ML20117P311
| ML20117P311 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 09/17/1996 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20117P310 | List: |
| References | |
| NUDOCS 9609230060 | |
| Download: ML20117P311 (1) | |
Text
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. - - - -.- ~__
l e
VYNPS 4
l 1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING I
l 1
l 1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY l
Applicability:
Apolicability:
l l
Applies to the interrelated Applies to trip setting of the
. variable associated with fuel instruments and devices which thermal behavior.
are provided to prevent the i
nuclear system safety limits from being exceeded.
Obiective:
Obiective:
To establish limits below which To define the level of the the integrity of the fuel process variable at which I
cladding is preserved.
automatic protective action is initiated.
Specification:
Specification:
l A.
Bundle Safety Limit (Reactor A.
Trio Settinos i
Pressure >800 osia and Core Flow >10% of Rated)
The limiting safety system trip settings shall be as When the reactor pressure is specified below:
>800 psia and the core flow l
is greater than 10% of 1.
Neutron Flux Trio
(
rated:
Settinos 1.
For the Cycle 19 core a.
loading, the existence Settino (Run Mode) of a Minimum Critical l
Power Ratio (MCPR) of When the mode switch l
l l
less than 1.10 (1.12 for is in the RUN i
l Single Loop Operation) position, the APRM l
shall constitute flux scram trip violation of the Fuel setting shall be as Cladding Integrity shown on Safety Limit (FCISL).
Figure 2.1.1 and l
Core loadings subsequent shall be:
l to Cycle 19 will require l
recalculaticn of the S_g0.66(W-AW)+54%
MCPR.
where:
S = setting in percent of l
rated thermal power (1593 MWt)
W = percent rated two loop drive flow where 4
100% rated drive flow is that 9609230060 960917 flow 4
PDR ADOCK 05000271 equivalent 6
P PDR to 48 x 10 lbs/hr core flow Amendment No. M, 44, 64, 90, 94, M9, 6
.