ML023430062
| 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 DAY (EFPD)
(continued)
EMERGENCY FEEDWATER INITIATION AND CONTROL (EFIC)
RESPONSE TIME ENGINEERED SAFETY FEATURE (ESF)
RESPONSE
TIME LEAKAGE reactor core at RTP for one full day.
(One EFPD is 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.)
The EFIC RESPONSE TIME shall be that time interval from when the monitored parameter 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.
The ESF RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF 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:
- 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 I
Amendment No.205 1.1-4
Definitions 1.1 i.i Definitions PHYSICS TESTS (continued)
PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
QUADRANT POWER TILT (QPT)
RATED THERMAL POWER (RTP)
REACTOR PROTECTION SYSTEM (RPS)
RESPONSE
TIME SHUTDOWN MARGIN (SDM)
These tests are:
- 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.
The PTLR is the unit specific document that provides the reactor vessel pressure and 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 w.ithin these operating limits is addressed in LCO 3.4.3, "RCS Pressure and Temperature Limits."
QPT shall be defined by the following equation and is expressed as a percentage.
QPT =100(
Power In Any Core Quadrant
-1 TAverage Power of all Quadrants RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2568 MWt.
The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS 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.
SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or (continued)
.I Amendment No. 205 Crystal River Unit 3 I
.L.,.--