ML060670044
| ML060670044 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  (NPF-003) |
| Issue date: | 03/02/2006 |
| From: | Plant Licensing Branch III-2 |
| To: | |
| Shared Package | |
| ML060400564 | List: |
| 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 Z
Functional 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 (bz 0
a'
'a
- 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 [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