ML20203F013
| ML20203F013 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 12/11/1997 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML19317C798 | List: |
| References | |
| NUDOCS 9712170263 | |
| Download: ML20203F013 (3) | |
Text
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WNPS 1.1 CATETY LIMIT 2.1 LIMI' RING SAFETY SYSTEM SF.TTING FUEL CLi_nnING Iiur.6RITY 1.1 F"JEL CLADDING I*f7EGRITY
2.1 Aeolicability
Aeolicability:
Applies to the interrelated Applies to trip setting of the instruments and devices which variable associated with fuel are provided to prevent the thermal behavior.
nuclear system safety limits from being exceeded.
Obiective:
Obiective To define the level of the To establish limits below which process varia,le at which the integrity c' the fuel automatic protective action is cladding is preserved, initiated.
Specification:
Speciflection:
A.
_ Bundle S.afety Limit (Peactor A.
Trio settines f.r. essure >800 osis and Core The limiting safety system Flow >104 of Rated) trip settings shall be as When the reactor pressure is specified below:
>800 psia and the core flow 1.
Neutron Flux Trio is greater than 10% of settines rated g,
1.
For the Cycle e
fer1}ne (Run Mode) loading, the ex sience of a Minimum Critical [
f' g When the mode switch Power Ratio _(MCPR) of is in the RUN
}
1ess thag(1,M (1r1@for position, the APRM
/. //
Single Loop Operation) flux scram trip shall constitute setting shall be as violation of the Fuel shown on Cladding Integrity Figure 2.1.1 and Safety Limit (FCISL).
shall.be:
Core load s subsequent to Cycle will require Sf_0.66(W-AW)+54%
recalcula on of the MCPR.
where:
S = setting in percent of rated
-thermal power (1593 MWt)
W = percent rated two loop drive flow where 100% rated l
drive flow is that 9712170263 971211 flow POR ADOCK 05000271 equivalent 6 I
P PDR to 48 x 10 I
lbs/hr core L
flow 6
Amendment No. H, 44, 64, H, 94, H9,150
Ys:HstON1 YAus.1 Nt'ci.e.ru l'ows.u Cout'on usoN
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- Vermont Yankee Nuclear Power Corp.-
Docket No. 50-271 BW 97-165 Page 1 of 2 Proposed Chance No.196 Revised Technical Specification Pane 1
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VYNPS i
'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 thermal behavior, are provided to prevent the nuclear system safety limits from being exceeded.
Obiectives Obiective:
To establish limits below which To define the level of the the integrity of the fuel process variable at which cladding is preserved, automatic protective action is initiated.
Fpecification:
Specification:
A.
Bundle _ Safety Limit (Reactor A.
Trip Settinos Pressure >800 psia and Core Flow >10% of Rated)
The limiting safety system trip Lettings shall be as When the reactor pressere is specified below:
>800 psia and the core flow is greater than 10% of 1.
Neutron Flux Trip rated:
Settinos l
1.
For the Cycle 20 core a.
APRM Flur Scram Trip loading, the existence Se,tting (Run Mode) of a Minimum Critical Power Ratio (MCPR) of When the mode switch l
less than 1.11 (1.13 for is in the RUN Single Loop Operation) position, the APRM 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 Core loadings subsequent shall be:
l to Cycle 20 will require recalculation of the S<0.66(W-AW)+54%
MCPR.
l where:
S = setting in percent of rated thermal power (1593 MWt)
W = percent rated two loop drive flow where 100% rated drive flow i
is that flow equivalent 6
i to 48 x 10 lbs/hr core flow l
Amendment No, 44, 44, 64, 99, 94, 149, +50, 6
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