ML040860266
| ML040860266 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/22/2004 |
| From: | Richard Ennis NRC/NRR/DLPM/LPD1 |
| To: | Kansler M Entergy Nuclear Operations |
| References | |
| TAC MC1842 | |
| Download: ML040860266 (1) | |
Text
VYNPS 1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING 1.1 FUEL CLADDING INTEGRITY Applicability:
Applies to the interrelated variable associated with fuel thermal behavior.
Objective:
To establish limits below which the integrity of the fuel cladding is preserved.
Specification:
A.
Bundle Safety Limit (Reactor Pressure >800 psia and Core Flow >10% of Rated)
When the reactor pressure is
>800 psia and the core flow is greater than 10% of rated:
I
- 1. A Minimum Critical Power Ratio (MCPR) of less than 1.07 (1.09 for Single Loop Operation) shall constitute violation of the Fuel Cladding Integrity Safety Limit (FCISL).
2.1 FUEL CLADDING INTEGRITY Applicability:
Applies to trip setting of the instruments and devices which are provided to prevent the nuclear system safety limits from being exceeded.
Objective:
To define the level of the process variable at which automatic protective action is initiated.
Specification:
A. Trip Settings The limiting safety system trip settings shall be as specified below:
- 1. Neutron Flux Trip Settings
When the mode switch is in the RUN position, the APRM flux scram trip setting shall be as shown on Figure 2.1.1 and shall be:
S<0.66(W-AW)+54%
where:
S = setting in percent of rated thermal power (1593 Wit)
W percent rated two loop drive flow where 100%
rated drive flow is that flow equivalent to 48 x 106 lbs/hr core flow Amendment No. 44, 44, 44, 9.G4, 94, 4--9, 4G4, 4-54, F4, 217 6