ML023430062

Technical Specifications, Increase Maximum Steady-state Core Power Level from 2544 Megawatts Thermal (Mwt) to 2568 Mwt

ML023430062
Person / Time
Site:	Crystal River
Issue date:	12/04/2002
From:	Mozafari B NRC/NRR/DLPM/LPD2
To:
References
TAC MB5289
Download: ML023430062 (3)

Text

-4 of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

2.C.(1) Maximum Power Level Florida Power Corporation is authorized to operate the facility at a steady state reactor core power level not in excess of 2568 Megawatts (100 percent of rated core power level).

2.C.(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 205 , are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.

The Surveillance Requirements contained in the Appendix A Technical Specifications and listed below are not required to be performed immediately upon implementation of Amendment 149. The Surveillance Requirements shall be successfully demonstrated prior to the time and condition specified below for each.

a) SR 3.3.8.2.b shall be successfully demonstrated prior to entering MODE 4 on the first plant start-up following Refuel Outage 9.

b) SR 3.3.11.2, Function 2, shall be successfully demonstrated no later than 31 days following the implementation date of the ITS.

c) SR 3.3.17.1, Functions 1, 2, 6, 10, 14, & 17 shall be successfully demonstrated no later than 31 days following the implementation date of the ITS.

d) SR 3.3.17.2, Function 10 shall be successfully demonstrated prior to entering MODE 3 on the first plant start-up following Refuel Outage 9.

e) SR 3.6.1.2 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.

f) SR 3.7.12.2 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.

g) SR 3.8.1.10 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.

h) SR 3.8.3.3 shall be successfully demonstrated prior to entering MODE 4 on the first plant start-up following Refuel Outage 9.

Amendment No.-3-3, 44-, 49, 205

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.) I (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 EFIC 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 shall be:

LEAKAGE

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) 1.1-4 Amendment No.205 Crystal River Unit 3

Definitions 1.1 i.i Definitions PHYSICS TESTS These tests are:

(continued) "Initial Tests and

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

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

c. Otherwise approved by the Nuclear Regulatory Commission.

that PRESSURE AND The PTLR is the unit specific document provides the reactor vessel pressure and TEMPERATURE LIMITS cooldown REPORT (PTLR) temperature limits, including heatup and reactor vessel fluence rates, for the current period. These pressure and temperature limits in shall be determined for each fluence period Plant accordance with Specification 5.6.2.19.

is operation w.ithin these operating limits addressed in LCO 3.4.3, "RCS Pressure and Temperature Limits."

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

(QPT)

QPT =100( Power In Any Core Quadrant -1 TAverage Power of all Quadrants RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 2568 MWt. I REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval its RPS from when the monitored parameter exceeds SYSTEM (RPS) RESPONSE TIME trip setpoint at the channel sensor until control rod electrical power is interrupted at the drive trip breakers. The response time may be measured by means of any series of sequential, entire overlapping, or total steps so that the response time is measured.

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

.I.L., .-- _ Amendment No. 205 Crystal River Unit 3