ML022030241

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Technical Specification Pages, Amendment No. 204 Re Table 3.3.1-1 (Page 1 of 1), Reactor Protection System Instrumentation
ML022030241
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 07/16/2002
From:
NRC/NRR/DLPM
To:
Florida Power Corp
References
TAC MB2499
Download: ML022030241 (4)
v • d • e


Text

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 1)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED CONDITIONS ACTION D.1 SURVEILLANCE ALLOWABLE VAI liF DCAIITD;MINT*Z FUNCTION

1. Nuclear Overpower
a. High Setpoint 1,2(' F SR 3.3.1.1 *104.9% RTP SR 3.3.1.2 SR 3.3.1.5 SR 3.3.1.7 (b), (b) G SR 3.3.1.1
b. Low Setpoint 2 3 4 (b), 5 Cb) SR 3.3.1.5 1,2 F SR 3.3.1.1
  • 618°F
2. RCS High Outlet Temperature SR 3.3.1.4 SR 3.3.1.6
3. RCS High Pressure 1,2 F SR 3.3.1.1
4. RCS Low Pressure SR 3.3.1.4 SR 3.3.1.6 SR 3.3.1.7 1,2(') F SR 3.3.1.1 RCS Variable Low
5. RCS Variable Low Pressure SR 3.3.1.4 Pressure equation in SR 3.3.1.6 COLR
6. Reactor Building High 1, 2, 3(ý F SR 3.3.1.1 *4 psig Pressure SR 3.3.1.4 SR 3.3.1.6 1,2 (a F SR 3.3.1.1 More than one pump
7. Reactor Coolant Pump Power Monitor (RCPPM) SR 3.3.1.4 drawing
8. Nuclear Overpower RCS Flow and Measured AXIAL POWER SR 3.3.1.3 Flow and AXIAL POWER IMBALANCE SR 3.3.1.5 IMBALANCE setpoint SR 3.3.1.6 envelope in COLR SR 3.3.1.7
9. Main Turbine Trip (Control Ž 45% RTP H SR 3.3.1.1 Ž45 psig Oil Pressure) SR 3.3.1.4 SR 3.3.1.6

_ 20% RTP I SR 3.3.1.1 Ž55 psig

10. Loss of Both Main Feedwater Pumps (Control Oil SR 3.3.1.4 Pressure) SR 3.3.1.6
11. Shutdown Bypass RCS High 2 (b), 3 (b) G SR 3.3.1.1
  • 1820 psig Pressure 4 (b), 5 Cb) SR 3.3.1.4 SR 3.3.1.6 (a) When not in shutdown bypass operation.

(b) During shutdown bypass operation with any CRD trip breakers in the closed position and the COD Control System (CRDCS) capable of rod withdrawal.

(c) With any CRD trip breaker in the closed posi tion and the CRDCS capable of rod withdrawal.

Crystal River Unit 3 3.3-5 Amendment No.204

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 pl Irlt /rTl I A ILI#"* [-- rl r-t*l IT D *MI:klT¢ ZUKVt.LL1LAI-C I¶CL&I LU-MLI FREQUENCY SURVEILLANCE SR 3.4.1.1 -------------------- NOTE------------------

With three RCPs operating, the limit is applied to the loop with two RCPs in operation.

Verify RCS loop pressure meets the RCS loop 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> pressure limits specified in the COLR.

SR 3.4.1.2 ------------------- NOTE With three RCPs operating, the limit is applied to the loop with two RCPs in operation.

Verify RCS hot leg temperature meets the 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> RCS hot leg temperature limit specified in the COLR, AND is < 605.8-F.

3.4.1.3 Verify RCS total flow rate meets the RCS 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR total flow rate limits specified in the COLR, AND is Ž133.5 E6 lb/hr with four RCPs operating or > 99.7 E6 lb/hr with three RCPs operating.

SR 3.4.1.4 -------------------- NOTE Only required to be performed when stable thermal conditions are established > 90% of ALLOWABLE THERMAL POWER.

Verify RCS total flow rate is within limit 24 months by measurement.

Amendment No. 2 04 Crystal River Unit 3 3.4-2

Procedures, Programs and Manuals 5.6 5.7 Procedures, Programs and Manuals 5.6.2.18 COLR (continued)

LCO 3.2.3 AXIAL POWER IMBALANCE Operating Limits LCO 3.2.4 QUADRANT POWER TILT LCO 3.2.5 Power Peaking Factors LCO 3.3.1 Reactor Protection System (RPS) Instrumentation SR 3.4.1.1 Reactor Coolant System Pressure DNB Limits SR 3.4.1.2 Reactor Coolant System Temperature DNB Limits SR 3.4.1.3 Reactor Coolant System Flow DNB Limits LCO 3.9.1 Boron Concentration

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC:

BAW-10179P-A, "Safety Criteria and Methodology for Acceptable Cycle Reload Analyses" (the approved revision at the time the reload analyses are performed) and License Amendment 144, SER dated June 25, 1992.

The approved revision number for BAW-10179P-A shall be identified in the COLR.

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d. The COLR, including any midcycle revisions or supplements,the shall be provided upon issuance for each reload cycle to NRC.

5.6.2.20 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. Other Applicable ITS:

3.4.4 RCS P/T Limits 3.4.11 Low Temperature Overpressure Protection

b. RCS pressure and temperature limits, including heatup andtest cooldown rates, criticality, and hydrostatic and leak limits, shall be established and documented in the PTLR.and The analytical methods used to determine the pressure rates temperature limits including the heatup and cooldown shall be those previously reviewed and approved by the NRC in BAW-10046A, Rev. 2, "Methods of Compliance With Fracture Toughness and Operational Requirements of 10 CFR 50, Appendix G," June 1986. The analytical method used to determine vessel fluence shall be those reviewed by the NRC and documented in BAW-2241P, May 1997. The analytical method used to determine LTOP limits shall be those reviously reviewed by the NRC based on ASME Code Case

-514. The Materials Program is in accordance with BAW-1543A, "Integrated Reactor Vessel Surveillance Program."

(continued)

Amendment No. 204 Crystal River Unit 3 5.0-23

RCS Pressure, Temperature, and Flow DNB Limits B 3.4.1 BASES APPLICABLE that transients initiated from the limits of this LCO will SAFETY ANALYSES meet the event-specific DNBR acceptance criterion. This is (continued) the acceptance limit for the RCS DNBR parameters. The transients analyzed for include loss of coolant flow events and dropped or stuck control rod events. A key assumption for the analysis of these events is that the core power distribution is within the limits of LCO 3.2.1, "Regulating Rod Insertion Limits," LCO 3.2.2, "APSR Insertion Limits,"

LCO 3.2.3, "AXIAL POWER IMBALANCE OPERATING LIMITS," and LCO 3.2.4, "QUADRANT POWER TILT."

For full power conditions, limits are set on loop parameters to meet the DNBR criterion. The minimum core outlet pressure is the limit value in the reactor coolant loop as measured at the hot leg pressure tap. The maximum hot leg temperature specified is the limit value as measured at the hot leg resistance temperature detector.

The minimum volumetric flow rate corresponds to the mass flow rate for four RCP operation at full power.

Additionally, analyses have been performed to establish the pressure, temperature, and flow rate requirements for three pump operation. The flow limits for three pump operation are approximately 25% lower than the four pump limits. To meet the DNBR criterion, a corresponding maximum power limit of less than the top of the "doghouse" (Power-Imbalance-Flow trip setpoint contained in the COLR) is required in combination with the 3 pump limits (see Bases for LCO 3.3.1, "RPS Instrumentation").

RCS DNB limits satisfy Criterion 2 of the NRC Policy Statement.

LCO Limits on RCS loop (hot leg) pressure, RCS hot leg temperature, and RCS total flow rate ensure that the core (conti nued)

Crystal River Unit 3 B 3.4-2 Amendment No. 204

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