ML18096A926

Proposed TS Table 3.3-1 Re Reactor Trip Sys Instrumentation & Table 4.3-1 Re Reactor Trip Sys Instrumentation Surveillance Requirements

ML18096A926
Person / Time
Site:	Salem
Issue date:	08/26/1992
From:	Public Service Enterprise Group
To:
Shared Package
ML18096A925	List: ML18096A924 ML18096A926
References
NUDOCS 9209020018
Download: ML18096A926 (6)

Text

"'ll '"O.,Q t:m.> ui

00 ~

"° t"'

0 t>:l l>PJ ~

gg I 0'"'6 c::

,::m z H

0..0 8 Ull'J......

00 om

"'llOllJ OllJ0-

0.....

llJ w

.t>.

w I w TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION FUNCTIONAL UNIT

11.

Pressurizer Water Level--High

12.

Loss of Flow -

Single Loop (Above P-8) 13.

14.

15.

16.

17.

Loss of Flow -

Two Loops (Above P-7 and below P-8)

Steam Generator Water Level--

Low-Low Steam/Feedwater Flow Mismatch and Low Steam Generator Water Level Undervoltage-Reactor coolant Pumps Underf requency-Reactor Coolant Pumps TOTAL NUMBER OF CHANNELS 3

3/loop 3/loop 3/loop 2/loop-level and 2/loop-flow mismatch 4-1/bus 4-1/bus CHANNELS TO TRIP 2

2/loop in any oper-ating loop 2/loop in two oper-ating loops 2/loop in any oper-ating loops MINIMUM CHANNELS OPERABLE 2

2/loop in each oper-ating loop 2/loop in each oper-ating loop 2/loop in each oper-ating loop APPLICABLE MODES 1, 2 1

1 1, 2 1/loop-level 1/loop-level 1, 2 coincident and 2/loop-with flow mismatch 1/loop-flow or 2/loop-mismatch in level and same loop 1/loop-flow mismatch 1/2 twice 4

1/2 twice 4

1 1

ACTION 7#

7#

7#

7#

6 6

ACTION 4 -

ACTION 5 -

ACTION 6 -

ACTION 7 -

SALEM -

UNIT 1

~

TABLE 3.3-1 !Cantin~

a.

Below P-6, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above P-6 but below 5% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER.

c.

Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

P-6, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above P-6, operation may continue.

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

b.

The inoperable channel is placed in the tripped condition within -r hou

• ri;£ 1AJOP!..eA~

~

s The Minimum ~Channels OPERABLE requirement is met; however, SAe aeei e i eAal channel may be bypassed for

'I -t hours for surveillance testing!\\ per Specification 4.3.1.1.

up to With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

3/4 3-6

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS Ul CHANNEL MODES IN WHICH

i>o t"'

CHANNEL FUNCTIONAL SURVEILLANCE ti:!

~

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED c

1.

Manual Reactor Trip Switch NA NA S/U(9)

NA z

H 8

I-'

2.

Power Range, Neutron Flux s

D (2), M(3)

M 1, 2 and Q(6)

3.

Power Range, Neutron Flux, NA R(6)

M 1, 2 High Positive Rate

4.

Power Range, Neutron Flux, NA R(6)

M 1, 2 High Negative Rate 5.

Intermediate Range, Neutron s

R(6)

S/U(l) 1, 2 and

• w Flux

6.

Source Range, Neutron Flux 5(7)

R(6)

M and S/U(l) 2, 3, 4, 5 and

• w

..::\\T I

7.

Overtemperature s

R M

1, 2 I-'

I-'

8.

Overpower..::\\T s

R M

1, 2

9.

Pressurizer Pressure--Low s

R M

1, 2

10.

Pressurizer Pressure--High s

R M

1, 2

11.

Pressurizer Water Level--High s R

~

~

1, 2

12.

Loss of Flow - Single Loop s

§'

R M

1 (1)

l

0. a (1)

l r1" z

0 V1 ID

(/)

ti>'

I:"

~

3:

TABLE 3.3-1 (Continued) c::

REACTOR TRIP SYSTEM INSTRUMENTATION z

H t-3 N

MINIMUM TOTAL NUMBER CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

11.

Pressurizer Water Level--High 3

2 2

1, 2

~

~~

12.

Loss of Flow - Single Loop 3/loop 2/loop in 2/loop in 1

7#

e (Above P-8) any aper-each aper-ating loop ating loop

13.

Loss of Flow -

Two Loops 3/loop 2/loop in 2/loop in 1

7#

(Above P-7 and below P-8) two aper-each aper-w ating loops ating loop

14.

Steam Generator Water 3/loop 2/loop in 2/loop in 1, 2 7#

w Level--Low-Low each aper-I any aper-w ating loops ating loop 15.

Steam/Feedwater Flow 2/loop-level 1/loop-level 1/loop-level 1, 2 7#

Mismatch and Low Steam and coincident and Generator Water Level 2/loop-flow with 2/loop-flow mismatch 1/loop-flow mismatch or mismatch in 2/loop-level same loop and 1/loop-flow

~

mismatch ro ::s

0.

16.

Undervoltage-Reactor Coolant El ro Pumps 4-1/bus 1/2 twice 4

1 6

s rt z

17.

Underf requency-Reactor Coolant 0.

4-1/bus Pumps t--'

1/2 twice 4

1 6

t--'

0

ACTION 4 ACTION 5 ACTION 6 ACTION 7 SALEM -

UNIT 2 TABLE 3.3-1 (Continued)

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above the P-6 (Block of Source Reactor Trip) setpoint but below 5% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status priQr to increasing THERMAL POWER above 5% of RATED THERMAL POWER.

c.

Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.

d.

Above 10% of RATED THERMAL POWER, the provisions of Specification 3. 0. 3 are not applicable.

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above the P-6 (Block of Source Range Reactor Trip) setpoint, operation may continue.

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

b.

The inoperable channel is placed in the tripped condition within + hou~.

"TH~ l.IJQ,~~L f.:,

S The Minimum \\ Channel OPERABLE requirement is met; however, on~ additieftal channel may be bypassed for I{ T hours for surveillance testing/\\ per Specification 4

• 3

• 1

• 1.

OF OT#~ CHANJV!LS With the number of OPERABLE channels one less than the up to Total Number o f Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition with 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

3/4 3-6 Amendment No. 28

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS FUNCTIONAL UNIT

1.

Manual Reactor Trip Switch 2.

Power Range, Neutron Flux

3.

Power Range, Neutron Flux, High Positive Rate w

4.

Power Range, Neutron Flux, I

~

High Negative Rate

~

~

ro

s 0.

9 ro ::s rt z

0.

N 00

5.

Intermediate Range, Neutron Flux 6.

Source Range, Neutron Flux

7.

Overtemperature aT

8.

Overpower aT 9.

Pressurizer Pressure--Low

10.

Pressurizer Pressure--High

11.

Pressurizer Water Level--High

12.

Loss of Flow - Single Loop CHANNEL CHECK N.A.

s N.A.

N.A.

s S(7) s s

s s

s s

CALIBRATION N.A.

D(2), M(3) and Q(6)

R(6)

R(6)

R(6)

R(6)

R R

R R

R R

CHANNEL MODES IN WHICH FUNCTIONAL TEST S/U(9)

M M

M S/U(l)

M and S/U(l)

M M

M M

M SURVEILLANCE REQUIRED N.A.

1, 2 1, 2 1, 2 1, 2 and

• 2, 3, 4, 5 and

• 1, 2 1, 2 1, 2 1, 2 1, 2 1