ML19317F077
| ML19317F077 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/11/1973 |
| From: | Murphy C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Thornburg H US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19317F074 | List: |
| References | |
| NUDOCS 8001080767 | |
| Download: ML19317F077 (1) | |
Text
UNITED ST/JTES
,A f ~ ~g ATOMIC ENERGY COMMISSION DIRECTORATE OF REGUINICRY OPERATIONS
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- h. D. Thornburg, Chief, Field Support and Enforcement Branch Directorate of Regulatory Operations, Headquarters DUKE POWER COMPANY (OCONEE 1), LICENSE NO. DPR-38, DOCKET NO. 50-269 -
EVALUATION OF THE EFFECTS OF REACTOR COOLANT FLOW IN EXCESS OF SAR VALUES Tests at Oconee 1 have revealed that the reactor coolant flow exceeds design flow by 10.8 percent. This discrepancy has been carried as unresolved item No. 73-4/1 in RO Inspection Report No. 50-269/73-4.
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According to preliminary information received from the licensee, the only basis for an upper limit to the design flow is the end-of-life (EOL) spring constant of the fuel assembly holddown spring.
Because of uncertainties of measuring flows, the licensee stated that flow measurements would be refined at 40 percent and 75 percent power levels and agreed to submit a report at the conclusion of the test at '
the 75 percent power level.
The licensee submitted the report to the Directorate of Licensing relating to the coolant flow measurements and the effects of the excess flow on August 23, 1973. A copy of this report is enclosed.
Preliminary evaluations of the Oconee Unit 2 HFT flow measurements indicate that the coolant flow may also be higher than the SAR value for Unit 2 even though the Unit 2 reactor coolant pumps are of different manufacture.
Other Babcock and Wilcox facilities, thus may also have flows higher than design values.
Would you please contact Licensing and ascertain if the licensee's report is acceptable to them and advise us so that we will know whether further action is required.
.s
- C. E. Murphy, lef Facilities Test and Startup RO:II CEM Branch
Enclosure:
As stated i
cc: DR Central Files l
RO:HQ Files 80010807&7
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