ML20069N666

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Correction to Amends 107 & 99 to Licenses NPF-2 & NPF-8. Pages 3/4 3-13 in Amends Were Inadvertently Issued W/O Including Changes That Occurred in Amends 104 & 99
ML20069N666
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 06/17/1994
From: Siegel B
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20069N669 List:
References
NUDOCS 9406230109
Download: ML20069N666 (2)


Text

)

TABLE 4 3-1 fContinued) 2

'n'ns t3A REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS mo

> tJ go CHANNEL MODES IN WHICH g fo CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE x

2,c FUNTIONAL UNIT CHECK CALIBRATION TEST REOUIRED

$ 04

< um 13.

Steam Generator Water S

R Q

1, 2

l 2: 80 Level--Low-Low bhOD Hma 14.

Deleted 2

c2 q

15.

Undervoltage - Reactor N.A.

R Q

1 l

g Coolant Pumps co l

E 16.

Underfrequency - Reactor N.A.

R Q

1 l

cy Coolant Pumps x

g 17.

Turbine Trip g

A.

Low Auto Stop Oil Pressure N.A R

S/U(9)(10)

N.A.

q B.

Turbine Throttle Valve N.A R

S /U (9 ) (10 )

N.A.

Closure t

as 18.

Safety Injection Input from ESF N.A.

N.A.

R(4) 1, 2 l

w o.

s*

okY 19.

Reactor Coolant Pump Breaker N.A.

N.A.

R 1

[

Position Trip

_w 20.

Reactor Trip System Interlocks N.A.

R S/U(8) 1 21.

Reactor Trip Breaker N.A.

N.A.

M(5) (14) (15),

1, 2, S/U (1) (14 ) (15) 3*,

4*,

5*

22.

Automatic Trip Logic N.A.

N.A.

M(5) 1, 2, 3*,

4*,

5*

E5 23.

Reactor Trip Bypass Breaker N.A.

N.A.

(13 ), R (11) 1, 2, inD 3*,

4*,

5*

.O Cs o=

".O

TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATIOfl SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH M

CHANtJEL CllANNEL FUNCTIONAL SURVEILLANCE FUNTIONAL UNIT CHECK CALIBRATlQU TEST REOUIRED M

7 13.

Steam Generator Water S

R Q

1, 2

l Level--Low-Low g

w H

14.

Steam /Feedwater Flow S

R Q

1, 2

l 9u Mismatch and Low Steam Q

Generator Water Level'

$g 15.

Undervoltage - Reactor N.A.

R Q

l l

o-Coolant Pumps cr 16.

Underfrequency - Reactor N.A.

R Q

l l

5' Coolant Pumps N

17.

Turbine Trip

^

A.

Low Auto Stop Oil Pressure N.A R

S/U(9)(10)

N.A.

etg B.

Turbine Throttle Valve N.A R

S/U(9)(10)

N.A.

to w Closure o.

s Er ^

18.

Safety Injection Input from ESF N.A.

N.A.

R(4) 1, 2 l

3 w

a e--

w

d 19.

Reactor Coolant Pump Breaker N.A.

N.A.

R 1

Position Trip e

E 20.

Reactor Trip System Interlocks N.A.

R S/U(8) 1 21.

Reactor Trip Breaker N.A.

N.A.

M ( 5) (14 ) (15),

1, 2 S/U (1) (14 ) (15) 3*,

4*,

5*

22.

Automatic Trip Logic N.A.

N.A.

M(5) 1, 2,

=$

3*,

4*,

5*

.g 23.

Reactor Trip Bypass Breaker N.A.

N.A.

(13),R(11) 1, 2,

.g8 3*,

4*,

5*

  • Deletion of this functional trip shall be implemented prior to 2,

.o startup from refuelirg outage 12.

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