ML17229A183

Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings

ML17229A183
Person / Time
Site:	Saint Lucie
Issue date:	12/20/1996
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17229A182	List: ML17229A181 ML17229A183 ML17229A184
References
NUDOCS 9612270074
Download: ML17229A183 (3)

Text

L-96-333 Attachment 3 ATTACHMENT3 ST. LUCIE UNIT 1 MARKED-UP TECHNICALSPECIFICATION PAGE Page,2-1 9612270074 96i220 VDR aDOCX OS000SS5 P PDR

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I I 2.0 SAFETY LIMITS ANO LIMITING SAFETY SYSTEN SETTINGS 2.1 SAFETY LIMITS p$gE g as&

~gL.f I REACTOR CORE 2.1.1 The combfnatfon of THERMAL PNER, pressurfzer pressure, and maxf-axan cold leg coolant temperature shall not exceed the lfmfts shown on Ff gure 2.1-1.

APPLICABILITY: MODES 1 and 2.

ACTION:

Whenever the point defined by the combfnatfon of maxfnam cold leg tetnper-ature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> .

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2750 psfa.

APPLICABILITY: MODES 1, 2, 3, 4 and 5.

ACTION:

MODES 1 and 2 Whenever the Reactor Coolant System pressure has exceeded 2750 psfa, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> .

MODES 3, 4 and 5 Whenever the Reactor Coolant System pressure has exceeded 2750 psfa, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.

Qt" L]= lE Amendment No.

ST. LUCIE - UNIT 1 2-1

L-96-333 Enclosure ENCLOSURE Siemens Power Corporation-Nuclear Division Report EMF-96-176, Revision 1 St. Lucie Unit 1 Small Break LOCA Analysis with 30% Steam Generator Tube Plugging December 1996