ML060670044: Difference between revisions
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(: 7. RC Pressure-Temperature S R(10) SA(9,10) 1,2 I | (: 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 | : 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 | : 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: | |||
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 | 9 | ||
: 12. Control Rod Drive Trip Breakers N.A. N.A. Q(8,9) and 1, 2 and | : 12. Control Rod Drive Trip Breakers N.A. N.A. Q(8,9) and 1, 2 and |
Latest revision as of 09:16, 14 March 2020
ML060670044 | |
Person / Time | |
---|---|
Site: | Davis Besse ![]() |
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 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