ML050470125
| ML050470125 | |
| Person / Time | |
|---|---|
| Site: | Catawba, Mcguire |
| Issue date: | 02/03/2005 |
| From: | Morris J Duke Energy Corp, Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML050470125 (5) | |
Text
Duke James R. Morris
- wPowere Vice President, Nuclear Support Nuclear Generation A Duke Energy Company Duke Power EC07H/526 South Church Street Chadotte, NC 28202-1006 February 3, 2005 Mailing Address:
P.O. Box 1006 EC07H U. S. Nuclear Regulatory Commission Charlotte, NC 28201-1006 Washington, D.C. 20555-0001 704-382-6041 ATTENTION: Document Control Desk 704-382-6056 fax james.mornis duke-energy.com
SUBJECT:
Duke Energy Corporation McGuire Nuclear Station Unit 2 Docket No. 50-370 Catawba Nuclear Station Unit 1 Docket Nos. 50-413 Response to Request for Additional Information Relief Request 04-GO-001 By letter dated August 6, 2004, pursuant to 10 CFR 50.55a (a) (3) (i), Duke Energy Corporation (Duke) requested the use of an alternative to the ASME Boiler Section XI, Figures IWB-2500-7 (a) and (b), 1989 Edition with no addenda for the Reactor Pressure Vessel (RPV) examinations scheduled for the fall 2004 outages at Catawba Unit 2 and Oconee Unit 3; and the spring 2005 outages at McGuire Unit 2 and Catawba Unit 1. The NRC staff requested additional information to complete the review of the subject relief request during a teleconference with Duke on August 18, 2004. The requested information was provided for Oconee Unit 3 and Catawba Unit 2 in a letter dated September 15, 2004. The requested information for McGuire Unit 2 and Catawba Unit I was not available at that time. A Safety Evaluation Report was subsequently received from the NRC staff on October 7, 2004 for Oconee Unit 3 and Catawba Unit 2.
Attachment I provides the information requested during the August teleconference for McGuire Unit 2 and Catawba Unit 1.
Duke is requesting approval of Relief Request 04-GO-001 for McGuire Unit 2 and Catawba Unit I prior to the spring 2005 outages.
Very truly your James R. Morris www. duke power corn (01
U. S. Nuclear Regulatory Commission February 3, 2005 Page 2 Attachment xc wv/att: W. D. Travers, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Sam Nunn Atlanta Federal Center 23T85 61 Forsyth St., SW Atlanta, GA 30303 L. N. Olshan (Addressee only)
NRC Senior Project Manager (ONS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 J. J. Shea (Addressee only)
NRC Senior Project Manager (MNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 S. E. Peters (Addressee only)
NRC Project Manager (CNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 M. E. Shannon, NRC Senior Resident Inspector (ONS)
J. B. Brady, NRC Senior Resident Inspector (MNS)
E. F. Guthrie, NRC Senior Resident Inspector (CNS)
U. S. Nuclear Regulatory Commission February 3, 2005 Page 3 bxc w/ att: R. L. Gill (ECO5O)
C. J. Thomas (MGOIRC)
K. L. Crane (MGOIRC)
N. T. Simms (MGO1RC)
L. A. Keller (CNOIRC)
K. E. Nicholson (CNO1RC)
L. J. Rudy (CNOIRC)
J. M. Ferguson - Date File (CNOISA)
A. J. Hogge G. J. Underwood R. K. Rhyne (EC05A)
J. J. McArdle (ECOSA)
North Carolina Municipal Power Agency Number 1 Saluda River Electric Cooperative, Inc.
Piedmont Municipal Power Agency North Carolina Electric Membership Corporation MNS MasterFile MC-801.01 (MGOIDM)
CNS MasterFile CN-801.01 (CN04DM)
ONS MasterFile ON-801.01 (ON03DM)
ELL
Attachment 1 RAI Questions and Responses for Relief Request 04-GO-001 Questions:
In order to complete a review of your relief request additional information is required. Please forward the specific RPV Nozzles affected for each plant and provide the following details in tabular format:
- 1) Component ID
- 2) Component Description (eg Recirc Loop A Outlet Nozzle to Vessel Weld @ 180 Deg Azimuth)
- 3) Nozzle Configuration (eg Code Case N-613-1 fig 2)
- 4) Full Exam coverage previously completed (eg Yes -Preservice & 1 st Interval)
- 5) Previous Weld Repair (eg NO)
- 6) Is Weld repair in Code Case Boundary (eg Yes)
Responses:
McGuire Unit 2 1 2 2 3 4 5 6 Component Description Azimuth Code Case Full Exam Previous Repair In ID N-613-1 Coverage Weld Code Case Figure Completed' Repair 2 Boundary 2RPV-W15 Outlet 220 1 Yes-PSI and No N/A Nozzle I" Interval ISI 2RPV-WI I Inlet Nozzle 670 1 Yes-PSI and No N/A IS'Interval ISI 2RPV-W12 Inlet Nozzle 1130 1 Yes-PSI and No N/A
'l' Interval ISI 2RPV-W16 Outlet 1580 1 Yes-PSI and No N/A Nozzle I' Interval ISI 2RPV-W17 Outlet 2020 1 Yes-PSI and No N/A Nozzle I' Interval ISI 2RPV-W13 Inlet Nozzle 2470 1 Yes-PSI and No N/A
___Interval ISI 2RPV-W14 Inlet Nozzle 2930 1 Yes-PSI and No N/A I" Interval ISI 2RPV-W18 Outlet 3380 1 Ycs-PSI and No N/A Nozzle It Interval ISI Footnote 1: Coverage of the examination volume from the vessel shell side as shown in ASME Section XI, Figure IWB-2500-7(a) was limited due to the dual sided scanning requirements contained in ASME Section V, Article 4 which was used to examine these welds in the first interval. The outlet and inlet nozzles are most like Figure IWB-2500-7(a) or Figure I in Code Case N-613-1.
Footnote 2: WesDyne International reviewed the fabrication records for these welds including the Westinghouse deviation notices, trip reports, surveillance reports and QC/NDE shop documentation for this reactor pressure vessel. The MNS site records were also reviewed. There is no documented evidence of weld repairs being made to the nozzle-to-shell welds.
Further, the current scan plan is being developed from previous data obtained during preservice and first interval inservice inspection. This plan will take into account the weld profile on the ID and will address any weld configurations considered to be beyond design.
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Catawba Unit 1 I 2 2 3 4 5 6 Component Description Azimuth Code Case Full Exam Previous Repair in ID N-613-1 Coverage NVeld Code Case Figure Completed' Repair 2 Boundary IRPV-W15 Outlet 220 1 Yes-PSI and No N/A Nozzle I" Interval 1SI IRPV-W1 1 Inlet Nozzle 670 1 Yes-PSI and No N/A
. _In Interval ISI IRPV-W12 Inlet Nozzle 1130 1 Ycs-PSI and No N/A In Interval ISI lRPV-W16 Outlet 1580 1 Yes-PSI and No N/A Nozzle I' Interval ISI IRPV-W17 Outlet 2020 1 Yes-PSI and No N/A Nozzle I' Interval 1SI IRPV-W13 Inlet Nozzle 2470 1 Ycs-PSI and No N/A I Interval IS _
lRPV-W14 Inlet Nozzle 2930 1 Yes-PSI and No N/A In Interval 1SI lRPV-W18 Outlet 3380 1 Yes-PSI and No N/A Nozzle I' Interval ISI Footnote 1: Coverage of the examination volume from the vessel shell side as shown in ASME Section XI, Figure IWB-2500-7(a) was limited due to the dual sided scanning requirements contained in ASME Section V, Article 4 which was used to examine these welds in the first interval. The outlet and inlet nozzles are most like Figure IWB-2500-7(a) or Figure 1 in Code Case N-613-1.
Footnote 2: WesDyne International reviewed the fabrication records for these welds including the Westinghouse deviation notices, trip reports, surveillance reports and QC/NDE shop documentation for this reactor pressure vessel. The CNS site records were also reviewed. There is no documented evidence of weld repairs being made to the nozzle-to-shell welds.
Further, the current scan plan is being developed from previous data obtained during preservice and first interval inservice inspection. This plan will take into account the weld profile on the ID and will address any weld configurations considered to be beyond design.
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