ML052690235
| ML052690235 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/19/2005 |
| From: | - No Known Affiliation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML052690235 (8) | |
Text
REACTOR TRIP SYSTE]
Functional Unit
- 12.
Loss of Flow -
Single Loop
- 13.
Loss of Flow -
Two Loops
- 14.
Steam/Generator Water Level-Low-Low
- 15.
DELETED
- 16.
Undervoltage-Reactor Coolant Pumps
- 17.
Underfrequency-Reactor Coolant Pumps
- 18.
- a.
Auto Stop Oil Pressure
- b.
Turbine Stop Valve Closure
- 19.
Safety Injection Input from ESF
- 20.
Reactor Coolant Pump Breaker Position Trip
- 21.
Reactor Trip Breaker TABLE 4.3-1 (Continued)
AM INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Channel Channel Functional Check Calibration Test S
R Q
S R
Q S
R Q
Modes in Which Surveillance Required 1
1 1, 2 N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
R Q
I R
N.A.
N.A.
N.A.
N.A.
N.A.
Q S/U (1)
R R
M (5,11) and S/U(')
1 I
1, 2 1,
2 1, 2 N.A.
1, 2,
3(14)
(14)
(14)
BEAVER VALLEY -
UNIT 1 3/4 3-12 Amendment No.267
.1 4
TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL FUNCTIONAL UNIT CHECK CHANNEL CHANNEL FUNCTIONAL CALIBRATION TEST MODES IN WHICH SURVEILLANCE REOUIRED 1.1 SAFETY INJECTION-TRANSFER FROM INJECTION TO THE RECIRCULATION MODE
- a.
Manual Initiation
- b.
Automatic Actuation Logic Coincident with Safety Injection Signal
- c.
Refueling Water Storage Tank Level-Low
- d.
Refueling Water Storage Tank Level -
Auto QS Flow Reduction N.A.
N.A.
S S
N.A.
N.A.
R R
R 1, 2, 3, 4 1, 2, 3 1, 2, 3 1, 2, 3 Q
M I
- 2.
- a.
Manual Initiation N.A.
N.A.
R 1, 2, 3, 4
- b.
Automatic Actuation Logic
- c.
Containment Pressure-High-High N.A.
N.A.
1, 2, 3, 4 S
R Q
1, 2,
3 BEAVER VALLEY -
UNIT 1 3/4 3-29a Amendment No.267
. P TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL FUNCTIONAL UNIT CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE REQUIRED
- 4.
STEAM LINE ISOLATION
- a.
Manual
- b.
Automatic Actuation Logic.
- c.
Containment Pressure--
Intermediate-High-High
- d.
Steamline Pressure--Low
- e.
Steamline Pressure Rate-High Negative
- 5.
TURBINE TRIP & FEEDWATER ISOLATION
- a.
Steam Generator Water Level--
High-High N.A.
N.A.
R 1, 2, 3 N.A.
N.A.
1, 2,
3 S
S R
R Q
Q Q
1, 2,
3 1, 2, 3 1, 2, 3 S
R S
R Q
1Q, 2, 3
- 6.
LOSS OF POWER
- a.
4.16kv Emergency Bus Under-voltage (Loss of Voltage)
Trip Feed & Start Diesel
- b.
4.16kv and 480v Emergency Bus Undervoltage (Degraded Voltage)
N.A.
N.A.
R R
Q Q
1, 2,
3, 4
1, 2, 3, 4 I
I BEAVER VALLEY -
UNIT 1 3 /4 3-31 Amendment No.267
TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS FUNCTIONAL UNIT CHANNEL CHECK CHANNEL MODES IN WHICH CHANNEL FUNCTIONAL SURVEILLANCE CALIBRATION TEST REQUIRED
- 7.
- a.
Steam Generator Water Level-Low-Low
- b.
Undervoltage-RCP S
S R
R Q
Q 1,
2, 3 1, 2 I
C.
S.I.
- d.
(Deleted)
- e.
Trip of Main Feedwater Pumps
- 8.
ESF INTERLOCKS
- a.
P-4
- b.
P-l1
- c.
P-12 See 1 above (all SI surveillance requirements)
N.A.
N.A.
R 1, 2, 3 N.A.
N.A.
R N.A.
R Q
1, 2,
3 1, 2, 3 1, 2, 3 N.A.
R Q
BEAVER VALLEY -
UNIT 1 3/4 3-31a Amendment No.267
TABLE 4.3-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS Channel Modes in Which Channel Channel Functional Surveillance Functional Unit Check Calibration Test Required
- 12. Loss of Flow -
Single Loop S
R Q
1 (Above P-8)
- 13. Loss of Flow - Two Loop S
R Q
1 (Above P-7 and Below P-8)
- 14. Steam/Generator Water Level-S R
Q 1, 2 Low-Low
- 15. DELETED.
- 16. Undervoltage-Reactor Coolant N.A.
R Q
1 Pumps (Above P-7)
- 17. Underfrequency-Reactor N.A.
R Q
1 Coolant Pumps (Above P-7)
- 18. Turbine Trip (Above P-9)
A.
Emergency Trip Header N.A.
R S/U()
1, 2 Low Pressure B.
Turbine Stop Valve N.A.
R S/U(1 1, 2 Closure
- 19. Safety Injection Input from N.A.
N.A.
R 1, 2 ESF
- 20. Reactor Coolant Pump Breaker N.A.
N.A.
R N.A.
Position Trip (Above P-7)
- 21. Reactor Trip Breaker N.A.
N.A.
Ma (5
- 11) 1 3 1 4(
and S/U 4'r 5 BEAVER VALLEY -
UNIT 2 3 /4 3-11 Amendment No. 149
TABLE 4.3-2 ENGINEERING SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL FUNCTIONAL UNIT CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE REQUIRED
- 1.
SAFETY INJECTION AND FEEDWATER ISOLATION
- a.
Manual Initiation
- b.
Automatic Actuation Logic and Actuation Relays
- c.
Containment Pressure-High
- d.
Pressurizer Pressure--Low
- e.
Steam Line Pressure--Low N.A.
N.A.
N.A.
R 1, 2, 3, 4 N.A.
1, 2, 3, 4 S
R S
R Q
Q Q
1, 2, 3 1, 2, 3 1, 2, 3 S
R 1.1 SAFETY INJECTION-TRANSFER FROM INJECTION TO THE RECIRCULATION MODE
- a.
Automatic Actuation Logic Coincident with Safety Injection Signal N.A.
N.A.
M(1) 1, 2, 3, 4
- b.
Refueling Water Storage Tank Level-Extreme Low S
R Q
1, 2, 3, 4
I BEAVER VALLEY -
UNIT 2 3 /4 3-33 Amendment No. 149
TABLE 4.3-2 (Continued)
ENGINEERING SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL FUNCTIONAL UNIT CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE REQUIRED
- 6.
LOSS OF POWER
- a.
4.16kv Emergency Bus
- 1.
Undervoltage (Trip Feed)
- 2.
Undervoltage (Start Diesel)
- b.
4.16kv Emergency Bus (Degraded Voltage)
- c.
480v Emergency Bus (Degraded Voltage)
- 7.
N.A.
R Q
Q N.A.
N.A.
N.A.
R 1, 2, 3, 1, 2, 3, 1, 2, 3, 4
4 R
4 I
Q l
R Q
1, 2, 3, 4
- a.
Automatic Actuation Logic and Actuation Relays N.A.
N.A.
1, 2, 3
- b.
Steam Generator Water Level-Low-Low
- 1.
Start Turbine Driven Pump
- 2.
Start Motor Driven Pumps S
R Q
1, 2, 3 1, 2, 3 S
R Q
(4) Manual initiation is included in Specification 3.7.1.2.
BEAVER VALLEY -
UNIT 2 3 /4 3-3 6 Amendment No.
149
TABLE 4.3-2 (Continued)
ENGINEERING SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL FUNCTIONAL UNIT CHECK CHANNEL CHANNEL FUNCTIONAL CALIBRATION TEST MODES IN WHICH SURVEILLANCE REQUIRED
- 7.
AUXILIARY FEEDWATER (continued)
- c.
RCP (Start Turbine-Driven Pump)
S R
Q 1, 2 I
- d.
Safety Injection (Start All Auxiliary Feedwater Pumps) e Trip of Main Feedwater Pumps (Start Motor-Driven Pumps)
See 1 above (all SI surveillance requirements)
N.A.
N.A.
R 1,
2, 3
- 8.
ENGINEERED SAFETY FEATURE INTERLOCKS
- a.
Reactor Trip, P-4
- b.
Pressurizer Pressure, P-li
- c.
Low-Low Tavg, P-12 N.A.
N.A.
N.A.
N.A.
R R
Q 1, 2, 3 1, 2, 3 1, 2, 3 R
Q BEAVER VALLEY -
UNIT 2 3 /4 3-37 Amendment No.149