ML060670044

Tech Spec Pages for Amendment 274 Framatome Mark B-HTP Fuel Design for Cycle 15

ML060670044
Person / Time
Site:	Davis Besse
Issue date:	03/02/2006
From:	Plant Licensing Branch III-2
To:
Shared Package
ML060400564	List: ML060400552 ML060670044
References
TAC MC6888
Download: ML060670044 (4)

Text

Figure 2.1-1 Reactor Core Safety Limit 2500 _240D -230()2200-.oM v),, 2100 -200C)1900 -_1800 1700 -_580 590 600 610 620 630 640 650 Reactor Outlet Temperature, F DAVIS-BESSE, UNIT 1 2-2 Amendment No. 11, 33, 45, 61, 123, 128, 149, 274 UFunctional unit m En 1. Manual reactor trip g 2. High flux 3. RC high temperature

4. Flux -- Aflux/flowv(l)

5. RC low pressure(')

6. RC high pressure 7. RC pressure-temperature(')

8. High flux/number of RC pur<D (b z 0 aa 9. Containment pressure high Lt=0\Table 2.2-1 Reactor Protection System Instrumentation Trip SetPoints Allowable values Not applicable.

<105.1% of RATED THERMAL POWER with four milmpq npersting*

<80.6% of RATED THERMAL POWER with three pumps operating*

<61 8'F*Pump allowable values not to exceed the limit lines shown in in the CORE OPERATING LIMITS REPORT for four and three pump operation.*

>1900.0 psig*<2355.0 psig*>(1 6.25 Tout -F -7899.0) psig*nps on(') <55.1% of RATED THERMAL POWER with one pump operating in each loop*<0.0% of RATED THERMAL POWER with two pumps operating in one loop and no pumps operating in the other loop*<0.0% of RATED THERMAL POWER with no pumps operating or only one pump operating*

<4 psig*00 K)-P 0 00 t'.-4-I tco M Z-TABLE 4.3-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 1. Anualn Reacto~r.ri

.. Hi.g F --u --.x T 2. High Flux N.A.S N.A.D(2), and Q(6,9)S/U(I)N.A.N.A.1,2 (: w* , g t'J P 0 E3 z: 9" (0 oW F t"--, 3. RC High Temperature

4. Flux -AFlux -Flow 5. RC Low Pressure 6. RC High Pressure 7. RC Pressure-Temperature

8. High Flux/Number of Reactor Coolant Pumps On 9. Containment High Pressure 10. Intermediate Rangc, Neutron Flux and Rate 11. Source Range, Neutron Flux and Rate 12. Control Rod Drive Trip Breakers 13. Reactor Trip Module Logic 14. Shutdown Bypass High Pressure 15. SCR Relays S S(4)S S S S R M(3) and Q(6,7,9)R R R(10)Q(6,9)S S E E(6)SA(9)N.A.SA(9)SA(9)SA(9,10)N.A.SA(9)N.A.(5)N.A;(5)Q(8,9) and StU(1)(8)Q(9)SA(9)R 1,2 1,2 1,2 1,2 1,2 1,2 1, 1,2 and *2, 3,4 and 5 1, 2 and *1, 2 and *2**, 3**, 4**, 5**1, 2 and *I S E(6)N.A.N.A.N.A.S N.A.N.A.R N.A.

TABLE 4.3-1 (Continued)

Notation (1) -If not perftrrmed in previous 7 days.(2) -Heat balan-e only, above 15% of RATED THERMAL POWER.(3) -When THERMAL POWER [TP] is above 50% of RATED THERMAL POWER [RTP], and at a steady state, compare out-of-core measured AXIAL POWER IMBALANCE[APIO] to incore measured AXIAL POWER IMBALANCE

[API 1] as follows: RTP [APIC -API 1 = Offset Error TP Recalibrate:

if the absolute value of the Offset Error is > 2.5%(4) -AXIAL POWER IMBALANCE and loop flow indications only.(5) -CHANNEL FUNCTIONAL TEST is not applicable.

Verify at least one decade overlap prior to each reactor startup if not verified in previous 7 days.(6) -Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) -Flow rate measurement sensors may be excluded from CHANNEL CALIBRATION.

However, each flow measurement sensor shall be calibrated at least once each REFUELING INTERVAL.(8) -The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of both the undervoltage and shunt trip devices of the Reactor Trip Breakers.(9) -Performed on a STAGGERED TEST BASIS.(10) -If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If.lhe as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the Limiting Trip Setpoint, or a value that is more conservative than the Limiting Trip Setpoint; otherwise, the channel shall be declared inoperable.

The Limiting Trip Setpoint and the methodology used to determine the Limiting Trip Setpoint, the predefined as-found acceptance criteria band, and the as-left setpoint tolerance band are specified in a document incorporated by reference into the Updated Safety Analysis Report.* -With any ccntrol rod drive trip breaker closed.** -When Shutdown Bypass is actuated.DAVIS-BESSE, UNIT 1 3/4 3-8 Amendment No. 43, 108, 123, 135, 185, 218, 274