ML19210E383
| ML19210E383 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/27/1979 |
| From: | Richard Bright FLORIDA POWER CORP. |
| To: | Fairtile M Office of Nuclear Reactor Regulation |
| References | |
| 3--3-E, 3-0-3-E, TAC-11945, NUDOCS 7912040441 | |
| Download: ML19210E383 (2) | |
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Florida Power CORPOnaYs'e November 27, 1979 File Code:
3-0-3-e Mr. Morton B.
Fairtile Project Manager Operating Reactors Branch No. 4 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555 Subjcct: Crystal River - Unit 3 Docket No. 50-302 Operating License No. DPR-72 Technical Specification Change Request No. 35
Dear Sir:
In our meeting of November 15, 1979, you requested confirmation as to the derivation of the maximum allowable nuclear overpower trip setpoints presently in Table 3.7-1 of the Crystal River - Unit 3 Technical Speci-fications.
In going back to our preoperational documentation, it was discovered that these allowable setpoints were derived using the equa-tion in the bases of Specification 3/4. 7.1.1, with the exception that 100.0% was used as the nuclear overpower trip setpoint, instead of the 105.5% nuclear overpower trip setpoint, as is specified in Table 2.2.1 of the Technical Specifications.
If a nuclear overpower trip setpoint of 100.0% is used in this equation, the maximum allowable nuclear overpower trip setpoint for one inoperable safety valve on any steam generator becomes 85.75% of rated thermal pow-er.
This number was then rounded-down to 85% so that it would be an in-teger.
Subsequently, because 100.0% was used in the equation, and with one valve inoperable, the maximum allowable setpoirt was reduced by 15%,
the trip setpoint for two inoperable safety valves was reduced by 30%,
which results in a maximum allowable setpoint of 70%.
For three inoper-able safety valves then, the maximum allowable nuclear overpower trip setpoint was determined to be 55% (100% -(3 x 15%)).
This should clear up the confusion as to the differences between the setpoints in Table 3.7-1 of the CR-3 Technical Specifications and the y
equation in the bases of that specification, which was supposed to have i
7 0120 4 0 M/
l474 553 General Office 3201 in rty.iourtn street soutn. P O Box 14042. St Petersburg Fionda 33733 813 - 866 515i
..o Mr. Morton B.
Fairtile Page Two November 27, 1979 been used to determine these setpoints.
The setpoints in our Technical Specification Change Request No. 35 were derived from the equation that is in the bases of that Specification in Change Request No. 35.
Fur-ther, the setpoints in Change Request No. 35, are based on a 100% Rated Thermal Power of 2544 MW. Therefore, they are conservative for a Rated t
Thermal Power of 2452 MW, and do not need to be revised when the power e
upgrade is granted by the IRC.
If you have any further questions on this subject, please do not hesi-tate to contact me.
Very truly yours, FLORIDA POWER CORPORATION Ronald M.
Bright Senior Radiological Licensing Eng*
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