ML052690235

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Technical Specifications Amendment for Beaver Valley, Units 1 and 2
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

. .

TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTE]AMINSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Modes in Which Channel Channel Functional Surveillance Functional Unit Check Calibration Test Required

12. Loss of Flow - Single Loop S R Q 1
13. Loss of Flow - Two Loops S R Q 1
14. Steam/Generator Water S R Q 1, 2 Level-Low-Low
15. DELETED
16. Undervoltage-Reactor Coolant N.A. R Q I Pumps
17. Underfrequency-Reactor N.A. R Q 1 I Coolant Pumps
18. Turbine Trip
a. Auto Stop Oil Pressure N.A. N.A. S/U (1) 1, 2
b. Turbine Stop Valve N.A. N.A. 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

21. Reactor Trip Breaker N.A. N.A. M(5,11) 1, 2, 3(14)

(14) (14) and S/U(')

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 MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED 1.1 SAFETY INJECTION-TRANSFER FROM INJECTION TO THE RECIRCULATION MODE

a. Manual Initiation N.A. N.A. R 1, 2, 3, 4
b. Automatic Actuation Logic N.A. N.A. 1, 2, 3 Coincident with Safety Injection Signal
c. Refueling Water Storage S R Q 1, 2, 3 I Tank Level-Low
d. Refueling Water Storage S R M 1, 2, 3 Tank Level - Auto QS Flow Reduction
2. CONTAINMENT SPRAY
a. Manual Initiation N.A. N.A. R 1, 2, 3, 4
b. Automatic Actuation Logic N.A. N.A. 1, 2, 3, 4
c. Containment Pressure- S R Q 1, 2, 3 High-High 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 MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

4. STEAM LINE ISOLATION
a. Manual N.A. N.A. R 1, 2, 3
b. Automatic Actuation Logic. N.A. N.A. 1, 2, 3
c. Containment Pressure-- S R Q 1, 2, 3 Intermediate-High-High
d. Steamline Pressure--Low S R Q 1, 2, 3
e. Steamline Pressure Rate-High S R Q 1, 2, 3 Negative
5. TURBINE TRIP & FEEDWATER ISOLATION
a. Steam Generator Water Level-- S R Q 1Q, 2, 3 High-High
6. LOSS OF POWER
a. 4.16kv Emergency Bus Under- N.A. R Q 1, 2, 3, 4 I voltage (Loss of Voltage)

Trip Feed & Start Diesel

b. 4.16kv and 480v Emergency N.A. R Q 1, 2, 3, 4 I Bus Undervoltage (Degraded Voltage)

BEAVER VALLEY - UNIT 1 3 /4 3-31 Amendment No.267

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

7. AUXILIARY FEEDWATER
a. Steam Generator Water S R Q 1, 2, 3 Level-Low-Low
b. Undervoltage-RCP S R Q 1, 2 I C. S.I. See 1 above (all SI surveillance requirements)
d. (Deleted)
e. Trip of Main N.A. N.A. R 1, 2, 3 Feedwater Pumps
8. ESF INTERLOCKS
a. P-4 N.A. N.A. R 1, 2, 3
b. P-l1 N.A. R Q 1, 2, 3
c. P-12 N.A. R Q 1, 2, 3 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 MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

1. SAFETY INJECTION AND FEEDWATER ISOLATION
a. Manual Initiation N.A. N.A. R 1, 2, 3, 4
b. Automatic Actuation Logic N.A. N.A. 1, 2, 3, 4 and Actuation Relays
c. Containment Pressure-High S R Q 1, 2, 3
d. Pressurizer Pressure--Low S R Q 1, 2, 3
e. Steam Line Pressure--Low S R Q 1, 2, 3 1.1 SAFETY INJECTION-TRANSFER FROM INJECTION TO THE RECIRCULATION MODE
a. Automatic Actuation Logic N.A. N.A. M(1) 1, 2, 3, 4 Coincident with Safety Injection Signal
b. Refueling Water Storage S R Q 1, 2, 3, 4 I Tank Level-Extreme Low 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 MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

6. LOSS OF POWER
a. 4.16kv Emergency Bus
1. Undervoltage (Trip Feed) N.A. R Q 1, 2, 3, 4 I
2. Undervoltage (Start N.A. R Q 1, 2, 3, 4 l Diesel)
b. 4.16kv Emergency Bus N.A. R Q 1, 2, 3, 4 (Degraded Voltage)
c. 480v Emergency Bus N.A. R Q 1, 2, 3, 4 (Degraded Voltage)
7. AUXILIARY FEEDWATER(4)
a. Automatic Actuation Logic N.A. N.A. 1, 2, 3 and Actuation Relays
b. Steam Generator Water Level-Low-Low
1. Start Turbine Driven S R Q 1, 2, 3 Pump
2. Start Motor Driven Pumps S R Q 1, 2, 3 (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 MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

7. AUXILIARY FEEDWATER (continued)
c. Undervoltage - RCP (Start S R Q 1, 2 I Turbine-Driven Pump)
d. Safety Injection (Start All See 1 above (all SI surveillance requirements)

Auxiliary Feedwater Pumps) e Trip of Main Feedwater Pumps N.A. N.A. R 1, 2, 3 (Start Motor-Driven Pumps)

8. ENGINEERED SAFETY FEATURE INTERLOCKS
a. Reactor Trip, P-4 N.A. N.A. R 1, 2, 3
b. Pressurizer Pressure, P-li N.A. R Q 1, 2, 3
c. Low-Low Tavg, P-12 N.A. R Q 1, 2, 3 BEAVER VALLEY - UNIT 2 3 /4 3-37 Amendment No.149