 0 0 45 03 60 E0 Other FROM DEG to DEG 03 NO SCAN SURFACE BEAM DIRECTION 11 LIMITED SCAN 1 1 03 2
[
1 0 2 C]
cw El ccw FROM L..
to L INCHES FROM WO to ANGLE:
0l 0 03 45 01 60 03 Other FROM DEG to DEG 03 NO SCAN 03 LIMITED SCAN SURFACE 010 2
to L ANGLE:
0 0 03 45 0 60 0l Other BEAM DIRECTION 01 1 0 2 0 cw 0 ccw INCHES FROM WO FROM Prepared By:
to DEG to I ____________________________________________________
Date. q-lý-04 ISketch(s) attached 0 yes i
Shl et.
of, Reviewed By:
I Authorized Inspector:
Date :J
'4*'
I A..JAA -A
¶4/
.A.'
-It V
FROM L DEG to Sheet _,ý'
of t
Date:(-,_/_,
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1 60S 2
60S 3
45 4
45 SHEAR I
60L 2
.111 21 0
21
.286 21
.286 21 AGGREGATE COVERAGE
.175 21 2.331 0
6.01 6.01 14.351 3.675 6.01 6.01 6.01 6.01 24.04 6.01 38.79 0.00 100.00 100.00 59.70 61.15 61.15% OF 25% (SCAN 1) =
LONG WAVE COVERAGE = 15.29% OF TOTAL WELD.
Item No:
B09.011.162 Prepared By:
Level: :ZZT Date:
Reviewed By:
Level:
Date:
DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined 0I Base Metal 0
Weld 0 Near Surface 11 Bolting 0 Inner Radius Area Calculation Volume Calculation
.26" X 1.1" =.286 SQ. IN.
.286 SQ. IN. X 21" = 6.006 = 6.01 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
N DUKE POWER COMPANY NDE-UT-5 UT PROFILE/PLOT SHEET Revision 1
".AAMINA I IUN SURFACE 1 4
liii 'IliI 3
I'll 2
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liii WELD I1 I.11 VIpLv& EXAMINATION SURFACE 2 A/
1 A/Z, Ill IIII 2
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Component ID/Weld No.
U Remarks:
270 Iivtem No:: *(..
Da Examiner:
tý Iz
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IDate: 9-Authorized Inspectqoj Date: 0 N
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IIII III I
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0/ /l!
Weld #
.2 ý? /2F No Data Recorded. Reference Calibration Sheet #'s ooo3
.o
.2,7 I o "
REQUEST FOR RELIEF 01-00 ATTACHIMENT 1 PAGES*.A
1 60 2
60 3
45 4
45 SHEAR 1
60L 2
.13 0
.338
.338 AGGREGATE
.208 21 21 21 21 COVERAGE 21 2.73 0
7.1 7.1 16.93 4.368 LONG WAVE 61.5% OF 25% (SCAN 1) =
15.25% OF TOTAL WELD DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0 Examination Volume/Area Defined 0 Base Metal 0
Weld 11 Near Surface 11 Bolting 0 Inner Radius Area Calculation Volume Calculation
.26 "X 1.3" =.338 SQ. IN.
.338 SQ. IN. X 21" = 7.098 = 7.1 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 7.1 7.1 7.1 7.1 28.4 7.1 38.45 0.00 100.00 100.00 59.61 61.52
DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2N12F494 Item No: B09.011.165 Remarks:
0D NO SCAN SURFACE BEAM DIRECTION DUE TO VALVE CONFIGURATION EO LIMITED SCAN C 1 0D 2 021 IC3 2 C3 cwC ccw FROM L
-__.N/A to L N/A INCHES FROM WO --
.5" to BEYOND ANGLE:
C 0 C 45 0 60 Cl Other
_FROM 0
DEG to 360 DEG C
NO SCAN SURFACE BEAM DIRECTION C1 LIMITED SCAN C 1 C1 2 C
1 I 2
C cw EC ccw FROM L.
to L INCHES FROM WO to ANGLE:
Cl 0 C] 45 C3 60 Cl Other FROM DEG to DEG C3 NO SCAN SURFACE BEAM DIRECTION C
LIMITED SCAN C 1 C1 2 C
1 iC 2
C cw Cl ccw FROM L to L INCHES FROM WO to ANGLE:
C1 0 C 45 C1 60 C1 Other FROM DEG to DEG C3 NO SCAN C
LIMITED SCAN SURFACE i1 C2 to L BEAM DIRECTION C1 1 C 2 Cl cw C ccw INCHES FROM WO ANGLE:
C 0 C 45 C1 60 C Other FROM to DEG to I __________________________________
A Prepared By:
Date: 9-/,2,co Sketch(s) attached 0 yes 13 no Sheet
/-/..
of 9-Reviewed By:
I Authorized Inspector:
Date:
--/
6ý
-PAAJ I ý FROM L
-4.ý Sheet 4/
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DUKE POWER COMpANy ULTRASONIC DATA SHEET FOR PLANAR REFLECTORS IN FERRITIC PRESSURE VESSELS St ti n
cv U nt Con o
e t W l D
0 Surefdae no:
I----c-" e Condition:
Cnz
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Procedure No:
I_____
Revision:
FCj
)cg~nsConriguraktion 700 2ZdBZoneI 6 0
.7M dBZoneII n
r 60'2ý_-dB Zone III Axial Scan Surf2ce: OD 600 7*.ZdB Zone Ill Circ.
Suffice Temp.lC)~
0 C A D
ue Date. :
4 LV
- L Ca.L Due Date.,
C llbration Sheet No:
0 0o L-. 7o05 Ooo0'7_oS
> 90% Coverage obtained:
yes E no E (see NDE.UTr4) Ulimitati*,n*re e,.
~ ~ ~~r a req uired Examiner:
Level:
Date:
Examinern No:
- oeh --- Dat Reviewed by:.-
< /
5* JJ Level:.
Date:
Level:
Authorized Inspector:
Date:
R EQUEST FOR RELIEF 01--00e ATTACHMENT 2 Page J of PAG51-.9
/
Form NDE-620 Revision 0
6.2 3.2 5.5 5.5 69 69 69 69 427.8 220.8 379.5 379.5 1407.6 434.7 434.7 434.7 434.7 1738.8 98.41 50.79 87.30 87.30 80.95 I
oI1/4' DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso 1-1;
- 1. : I I - I -
5 1
1, 1
1 m
_,i Examination Volume/Area Defined O Base Metal 13 Weld 0 Near Surface 11 Bolting 0 Inner Radius Area Calculation Volume Calculation ZONE I 6.3 SQ. IN X 69 IN. = 434.7 CU. IN.
SEE DRWG. 6.3 SQ. 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 70 70 70 70 S2 S1 Cw CCw
1207.5 103.5 979.8 979.8 3270.6 1205.7 1207.5 1207.5 1207.5 4830 q OT q DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined 0 Base Metal 0
Weld 0 Near Surface 1l Bolting El Inner Radius Area Calculation Volume Calculation ZONES II & I1l 17.5 SQ. IN. X 69 IN. = 1207.5 CU. IN.
SEE DRWG. 17.5 SQ. 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 60 60 60 60 S2 S1 CW CCW 17.5 1.5 14.2 14.2 69 69 69 69 100.15 8.57 81.14 81.14 67.71
[item No:
C02.021.007 Prepared By:
Level:
Date: O ' 3 Reviewed By:
Level:
Date:
Zia/27:
4-2 tý
60 COVERAGE 67.7%
70 COVERAGE 81 %
AGGREGATE COVERAGE 74.4%
Item No:
C02.021.007 Prepared By:
Level:
-r" Date:
i Z,3,_0 Reviewed By:
IV Level:
Date:
I S-6f -7 DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined o1 Base Metal 0
Weld 01 Near Surface 0 Bolting 01 Inner Radius Area Calculation Volume Calculation Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Scan # Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.in.)
Percent Coverage
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_000 Z
-600,2-0 127 REQUEST FOR RELIEF 01--00 ATTACHMENT 3
,p 6-sI-
,/,
0, /V I ;, /C,/ f"3
1 60S 2
60S 3
45 4
45 SHEAR 2
60L 2
1 Cw CCw WAVE 1
0 21
.105 21
.266 21
.266 21 AGGREGATE COVERAGE
.161 21 0
2.205 5.59 5.59 13.385 3.381 5.59 5.59 5.59 5.59 22.36 5.59 0.00 39.45 100.00 100.00 59.86 60.48 LONG WAVE 60.48% OF 25% (SCAN 1) = 15.1 LONG WAVE COVERAGE 15.12% OF TOTAL WELD
(
3 o-F /
DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination VolumelArea Defined 0 Base Metal 10 Weld I Near Surface 01 Bolting 0 Inner Radius Area Calculation Volume Calculation
- SEE DRAWING
.266 SQ. IN. X 21 IN. = 5.586 CU. IN.
.266 SQ. IN.
= 5.59 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
-N
-N DUKE POWER COMPANY NDE-UT-5 UT PROFILE/PLOT SHEET Revision 1 EXAMINATION SURFACE 1 V,4Lvd-4 iii1 3
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.Date:
Reviewed By:
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Authorized Inspecte.
9-15-.00 Level:2 I Date:
I Date: F
,50 0
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REQUEST FOR RELIEF 01-001 ATTACHMENT 3 PAGES S 10
McGuire Unit #2 EOC13 Item #
(o,5 o 2 /. o08 /
Weld #
,2 oCPA-,TE No Data Recorded. Reference Calibration Sheet #'s NO9 200 7 3 o Pa-i3 eý '7
1 450 2
45*
3 60°S 4
60°S 60S L-WAVE 4
60L CW
.15 11 CCw
.15 11 Si 0
11 S2
.049 11 SHEAR WAVE AGGREGATE COVERAGE 2
.083 11 1.65 1.65 0
0.539 3.839 0.913 1.65 1.65 1.65 1.65 6.6 1.65 L-WAVE COVERAGE = 55.33% OF 25% (SCAN 4) =13.8 %
13.8% OF TOTAL WELD Ao 0 DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined 0 Base Metal 0
Weld 0 Near Surface 13 Bolting El Inner Radius Area Calculation Volume Calculation 1.0 X.15 =.15 SQ. IN.
.15 SQ. IN. X 11" = 1.65 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 100.00 100.00 0o00 32.67 58.17 55.33
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