ML16141B017

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Forwards Safety Evaluation Re Licensee Third 10-yr Interval ISI Request for Relief 95-94
ML16141B017
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 05/03/1996
From: Berkow H
NRC (Affiliation Not Assigned)
To: Hampton J
DUKE POWER CO.
Shared Package
ML16141B018 List:
References
TAC-M93944, TAC-M93945, TAC-M93946, NUDOCS 9605070186
Download: ML16141B017 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION Ir WASHINGTON, D.C. 20555-0001 May 3, 1996 Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P.O. Box 1439 Seneca, SC 29679

SUBJECT:

OCONEE NUCLEAR STATION, UNIT 1 - THIRD TEN-YEAR INTERVAL INSERVICE INSPECTION REQUEST FOR RELIEF NO. 95-04 (TAC NOS. M93944, M93945, AND M93946)

Dear Mr. Hampton:

By letter dated October 5, 1995, you submitted Request for Relief No. 95-04 from certain ASME Code requirements that you determined to be impractical to perform at Oconee Nuclear Station, Units 1, 2, and 3, during the third 10-year interval inservice inspection. Supplemental information was provided in your submittal dated February 27, 1996. Relief was requested from the requirements of Section XI of the ASME Code to perform a volumetric examination of greater than 90 percent of the weld area for the specific welds covered by this request. Performance of the Code-required examination coverage is precluded by component interfaces. To meet the Code requirements, extensive design modifications would be necessary to provide access for examination. We note that in the case of Oconee Units 1 and 2, the percent of coverage obtainable for the subject welds was estimated based on examinations performed on equivalent Oconee Unit 3 components. If the actual examination coverage for Units 1 and 2 is less than this estimate, you must submit a new request for relief based on the actual coverage obtained.

The NRC staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory, has reviewed and evaluated your request and has concluded that certain requirements of the Code are impractical.

The staff has determined that the extent of coverage obtained for the specific welds covered by this request provides reasonable assurance of the structural reliability and operational readiness of the reactor pressure vessel welds and steam generator nozzle welds. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i),

for Unit 3, relief is granted as requested for Request for Relief 95-04 and, for Units 1 and 2, relief is granted provided that the examination coverage for welds at Units 1 and 2 is as much as that estimated using Unit 3 examinations. The staff's evaluation and conclusions are contained in the enclosed Safety Evaluation. This relief is authorized by law and will not 9605070186 9-60-503

'LECENTER cc PDR ADOCK 05000269 P

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Mr. J. May 3, 1996 endanger life or property or the common defense and security, and is otherwise in the public interest, giving due consideration to the burden that could result if the requirements were imposed on your facility.

Sincerely, Original signed by:

Herbert N. Berkow, Director Project Directorate 11-2 Divisionof Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270 and 50-287,

Enclosure:

Safety Evaluation cc w/encl:

See next page DISTRIBUTION:

Docket File PUBLIC PDH1-2 R/F SVarga JZwolinski HBerkow LBerry DLaBarge OGC, 0-15 B18 GHill (6), T-5C3 ACRS, TWF GTracy, 0-17 G21 EMerschoff, RH RCrlenjak, RII

  • See previous concurrence To receive a copy of this document, indicate in the box:

"C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" No copy OFFICE LA:PD22: R E P D

P D:P OGC*

NAME LBERRY V

cDLABAR dw HBEAKO MYoung DATE 2-/96

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_4/29/96 DOCUMENT NAME: G:\\OCONEE\\RR9504 OFFICIAL RECORD COPY

Mr. J.

May 3, 1996 endanger life or property or the common defense and security, and is otherwise in the public interest, giving due consideration to the burden that could result if the requirements were imposed on your facility.

Sincerely, He bert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects -

I/II Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270 and 50-287

Enclosure:

Safety Evaluation cc w/encl:

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, SouthCarolina 29201 County Supervisor of Oconee County Walhalla, South Carolina 29621