ML032390631
| ML032390631 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba  |
| Issue date: | 08/19/2003 |
| From: | Mccollum W Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 03-GO-012 | |
| Download: ML032390631 (7) | |
Text
~ Duke Duke Energy Corporation Duke
~~~~~~~~~~~~~~~~~~~~~526 South Church Strae M Energy.
P.O. Box 1006 Charlotte, NC 28201-1006 August 19, 2003 U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Duke Energy Corporation Oconee Unit 3 Docket No. 50-287 McGuire Nuclear Station, Unit 2 Docket No. 50-370 Catawba Nuclear Station, Units 1 & 2 Docket Nos. 50-413, 50-414 Relief Request for Alternative to ASME Section XI Relief Request 03-GO-012 Pursuant to 10 CFR 50.55a (a) (3) (i), Duke Energy Corporation (Duke) requests the use of an alternative to the ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition with no addenda, Table IWB-2500-1, Examination Category B-D, Item No. B3.100, Nozzle Inner Radius Sections. Duke requests the use of the alternative for the Oconee Unit 3 third 10-year Interval Examination and the McGuire Unit 2 and Catawba Units 1 and 2 second 10-year Interval Examination.
Specifically, Duke requests relief to perform a remote VT-1 examination in lieu of the volumetric examination required in Table IWB-2500-1 Examination Category B-D, Full Penetration Welds of Nozzles In Vessels, Item No. B3. 100, Nozzle Inner Radius Sections.
A detailed description of the proposed alternative and justification is included as an attachment to this letter. Duke is requesting approval of this request by August 19, 2004, to support the Oconee Unit 3 outage in the fall of 2004. Questions regarding this request may be directed to R. K. Nader at 704-382-0979.
Very truly yours, W. R. McCollum, Jr Senior Vice President, Nuclear Support
U. S. Nuclear Regulatory Commission August 19, 2003 Page 2 Attachment xc wlatt:
L. A. Reyes, 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 R. E. Martin (Addressee only)
NRC Senior Project Manager (MNS and CNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 205550001 M. E. Shannon, Senior Resident Inspector (ONS)
E. F. Guthrie, NRC Senior Resident Inspector (CNS)
J. B. Brady, NRC Senior Resident Inspector (MNS)
U. S. Nuclear Regulatory Commission August 19, 2003 Page 3 bxc w/ att:
M. T. Cash (ECO50)
C. J. Thomas (MGO1RC)
K. L. Crane (MG 1RC)
N. T. Simms (MGOIRC)
G. D. Gilbert (CNOIRC)
K. E. Nicholson (CNOIRC)
L. J. Rudy (CNOIRC)
L. E. Nicholson (ON03RC)
J. E. Smith (ON03RC)
R. P. Todd (MD02FE)
J. M. Ferguson - Date File (CNOISA)
R. K. Rhyne (ECO7J)
J. J. McArdle (ECO7J)
T. Wills (WC28H)
R. 0. Sharpe (WC28H)
J. 0. Barbour (ECO7)
MNS MasterFile MC-801.01 (MGO1DM)
CNS MasterFile CN-801.01 (CN04DM)
ONS MasterFile ON-801,01 (ON03DM)
ELL
U. S. Nuclear Regulatory Commission August 19, 2003 Page 4 bxc w/ attach: North Carolina Municipal Power Agency Number 1 1427 Meadowwood Boulevard P. O. Box 29513 Raleigh, NC 27626 Saluda River Electric Cooperative, Inc.
P. O. Box 929 Laurens, SC 29360 Piedmont Municipal Power Agency 121 Village Drive Greer, SC 29651 T. Richard Puryear North Carolina Electric Membership Corporation P. O. Box 27306 Raleigh, NC 27611
03-GO-012 Page of 3 DUKE ENERGY CORPORATION Oconee Nuclear Station Unit 3 McGuire Nuclear Station Unit 2 Catawba Nuclear Station Units 1 & 2 10-YEAR INTERVAL REQUEST FOR RELIEF NO. 03-GO-012 Pursuant to 10CFR50.55a (a) (3) (i),
Duke Energy Corporation (Duke) proposes an alternative to the requirements of ASME Section XI, 1989 Edition with no addenda, Table IWB-2500-1, Examination Cate-gory B-D, Item No. B3.100, Nozzle Inner Radius Sections.
I.
System/Components for Which the Alternative Applies:
Category B-D Full Penetration Welds of Nozzles in Vessels Item Numbers:
Oconee Unit B03.100.001 B03.100.002 B03.100.003 B03.100.004 B03.100.005 B03.100.006 3
3-RPV-WR13 3-RPV-WR13A 3-RPV-WR12 3-RPV-WR12A 3-RPV-WR12B 3-RPV-WRl2C McGuire Unit 2 B03.100.001 2RPV-Wll B03.100.002 2RPV-W12 B03.100.003 2RPV-W13 B03.100.004 2RPV-W14 B03.100.005 2RPV-W15 B03.100.006 2RPV-W16 B03.100.007 2RPV-W17 B03.100.008-2RPV-W18 Catawba Unit B03.100.001 B03.100.002 B03.100.003 B03.100.004 B03.100.005 B03.100.006 B03.100.007 B03.100.008 1
lRPV-Wll 1RPV-W12 lRPV-W13 1RPV-W14 1RPV-W15 lRPV-W16 IRPV-W17 1RPV-W18
03-GO-012 Page 2 of 3 Catawba Unit 2 B03.100.001 2RPV-105-121A B03.100.002 2RPV-105-121B B03.100.003 2RPV-105-121C B03.100.004 2RPV-105-121D B03.100.005 2RPV-107-121A-B03.100.006 2RPV-107-121B B03.100.007 2RPV-107-121C B03.100.008 2RPV-107-121D II.
Code Requirement: ASME Section XI, Table IWB-2500-1 Examina-tion Category B-D, Full Penetration Welds of Nozzles In Ves-sels, Volumetric Examination, Figure IWB-2500-7(b), Examina-tion Volume M-N-O-P of ASME Section XI, 1989 Edition with no addenda.
III. Code Requirement for Which the Alternative is Requested, Relief is requested to perform a remote VT-l examination in lieu of the volumetric examination required in Table IWB-2500-1 Examination Category B-D, Full Penetration Welds of Nozzles In Vessels, Item No. B3.100, Nozzle Inner Radius Sections.
IV. Basis for Relief. Pursuant to 10CFR50.55a (a) (3) (i), Relief is requested to perform a remote VT-1 examination in lieu of the required volumetric examination on the basis that the pro-posed alternative provides an acceptable level of quality and safety.
V.
Alternative Method for Ultrasonic Examination.
Duke Energy Corporation proposes to use a remote VT-1 examina-tion of surface M-N as shown in ASME Section XI, Figure IWB-2500-7(b) of the 1989 Edition with no addenda.
The remote VT-1 equipment will have sufficient magnification and sensitivity to resolve a 0.001 inch wire in lieu of the sensitivity re-quired for an ultrasonic examination. The examination results will be evaluated in accordance with ASME Section XI, IWB-3140, 1989 Edition with no addenda. Crack-like surface flaws exceeding the acceptance criteria of Table IWB-3512-1 are un-acceptable for continued service unless the reactor vessel meets the requirements of IWB-3142.2, IWB-2142.3 or IWB-3142.4. When applying Table IWB-3512-1 criteria, crack depth will be assumed to be equal to one-half of the measured crack length.
03-GO-012 Page 3 of 3 VI.
Justification for the Granting of Reliefs The nozzles in the reactor pressure vessels are made of forged SA-508 ferritic steel with stainless steel cladding.
These nozzles were nondestructively examined during fabrica-tion and subsequently examined inservice twice using the ul-trasonic method.
There were no examination findings and no flaws were detected in any of the reactor pressure vessel noz-zle inner radius sections.
According to a NRC memorandum('], the NRC staff has indicated that an ultrasonic examination could be replaced by an en-hanced VT-1 visual examination for the proposed nozzle inspec-tions.
Subsequent to that memorandum, the NRC granted re-quests similar to this-request to Florida Power and Light for Turkey Point Units 3 & 4 (submitted May 6, 2002 and approved August 15, 2002) and Public Service Electric and Gas for Salem Units 1 & 2 (submitted February 11, 2002 and approved March 21, 2002).
Like Florida Power and Light and Public Service Electric and Gas, Duke proposes to use high magnification cameras to give 1-mil resolution capability for the remote VT-1 examination of the accessible portion of the nozzle inner radius section sur-face area.
With this resolution, it is highly likely that Duke would detect and disposition flaws using the allowable flaw length criteria in Table WB-3512-1 of the ASME Code,Section XI, for the disposition of any linear flaws.
There-fore, the proposed alternative provides reasonable assurance of structural integrity.
VII. Implementation:
Duke Energy will perform the remote VT-1 ex-amination of the reactor pressure vessel nozzle inner radii in conjunction with the Oconee Unit-3 3rd 10 year Interval Exami-nation; the McGuire Unit-2 2nd 10 year Interval Examination; The Catawba Units 1 and 2 2nd 10 year interval Examination.
Sponsored By e
D*
17 ate 1-3-°3 Approved By
/
DateQ203
'NRC Memorandum from K.R. Wichman to W.H. Bateman dated May 25, 2000;
Subject:
The Third Meeting with the Industry to Discuss the Elimination of RPV Inner Radius Inspection (ADAMS Accession No. ML003718630).