ML040610109
| ML040610109 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/19/2004 |
| From: | Jamil D Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 04-CN-001 | |
| Download: ML040610109 (20) | |
Text
f Duke Powere A Duke Energy Company D.M. JAMIL Vice President Duke Power Catawba Nuclear Station 4800 Concord Rd. / CNO1 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax February 19, 2004 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Corporation Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Request for Relief Number 04-CN-001 Relief from Volumetric Weld Inspection Requirements Pursuant to 10 CFR 50.55a(g)(6)(i), please find attached Request for Relief 04-CN-001.
This request for relief is associated with Category B-J full penetration welds of nozzles in vessels, branch connection welds, NPS 4 or larger.
The attachment to this letter contains all technical information necessary in support of this request for relief.
Duke Energy Corporation is requesting NRC review and approval of this request at your earliest opportunity.
There are no regulatory commitments contained in this letter or its attachment.
If you have any questions concerning this material, please call L.J. Rudy at (803) 831-3084.
Very truly yours, LJR/s Attachment
~c~c(7 www. duke-energy. corn
Document Control Desk Page 2 February 19, 2004 xc (with attachment):
L.A. Reyes, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 E.F. Guthrie, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station S.E. Peters, Project Manager (addressee only)
U.S. Nuclear Regulatory Commission Mail Stop 0-8 G9 Washington, D.C. 20555-0001
Page 1 of3 DUKE ENERGY CORPORATION Catawba Nuclear Station Units 1 and 2 10-YEAR INTERVAL REQUEST FOR RELIEF NO. 04-CN-001 Pursuant to 10 CFR 50.55a (g) (6) (i) Duke Energy Corporation (Duke) has determined the compliance with certain requirements of ASME Section XI, 1989 Edition with no addenda is impractical for the Third Period of the Second 10 Year Inspection Interval and therefore requests relief.
I.
System/Components for Which the Relief is Requested:
Category B-J Full Penetration Welds of Nozzles in Vessels Branch Connection Welds-NPS 4 or Larger Item Numbers:
Catawba-2 B09.031.001, Weld #2NC11-WN7 and B09.031.002, Weld #2NC11-WN8 Catawba-1 B09.031.002, Weld #INC22-WN8 Scheduled for EOC 15 (Outage 7)
II.
Code Requirements:
- 1.
ASME Section XI, Table IWB-2500-1 Examination Category B-J, Pressure Retaining Welds In Piping, Figure IWB-2500-11 Examination Volume C-D-E-F.
- 2.
ASME Section XI, Appendix III, III-2200 Personnel Requirements, III-2200 (b).
III. Code Requirement for Which Relief is Requested:
Relief is requested from the requirement to perform a volumetric examination of volume C-D-E-F as shown in Figure IWB-2500-11 for the above referenced branch connection welds.
IV.
Basis for Relief:
ASME Section XI, Appendix III, III-2200 (b) requires personnel who perform recording or determine which indications are to be recorded to successfully complete the qualification require-ments of IWA-2300 using the examination procedure for UT of Piping.
"The qualification shall include demonstrated profi-ciency in discriminating between flaw indications and indications of geometric or metallurgical origin."
The wrought austenitic stainless steel pressurizer surge line branch connection welds join centrifugally cast stainless steel main coolant piping to forged stainless steel nozzles.
Page 2 of 3 The only access for examination is from the main loop piping side of the welds (See attachments).
Demonstration of the ultrasonic procedure was attempted using a mock-up of similar materials with known flaws (thermal fatigue cracks).
The flaw depths used in the mock-up were in the range of flaw depths required by ASME Section XI, Appendix VIII, Supplement 2, 1995 Edition with the 1996 Addenda.
The cracks could not be detected using refracted longitudinal, dual element, lMHz probes. Techniques using these probes are considered the best available for examination of welds in cast stainless steel piping.
Therefore, Duke Energy Corporation concludes that no effective ultrasonic examination can be performed on these welds.
Alternative Examination:
There is no volumetric examination alternative.
There is no access to the inside surfaces of the welds and radiography cannot be performed because of the weld joint geometry.
As an alternative, Duke Energy Corporation proposes to use the Code required surface examination, Liquid Penetrant and the VT-2 examination performed during system pressure tests as an alternative to the volumetric examination.
V.
Justification for Granting Relief:
The nozzles connected to the main coolant loop piping are made of forged SA-182 type 316 stainless steel. The main coolant loop piping is SA-351 CF8A centrifugally cast stainless steel.
These welds were nondestructively examined during fabrication and subsequent inservice inspections in the First 10 Year Inspection Interval. No flaws were detected.
Duke Energy will use Code required pressure testing, Liquid Penetrant examination and VT-2 visual examination in lieu of the Code required volumetric examination.
These examinations will provide adequate assurance of pressure boundary integrity.
In addition to the above Code required examinations (surface and pressure test), there are other activities which provide a high level of confidence that, in the unlikely case that leakage greater than 1.0 gpm did occur through these areas/welds, it would be detected and corrected.
Specifically, leakage from these areas/welds would be detected by the Reactor Coolant System (RCS) mass balance / system leakage calculation which is performed at least once every three days under procedure PT/i, 2/A/4150/OID, "NC System Leakage Calculation".
This RCS leakage calculation is a
Page 3 of 3 requirement of Technical Specification 3.4.13, "RCS Operational Leakage".
Leakage is also evaluated in accordance with Technical Specification 3.4.15, RCS Leakage Detection Instrumentation. The leakage could be detected through several methods. These include the Reactor Building air particulate monitor, the Iodine monitor, and gaseous monitor, which are capable of detecting any fission products released from coolant leakage.
Others include the level indicator in the Reactor Building normal sump, the level indicator in the Ventilation Unit Condensate Drain Tank, and a loss of level in the Volume Control Tank.
This will provide reasonable assurance of weld/component integrity.
VI.
Implementation Schedule:
Duke Energy will continue to perform liquid penetrant, pressure testing and VT-2 examinations scheduled during the remainder of the Catawba Unit 1 and 2, Second 10 Year Interval Inservice Inspection.
Stephen L. Mays from Catawba Engineering provided input to Section V.
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Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Percent Coverage Scan # Angle Direction (sq.in.)
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Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Percent Coverage Scan # Angle Direction (sq.in.)
(in.)
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Total Aggregate Coverage 48.10 See attached calculations for loss of coverage. This has been converted to % of coverage above.
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CABLES Search Unit #
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