ML021330160
| ML021330160 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 04/24/2002 |
| From: | Barron H Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML021330160 (18) | |
Text
P Duke D Power.
A Duke EwW Company Duke Power Company A Duke Energy Company McGuire Nuclear Station MGO1VP 12700 Hagers Ferry Rd.
Huntersville, NC 28078-9340 H. B. Barron Vice President, McGuire Nuclear Generation Department April 24, 2002 (704) 875-4800 OFFICE (704) 875-4809 FAX U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001
Subject:
McGuire Nuclear Station, Unit 1 Docket No. 50-369 Relief Request 01-006 Pursuant to 10CFR50.55a(g)(5)(iii), Duke Energy Corporation requests relief from certain ASME Section XI Code requirements as described in the attached Relief Request No.01-006.
This relief request addresses cases of limited examination coverage of reactor vessel weld inspections performed during the end of fuel cycle (EOC) 14 for Unit 1. 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.
The enclosed relief request describes for each specified case that the ASME Code requirement is impractical. Each specific instance is described in detail, including a basis for why a reasonable assurance of structural integrity exists.
Although, submittal of Relief Request No.01-006 satisfies a previous identified commitment,1 there are no additional commitments associated with this relief request.
Please direct any questions regarding this request to Norman T. Simms of Regulatory Compliance at (704) 875-4685.
Sincerely, H. B. Barron Enclosure
' Letter, H. B. Barron to NRC, Dated July I1, 2001, Inservice Inspection Report Abc<7
U.S. Nuclear Regulatory Commission April 24, 2002 Page 2 of 2 xc w/enclosure:
Mr. L. A Reyes US Nuclear Regulatory Commision, Region HI 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 08G9 Washington, D.C. 20555 S. M. Shaeffer Senior NRC Resident Inspector McGuire Nuclear Station
bxc w/o encl:
bxc w/ encl:
R.K. Rhyne R. Branch G.J. Underwood D.E. Caldwell G.D. Scarboro R.D. Klein (MGO0MM)
N.T. Simms RCG Files Master File # 1.3.2.13 NRIA File/ELL
ENCLOSURE RELIEF REQUEST NO.01-006
Serial No.01-006 Page 1 of 9 Duke Energy Corporation McGuire Nuclear Station Unit 1 SECOND 10-YEAR INTERVAL REQUEST FOR RELIEF NO.01-006 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 this request are six Examination Category B-A welds.
The McGuire Unit 1 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 refueling outage EOC-14.
Code Case N-460 applies to the examinations performed during this outage.
I.
System / Component(s) for Which Relief is Requested:
Examination Category B-A:
Pressure Retaining Welds in Reactor Vessel, Lower Shell to Bottom Head Circumferential Weld ID Number Item Number 1RPV10-442 B01.011.003 II.
Code Requirement:
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition, Table IWB-2500-1, lists the following requirements for the examination category as shown below:
Figure IWB-2500-1.
Examination Volume E-F-G-H.
Serial No.01-006 Page 2 of 9 III.
Code Requirement from Which Relief Is Requested:
Relief is sought from the requirement to scan 100% of the examination volume.
IV.
Basis for Relief:
During the ultrasonic examination of this weld, 100%
of the required examination volume could not be achieved.
As shown in Attachment 1 (Page 1 of 1) the examination coverage was limited to 69.00% due to the proximity of the Core Guide Lugs.
The percent of coverage represents the aggregate coverage of all scans for the weld.
In order to achieve more coverage, the Core Guide Lugs would have to be moved to allow greater access for scanning, which is impractical.
V.
Alternate Examinations or Testing:
No additional ultrasonic examinations are planned during the current interval for this weld.
However a visual examination was performed on the interior of the reactor vessel per the requirements of the ASME Section XI Code.
The visual examination of the vessel interior did not identify any rejectable conditions.
VI.
Justification for the Granting of Relief:
Ultrasonic examination of this weld was conducted using personnel, equipment and procedures qualified in accordance with ASME Section XI, Appendix VIII, 1995 Edition with the 1996 Addenda as administered through the Performance Demonstration Initiative (PDI)
Program.
Although 100% coverage of the examination volume could not be achieved, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity.
Due to the design of the reactor vessel and location of the Core Guide Lugs it is not feasible to obtain the examination coverage required.
Based on the portions and results of the required volumetric and visual examinations performed during this outage, it's our opinion that this combination of examinations provides a reasonable assurance of component integrity.
Serial No.01-006 Page 3 of 9 VII.
Implementation Schedule:
No additional ultrasonic examination is planned during the current interval for this weld.
Viii.
References:
Page 1 of 1.
Information for this weld is shown on
Serial No.01-006 Page 4 of 9 I.
System / Component(s) for Which Relief is Requested:
Examination Category B-A:
Pressure Retaining Welds in Reactor Vessel, Lower Shell Longitudinal Weld ID Numbers Item Numbers IRPV3-442A B01.012.007 IRPV3-442B B01.012.008 1RPV3-442C B01.012.009 II.
Code Requirement:
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition Table IWB-2500-1, lists the following requirements for the examination category as shown below:
Figure IWB-2500-2.
Examination Volume A-B-C-D.
III.
Code Requirement from Which Relief Is Requested:
Relief is sought from the requirement to scan 100% of the examination volume.
IV.
Basis for Relief:
During the ultrasonic examination of these welds, 100%
of the required examination volume could not be achieved.
As shown in Attachment 2 (Pages 1-2),
the examination coverage was limited to 79.00% due to the proximity of the Core Guide Lugs.
The percent of coverage represents the aggregate coverage of all scans for these welds.
In order to achieve more coverage, the Core Guide Lugs would have to be moved to allow greater access for scanning, which is impractical.
Serial No.01-006 Page 5 of 9 V.
Alternate Examinations or Testing:
No additional examinations are planned during the current interval for these welds.
However a visual examination was performed on the interior of the reactor vessel per the requirements of the ASME Section XI Code.
The visual examination of the vessel interior did not identify any rejectable conditions.
VI.
Justification for the Granting of Relief:
Ultrasonic examination of these welds was conducted using personnel, equipment and procedures qualified in accordance with ASME Section XI, Appendix VIII, 1995 Edition with the 1996 Addenda as administered through the Performance Demonstration Initiative (PDI)
Program.
Although 100% coverage of the examination volume could not be achieved, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity.
Due to the design of the reactor vessel and location of the Core Guide Lugs it is not feasible to obtain the examination coverage required.
Based on the portions and results of the required volumetric and visual examinations performed during this outage, it's our opinion that this combination of examinations provides a reasonable assurance of component integrity.
VII.
Implementation Schedule:
No additional ultrasonic examination is planned during the current interval for this weld.
VIII.
References:
Information for these welds is shown on Pages 1-2.
Serial No.01-006 Page 6 of 9 I.
System / Component(s) for Which Relief is Requested:
Examination Category B-A:
Pressure Retaining Welds in Reactor Vessel, Bottom Head Circumferential Weld ID Number Item Number 1RPV4-469 B01.021.002 II.
Code Requirement:
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition Table IWB-2500-1, lists the following requirements for the examination category as shown below:
Figure IWB-2500-3.
Examination Volume A-B-C-D.
III.
Code Requirement from Which Relief Is Requested:
Relief is sought from the requirement to scan 100% of the examination volume.
IV.
Basis for Relief:
During the ultrasonic examination of this weld, 100%
of the required examination volume could not be achieved.
As shown in Attachment 3 (Page 1 of 1), the examination coverage was limited to 49.00% due to the proximity of In-core Instrument Nozzles.
The percent of coverage represents the aggregate coverage of all scans for the weld.
In order to achieve more coverage, the In-core Instrument Nozzles would have to be moved to allow greater access for scanning, which is impractical.
Serial No.01-006 Page 7 of 9 V.
Alternate Examinations or Testing:
No additional ultrasonic examinations are planned during the current interval for this weld.
However a visual examination was performed on the interior of the reactor vessel per the requirements of the ASME Section XI Code.
The visual examination of the vessel interior did not identify any rejectable conditions.
VI.
Justification for the Granting of Relief:
Ultrasonic examination of this weld was conducted using personnel, equipment and procedures qualified in accordance with ASME Section XI, Appendix VIII, 1995 Edition with the 1996 Addenda as administered through the Performance Demonstration Initiative (PDI)
Program. Although 100% coverage of the examination volume could not be achieved, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity.
Due to the design of the reactor vessel and location of the In-core Instrument Nozzles it is not feasible to obtain the examination coverage required.
Based on the portions and results of the required volumetric and visual examinations performed during this outage, it's our opinion that this combination of examinations provides a reasonable assurance of component integrity.
VII.
Implementation Schedule:
No additional ultrasonic examination is planned during the current interval for this weld.
VIII.
References:
Information for this weld is shown on Page 1 of 1.
Serial No.01-006 Page 8 of 9 I.
System / Component(s) for Which Relief is Requested:
Examination Category B-A:
Pressure Retaining Welds in Reactor Vessel, Nozzle Belt Shell to Flange Weld ID Number Item Number IRPV7-442 B01.030.002 II.
Code Requirement:
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition Table IWB-2500-1, lists the following requirements for each examination category as shown below:
Figure IWB-2500-4. Examination Volume A-B-C-D.
III.
Code Requirement from Which Relief Is Requested:
Relief is sought from the requirement to scan 100% of the examination volume.
IV.
Basis for Relief:
During the ultrasonic examination of this weld, 100%
of the required examination volume could not be achieved.
As shown in Attachment 4, (Page 1 of 1) the examination coverage was limited to 90.00% due to Keyway Specimen Tube Cutouts.
The percent of coverage represents the aggregate coverage of all scans for the weld.
In order to achieve more coverage, the Keyway Specimen Tube Cutouts would have to be moved to allow greater access for scanning, which is impractical.
V.
Alternate Examinations or Testing:
No additional ultrasonic examinations are planned during the current interval for this weld.
However a visual examination was performed on the interior of the reactor vessel per the requirements of the ASME Section XI Code.
The visual examination of the vessel interior did not identify any rejectable conditions.
Serial No.01-006 Page 9 of 9 VI.
Justification for the Granting of Relief:
Ultrasonic examination of this weld was conducted using personnel, equipment and procedures qualified in accordance with ASME Section XI, Appendix VIII, 1995 Edition with the 1996 Addenda as administered through the Performance Demonstration Initiative (PDI)
Program. Although 100% coverage of the examination volume could not be achieved, the amount of coverage obtained for this examination provides an acceptable level of-quality and integrity.
Due to the design of the reactor vessel and location of the Keyway Specimen Tube Cutouts it is not feasible to obtain the examination coverage required.
Based on the portions and results of the required volumetric and visual examinations performed during this outage, it's our opinion that this combination of examinations provides a reasonable assurance of component integrity.
VII.
Implementation Schedule:
No additional ultrasonic examination is planned during the current interval for this weld.
VIII.
References:
Information for this weld is shown on Page 1 of 1.
The following individuals were involved in the development of this request for relief.
Terry Moore (McGuire Reactor Systems Engineer) 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 By:
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Date
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Approved By: __
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