ML17229A183
ML17229A183 | |
Person / Time | |
---|---|
Site: | Saint Lucie ![]() |
Issue date: | 12/20/1996 |
From: | FLORIDA POWER & LIGHT CO. |
To: | |
Shared Package | |
ML17229A182 | List: |
References | |
NUDOCS 9612270074 | |
Download: ML17229A183 (3) | |
Text
L-96-333 ATTACHMENT3 ST. LUCIEUNIT1 MARKED-UPTECHNICALSPECIFICATION PAGE Page,2-1 9612270074 96i220 VDR aDOCX OS000SS5 P
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2.0 SAFETY LIMITS ANO LIMITINGSAFETY SYSTEN SETTINGS 2.1 SAFETY LIMITS REACTOR CORE
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2.1.1 The combfnatfon of THERMAL PNER, pressurfzer
- pressure, and maxf-axan cold leg coolant temperature shall not exceed the lfmfts shown on Ffgure 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 LOCAAnalysis with 30% Steam Generator Tube Plugging December 1996