ML20148E000

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Forwards SER Re 960724 Request Relief from Volumetric Exam Coverage Requirements of ASME Code,Section XI,1989 Edition, for Certain Welds in SG & in Letdown Cooler Heat Exchangers for Oconee Units 1,2 & 3.Request Granted
ML20148E000
Person / Time
Site: Oconee  Duke energy icon.png
Issue date: 05/29/1997
From: Berkow H
NRC (Affiliation Not Assigned)
To: Hampton J
DUKE POWER CO.
Shared Package
ML16141B206 List:
References
TAC-M96201, TAC-M96202, TAC-M96203, NUDOCS 9706020221
Download: ML20148E000 (3)


Text

MAY 29, 1997

- " Mr. J. W. Hampten Vice Presid:nt, Oconee Site Duke Power Company P. O. Box 1439 Seneca, SC 29679

SUBJECT:

REQUEST FOR RELIEF N0. 96-02, THIRD TEN-YEAR INSERVICE INSPECTION INTERVAL - OCONEE NUCLEAR STATION UNITS 1, 2, AND 3 (TAC NOS.

M96201, M96202, AND M96203)

Dear Mr. Hampton:

By letter dated July 24, 1996, and supplemented by letter dated April 1, 1997, Duke Power Company requested relief from the volumetric examination coverage requirements of the ASME Code, Section XI,1989 Edition; for certain welds in the steam generators and in the letdown cooler heat exchangers for the Oconee Nuclear Station, Units 1, 2, and 3. The staff's evaluation and conclusions 4

are contained in the enclosed Safety Evaluation.

The staff has reviewed the licensee's Request for Relief No. 96-02, Revision 1 (which uses Oconee Nuclear Station Unit 2 as the basis and was extended to include Units 1 and 3), concerning the limited volumetric examination that is complemented by the VT-2 visual examination of the subject welds, and has concluded that it provides reasonable assurance of a leak-tight pressure boundary and hence, an operational readiness for each of the components. Compliance with the Code requirements are impractical due to weld geometry and/or interference. If the Code requirements were imposed, the components would have to be redesigned and installed, which would impose a significant burden on the licensee. Therefore, the requested relief from the Code requirement is granted for Unit 2, pursuant to 10 CFR 50.55a(g)(6)(i).

It is also granted, pursuant to 10 CFR 50.55a(g)(6)(i) for the identical welds in Units 1 and 3, provided that the volumetric examination percentage of the identical welds in these units remain at least equal to or greater than the corresponding percentages described in this relief request. In addition, the Code-required hydrostatic test will be performed at 1.25 times the system design pressure. The requested relief is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.

Sincerely, ORIGINAL SIGNED BY:

d$ T D W e9d i Pa Herbert N. Berkow, Director aWs 2 F FS W U U b7 Project Directorate II-2 9706020221 970529 Division of Reactor Projects - I/II hDR ADOCK0500g9 Office of Nuclear Reactor Regulation }l Docket Nos. 50-269, 50-270 and 50-287 f)

Enclosure:

Safety Evaluation i

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May 29,1997 Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. O. Box 1439 Seneca, SC 29679

SUBJECT:

REQUEST FOR RELIEF N0. 96-02, THIRD TEN-YEAR INSERVICE INSPECTION INTERVAL - OCONEE NUCLEAR STATION UNITS 1, 2, AND 3 (TAC NOS. ,

M96201, M96202, AND M96203) l

Dear Mr. Hampton:

l By letter dated July 24, 1996, and supplemented by letter dated April 7, 1997, 1 Duke Power Company requested relief from the volumetric examination cesrage j requirements of the ASME Code, Section XI, 1989 Edition, for certain welds in the steam generators and in the letdown cooler heat exchangers for the Oconee l Nuclear Station, Units 1, 2, and 3. The staff's evaluation and conclusions are contained in the enclosed Safety Evaluation.

The staff has reviewed tne licensee's Request for Relief No. 96-02, Revision 1 (which uses Oconee Nuclear Station Unit 2 as the basis and was extended to include Units 1 and 3), concerning the limited volumetric examination that is complemented by the VT-2 visual examination of the subject welds, and has concluded that it provides reasonable assurance of a leak-tight pressure boundary and hence, an operational readiness for each of the components. Compliance with the Code requirements are impractical due to weld geometry and/or interference. If the Code requirements were imposed, the components would have to be redesigned and installed, which would impose a significant burden on the licensee. Therefore, the requested relief from the Code requirement is granted for Unit 2, pursuant to 10 CFR 50.55a(g)(6)(i).

It is also granted, pursuant to 10 CFR 50.55a(g)(6)(1) for the identical welds in Units 1 and 3, provided that the volumetric examination percentage of the identical welds in these units remain at least equal to or. greater than the corresponding percentages described in this relief request. In addition, the Code-required hydrostatic test will be performed at 1.25 times the system design pressure. The requested relief is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.

Sincerely,

[dt":A. l Herbert 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/ enc 1: See next page

Oconee Nuclear Station j Units 1, 2, and 3 i

cc:

Mr. Paul R. Newton Mr. J. E. Burchfield Legal Department (PB05E) Compliance Manager

Duke Power Company Duke Power Company 422 South Church Street Oconee Nuclear Site
Charlotte, North Carolina 28242-0001 P. O. Box 1439 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. O. Box 629 Framatome Technologies Raleigh, North Carolina 27602
Suite 525 1700 Rockville Pike Mr. G. A. Copp Rockville, Maryland 20852-1631 Licensing - EC050 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 Senior Resident Inspector U. S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Regional Administrator, Region II U. S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 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 Mr. Dayne H. Brown, Director Division of Radiation Protection North Carolina Department of Environment, Health and Natural Resources P. O. Box 27687 Raleigh, North Carolina 27611-7687