ML042330371
| ML042330371 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba  |
| Issue date: | 08/10/2004 |
| From: | Mccollum W Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 03-GO-006 | |
| Download: ML042330371 (10) | |
Text
~ vDuke rWPowere 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 August 10, 2004 U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Mailing Address:
P. 0. Box 1006 - EC07H Charlotte, NC 28201-1006 704 382 8983 704 382 6056 fax wrmccoll@duke-energy. corn ATTENTION: Document Control Desk
SUBJECT:
Duke Energy Corporation Oconee Units 1, 2 & 3 Docket Nos. 50-269, 50-270, 50-287 McGuire Nuclear Station, Unit 2 Docket No. 50-370 Catawba Nuclear Station, Units 1 & 2 Docket Nos. 50-413, 50-414 Response to Request for Additional Information Relief Request 03-GO-006 Duke Energy Corporation (Duke) submitted Relief Request 03-GO-006 for Oconee Units 1, 2 and 3, McGuire Unit 2 and Catawba Units 1 and 2 on September 8, 2003. By letter dated July 30, 2004 the NRC Staff had requested additional information with respect to several issues within the relief request. The Duke response to this request is attached.
Upon further review Duke has determined that Relief Request 03-GO-006 is only needed for Catawba Units I and 2. Duke is therefore withdrawing this request for Oconee Units 1, 2, and 3 and McGuire Unit 2. Questions regarding this submittal may be directed to Mary Hazeltine at 704-382-5880.
Very tnily yours, William R. McCollun AD4~7 www.dukepower.com
U. S. Nuclear Regulatory Commission August 10, 2004 Page 2 Attachment xc w/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 August 10, 2004 Page 3 bxc w/ att:
R. L. Gill (ECO50)
C. J. Thomas (MGOIRC)
K. L. Crane (MGOlRC)
N. T. Simms (MGO1RC)
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 (ECO5A)
J. J. McArdle (EC05A)
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
REQUEST FOR ADDITIONAL INFORMATION ON RELIEF REQUEST 03-GO-006 DUKE POWER COMPANY CATAWBA UNITS 1 & 2 DOCKET NOS. 50-413 AND 50-414
- a.
Item I "System/Components for which the Alternative Applies" states under Category B-B (B2.1 1, B2.12) that Shell-to-Head welds are in the scope of the subject relief request.
But, in Item V "Alternative Method for Ultrasonic Examination" it is stated that for head-to-shell welds where the ratio of the inside diameter to the outside diameter of the head prevents the 60 deg beam angle from intercepting the inside surface, the PDI qualified procedure will not be used. Please explain your examination method for the limiting case of head-to-shell welds that are in the scope of the relief request.
Response
Where the geometric conditions do not permit the use of a 600 beam angle, 350, 450 and straight beam scans will be used in accordance with ASME Section V, Article 4.
- b.
Please provide a brief explanation on the applicability of the reactor vessel examination procedure that is qualified in accordance with Supplements 4 and 6 of Appendix VIII, ASME Code,Section XI, 1995 Edition through 1996 Addenda for the ultrasonic technique, procedure, and personnel using PDI to be suitable for the welds in the steam generator and the pressurizer in regard to the following:
- a. Materials, thickness, diameter, product form.
- b. Scanning from inside vs. outside.
Response
The manual ultrasonic procedures, PDI-UT-6 and NDE-620 are qualified for Supplement 4 and Supplement 6 flaw detection from the vessel outside surface. The thickness (2.0" to 7.64"), material type (ferritic steel),
diameter (N/A) and product form (rolled or forged) are within the scope of the procedures as qualified during performance demonstration. See attached PDQS sheets (PDQS Nos. 370 and 442).
Performance Demonstration Initiative Program Printed:
01-Maty-01 PDQS No:
370 In Accordance ivith the PDI Implementation of Section XI, Appendix VilN Specific Detail of Qualifications 0418171CI Owner: Duke Power Company Procedurc: NDE-620; Revision: 7; Addenda: 0 Ultrasonic Examination of Fcrritic Pressure Vessel Welds Greater Than 2 Inchtes In Thickness PDQS Rev:
0 Hlardware:
N/A Date of Issue:
09-Apr-99 Aquisition SNN'Type/Rev: N/A Category:
RPV Analysis SWV Type/Rev:
N/A Scan Application: Manual Ranees Demonstrated:
[Supplement: Supplement 4 ofASME Appendix VIII TestDate:
12-Mar-99 1 IMaterial:
Ferritic with SMAW as Ground. Cladding I
l Surface:
Outer Diameter I
Access:
dual I
Examination: Detection Thickness Range: N/A to 7.64 1 a.
I Supplement: Supplement 6 of ASME Appendix Vil TestDate:
12-Mar-99 I Material:
Ferritic with SMAW as Ground. Cladding I
Surface:
Outer Diameter Access:
dual Examination: Detection Thickness Range: 2.00 to-- 7.64 I
Page I of 3
Performance Demonstration Initiative Program In Accordance with the PDI Implementation of Section XI, Appendix VIII Specific Detail of Qualifications Owner: Duke Power Company Printed:
01-May-01 PDQS No:
370 0418171CI Procedure: NDE-620; Revision: 7; Addenda: 0 Ultrasonic Examination of Ferritic Pressure Vessel Welds Greater Than 2 Inches In Thickness PDQS Rev:
0 Hardware:
N/A Date of Issue:
09-Apr-99 Category:
RPV Scan Application: Manual Aquisition SW Type/Rev: N/A Analysis SW Type/Rev:
N/A Supplement 4 Acceptance Criteria:
When 'Length Sizing' is indicated, the 0.750 RMS acceptance criteria per the PDl Program Description has been achieved.
When 'Through Wall Extension' is indicated, the 0. 150 RMS acceptance criteria per the PD1 Program Description has been achieved.
Supplement 6 Acceptance Criteria:
When 'Length Sizing" is indicated, the 0.750 RMS acceptance criteria per the PDl Program Description has been achieved.
When 'Through Wall Extension' is indicated, the 0.250 RMS and 0.7 Slope acceptance criteria per the PDI Program Description has been achieved.
Comments:
I The specimen set used to demonstrate this procedure included specimens with a maximum thickness of 6.88" (not including clad).
2 Based on the specimen set thickness from the comment above, the "Thickness Range" specifed above includes the "90% of Maximum Thickness" allowance per Appendix Vill.
3 The maximum range of the supplement 4 volume is based on the specimen set Thickness including the "90% of Maximum Thickness" allowance per Appendix Vill.
4 See procedure for combinations of instrument, search unit and pulse tuning controls that have been qualified.
Limitations:
0 None Page 2 of 3
Performance Demonstration Initiative Program Printed:
0I-May-OI PDQS No:
370 In Accordance with the PDI Implementation of Section Xl, Appendix Vill Specific Detail of Qualifications 0418 171C Owner: Duke Power Company Procedure: NDE-620; Revision: 7; Addenda: 0 Ultrasonic Examination of Ferritic Pressure Vessel Welds Greater Than 2 Inches In Thickness PDQS Rev:
0 llardware:
N/A Date of Issue:
09-Apr.99 Aquisition SNN Type/Rev: N/A Category:
N/A Scan Application: Manual The above procedure has met the requirements of The Performance Demonstration Initiative's Implementation of The American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Appendix Vil as stated in this document.
Date:
M1. E. Gothard Plerformance Demonstration Initiative Reactor Pressure Vessel Supervisor/Level Ill Date:
F. L. Becker Performance Demonstration Initiative Administrator This document is not xathentic without a raised seat.
Page 3 of 3
Performance Demonstration Initiative Program Printed 05-NMar-03 PDQS No:
442 In Accordance -Aith the PDI Implementation of Section XI, Appendix V1II Specific Detail of Qualifications 04080502 Owner: Performance Demonstration Initiative Procedure: PDI-UT-6; Revision: F; Addenda: 0 PDI Generic Procedure for the Manual Ultrasonic Examination of Reactor Pressure Vessel WVelds PDQS Rev:
5 Hardware:
N/A Date of Issue:
26-Feb-03 Aquisition SW Type/Rev: N/A Category:
NIA Scan Application: Manual Ranges Demonstrated:
ISupplement: Supplement 4 ofASME Appendix VIII TestDate:
27-Sep-01 1 Material:
Ferritic with SMAW as Ground. Cladding Surface:
Outer Diameter 1
Access:
dual Examination:
Detection Thickness Range: N/A to 7.64 1
I Access:
single I
l Examination:
Detection Thickness Range: N/A to 7.64 1
!1 Supplement: Supplement6ofASME Appendix VIII TestDater-.. 27-Sep-01 I Material:
Ferritic with SMAW as Ground. Cladding I
I Surface:
Outer Diameter I
Access:
dual I
Examination:
Detection Thickness Range: 2.00 to 7.64 I
Access:
single I
I Examination:
Detection Thickness Range: 2.00 to 7.64 I L
a Page I of 3
, 4 Performance Demonstration Initiative Program In Accordance with the PDI Implementation of Section XI, Appendix VIII Specific Detail of Qualifications Printed 05-Mtar.03 PDQS No:
442 04080502 Owner: Performance Demonstration Initiative Procedure: PDI-UT-6; Revision: F; Addenda: 0 PDI Generic Procedure for the Manual Ultrasonic Examination of Reactor Pressure Vessel Welds PDQS Rev:
5 Hardware:
N/A Date of Issue:
26-Feb-03 Category:
RPV Sean Application: Manual Aquisitlon SW Type/Rev: N/A Analysis SW Type/Rev:
N/A Supplement 4 Acceptance Criteria:
When 'Length Sizing' is indicated, the 0.750 RMS acceptance criteria per the PDI Program Description has been achieved.
When 'Through Wall Extension' is indicated, the 0.1 50 RMS acceptance criteria per the PDI Program Description has been achieved.
Supplement 6 Acceptance Criteria:
When 'Length Sizing' is indicated, the 0.750 RMS acceptance criteria per the PDI Program Description has been achieved.
When "Through Wall Extension' is indicated, the 0.250 RMS and 0.7 Slope acceptance criteria per the PDI Program Description has been achieved.
Comments:
I Single Side Endorsement has been issued in accordance with EPRI Document 1001037, for implementation of 10 CFR 50.55a (b)(2)(xv)(G)(I),(2) and I OCFRS0.55a(b)(2)(xvi)(A) requirements for ferritic vessel examinations.
2 This procedure includes the same essential variables as specified in PDI-UT-6 rev E, with any additional qualified equipment listed on Tables I and 2.
3 The specimen set used to demonstrate this procedure included specimens with a maximum thickness of 6.88" (not including clad).
4 Based on the specimen set thickness from the comment above, the "Thickness Range specifed above includes the "90% of Maximum Thickness" allowance per Appendix Vill.
5 The maximum range of the supplement 4 volume is based on the specimen set Thickness including the "90% of Maximum Thickness" allowance per Appendix Vill.
6 See Tahles I & 2 for combinations of instrument. search unit and pulse tuning controls that have been qualified.
7 This revision replaces revision E of this procedure.
Limitations:
I This procedure is qualified for flaw detection only.
Page 2 of 3
Performance Demonstration Initiative Program Printed 05-Mar.03 PDQS No:
442 In Accordance Aith the PDI Implementation of Section XI, Appendix Vill Specific Detail of Qualifications 04080502 Owner: Performance Dcmonstration Initiative Procedure: PDI-UT-6; Revision: F; Addenda: 0 PDI Gcneric Procedure for the Manual Ultrasonic Examination of Reactor Pressure Vessel Welds PDQS Rev:
5 Hardware:
N/A Date of Issue:
26-Feb-03 Aquisition SW Type/Rev: N/A Category:
N/A Scan Application: Manual The above procedure has met the requirements of The Performance Demonstration Initiative's Implementation of The American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Appendix Vill as stated in this document.
Date:
NI. E. Gothard Performance Demonstration Initiative Reactor Pressure Vlessel Supervisor/Level [i1 Date:
F. L. Becker Performance Demonstration Initiative Administrator This document is not authentic without a raised seal.
Page 3 of 3