ML16141A863
| ML16141A863 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/12/1995 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | Hampton J DUKE POWER CO. |
| Shared Package | |
| ML16141A864 | List: |
| References | |
| TAC-M85024, TAC-M85025, TAC-M85026, NUDOCS 9502030155 | |
| Download: ML16141A863 (3) | |
Text
January 12, 1995
,Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 - SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION REQUEST FOR RELIEF NO. 92-14 (TAC NOS. M85024, M85025, AND M85026)
Dear Mr. Hampton:
By letter dated November 24, 1992, Duke Power Company submitted Request for Relief No. 92-14 from certain ASME Code requirements that you determined to be impractical to perform at Oconee Nuclear Station, Units 1, 2, and 3, during the second 10-year interval inservice inspection. Relief is requested from the volumetric examination requirements of the inside radius of welds on the High Pressure Injection (HPI) Letdown Coolers. The Code-required examinations could not be performed due to the geometry of the cooler design.
The NRC staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory, has reviewed and evaluated the November 24, 1992, submittal and supporting information. The staff has concluded that certain requirements of the Code are impractical and that pursuant to 10 CFR 50.55a(g)(6)(i), relief may be granted as requested by Request for Relief 92-14. The staff has also concluded that your examination of the associated nozzle-to-vessel weld will provide reasonable assurance of the structural reliability for the HPI letdown cooler nozzle inside radius sections. The staff's evaluation and conclusions are contained in the enclosed Safety Evaluation. This 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, given due consideration to the burden that could result if the requirements were imposed on your facility.
Sincerely, Original signed by:
C7 f
Hrbert N. Berkow, Director Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270 DISTRIBUTION:
JZwolinski and 50-287 Docket Fi-e7 Wens "14PUBLIC
-LBerry
Enclosure:
Safety Evaluation PDII-3 R/F OGC, 0-15 B18 SVarga ACRS(4), TWE cc w/enclosure:
See next page HBerkow EMerschoff, Rh RSpessard, 0-9 A2 JLieberman, 0-7 H5 EJordan, T-4 D18 GHill (2), T-5 C23 OC/LFDCB T-9 ElO GTracy, 0-17 G21 To receive a copy of this document, indicate in the box:
"C" = Copy without attachment/enclosurq "E' = Copy with attachment/enclosure "N"
=No copyA OFFICE LA:PD23:DRPE E
PM:PD23:DRPE E
D:PD)23i E OGC E
NAME LBerry LWiens:cw HBerkL DATE
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/ 1,895 DOCUMENT NAME:
G:\\OCONEE\\RR214.cLTR DATE203/155/950//5112/9
/19 PDR ADOCK 05000269 P
_____PDR
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UNITED STATES Z
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-40001 January 12, 1995 Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 - SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION REQUEST FOR RELIEF NO. 92-14 (TAC NOS. M85024, M85025, AND M85026)
Dear Mr. Hampton:
By letter dated November 24, 1992, Duke Power Company submitted Request for Relief No. 92-14 from certain ASME Code requirements that you determined to be impractical to perform at Oconee Nuclear Station, Units 1, 2, and 3, during the second 10-year interval inservice inspection. Relief is requested from the volumetric examination requirements of the inside radius of welds on the High Pressure Injection (HPI) Letdown Coolers. The Code-required examinations could not be performed due to the geometry of the cooler design.
The NRC staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory,,has reviewed and evaluated the November 24, 1992, submittal and supporting information. The staff has concluded that certain requirements of the Code are impractical and that pursuant to 10 CFR 50.55a(g)(6)(i), relief may be granted as requested by Request for Relief 92-14. The staff has also concluded that your examination of the associated nozzle-to-vessel weld will provide reasonable assurance of the structural reliability for the HPI letdown cooler nozzle inside radius sections. The staff's evaluation and conclusions are contained in the enclosed Safety Evaluation. This 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, given due consideration to the burden that could result if the requirements were imposed on your facility.
c rely bert N. Berkow, Director roject Directorate 11-3 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/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 Caro.lina 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 - 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 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