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

U Table 2.2-1 Reactor Protection System Instrumentation Trip SetPoints Z

Functional unit Allowable values m

En 1. Manual reactor trip Not applicable.

g 2. High flux <105.1% of RATED THERMAL POWER with four milmpq npersting*

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

3. RC high temperature <61 8'F*

4. Flux -- Aflux/flowv(l) Pump allowable values not to exceed the limit lines shown in in the CORE OPERATING LIMITS REPORT for four and three pump operation.*

5. RC low pressure(') >1900.0 psig*

6. RC high pressure <2355.0 psig*

7. RC pressure-temperature(') >(1 6.25 Tout -F - 7899.0) psig*

00

8. High flux/number of RC pur nps on(') <55.1% of RATED THERMAL POWER with one pump operating in each loop*

K)

<D

<0.0% of RATED THERMAL POWER with two pumps operating in one loop (b and no pumps operating in the other loop*

z

-P

<0.0% of RATED THERMAL POWER with no pumps operating or only one 0

0 pump operating*

00 a'

t'.

'a 9. Containment pressure high <4 psig*

Lt=

0\

-4

-I

TABLE 4.3-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE tco FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED M

1.Hi.g AnualnF uReacto~r.ri N.A. N.A. S/U(I) N.A.

.. x -- - T-.

Z-

2. High Flux S D(2), and Q(6,9) N.A. 1,2

3. RC High Temperature S R SA(9) 1,2

4. Flux - AFlux - Flow S(4) M(3) and Q(6,7,9) N.A. 1,2

5. RC Low Pressure S R SA(9) 1,2

6. RC High Pressure S R SA(9) 1,2

(: 7. RC Pressure-Temperature S R(10) SA(9,10) 1,2 I

8. High Flux/Number of Reactor S Q(6,9) N.A. 1,2 Coolant Pumps On

9. Containment High Pressure S E SA(9) 1, w 10. Intermediate Rangc, Neutron S E(6) N.A.(5) 1,2 and *

• ,

Flux and Rate t'J E3 11. Source Range, Neutron Flux S E(6) N.A;(5) 2, 3,4 and 5 g and Rate z:

9

12. Control Rod Drive Trip Breakers N.A. N.A. Q(8,9) and 1, 2 and

• P0

" (0 StU(1)(8)

13. Reactor Trip Module Logic N.A. N.A. Q(9) 1, 2 and

• oW F

14. Shutdown Bypass High Pressure S R SA(9) 2**, 3**, 4**, 5**

t"-

- , 15. SCR Relays N.A. N.A. R 1, 2 and

• 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 [API1] 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