ML16141A872
| ML16141A872 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/09/1995 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | Hampton J DUKE POWER CO. |
| Shared Package | |
| ML16141A873 | List: |
| References | |
| TAC-M91054, TAC-M91055, NUDOCS 9502270156 | |
| Download: ML16141A872 (3) | |
Text
Fo ary 9, 1995 Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, South Carolina 29679
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1 AND 2 - SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION REQUEST FOR RELIEF NO. 93-11 (TAC NOS. M91054 AND M91055)
Dear Mr. Hampton:
By letter dated November 10, 1993, Duke Power Company submitted Request for Relief No. 93-11 from certain ASME Code requirements that you determined to be a hardship or unusually difficult to perform at Oconee Nuclear Station, Units 1 and 2, during the second 10-year interval inservice inspection. Additional information was provided in letters dated May 17 and 24, 1994. Specifically, relief was requested from the periodic hydrostatic pressure test for the ASME Class 3 sections of feedwater piping supplying the main feedwater for each steam generator. In lieu of the Code-required test, approval was requested to perform a visual examination with the system at normal operating pressure.
The NRC staff has reviewed and evaluated your request, and has determined that performance of the Code-required testing would impose an undue hardship or unusual difficulty without a compensating increase in the level of quality and safety due to the inability to isolate portions of the Class 3 feedwater piping from the steam generators. The staff has concluded that your proposed alternative examination of the welds will provide reasonable assurance of the structural reliability of this section of feedwater piping, and is authorized purusuant to 10 CFR 50.55a(a)(3)(ii). The staff's evaluation and conclusions are contained in the enclosed Safety Evaluation.
Sincerely,
/s/
Herbert N. Berkow, Director Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation Docket Nos. 50-269 DISTRIBUTION:
JZwolinski and 50-270 Docket-File ens
Enclosure:
PUBLIC 5
Safety Evaluation PDII-3 R/F GC, 0-15 B18 SVarga ACRS (4), TWF cc w/enclosure:
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WASHINGTON, D. C. 20555 February 9, 1995 Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, South Carolina 29679
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1 AND 2 - SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION REQUEST FOR RELIEF NO. 93-11.
(TAC NOS. M91054 AND M91055)
Dear Mr. Hampton:
By letter dated November 10, 1993, Duke Power Company submitted Request for Relief No. 93-11 from certain ASME Code requirements that you determined to be a hardship or unusually difficult to perform at Oconee Nuclear Station, Units 1 and 2, during the second 10-year interval inservice inspection. Additional information was provided in letters dated May 17 and 24, 1994. Specifically, relief was requested from the periodic hydrostatic pressure test for the ASME Class 3 sections of feedwater piping supplying the main feedwater for each steam generator. In lieu of the.Code-required test, approval was requested to perform a visual examination with the system at normal operating pressure.
The NRC staff has reviewed and evaluated your request, and has determined that performance of the Code-required testing would impose an undue hardship or unusual difficulty without a compensating increase in the level of quality and safety due to the inability to isolate portions of the Class 3 feedwater piping from the steam generators. The staff has concluded that your proposed alternative examination of the welds will provide reasonable assurance of the structural reliability of this section of feedwater piping, and is authorized purusuant to 10 CFR 50.55a(a)(3)(ii). The staff's evaluation and conclusions are contained in the enclosed Safety Evaluation.
Sincerely, erbert N. Berkow, Director Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation Docket Nos. 50-269 and 50-270
Enclosure:
Safety Evaluation cc w/enclosure:
See next page
Mr. J. W. Hampton Duke Power Company Oconee Nuclear Station cc:
A. V. Carr, Esquire Mr. Ed Burchfield Duke Power Company Compliance 422 South Church Street Duke Power Company Charlotte, North Carolina 28242-0001 Oconee Nuclear Site P. 0. Box 1439 J. Michael McGarry, III, Esquire Seneca, South Carolina 29679 Winston and Strawn 1400 L Street, NW.
Ms. Karen E. Long Washington, DC 20005 Assistant Attorney General North Carolina Department of Mr. Robert B. Borsum Justice Babcock & Wilcox P.0. Box 629 Nuclear Power Division Raleigh, North Carolina 27602 Suite 525 1700 Rockville Pike Mr. G. A. Copp Rockville, Maryland 20852 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