ML20073K016

Proposed Tech Specs Re Rated Thermal Power Level Increase

ML20073K016
Person / Time
Site:	Crystal River
Issue date:	09/30/1994
From:	FLORIDA POWER CORP.
To:
Shared Package
ML20073K013	List: 3F0994-08, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 199,Rev 0,increasing Rated Thermal Power Level ML20073K016
References
NUDOCS 9410070264
Download: ML20073K016 (3)

Text

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. ATTACHMENT 2 APPENDIX A CR-3 TECHNICAL SPECIFICATIONS 2 Pages i

9410070264 Y40930 PDR ADOCK 05000302 P PDR I

, Definitions 1.1 1.1 Definitions EFFECTIVE FULL POWER reactor core at RTP for one full day. (One EFPD is DAY (EFPD) 2568 MWt times 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or 61,632 MWhr.) l (continued)

EMERGENCY FEEDWATER The EFIC RESPONSE TIME shall be that time INITIATION AND CONTROL interval from when the monitored parameter (EFIC) RESPONSE TIME exceeds its Efl0 actuation setpoint at the channel sensor until the emergency feedwater equipment is capable of performing its safety function (i.e., valves travel to their required positions, pump discharge pressures reach their required values, etc.) Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval FEATURE (ESF) RESPONSE from when the monitored parameter exceeds its ESF TIME actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE, such as that from pump seals or valve packing, that is captured and conducted to collection systems or a sump or collecting tank; or

2. LEAKAGE into the containment atmosphere from sources that are both specifically located and quantified and known not to interfere with the operation of leakage detection systems and not to be pressure boundary LEAKAGE; or (continued)

Crystal River Unit 3 1.1-4 Amendment No.

Definitions 1.1 1.1 Definitions PHYSICS TESTS These tests are:

(continued)

a. Described in Chapter 13, " Initial Tests and Operation" of the FSAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

PRESSURE AND The PTLR is the unit specific document that TEMPERATURE LIMITS provides the reactor vessel pressure and REPORT (PTLR) temperature limits, including heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall

> be determined for each fluence period in accordance with Specification 5.6.2.19. Plant operation within these operating limits is addressed in LC0 3.4.3, "RCS Pressure and Temperature Limits."

QUADRANT POWER TILT QPT shall be defined by the following equation and (QPT) is expressed as a percentage.

=

Power In Any Core Quadrant QPT 100 ( Average Power of all Quadrants _y)

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 2568 MWt. l REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE from when the monitored parameter exceeds its RPS TIME trip setpoint at the channel sensor until electrical power is interrupted at the control rod drive trip breakers. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or (continued)

Crystal River Unit 3 1.1-6 Amendment No.