ML040860266

Technical Specification, Safety Limit Minimum Critical Power Ratio Values in Technical Specification 1.1.A.1 to Incorporate Results in cycle-specific Core Reload Analysis for Cycle 24 Operation

ML040860266
Person / Time
Site:	Vermont Yankee
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 2.1 FUEL CLADDING INTEGRITY Applicability: Applicability:

Applies to the interrelated Applies to trip setting of the variable associated with fuel instruments and devices which are thermal behavior. provided to prevent the nuclear system safety limits from being exceeded.

Objective: Objective:

To establish limits below which To define the level of the process the integrity of the fuel variable at which automatic cladding is preserved. protective action is initiated.

Specification:

Specification:

A. Trip Settings A. Bundle Safety Limit (Reactor Pressure >800 psia and Core The limiting safety system Flow >10% of Rated) trip settings shall be as specified below:

When the reactor pressure is

>800 psia and the core flow is 1. Neutron Flux Trip Settings greater than 10% of rated:

a. APRM Flux Scram Trip

1. A Minimum Critical Power Setting (Run Mode)

Ratio (MCPR) of less than 1.07 (1.09 for Single Loop When the mode switch I Operation) shall constitute is in the RUN violation of the Fuel position, the APRM Cladding Integrity Safety flux scram trip Limit (FCISL). 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