ML16134A633
| ML16134A633 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/01/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 7904030412 | |
| Download: ML16134A633 (3) | |
Text
DISTRIBUTION:
UD5cket File NRC PDR Docket No. 50-287 L PDR ORB#4 Rdg ACRS (16)
NRR Rdg BGrimes RReid TJiarter Mr. William 0. Parker, Jr.
Rlngram Gray File Vice President - Steam Production MFairtile Duke Power Company CelD P. 0.
Box 2178 Charlotte, North Carolina 28242 R & E (5)
RVollmer TERA
Dear Mr. Parker:
JRa JRBuchanan RE: OCONEE NUCLEAR STATION UNIT NO. 3 Currently you are administratively applying revised reactor coolant pressure-temperature limits at your facility which reflect the possible use of an atypical weld wire in the reactor vessel welds.
Babcock & Wilcox has continued their investigation of this possible, problem and all evidence developed to date strengthens our belief that the likelihood that atypical weld wire was actually used in reactor vessels is very low. Further information, including effects of radiation on the atypical material is scheduled to be submitted within the next several months.
Nevertheless, we believe that pending final resolution of this-matter, expected by June 1979, continued administrative application-of the revised limits is appropriate.
Sincerely, O)rIgifl31 sgnefd Y Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors cc:
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'q,0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 1, 1979 Docket No. 50-287 Mr. William 0. Parker, Jr.
Vice President - Steam Production Duke Power Company P. 0. Box 2178 Charlotte, North Carolina 28242
Dear Mr. Parker:
RE: OCONEE NUCLEAR STATION UNIT NO. 3 Currently you are administratively applying revised reactor coolant pressure-temperature limits at your facility which reflect the possible use of an atypical weld wire in the reactor vessel welds.
Babcock & Wilcox has continued their investigation of this possible problem and all evidence developed to date strengthens our belief that the likelihood that atypical weld wire was actually used in reactor vessels is very low. Further information, including effects of radiation on the atypical material is scheduled to be submitted within the next several months.
Nevertheless, we believe that pending final resolution of this matter, expected by June 1979, continued administrative application of the revised limits is appropriate.
Sincerely, Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors cc:
See next page
Duke Power Company cc:
Mr. William L. Porter Duke Power Company Post Office Box 2178 422 South Church Street Charlotte, North Carolina 28242 J. Michael McGarry, III, Esquire DeBevoise & Liberman 700 Shoreham Building 806 15th Street, N.W.
Washington, D. C. 20005 U. S. Nuclear Regulatory Commission Region II Office of Inspection and Enforcement ATTN:
Mr. Francis Jape' 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Oconee Public Library 201 South Spring Street Walhalla, South Carolina 29691