ML15218A264
| ML15218A264 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/03/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | Hampton J DUKE POWER CO. |
| Shared Package | |
| ML15218A265 | List: |
| References | |
| TAC-M95292, NUDOCS 9605150354 | |
| Download: ML15218A264 (3) | |
Text
Mr. J. W. Hampton May 3, 1996 Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
STEAM GENERATOR 2A UPPER HEAD-TO-TUBESHEET WELD FLAW EVALUATION OCONEE NUCLEAR STATION UNIT 2 (TAC NO. M95292)
Dear Mr. Hampton:
On May 3, 1996, you submitted a report for NRC approval in accordance with Paragraph IWB-3610 of Section XI of the American Society of Mechanical Engineers (ASME) Code. This report contains your evaluation of flaw indications in the upper head-to-tubesheet weld in Steam Generator A from ultrasonic (UT) examinations conducted during the 1996 refueling outage at the Oconee Nuclear Station, Unit 2 (Oconee 2).
The examinations were performed in accordance with the requirements of the ASME Code,Section XI, 1989 Edition.
The report indicates that one UT indication from the upper head-to-tubesheet weld exceeds the allowable flaw size specified in IWB-3500 of Section XI of the ASME Code and requires flaw evaluation using IWB-3610 and Appendix A of the ASME Code.
As expained in the enclosed safety evaluation, we find the analysis acceptable. The flaw at the upper head-to-tubesheet weld has flaw depth of 0.8 inch. After considering flaw growth, your evaluation indicates that the flaw satisfied the fracture mechanics criteria of Paragraph IWB-3612 of Section XI of the ASME Code. Based on your evaluation, the weld is acceptable for service for the remainder of the plant's operating license. However, the area containing this flaw shall be reexamined during the next three inspection periods as required by IWB-2420 of the ASME Code.
Sincerely, Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation Docket No. 50-270 Distribution k
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BElli ot
Enclosure:
Safety Evaluation PUBLIC JCrlenjak, RII PDII-2 R/F KWichman cc:
See next page ACRS SVarga JZwolinski OGC To receive a copy of this document, indicate in the box:
"C" = Copy without attachment/enclosure "E"= Copy with attachment/enclosure "N" = No copy, 4
NAME 1tv LBerry 915 DLa a)Ikge H
ow DATE 5/9F/96 1 5 3/96
-/ /96
-OFFICIAL RECORD COPY 960 5354 960503 NRC FILE CENTUR COPY PDR ADOCK 05000270 P
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
- 0 May 3, 1996 Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
STEAM GENERATOR 2A UPPER HEAD-TO-TUBESHEET WELD FLAW EVALUATION OCONEE NUCLEAR STATION UNIT 2 (TAC NO. M95292)
Dear Mr. Hampton:
On May 3, 1996, you submitted a report for NRC approval in accordance with Paragraph IWB-3610 of Section XI of the American Society of Mechanical Engineers (ASME) Code. This report contains your evaluation of flaw indications in the upper head-to-tubesheet weld in Steam Generator A from ultrasonic (UT) examinations conducted during the 1996 refueling outage at the Oconee Nuclear Station, Unit 2 (Oconee 2).
The examinations were performed in accordance with the requirements of the ASME Code,Section XI, 1989 Edition..
The report indicates that one UT indication from the upper head-to-tubesheet weld exceeds the allowable flaw size specified in IWB-3500 of Section XI of the ASME Code and requires flaw evaluation using IWB-3610 and Appendix A of the ASME Code.
As explained in the enclosed safety evaluation, we find your analysis acceptable. The flaw at the upper head-to-tubesheet weld has flaw depth of 0.8 inch. After considering flaw growth, your evaluation indicates that the flaw satisfied the fracture mechanics criteria of Paragraph IWB-3612 of Section XI of the ASME Code. Based on your evaluation, the weld is acceptable for service for the remainder of the plant's operating license. However, the area containing this flaw shall be reexamined during the next three inspection periods as required by IWB-2420 of the ASME Code.
Sin rely, Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation Docket No. 50-270
Enclosure:
Safety Evaluation cc:
See next page
Mr. J. W. Hampton Duke Power Company Oconee Nuclear Station cc:
Mr. Paul R. Newton Mr. Ed Burchfield Legal Department (PB05E)
Compliance Duke Power Company Duke Power Company 422 South Church Street Oconee Nuclear Site Charlotte, North Carolina 28242-0001 P. 0. Box 1439 Seneca, South Carolina 29679 J. Michael McGarry, III, Esquire Winston and Strawn Ms. Karen E. Long 1400 L Street, NW.
Assistant Attorney General Washington, DC 20005 North Carolina Department of Justice Mr. Robert B. Borsum P. 0. Box 629 B&W Nuclear Technologies Raleigh, North Carolina 27602 Suite 525 1700 Rockville Pike Mr. G. A. Copp Rockville, Maryland 20852-1631 Licensing -
ECO50 Duke Power Company Manager, LIS 526 South Church Street NUS Corporation Charlotte, North Carolina 28242-0001 2650 McCormick Drive, 3rd Floor Clearwater, Florida 34619-1035 Dayne H. Brown, Director Division of Radiation Protection Senior Resident Inspector North Carolina Department of U. S. Nuclear Regulatory Commission Environment, Health and Route 2, Box 610 Natural Resources Seneca, South.Carolina 29678 P. 0. Box 27687 Raleigh, North Carolina 27611-7687 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 Atlanta, Georgia 30323 Max Batavia, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 County Supervisor of Oconee County Walhalla, South Carolina 29621