ML042660386
| ML042660386 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba  |
| Issue date: | 09/15/2004 |
| From: | Mccollum W Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RR 04-GO-001 | |
| Download: ML042660386 (5) | |
Text
Duke MiPowere A Duke Energy Company WILLIAM R MCCOLLUM, JR.
VP, Nuclear Support Duke Energy Corporation Duke Power EC07H / 526 South Church Street Charlotte, NC 28202-1802 September 15, 2004 U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION: Document Control Desk Mailing Address:
P. 0. Box 1006 - EC07H Charlotte, NC 28201-1006 704 382 8983 704 382 6056 fax wrmccoll@duke-energy. corn
SUBJECT:
Duke Energy Corporation Oconee Nuclear Station Unit 3 Docket No. 50-287 Catawba Nuclear Station Unit 2 Docket Nos. 50-414 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. Attachment I provides the information requested during this call for Catawba Unit 2 and Oconee Unit 3.
Duke is requesting approval of Relief Request 04-GO-001 for Oconee Unit 3 and Catawba Unit 2 as initially requested in the August 6, 2004 submittal in order to support the fall 2004 outages.
The requested information for McGuire Unit 2 and Catawba Unit I is not available at this time.
Very truly yours, XWilliain R. NMcCo~lun
.$, c-www. dukepower. corn
U. S. Nuclear Regulatory Commission September 15, 2004 Page 2 Attachment xc %v/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 September 15, 2004 Page 3 bxc w/ att:
R. L. Gill (ECO50)
C. J. Thomas (MGO1RC)
K. L. Crane (MGOIRC)
N. T. Simms (MGOIRC)
L. A. Keller (CNOIRC)
K. E. Nicholson (CNOIRC)
L. J. Rudy (CNOIRC)
B. G. Davenport (ON03RC)
J. E. Smith (ON03RC)
R. P. Todd (ON03RC)
J. M. Ferguson - Date File (CNOISA)
R. K. Rhyne (EC05A)
J. J. McArdle (EC05A)
North Carolina Municipal Power Agency Number I 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 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 & I st Interval)
- 5) Previous Weld Repair (eg NO)
- 6) Is Weld repair in Code Case Boundary (eg Yes)
Responses:
ONS-3 l
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' Repair2 Boundary 3-RPV-Outlet X axis I
Yes-PSI, I" No N/A WRI3 Nozzle and 2nd Interval ISI 3-RPV-Outlet Z axis I
Yes-PSI, 1"'
No N/A WR13A Nozzle and 2"d Interval ISI 3-RPV-Inlet Nozzle W-X axis I
Yes-PSI, I" No N/A WR12 and 2d Interval ISI 3-RPV-Inlet Nozzle X-Y axis I
Yes-PSI, I" No N/A WRI2A and 2nd Interval ISI 3-RPV-Inlet Nozzle Y-Z axis I
Yes-PSI, I' No N/A WR I 2B and 2"'
Interval ISI 3-RPV-Inlet Nozzle Z-W axis I
Yes-PSI, 15' No N/A W 12C and 2"d
_Interval ISI 3-RPV-Core Flood W axis 2
Yes-PSI, I" No N/A WR54 Nozzle and 2nd
_ _Interval ISI 3-RPV-Core Flood Y axis 2
Yes-PSI, lt No N/A WR54A Nozzle and 2"d Interval ISI Footnote 1:
Coverage of the examination volume from the vessel shell side as shown in ASME Section Xl, 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 and second intervals.
Page I of I
The outlet and inlet nozzles would be most like Figure IWB-2500-7(a) or Figure I in Code Case N-613-1. However, the welds are double U's instead of welded only from the outside. The core flood nozzle "veld is more like 1WB-2500-7(b) or Figure 2 of N-613-1 except again the configuration is a double U. As shown in the figures the main difference is the transition radius being a part of the nozzle or a part of the weld. In either case since the shell thickness is 12 inches the Ts/2 criteria of 6 inches from the edge of the weld extends into areas which are very difficult to examine due to the contour of the surface.
Footnote 2:
An investigation of the weld repair issue was conducted by station personnel that confidently concluded that no weld repairs were performed since original construction. Framatome Engineering performed a design review of ONS-3 and concluded that if repairs had been performed the cavities would have been excavated to an extent to clear the defect and made suitable for manual repair. The cavity would have been predominantly in the weld metal since the defects would have been in the weld or along the weld fusion line. The weld prep would only have been enlarged to allow access along the fusion line. Excavations would have been from the OD or ID depending upon where the defect was expected to be, i.e. nearest surface. Therefore, if there were weld repairs, there is very high assurance that the actual OD or ID weld surface is the largest extent of the weld as measured from the weld centerline.
Further, the current scan plan was developed from previous data obtained during preservice inspection. This plan takes into account the weld profile on the ID and would address any weld configurations considered to be beyond design.
CNS-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 '
Repair2 Boundary 2RPV-107-Outlet 220 1
Yes-PSI and No N/A 121B Nozzle I' Interval ISI 2RPV-105-Inlet Nozzle 670 1
Yes-PSI and No N/A 121B I' Interval ISI 2RPV-105-Inlet Nozzle 1130 1
Yes-PSI and No N/A 121A I' Interval ISI 2RPV-107-Outlet 1580 1
Yes-PSI and No N/A 121A Nozzle I' Interval ISI 2RPV-107-Outlet 2020 1
Yes-PSI and No N/A 121D Nozzle I' Interval 1SI 2RPV-105-Inlet Nozzle 2470 1
Yes-PSI and No N/A 121D I' Interval IS1 2RPV-105-Inlet Nozzle 2930 1
Yes-PSI and No N/A 121C I' Interval ISI 2RPV-107-Outlet 3380 1
Yes-PSI and No N/A 121C 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.
Footnote 2:
WesDyne International reviewed the fabrication records for these welds including the Combustion Engineering Inspection Report, Westinghouse deviation notices, trip reports, surveillance reports and QCINDE shop documentation for this reactor pressure vessel. The CNS site records were reviewed also. There is no documented evidence of weld repairs being made to the nozzle-to-shell welds.
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