ML20203F013

Proposed Tech Specs Revising Current Value for SLMCPR for Cycle 20,next Operating Cycle

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: BVY-97-165, Application for Amend to License DPR-28,revising Current Value for SLMCPR for Cycle 20,next Operating Cycle. Proprietary Summary of Plant SLMCPR Evaluation for Cycle 20, Encl.Proprietary Info Withheld,Per Encl GE Affidavit ML20203F013
References
NUDOCS 9712170263
Download: ML20203F013 (3)

Text

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WNPS 1.1 CATETY LIMIT 2.1 LIMI' RING SAFETY SYSTEM SF.TTING F"JEL CLADDING I*f7EGRITY 2.1 FUEL CLi_nnING Iiur.6RITY

1.1 Aeolicability

Aeolicability:

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.

Obiective Obiective:

To establish limits below which To define the level of the process varia,le at which the integrity c' the fuel cladding is preserved, automatic protective action is initiated.

Specification:

Speciflection:

_ Bundle S.afety Limit (Peactor A. Trio settines A.

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, For the Cycle e c. APRM Flux Scram Trio

1. fer1}ne (Run Mode) loading, the ex sience f' g When the mode switch of a Minimum Power Ratio _(MCPR)Critical 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 to 48 x 10 6 I

P PDR I

lbs/hr core L flow 6

Amendment No. H, 44, 64, H, 94, H9,150

1 . .

Ys:HstON1 YAus.1 Nt'ci.e.ru l'ows.u Cout'on usoN s- .,

- Vermont Yankee Nuclear Power Corp.-

Docket No. 50-271 '

BW 97-165 Page 1 of 2 Attachment 4 Proposed Chance No.196 '

Revised Technical Specification Pane  ;

1 4

s COttFRMNP%%MC9R %%'O

, l VYNPS i l

'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

1. For the Cycle 20 core a. APRM Flur Scram Trip l

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 i to 48 x 10 6 lbs/hr core

! flow l Amendment No, 44, 44, 64, 99, 94, 149, +50, 6 l

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