ML16134A677

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Advises That Review of Info on Mods to Emergency Feedwater Sys & Repairs Made to once-through Steam Generators Complete.Plant May Resume Operation W/Listed Conditions
ML16134A677
Person / Time
Site: Oconee 
Issue date: 09/29/1982
From: Lainas G
Office of Nuclear Reactor Regulation
To: Tucker H
DUKE POWER CO.
Shared Package
ML16134A678 List:
References
NUDOCS 8210210292
Download: ML16134A677 (3)


Text

September 29, 12 DISTRI.BUTION:

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Docket No. 50-287 ADe Agazio DBrinkman AHafiz OELD CMiles AEOD ASLAB IE TBarnhart-12 Mr. Hal B. Tucker ACRS-10 OParr Vice President - Nuclear Production Duke Power Company P. 0. Box 33189 422 South Church Street Charlotte, North Carolina 28242

Dear Mr. Tucker:

SUBJECT:

ONCE-THROUGH STEAM GENERATOR (SG) REPAIR AND EMERGENCY FEEDWATER (EFW) SYSTEM MODIFICATION - SAFETY EVALUATION REPORT The NRC has completed its review and evaluation of your submittals dated May 14, June 14, August 27 and September 10, 1982. These sub mittals provide information relative to modifications Duke Power Company has made to the EFW system and repairs made to the once-through SGs of the Oconee Nuclear Station, Unit 3. These submittals also provide responses to our.letter of June 23, 1982, pursuant to the provisions of 10 CFR 50.54(f).

We have concluded, based on our evaluation of your submittals fn our enclosed Safety Evaluation Report that it is acceptable for Duke Power Company to resume power operation at the Oconee Nuclear Station, Unit 3 provided:

1) the minimum flow test veri-fies acceptable minimum flow,
2) an acceptable water hammer test verifies no water hammer, and 3) an inspection of the stabilized internal header is performed at each of the next two refueling outages and the next 10 year Inservice Inspection. We request that you submit confirmation of the above tests within 30 days of their completion.

Si ncerely, G.C. Ltana/

Gus C. Lainas, Assistant Director 8210210292 820929 for Operating Reactors PDR ADOCK 05000287 Division of Licensing P

PDR

Enclosure:

Safety Evaluation Report cc w/enclosure:

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DATE FORM.318.(040)

OFFCIA RECORD* COPY 191-35-9.0 NRc FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD CO PY USGPO: 1981-335-960

Duke Power Company cc w/enclosure(s):

Mr. William L. Porter Duke Power Company P. 0. Box 33189 422 South Church Street Office of Intergovernmental Relations Charlotte, North Carolina 28242 116 West Jones Street Raleigh, North Carolina 27603 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission, Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Regional Radiation Representative EPA Region-IV 345 Courtland Street, N.E.

Atlanta, Georgia 30308 William T. Orders Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 J. Michael McGarry, III, Esq.

DeBevoise & Liberman 1200 17th Street, N.W.

Washington, D. C. 20036

UNITED STATES NUCLEAR REGULATORY CO SSION WASHINGTON, D. C. 20555 September 29, 1982 Docket No. 50-287 Mr.

al B. Tucker Vice esident - Nuclear Production Duke Po r Company P. 0. Box 33189 422 South urch Street Charlotte, N th Carolina 28242

Dear Mr. Tucker:

SUBJECT:

ONCE-THROUGH STEAM GENERATOR (SG) REPAIR AND EMERGENCY FEEDWATER IFW) SYSTEM MODIFICATION'- SAFETY EVALUATION REPORT The NRC has completed i review and evuation of your submittals dated May 14, June 14, A 'ust 27 and September 10, 1982. These sub mittals provide informationirelative o modifications Duke Power Company has made to the EFW system and repapirs made to the once-through SGs of the Oconee Nuclear Station, Unt 3' These submittals also provide responses. to our letter of. June 23, 1982, pursuant to the provisions of 10 CFR 50.54(f).

We have concluded, based on our evaluation of your submittals in our enclosed Safety Evaluatiop'Report that it is acceptable for Duke.Power Company to resume poweroperation at thOconee Nuclear Station, Unit 3 provided: 1) the minimum flow test veri fes acceptable minimum flow,

2) an acceptable water hammer test verifies no water hammer, and 3) an inspection of the stfbilized internal header is performed at each of the next two refueling outages and the next 10 year Inservice Inspection. We request that youfsubmit confirmation of the ab'bve tests within 30 days of their completion.

Sincerely, Gus C. Lainas, Asistant Director for Operating.Rea ors Division of Licensin

Enclosure:

Safety Evaluation Report cc w/enclosure:

See next page