ML19316A273
| ML19316A273 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/05/1977 |
| From: | Parker W DUKE POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912050844 | |
| Download: ML19316A273 (2) | |
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Re: Oconee Nuclear Station Docket Nos. 50-269, -270, -287
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Dear Sir:
My letter dated March 1, 1977, submitted in response to your letter of October 12, 1976, requested an amendment to the Oconee Nuclear Station Technical Specifications to provide for surveillance testing of the reactor internals vent valves. The proposed change to the Technical Specifications required opening force for the reactor internals vent valves equivalent to 1.0 psid. This change will have no significant ef fect on the peak cladding temperature during a LOCA. The large break LOCA analysis which is reported in BAW-10103, was reviewed and it was determined that, with the exception of the first 0.2 seconds of the reflooding phase of the accident, a pressure differential in excess of 1.0 psid was maintained across the vent valves. Therefore, the vent valves would remain fully open during reflooding, except for the first 0.2 seconds, even if the proposed 1.0 psid force was required. For the analysis in BAW-10103, the vent valves were always fully open.
T'us, the proposed change could only have a 0.2 second effect.
Even if it were assumed that the cladding would undergo an adiabatic heatup over the 0.2 interval, the peak cladding temperature would increase by only 7oF.
In actuality, the 0.2 second interval would be decreased by the rapid increase in upper plenum pressure which would occur with the vent valves closed. Additionally, over the 0.2 second delay, the heatup would not be adiabatic. The expected increase in cladding temperature would be only 3 F.
Thus, *he cladding temperatures reported in BAW-10103 are essentially unaffected by the proposed change.
Very truly yours, w A' ca &
William O. Parker, Jr.
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