Text

Proposed Tech Specs Re Requirements Associated with Control Room & Fuel Handling Bldg Ventilation Sys
	ML20154A428
Person / Time
Site:	South Texas
Issue date:	09/28/1998
From:	; HOUSTON LIGHTING & POWER CO.
To:	;
Shared Package
ML20154A416	List: ML20154A412; ML20154A428;
References
	NUDOCS 9810020306
	Download: ML20154A428 (50)
	v • d • e

--

- = -

INSTRUMENTATION l

l 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSlEM INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3.3.2 -The Engineered Safety Features Actuation System (ESFAS) instrumentation l

channels and interlocks shown in; Table 3.3-3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown :n the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Chapter 16 in the UFSAR.

APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a.

With an ESFAS Instrumentation er Interlock Trip Setpoint trip less conservative than the value shewn in the Trip Setpoint column but more conservat.ive-than the value shcwn in the Allowable Value column of lable 3.'3-4, adjust the Setpoint consistent with the' Trip Setpoint value.

b.

With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than the value shown in the A11cwable Value column of Table 3.3-4, either:

1.

Adjust the Setpoint consistent with the Trip Setpoint value of Table 3.3-4, and determine within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that Equation 2.2-1 was satisfied for the affected channel, or 2.

Declare the channel inoperable and apply the applicable ACTION l

statement requirements of Table 3.3-3 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent v ath the Trip Setpoint value.

l Equation 2.2-1 Z + R + S s TA Where:

I = The value from Column Z of Table 3.3-4 for the affected

channel, R - The "as-measured" value (in percent span) of rack error for the effected' channel, S = Either the "as-measured" value (in percent span) of the sensor M.or, or the value from Column S (Sensor Error) of

(

Table 3.3-4 for the affected channel, and l

l TA - The value from Column TA (Total Allowance) of Table 3.3-4 l

for the affected channel.

i i

c.

With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.

SOUTH TEXAS - UNITS 1 & 2 3/4 3-16 Unit 1 - Amendment No.50 Unit 2 - Amendment No.39 9810020306 980928" hDR ADOCK 05000498 PM

1811BUMENTATION SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic acutation logic and relays shall be demonstrated OPERABLE by performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3.2.

4.3.2.2 The ENGINEERED SAFETY FEdTURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least one train so that:

a.

Each logic train is tested at least once per 36 months, b.

Each actuation train is tested at le'ast once per 54 months *, and c.

One channel per function so that all channels are tested at least once per N times 18 months where H is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" column of Table 3.3-3.

l F

TT-'an ESFAS instrumentation channel is inoperable due to response times exceeding the required limits, perform an engineering evaluation to determine if the test failure is a result of degradation of the actuation relays.

If degradation of the actuation relays is determined to be the cause, increase the ENGINEERED SAFETY FEATURES RESPONSE TlHE surveillance frequency such that all trains are tested at least once per 36 months.

SOUTH TEXAS - UNITS 1 & 2 3/4 3-17 Unit 1 - Amendment No. 50 Unit 2 - Amendment No. 39

io -

TABLE 3.3-3 O'

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION-

. at h!

MINIMUM l

TOTAL NO.

CHANNELS CHANNELS APPLICABLE

'l FUNCTIONAL UNIT' 0F CHANNELS TO TRIP OPERABLE MODES ACTION i

c:

25 Di 1.

Safety Injection (Reactor i

Trip, Feedwater Isolation, s.

e.

Control Room Emergency Ventilation, Start Standby-no Diesel Generators, Reactor i

Containment Fan Coolers, l

and Essential Cooling Water).

t u,

a.

Manual Initiation 2

1 2

1,2,3,4 19 1

u, b.

Automatic Actuation

,f g'-

Logic 2

f 2

1,2,3,4 14 c.

Actuation Relays 3

2 3

1,2,3,4 14

'y d.

Containment 3

2 2

1,2,3,4 15 Pressure--High-1 c:

5L e.

Pressurizer 4

2 3

1, 2, 3#

20 i

Pressure--Low i

t 3T f.

Compensated Steam 3/ steam line 2/ steam line 2/ steam line 1, 2, 3#

15 Line Pressure-Low any steam line in each steam St line j

8 i

n WO b

4 t

TABLE 3.3-3 (Continued)

}j ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION Y

5-MINIMUM MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE

[ FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION z

[]. 2.

Containment Spray a.

Manual Initiation 2

1 with 2

1,2,3,4 19 ll 2 coincident switches b.

Automatic Actuation Logic 2

1 2

1,2,3,4 14 c.

Actuation Relays 3

2 3

1,2,3,4 14 s

j' High-3

~ 2 3

1,2,3 17 d.

Containment Pressure--

4 e

3.

Containment Isolation a.

Phase "A" Isolation 1)

Manual Initiation 2

1 2

1,2,3,4 19 2)

Automatic Actuation Logic 2

1 2

1,2,3,4 14 3)

Actuation Relays 3

2 3

1,2,3,4 14 4)

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

l

TABLE 3.3-3 (Continued) w ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION E

M MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE g FUNCTION 6L UNIT OF CHANNELS TO TRIP-OPERABLE MODES ACTION l

Conf.ainmentIsolation(Continued) 3.

b.

Containieent Ventilation e*

Isolation 1)

Automatic Actuation

~

Logic 2

1 2

1,2,3,4 18 e

2)

Actuation Relays ***

3 2

3 1,2,3,4 18 m

3)

Safety Injection ***

-See Item 1. above for all Safety Injection initiating functions and requirements.

{

4)

RCB Purge l

gg gg Radioactivity-High 2

1 2

1,2,3,4,5

,6 18 l

ws*

5)

Containment Spray-See Item 2. above for Containment Spray manual initiating functions

{

Manual Initiation and requirements.

6)

Phase "A" Isolation-See Item 3.a. above for Phase "A" Isolation manual initiating Manual Isolation functions and requirements.

j c.

Phase "B" Isolation e

1) Automatic' Actuation 2

1 2

1,2,3,4 14 i

y logic

2) Actuation Relays 3

2 3

1,2,3,4 14 l

3) Containment Pressure--

4 2

3 1,2,3 17 i

.R High-3

4) Containment Spray-See Item 2. above for Containment Spray manual initiating s

Manual Initiation functions and requirements.

5 i

=

d.

RCP Seal Injection Isolation l

P

1) Automatic Actuation 1

1 1

1,2,3,4 16 Logic and Actuation Relays I

t

TABLE 3.3-3 (Centinued)

ENGINEERED SAFETY FEATURES AC.UATION SYSTEM INSTRUMENTATION se i

HINIMUM' 4

g; TOTAL NO.

CHANNELS CHANNELS APPLICABLE B; FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 3.d.

RCP Seal Injection Isolation (Continued) c

'E g!.

2) Charging Header 1

1 1

1,2,3,4 16 Pressure - Low Coincident with Phase See item 3.a. above for Phase "A" Isolation initiating functions no "A" Isolation and requirements i

4.

Steap Line Isolation a.

Manual Initiation I

22

1) Individual 2/ steam line 1/ steam line 2/ operating 1,2,3 24 i'

steam line 5

2) System 2

1 2

1,2,3 23 b.

Automatic Actuation 2

1 2

1,2,3 22 i

Logic and Actuation EF Relays l

??

c.

Steam Line Pressure -

Negative Rate--High 3/ steam line 2/ steam line 2/ steam line 3###

15

[

any steam in each steam g7 line line E

R d.

Containment Pressure -

3 2

2 1,2,3 15 ll High-2

!I e.

Compensated Steam Line 3/ steam line 2/ steam line 2/ steam line 1, 2, 3#

15 Pressure - Low any steam in each steam line line i

b o

MW

=

1

, TABLE 3.3-3 (C ntinued)

ENGINEERED SAFETY FEATURES' ACTUATION SYSTEM INSTRUMENTATI0tt

{

MINIMUM M

x TOTAL NO.

CHANNELS CHANNELS APPLICABLE E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 5.

Turbine Trip and Feedwater Isolation a.

Automatic Actuation 2

1 2

1,2,3 25 h

Logic and Actuation Relays

~

i e-b.

Steam Generator 4/stm. gen.

2/stm. gen.

3/stm. gen.

1,2,3 20 Water Level--

in any oper-in each-High-High (P-14) ating stm.

operating gen.

stm. gen.

R c.

Deleted D

Y d.

Deleted M

e.

Safety Injection See ' Item 1. for all Safety Injection initiating functions and requirements.

i T,yg-Low coincident with f.

c1 Reactor Trip (P-4) 4 (1/ loop) 2 3-1,2,3 20 l

(Feedwater Isolation Only)

I 8

i E

Jh

TABLE 3.3-3 (Ccntinued) i i

EI ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION i

Si a: -

MINAMUM

((

TOTAL NO.

CHANNELS CHANNELS APPLICABLE 1

3; FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 6.

Auxiliary Feedwater a

a.

Manual Initiation 1/ pump 1/ pump 1/ pump 1,2,3 26

((

e-b.

Automatic Actuation Legic 2

1 2

1, 2, 3 22 c.

Actuation Relays 3

2 3

1,2,3 22 i\\

d.

Stm. Gen. Water Level--

i Low-Low i

Start Motor-R>

Driven Pumps 4/sta. gen.

2/stm. gen.

3/stm. gen.

1,2,3 20 and Turbine-in any stm.

in each (f

Driven Pump gen.

stm. gen.

e.

Safety Injection See Item 1. above for all Safety Injection initiating functions-and co

.)

requirements.

f.

Loss of Power (Motor See Item 8. below for all Loss of Power initiating functions and

. Driven Pumps Only) requirements.

[

i t

7.

Automatic Switchover to Containment Sump ****

a.

Automatic Actuation 3-1/ train 1/ train 1/ train 1,2,3,4 19 Logic and Actuation Relays b.

RWST Level--Lo'w-Low 3-1/ train 1/ train 1/ train 1, 2, 3, 4 19 k

Coincident With:

See Item 1. above for all Safety Injection initiating functions l

Safety Injection and requirements.

I

TABLE 3.3-3 (Continued)-

l ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM

~

h TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT-0F CHANNELS TO TRIP OPERABLE MODES ACTION l

Cj'i 8.

Loss of Power w

a.

4.16 kV ESF Bus Under.

4/ bus 2/ bus 3/ bus 1,2,3,4 20

[

voltage-Loss of Voltage e.

ro b.

4.16 kV ESF Bus Under-voltage-Tolerable Degraded Voltage Coincident with SI 4/ bus 2/ bus 3/ bus 1,2,3,4 20

[

w A

c.

4.16 kV ESF Bus Under-t voltage - Sustained w

A Degraded Voltage 4/ bus 2/b'us 3/ bus 1, 2, 3, 4 '

20 i

i 9.

Engineered Safety Features

[

Actuation System Interlocks e

a.

Pressurizer Pressure, 3

2 2

1,2,3 21 3.

P-11

-}

e 4

2 3

1,2,3 21 7

b.

Low-Low T,yg, P-12 F

c.

Reactor Trip, F-4 2

1 2

1,2,3 23

$g.

an f

k i

t i

TABLE 3.3-3 u ntinutd)

[

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 2

M MINIMUM 5

TOTAL NO.

CHANNELS CHANNELS APPLICABLE 7 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

$ 10.

Control Room Ventilation U

Manual Initiation 3(1/ train) 2(1/ train) 3(1/ train)

All 27 a.

[

b.

Safety Injection See Item 1. above for all Safety Injection initiating-l functions and requirements.

m c.

Automatic Actuation Logic 3

2 3

All 27 and Actuation Relays i

d.

Control Room Intake Air 2

1 2

All 28 i

Radioactivity - High m

I 2

e.

Loss of Power See Item 8. above for all loss of Power initiating functions and requirements.,

w m

11.

FHB HVAC a.

Manual Initiation 3(1/ train) 2(1/ train) 3(1/ train) 1, 2, 3, 4 or 29, 30 with irradiated fuel in spent fuel pool b.

Automatic Actuation 3

2 3

1, 2, 3, 4 or 29, 30 Logic and Actuation with irradi-i Relays ated fuel in spent fuel pool 3

c.

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

O d.

Spent Fuel Pool Exhaust 2

1 2

With irradi-30

.a Radioactivity - High ated fuel in o

spent fuel pool

_m TABLE 3.3-3 (Continued)

TABLE NOTATIONS I

- - Function is actuated by either actuation train A or actuation train B.

Actuation train C is not used for this function.

I

- - - Automatic switchover to containment sump is accomplished for each train using the corresponding RWST level transmitter.

Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.

##During CORE Ai.TERATIONS or movement of irradiated fuel within containment.

4

1. 1. Trip function automatically blocked above P-11 and may be blocked below P-11 when Low Compensated Steamline Pressure Protection is not blocked.

ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANOBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15 - With the number of OPERA'BLE channels one less than the Total Number of Channels, operatio'n may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the l

inoperable channel.is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

4 ACTION 16 - With the Charging Header Pressure channel inoperable:

l i

a)

Place the Charging Header Pressure channel in the tripped condition within one hour and 4

b)

Restore the Charging Header Pressure channel.to operable status within 7 days or be in at least Hot Standby within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in Cold Shutdown within the following

)

-30 hours.

. ACTION 17 - With the number of OPERABLE channels one less than the Total Number of Chann.els, operation may proceed provided the inoperable channel is placed in'the bypassed condition.and the Minimum r

Channels OPERABLE requirement is met. One additional channel may be bypassed for~ up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

)

' ACTION 18 - With less than the' Minimum Cha'nnels OPERABLE requirement, i

operation may continue provided the containment purge supply j

and exhaust valves are maintained closed.

SOUTH TEXAS - UNITS 1 & 2 3/4 3-26 Unit 1 - Amendment No. J,4

( ?

TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACTION 19 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 20 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed prov.ided the following conditions are satisfied; The inoperable channel is placed in the tripp~ed condition a.

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 21 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, ~or apply Specification 3.0.3.

ACTION 22 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 23 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 24 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.

ACTION 25 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

1 SOUTH TEXAS - UNITS 1 & 2 3/4 3-27 Unit 1 - Amendment No. 24 Unit 2 - Amendment No.14

TSI

-121 TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACTION 26 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, declare the affected Auxiliary Feedwater Pump inoperable and take ACTION required by Specification 3.7.1.2.

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ACTION 28

".nnee e,

u + s.. +.s.m_....w m_.e_ r. n..o _c o.. n o i_ e,. n.. _s m. m..m.,.,,. m_ e, +sse-9 th ".i,imum Channel: 0."E'i^SLE r ^uir :ent within i h ur f:012tc th: C,-tr:1 " :: Env^10p: :nd ::intain Operation ;f th venti-

!:ti:n :y:ter the 'iltered-recircul: tion :0dcr.

4-

."00 0 5 ;,d 0; With the number of OPERABLE channels less.than the Minimum, Channels OPERABLE requirement,'

hin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . initiate and. maintain operation of the Control Room Makeup and C1'eanup Filtration System (at 100% capacity) in the recirculation and makeup filtration mode.

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ACTION 30 - With irradiated fuel in the spent fuel pool: With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, fuel movement within the spent fuel pool or crane operation with loads over the spent fuel pool may proceed provided the FHB exhaust air filtration' system is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers.

SOUTH TEXAS - UNITS 1 & 2 3/4 3-28

Inserts to page 3/4 3 - 28 Insert 1 ACTION 27 For an INOPERABLE channel, declare its associated ventilation train INOPERABLE and carry out the actions of Specification 3.7.7 Insert 2 l

ACTION 29 For an INOPERABLE channel, declare its associated ventilation train INOPERABLE and carry out the actions of Specification 3.7.8 l

l-l s

E

'ww*

~ ~

i i

4 1

i TABLE 3.3-4 ENGINEERED SAFETY FE.f0RES ACTUATION SYSTEM INSTRUMENTATION TRIP SSTPOINTS d

g TOTAL SENSOR ERROR i

g FUNCTIONAL UNIT ALLOWANCE (TA)

Z (S)

TRIP SETPOINT ALLOWABLE VALUE 1.

Safety Inject.fon (Reactor Trip.

(

3 Feedwater Isolation, Control 1

Room Emergency Ventilation, Start Standby Diesel Generators, Reactor s

l Containment Fan Coolers, and Essential Cooling Water) i m

a.

Manual Initiation N.A.

N.A.

b.

Automatic Actuation, Logic N.A.

N.A.

N. A.

c.

Actuation Relays N.A.

N.A.

d.

Containment Pressure--Nigh 1 3.6 0.7 2.0 1 3.0 psig 1 4.0 psig l

e.

Pressurizer Pressure--Low 19.6 17.4 2.0

> 1857 psig 1 1851 psig l

1 f.

Compensated Steam Line 16.4 12.8 2.0 1 735 psig 2 709 psiq*

l Pressure-Low

.- c-

5. 5.

t 2.

Containment Spray

~"

y-a.

Manual Initiation N.A.

N.A.

?E 2@

b.

Automatic Actui.fon Logic N.A.

N.A.

l TS 22 c.

Actuation Relays N.A.

N.A.

-e d.

C atainment Pressure--Nigh-3 3.6 0.7

2. 0

$ 9.5 psig 5 10.5 psig l

i c

e l

TABLE 3.3-4 (Continued) 8 h

ENGINEERED SAFETY FFATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS h

TOTAL SENSOR ERROR 3 FUNCTIONAL UNIT ALLOWANCE (TA)

Z (S)

TRIP SETPOINT ALLOWABLE VALUE t

[

3.

Containment Isolation a.

Phase "A" Isolation

[

1) Manual Initiation N.A.

N.A.

e'

2) Automatic Actuation 1.ogic N.A.

H.A.

N.A.

3). Actuation Relays N.A.

N.A.

H. A. '

N.A.

4) Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.

b.

Containment Ventilation Isolation m1

1) Automatic Actuation H.A.

N.A.

y N -Logic U

2) Actuation Relays N.A.

N.A.

H.A.

N.A.

3) Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and All'owable Values.

1

4) RCB Purge 3.1x10 1.8x10 1.3x10

<5x10 4

<6.4x10 4

^

~

Radioactivity-High pCi/cc pCi/cc pCi/cc pCi/cc pCi/cc gg

?%

5) Containment Spray -

See Item 2. above for Containment Spray manual initiation Trip Manual Initiation Setpoints an,d Allowable Values.

m.-.

6) Phase "A" Isolation -

See Item 3.a. above for Phase "A" Isolation manual initiation

((

Manual Initiation Trip Setpoints and Allcwable Values.

c.

Phase "B" Isolation

}{

1) Automatic Actuation N.A.

N.A.

{

((

Logic

??

2-) Actuation Relays N.A.

N.A.

a9

3) Containment Pressure--

~3.6 0.7 2.0 1 9.5 psig i 10.5 psig l

~

High-3

4) Containment Spray-See Item 2. above for Containment Spray manual initiation Trip Manual Initiation Setpoints and Allowable Values.

l

C TABLE 3.3-4 (Continued)

o h

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL SENSOR ERROR ALLOWANCE (TA)

Z (S)

TRIP SETPOINT'~ ALLOWABLE VALUE g FUNCTIONAL UNIT Y

d.

RCP Seal Injection Isolation 5

1) Automatic Acutation N.A.

N.A.

~.;

Logic and Activation Rel'ays

2) Charging Header 4.6 1.0 2.0 1 560.0 psig 1 495.4 psig Pressure - Low

~

Coincident with See Item 3.a. above for Phase "A" Isolation Setpoints and Allowable Phase "A" Isolation Values 4.

Steam Line Isolation I

R a.

Manual Initiation N.A.

N.A.

a Y

b.

Automatic Actuation Logic H.A.

N.A.

H.A.

N. A.-

O and Actuation Relays c.

Steam Line Pressure -

2.6 0.5 0

< 100 psi

-< 126 osi++

l Negative Rate--High 99 d.

Containmenti Pressure -

3.6 0.7 2.0

< 3.0 psig

< 4.0 psig l

.?

High-2 Compensated ~ Steam Line 16.4 12.8

2. 0

> 735 psig 2 709 psig*

v-e.

Pressure - Low

,p 5N R R 5.

Turbine Trip and Feedwater s2 Isolation

~H.A.

A'utomatic Actuattor. Logic N.A.

N.A.

a.

2

.P

.and Actuation Relays o

b.

Steam Generator Water 10.8 6.5 2.0+0.2#

< 87.5% of

< 89.a % of l

iiarrow range narrow range Level--High-High (P-14) instrument instrument

span, span.

t c.

Deleted

[

k TABLE 3.3-4 (Continued)

. ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS M

TOTAL SENSOR ERROR y FUNCTIONAL UNIT ALLOWANCE ~(TA)

Z (S)

~

TRIP SETPOINT ALLOVABLE VALUE 5.

Turbine Trip and Feedwater E

Isolation (Continued)

[

d.

Deleted e.

Safety Injection See Item 1 above for all Safety Injection Trip

[

Setpoints and Allowable Values.

4.5 1.1 0.8

> 574*F

> 571.7 'F l

T,yg-Low Coincident with f.

Reactor Trip (P-4)

(Feedwater Isolation Only)

[

6.

Auxiliary Feedwater b

Manual Initiation N.A.

N.A.

a.

b.

Automatic Actuation Logic N.A.

N.A.

c.

Actuation Relays N.A.

N.A.

!I. A.

?E d.

Steam Generator Water 20.0 15.3 2.0+0.2#

> 33.0% of

> 30.7% of l

narrow range narrow range Level--Low-Low instrument instrument

span, span.

". ~.

FF e.

Safety Injection See Item 1. above for' all Safety Injection Trip Setpoints and Allowable Values.

gg

?%

I 5,-.

.O St e

TABLE 3.3-4 (Continued) v, 8

5p ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

-e

!?

TOTAL SENSOR ERROR

$; FUNCTIONAL UNIT ALLOWANCE (TA)

Z (S)

TRIP SETPOINT ALLOWABLE VALUE 6.

Auxiliary Feedwater (Continued) 5 Ci f.

Loss of Power (Motor See Item 8. below for all Loss of Power Trip Driven Pumps Only)

Setpoints and Allowable Values.

e.

7.

Autopatic Switchover to m

Containment Sump a.

-Automatic Actuation Logic N.A.

N.A.

and Actuation Relays t'

b.

RWST Level--Low-Low 5.0 1.21 2.0

-> 11%

~> 9.1%

Coincident With:

i' Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable t'

Values.

8.

Loss of Power a.

4.16 kV ESF Bus Undervoltage N.A.

N.A.

> 3107 volts

> 2979 volts (Loss of Voltage)

Gith a < 1.75 Gith a < 1.93 second time second time delay.

delay.

b.

4.16 kV ESF Bus Undervoltage N.A.

N.A.

> 3835 volts

> 3786 volts (Tolerable Degraded Veltage With a < 35 Gith a < 39 Coincident with SI) second time second Time delay.

delay.

i c.

4.16 kV ESF Bus Undervoltage N.A.

N.A.

> 3835 volts

> 3786 volts (Sustained Degraded Voltage)

Gith a < 50 Gith a < 55 second time second Time delay.

delay.

6

TABLE-3.3-4 (Continued) 8 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 5

x M

TOTAL SENSOR ERROR ALLOWANCE (TA)

Z (S)

TRIP SETPOINT ALLOWABLE VALUE y FUNCTIONAL UNIT

[

9.

Engineered Safety Features 4

Actuation System Interlocks Pressurizer Pressure, P-11 N.A.

N.A.

5 1985 psig 51995 psig l

z a.

N.A.

> 563*F

> 560.7 *F l

Low-tow T,yg, P-12

[

b.

Reactor Trip, P'-4 H.A.

N.A.

c.

10. Control Room Ventilation Manual Initiation N.A.

N.A.

j y

a.

See Item 1. above for all Safety Injection Trip b.

Safety Injection Setpoints and Allowable Values.

Automatic Actuation Logic N.A.

N.A.

c.

and Actuation Relays

d. i Control Room Intake Air 3.7x10 s 2.2x10 5 1.6x10 5

<6.1x10 5

<7.8x10 5 i

((

Radioactivity - High pCi/cc pCi/cc pCi/cc pCi/cc FCi/cc See Item 8. above for all Loss of Power Trip Setpoints and i

a.

Loss of Power Allowable Values.

1 FF 65 11.

FHB HVAC Manual Initiation N.A.

N.A.

l wa a.

AA 55 l

o t.

.3 -

-- = -

+

a TABLE 3.3-4 (Continued)

~-

-co8.

5$

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

{

h!

TOTAL SENSOR ERROR d; FUNCTIONAL UNIT-ALLOWANCE (TA)

Z (S)

TRIP SETPOINT ALLOWABLE VALUE h 11. FHBfVAC'(Continued) b!

b.

Automatic Actuation N.A.

N.A.

-Logic and Actuation 7

e.

Relays m

c.

Safety Injection See Item 1. above for all Safety Injection Trip Setpoints'and Allowable Values.

d.

Spent Fuel Pool Exhuast

-3.1x10 4 1.8x10 4 1.3x10 4

<5.0x10 4

<6.4x10 4 gg Radioactivity - High pCi/cc pCi/cc pCi/cc pCi/cc pCi/cc s.

~

M i

b i

i t

l 1

2 I

a

TABLE 3.3-4 (Continued)

TABLE NOTATIONS 4

Time constants utilized in the lead-lag controller for Steam Line Pressure-Low are 7, 2 50 seconds and 7, s 5 seconds. CHANNEL CALIBRATION shall ensure that these time constants are adjusted to these values.

- The time constant utilized in the rate-lag controller for Steam Line Pressure-Negative Rate-High is greater than or equal to 50 seconds.

CHANNEL CALIBRATION shall ensure that this time constant is adjusted to this value.

2.0% span for Steam Generator Level;'O.2% span for Reference Leg RTDs.

ff Deleted.

l

1. 1. This setpoint value may be increased up to the equivalent limits of ODCH Control 3.11.2.1 in accordance with the methodology and parameters of the ODCH during containment purge or vent for pressure control, ALARA and respirable air quality considerations for personnel entry.

l SOUTH TEXAS - UNITS 1 & 2 3/4 3-36 Unit 1 - Amendment No. 4,4,47, 61 Unit 2 - Amendment No. 36,50 l

TABLE 3.3-5 (This table number not used) 4 SOUTH TEXAS - UNITS 1 & 2 3/4 3-37 Unit 1 - Amendment No. 50 Unit 2 - Amendment No. 39

1 l

\\

TABLE 3.3-5 (Continued) i i

(This table number not used) l 1

l i

I l

1 i

d i

1 SOUTH TEXAS - UNITS 1 & 2 3/4 3-38 Unit 1 - Amendment No. 4, 50 Unit 2 - Amendment No. 39

l TABLE 3.3-5 (Continued)

(This table number not used) e l

I SOUTH TEXAS - UNITS 1 & 2 3/4 3-39 Unit 1 - Amendment No. 50 Unit 2 - Amendment no. 39

TABLE 3.3-5 (Continued) 1 (This table number not used) 1, I

e i

l l

i 1

l

'I SOUTH TEXAS UNITS 1 & 2 3/4 3-40 Unit 1 - Amendment No. % 50 Unit 2 - Amendment No. 39

l TABLE 3.3-5 (Continued) l (This table number not used) 1

\\

i l

i SOUTH TEXAS - UNITS 1 & 2 3/4 3-41 Unit 1 - Amer.dment No. 50 Unit 2 - Amen'iment No. 39

IABLE 4.3-7 O5 ENGINEERED SATITY FEAIURES ACTUATION SYSTEM IMSTRUMENTATION

)

-~~' SURVIl[llANCLREQUIREMENIS DIGITAL OR TRIP ANALOG ACTUATING MODES h

CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL CHANNFL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE g FUNCTIONAL UNIT CHECK CAllBRATION TEST TEST LOGIC TEST TEST TEST IS R6(UIRED

[

1. Safety Injection (Reactor Trip, Feedwater Isolation, m

Control Room Emergency Ventilation, Start Standby Diesel Generators Reactor Containment Fan Coolers, and Essentini Cooling Water) ys

[

a. Manual Inttiatton N.A.

N.A.

R N.A.

M.A.

N.A.

1,2,3,4

b. Automatic Actuation N.A.

N.A.

Q(1)

N.A.

1, 2, 3, 4 l

Logic

c. Actuation, Relays N.A.

N.A.

Q(6)

Q(4.5) 1, 2, 3, 4 l

d. Containment Pressure-S R

Q N.A.

N.A.

M.A.

1,2,3,4 l

High-1 j

r" m-

e. Pressurizer Pressure-S R

Q N.A.

N.A.

M.A.

N.A.

1,2,3 l

pp Low eo

f. Compensated Steam Line S

.i Q

N.A.

M.A.

N.A.

1,2,3 l

a g,

Pressure-Low e c.

O C.~

E e

I Allil 4.3-2 (Continued),

m8 7,*

[NGINEERr0 SAffTY FEA1URI5 ACTUATION SYSTEM INSTRUMENTATION 5tlRVI llI ANCI', RigtllR_I Ml_Nis 2;

DIGIIAL OR TRIP ANALOG ACTUATING MODES CHANNLL DEVICE MASTER SLAVE FOR WHICN c-5 CNANNEL CilANNEL CilANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE TJ FUNCTIONAL UNIT CHECK CAllBRA110N IL5T TEST LOGIC TEST TEST TEST IS REQUIRED

2. Containment Spray c.

~

a. Manual Initiation N.A.

N. A.

N.A.

R N.A.

N.A.

1,2,3,4 b.' Automatic Actuation N.A.

N.A.

Q(1)

N.A.

1,2,3,4 l

Logic

c. Actuation Relays N.A.

N.A.

Q(6)

Q 1,2,3,4 l

w A

d. Containment Pressure-S R

Q N.A.

N.A.

1, 2, 3 l

High-3

3. Containment Isolation

a. Phase "A" Isolation

1) Manual li.itiation N.A.

N. A.

N.A.

R N.A.

N. A.

N.A 1,2,3,4 ec

2) Automatic Actuation N.A.

N.A.

g(1)

N.A.

1,2,3,4 l

logic

{

3) Actuation Relays N.A.

N. A.

N.A.

.N.A.

N.A.

Q(6)

Q(4) 1, 2, 3, 4 l

FF

4) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

((

b ' ntainment Ventilation Isolation am

((

1) Automatic Actuation N. A.

N.A.

N. A.

N.A.

Q(1)

N.A.

1, 2, 3, 4 l'

yy 1.ogic gg

2) Actuation Relays N.A.

N. A.

N.A.

Q(6)

Q 1,2,3,4 l

c.

7 1ABLE4.3-2(Co..inued),-

'8 ENGINEERED SArt.1Y FEATURES ACTUATION SYSTEM INSTRUMENTATION-i SURVEILLANCE REQUIREMENTS M

OIGITAL-OR TRIP 5

ANALOG ACTUATING MODES-CHANNEL

- DEVICE MASTED SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION.

RELA'

'ELAY SURVEILLANCE E-FUNCTIONAL UNIT CHECK CAllBRATION TEST TEST

-LOGIC TEST TEST IEST IS REQUIRED U

3. Containment Isolation-(Continued)

[

3) Safety Injection See item 1. above for all Safety Injection' Surveillance Requirements.

i) RCB Purge

~

Radioactivity-High 5

R Q

N.A.

N. A.

1,2,3,4,5*,6*

l

5) Containment Spray -

See Item 2. above for Containment Spray manual initiation Surveillance Manual Initiation Requirements.

6) Phase "A" Isolation-See Item 3.a. above for Phase "A" Isolation manual initiation

+

w 1

Manual Initiation Surveillance Requirements.

c. Phase "B" Isolation

1) Automatic Actuation N.A.

N.A.

Q(1)

N.A.

1,2,3,4 l

Logic

2) Actuation Relays N.A.

N.A.

Q(6)

Q 1,2,3,4 l

3) Containment S

R Q

N.A.

1,2,3 l

Pressure--High-3

~~

4) Containment Spray-See Item 2. above for Containment Spray manual initiation Surveillance Requirements.

Manual Initiation FF 4

gg

d. RCP Seal Injection gg Isolation mm AA

1) Automatic Actuation N.A N.A.

N.A.

Q Q

1,2,3,4 gg togic and Actuation Relays

2) Charging Header S

R Q

N.A.

1,2,3,4 l

u, Pressure - Low Coincident with See Item 3.a. above for Phase "A" surveillance requirements.

l Phase "A" Isolation i

t m

m

TABLE _4.3-2 (Continued) i w

'Eg ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEitLANCE REQUIREMENTS O?

OlGITAL OR TRIP ANALOG ACTUATING MODES e

CHANNEL DEVICE MASTER SLAVE FOR WHICH 5

CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE d

. FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST 15 REQUIRED a

e

4. Steam Line Isolation ro

a. Manual Initiation N. A.

N.A.

R N.A.

N.A.

1, 2, 3

b. Automatic Actuation N.A.

N.A N.A N.A.

Q(1)

Q(6)

Q 1,2,3 l

Logic and Actuation h

Relays

c. Steam Line Pressure-S R

Q N.A.

N.A.

3 l

y Negative Rat. *High t

?

d. Containmenc. Pressure -

S R

Q N.A.

N.A.

1,2,3 l

High-2

~

e. Compensated Steam Line S

R Q

N.A.

1,2,3 l

Pressure-Low

s

5. Turbine Trip and Feedwater Isolation 3-r I

N.A.

Q(1)

Q(6)

Q(4) 1, 2; 3 l

l

a. Automatic Acteation N.A.

'g Logic and Actuation Relays

., 2

.E

b. Steam Generator Water S

R Q

N.A.

1,2,3 l

Level-High-High (P-14) 2

,o

c. Deleted m

a.

d. Deleted

e. Safety Injection See Iter 1. above for all Safety Injection Surveillance Requirements.

l

TABLE 4.3-2 (Continued)

ENGINEERED SArtiY l'lAIURLS ACIUAll0N SYSIEM INSTRUMENTATION y'i 1

NRVEILtANCE REQUlREMENI5 DIGITAL OR

'1 RIP W

ANAL.0G ACTUATING MODES U

CilANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE g FUNCTIONAL UNIT CHECK CAllBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED 3

5. Turbine Trip and Feedwater i

lsolation (Continued)

f. T

-L w Coincident S

R Q

N.A.

1,2,3 l

avg with Reactor Trip (P-4)

(Feedwater Isolation Only)

6. Auxiliary Feedwater

a. Manual Initiation N.A.

N. A.

N.A.

R N.A.

N.A.

1,2,3

~

i y

b. Automatic Actuation N.A.

N.A.

Q(1)

N.A.

1,2,3 l

g logic

c. Actuation Relays N.A.

N.A.

N. A.

N.A.

Q(6)

Q 1, 2, 3 l

d. Steam Generator Water S

R Q

N.A.

N.A N.A 1,2,3

[

f Level--Low-tow

e. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

f. Loss of Power See Item 8. below for all Loss of Power Surveillance Requirements.

CC11 7.

Automatic Switchover to

((

Containment Sump

a. Automatic Actuation N.A.

N.A.

N. A.

N.A.

Q(6)

Q 1,2,3,4 l

TF Logic and Actuation i

((

Relays 35

b. RWST Level--Low-low 5

R Q

N.A.

N.A 1,2,3,4 l

~

3A Coincident With, t

?

Safety Injection See Item 1. above for all Safety injection Surveillance Requirements.

j we m --

m

_ TABLE 4.3-2 (Continued) u Uy ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS h

DIGITAL OR TRIP ANALOG ACTUATING MODES e

CHANNEL DEVICE MASTER SLAVE. FOR WHICH

.5-CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE 1

d FUNCTIONAL UNIT CHECK CAllBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED c-

8. Loss of Power

~

a. 4.16 kV ESF Bus N.A.

R N.A Q

N.A.

N. A.

N.A.

1, 2, 3, 4 l

Undervoltage (Loss of Voltage) w

b. 4.16 kV ESF Bus N. A.

R N.A.

Q N.A.

N.A.

1,2,3,4 l

1 Undervoltage (Tolerable Degraded Voltage w

g Coincident with SI)

c. 4.16 kV ESF Bus N.A.

R N. A.

Q N.A.

N.A.

1,2,3,4 l

Undervoltage (Sustained Degraded Voltage)

=c 3.3.

9. Engineered Safety Features Actuation

"~

System Interlocks FF

a. Pressurizer N.A.

R Q

N.A.

1,2,3 I

Q Pressure, P-11 3 3

[}

h. Low-Low T,y. P-12 N.A.

R Q

N.A.

1,2,3 l

l o"

c. Reactor Trip, P-4 N.A.

N.A N.A.

R N.A.

N.A.

1, 2, 3 07 10. Control Room Ventilation

a. Manual Initiation N.A.

N.A.

R N.A.

N.A.

All 5

w TABLE 4.3-2 (Continued)

S ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

[

SURVEILLANCE REQUIREMENTS

=g DIGITAL TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH E.

CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE y

FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED

[ 10. Control Room Ventilation (Continued)

b. Safety Injection See Item 1. above' for all Safety Injection Surveillance Requirements.

c. Automatic Actuation N.A.

N. A.

N.A.

Q(6)

N.A.

All l

Logic and Actuation Relays s^

d. Control Room Intake Air S R

Q N.A.

N.A.

All l

1 Radioactivity-High co

e. Loss of Power See Items 8. above for all loss of Power Surveillance Requirements.

11. FHB HVAC

a. Manual Initiation N.A.

N.A.

R N.A.

N.A.

1,2,3,4, WE or with i

irradiated fuel in the spent fuel yp pool ee RR

b. Automatic Actuation N.A.

N.A.

N. A.

N.A.

Q(6)

N.A.

1,2,3,4,l 44 Logic and Actuation or with EA Relays irradiated y=

fuel in the

??

spent fuel pool s c.,

we v

i

m -

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

['

g SURVEILLANCE RE0UIREMENTS m;;

' DIGITAL OR TRIP-a ANALOG ACTUATING MODES

~g.

CHANNEL DEVICE MASTER SLAVE FOR WHICH i

g._ CHANNEL-CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY ' RELAY SURVEILLANCE ~

m FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST-IS REQUIRED-i 11.

FHB HVAC.(Continued) t to l

c. -Safety Injection See Item 1. above for a!' Safety Injection Surveillance Requirements.

i l

d.

Spent Fuel Pool S

R Q

N.A.

With i

Exhaust Radio-irradiated activity-High fuel in spent fuel pool.

l m

?

[

TABLE NOTATION

{

h (1)

Each train shall be tested at least every 92 days on a STAGGERED TEST BASIS.

l l

(2) Deleted (3) Deleted

~

(4)

Except relays K807, K814, K829 (Train B only), K831, K845, K852 and K854 (Trains B and C only) which ccaa shall be tested at least once per 18 months during refueling and during each COLD SHUIDOWN exceeding 24 i

hours unless they have been tested within the previous 92 days.

N (5)

Except relay K815 which shall be tested at indicated interval only when reactor coolant pressure is above I

700 psig.

.i

!g (6)

Each actuation train shat > be tested at least every 92 < lays on a STAGGERED TEST BASIS. Testing of each 9-g-actuation train shall inttude master relay-testing of both logic trains.

If an ESFAS instrumentation jg channel is inoperable due to failure of the Actuation Logic Test and/or Master Relay Test, increase the surveillance frequency such that each train is tested at least every 62 days on a STAGGERED TEST BASIS

-r gg unless the failure can be determined by performance of an engineering evaluation to be a single random failure.

O.**'

E

During CORE ALTERATIONS or movement of irradiated fuel within containment.

PLANT SYSTEMS 3/4.7.7 CONTROL ROOM MAKEVP AND CLEANUP FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.7 Three independent Control R:om Makeup and Cleanup Filtration Systems shall be OPERABLE.

APPLICABILITY: All MODES.

ACTION:

MODES 1, 2, 3 and 4:

a.

With one Control Roort. Makeup and Cleanup Filtration System inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With two Control Room Makeup and Cleanup Filtration Systems inoperable, restore at least two systems to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and l

in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

"5 EDES 5 and 6:

a.

With one Control Room Makeup and Cleanup Filtration System inoperable, restore the inoperable system to CPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE Control Room Makeup and Cleanup Filtration Systems in the recirculation and makeup air filtration mode,A<xwsser 4).

b.

With two Control Room Makeup and Cleanup Filtration Systems inoperable, or with the OPERABLE Control Room Makeup and Cleanup Filtration System, required to be in the recirculation and makeup air filtration mode by ACTION a., not capable of being powered by an OPERABLE emergency power source, suspend.a'll operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE PE0VIREMENTS 4.7.7 Each Control Room Makeup and Cleanup Filtration System shall be demonstrated OPERABLE:

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air a.

temperature is less than or equal to 7FF;

b. ~ At least once per 92 days on a STAGGERED TEST BASIS by initiating, l

from the control room, flow through the HEPA filters and charcoal adsorbers of the makeup and cleanup air filter units and verifying that the system operates for at least 10 continuous hours with the makeup filter unit heaters operating; SOUTH TEXAS - UNITS 1 & ?

3/4 7-16 Unit 1 - Amendment No. 59 Unit 2 - Amendment No. 47

i Inserts to Page 3/4 7 - 16 Insert 3 With three Control Room Makeup and Cleanup Filtration Systems inoperable, c.

restore at least one system to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Insert 4 4

, or suspend all operations involving CORE ALTERATIONS, movement of spent fuel,

- and crane operation with loads over the spent fuel pool.

1

)

'1 4

+

r' w

e m

-c--

--*'e

PLANT SYSTEMS EURVJ{J!14NICLRE@lBEMENTS (ContinueID c.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communi-cating with the system by:

1)

Verifying that the makeup and cleanup systems satisfy the in place penetration and bypass leakage testing acceptance criteria of less than 0.05% for HEPA filter banks and 0.10% for charcoal adsorber banks and uses the test procedure guidance in Regulatory Positions C.S.a, C.S.c, and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 6000 cfm i 10% for the cleanup units and 1000 cfm i 10% for the makeup units; 2)

Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accor-dance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revi-sion 2, March 1978, for a methyl iodide penetration of less than 1.0% when tested at a temperature of 30 C and a relative humidity of 70%; and 3)

Verifying a system flow rate of 6000 cfm 10% for the cleanup units and 1000 cfm i 10% for the makeup units during system operation when tested in accordance with ANSI N510-1980.

d.

Af ter every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of char c.dscrber operat.iom by verifying, within 31 days after removal, t.s a lai, oratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing triteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1.0% when tested at a temperature of 30 C and a relative humidity of 70%;

e.

At least once per 18 months by:

1)

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6.1 inches Water Gauge for the makeup units and 6.0 inches Water Gauge for the cleanup units while operating the system at a flow rate of 6000 cfm i 10% for the cleanup units and 1000 cfm i 10% for the makeup units; 2)

Verifying that on a control room emergency ventilation test signal (High Radiation and/or Safety Injection test signal), the system automatically switches into a recirculation and makeup air filtration mode of operation with flow through the HEPA filters and charcoal adsorber banks of the cleanup and makeup units; SOUTH TEXAS - UNITS 1 & 2 3/4 7-17

- -.. - - -. ~. -... _ -

.i PLANT SYSTEKS 1

SURVEILLANCE RE0VIREMENTS (Continued) 4 3)

Verifying that the system maintains the control room envelope at a positive pressure of greater than er equal to 1/8 inch Water Gauge at less that or equal to a pressurization flow of 2000 cfm relative to adjacent areas' during system operation; and l

i 4)

Verifying that the makeup filter unit heaters dissipate 4.5 i i

0.45 kW when tested in accordance with ANSI N510-1980.

i f.

After each complete or partial replacement of a HEPA filter bank, by verifying that the llEPA filter bank satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI H510-1980 for a DOP test aerosol while operating the system at a flow rate of 6000 cfm i 10% for the cleanup units and 1000 cfm i 10% for the makeup units; and g.

After each complete or partial replacement of a enarcoal adsorber bank, by verifying that the charcoal adsorber bank satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.10% in accordance with ANSI N510-1960 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 6000 cfm i 10% for the cleanup units and 1000.cfm i 10% for the makeup units.

4 SOUTH TEXAS - UNITS 1 & 2 3/4 7-18 Unit 1 - Amendment No. 7,88 Unit 2 - Amendment No. 75

+

i.

PLANT SYSTEMS 3/4.7.8 FUEL HANDLING BUILDING (FHB) EXHAUST AIR SYSTEM l

QITINGCONDITIDNFOROPERATION 3.7.8 The FHB Exhaust Air System comprised of the following components shall be OFERABLE:

Two independent exhaust air filter trains, Q

^

a.

b.

Three hd;gniat exhaust 5:::t:;- f:::/- Gm4-M.kon +rmns]

t ee " & p d nt 2 9 & r t f:r, : d

^

i

^:ce & th 9 ;:r:.

APPLICABIL'ITYI H0 DES 1, 2, 3, and 4.

1 i

ACTION:

,fTi~ MSEEr 5) l With le s than the ove FHB aust Ai System mponents OP BLE but ith]

I i

at le t one FHB haust air 11ter tr in, two HB exhaust oster fa, two j

FHB ain exhaus fans and sociate ampers ERABLE, re ore the.

operable 3 sy em to OPE LE status ithin 7 ays or e in at lea HOT STA BY within /

4 i

e next 6 h rs and in OLD SHUI OWN wit n the foll ing 30 h rs f j

SUJLVEILLANCE REOUIREMENTS 4.7.,8. The Fuel Handling Building Exhaust Air System shall be demonstrated 4

OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by initiating, a.

from the control room, flow through the HEPA filters and charcoal 4

adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating with two of the three i

exhaust booster fans and two of the three main exhaust fans operat-ing to maintain adequate air flow rate; b.

At least once per 18 months and (1) after any structural maintenance on the.HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communi-i cating with the system by:

1)

Verifying that the cleanup system satisfies the in place penetration and bypass leakage testing hcceptance criteria of less than 0.05% for HEPA filter banks and 0.10% for charcoal adsorber banks and uses the test procedur,e. guidance in Regula-j tory Positions C.S.a. C.S.c, and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 29,000 cfm L

1 1M; 2)

Verifying, within 31 days after removal, that a ~aboratory analysis of a representative carbon sample obtained in accor-1 dance with Regulatory Position C.6.b of Regulatory Guide 1.52, SOUTH TEXAS - UNITS 1 & 2 5/4 7-19 I

~.

Insert 5 to Page 3/4 7 - 19 With one FHB exhaust air filter train inoperable, restore the inoperable filter train a.

to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With two FHB exhaust air filter trains inoperable, restore at least one inoperable filter train to OPERABLE status with 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With one FHB exhaust ventilation train inoperable, restore the inoperable c.

ventilation train to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

With more than one FHB exhaust ventilation train inoperable, restore at least two exhaust ventilation trains to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

1 l

l' i

i.

1 i

~ - -.

-~. - -. - --

l FLANT SYSTEMS i

i SURVEILLANCE REOUIREMENTS (Continued) l Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revi-sion 2, ll arch 1978, for a cothyl iodide penetration of less than 1.0% when tested at a temperature of 30*C and a relative l

humidity of 70%; and g

3)

Verifying a system flow rate of 29,000 cfm i 10% during system' operation with two of the three exhaust booster fans and two of the three main exhaust fans operati.ng when tested in accordance with ANSI H510-1980. All combinations of two exhaust booster l

fans and two main exhaust fans shall be tested.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal edsorber operation, by verifying, c.

within 31 days after removal, that a laboratory analysis of a j

representative. carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, l

meets the laboratory testing criteria of Regulatory Position C.6.a l

of Regulatory Guide 1.52, Revision 2. March 1978, for a methyl iodide penetration of less than 1.0% when tested at a temperature of j

30*C and,a relative humidity of 70%;

d.

At least once per 18 months by:

l 1)

Verifying that the pressure drop across the combined HEPA l

filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the system at a flow rate of 29,000 cfm i 10%,

2)

Verifying that the system starts on High Radiatioa and Safety Injection test signals and directs flow through the HEPA filters and charcoal adsorbers, 3)

Verifying that the system maintains the FHB at a negative pressure of greater than or equal to 1/8 inch Water Gauge relative to the outside atmosphere, and 4)

Verifying that the heaters dis ate 38 i 2.3 kW when tested in accordance with ANSI N510-1980 After each complete or partial replacement of a HEPA filter ba'nk, e.

by verifying that the HEPA filter bank satisfies the in place pene-tration and hypass leakage testing acceptance criteria of less than j

0.05% in accordance with ANSI H510-1930 for a DOP test aerosol while operating the system at a flow rate of 29,000 cfm i 10%; and f.

After each complete or partial-replacement of a charcoal adsorber bank, by verifying that the charcoal adsorber bank satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.10% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a j.

flow rate of 29,000 cfm i 10%.

I'

('*Duringth irstsixweeksa rMarch 28,1949(festing will be reconf'ed for)

( both r

.M and 38 kW heat

.f 1

1 SOUTH TEXAS - UNITS 1 & 2 3/4 7-20 Unit 1 - Amendment No. 6 4

m

~ REFUELING OPERATIONS 3/4.9.12 FUEL HANDLING BUILDING EXHAUST AIR SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 The FH8 Exhaust Air System' comprised of the following components shall be OPERABLE:

(

a.

Two exhaust air filter trains, i

b.

Two of thr= exhaust S=&r fr:,q@ilakion 4rtunQ g

c.

T= ;f thr= :& =h=:t fr:, =d g

d.

a: r 6 ted d p re.

APPLICABILITY.: Whenever irradiated fuel is in the spent fuel pool.

ACTION:

With less than the above FHB Exhvist Air System components OPERABLE a.

but with at least one FHB exhaust air filter train, one FHB exhaust

[venblA4cn WM QguatetAsn/EneqMB Aakn4xhaiusy farf. And/ assoc 4imd/dambert)

OPERABLE, fuel movement within the spent fue"I poo' or crane operation with 1 *ds over the spent fuel pool may proceed provided the OPERABLE FHL Maust Air System components are capable of being powered from an L BLE emergency power source and are in operation and discharging th. sugh at least one train of HEPA filters and charcoal absorbers, b.

With no FHB exhaust air filter train OPERABLE, suspend all

)

operations involving movement of fuel within the spent fuel pool or crane operation with loads over the spent fuel pool.

The provisions of Specification 3.0.3 are not applicable.

c.

SURVEILLANCE RE0VIREMENTS 4.9.12 The above required FHB Exhaust Air Systems shall be demonstrated OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by initiating, a.

from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating with the operable exhaust booster fans and the operable main exhaust fans operating to maintain adequate air flow rate;

' At least one FHB exhaust air filter train, one FHB exhaust booster fan, and one FHB main exhaust fan are capable of being powered from an OPERABLE onsite emergency power source.

SOUTH TEXAS - UNIls 1 & 2 3/4 9-14 Unit 1 - Amendment No. 71 Unit 2 - Amendment No. 60 a

3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION The 0FERABILITY of the Reactor Trip System and the Engineered Safety Features Actuation System instrumentation and interlocks ensures that:

(1) the associated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintaired, (3) sufficient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance, and (4) sufficient system functional capability is available from diverse parameters.

The OPERABILITY of these systems is required to provide the overall

. rcliability, redendhncy, and diversity assumed availabic in the facility design for the protection and mitigation of accident and transient conditions.

The integrated operation of each of these systems is consistent with tLa assumptions used in the safety analyses.

The Survsillance Requirements

. specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability. Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, " Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System," supplements to.that report, and the South Texas Project probabilistic safety assessment (PSA). SurYeillance intervals and out of service times were determined based on maintaining an appropriate level of reliability of the Reactor Protection System instrumentation.

The Engineered Safety Features Actuation System Instrumentation Trip Setpoints specified in Table 3.3-4 are the nominal values at which the bistables are set for each functional unit. A Setpoint is considered to be adjusted consistent with the nominal value when the "as measured" Setpoint is within the band allowed for calibration accuracy.

To accommodate the instrument drift assumed to occur between operational tests and the accuracy to which Set >oints can be measured and calibrated, Allowable Values for the Setpoints lave been specified in Table 3.3-4.

Operation with Setpoints less conservative than the Trip Setpoint but within the Allowable Value is acceptable since an allowance.has been made in the safety analysis to accommodate this error. An optional provision has been included for determining the OPERABILITY of a channel when its Trip Setpoint is found to exceed the Allowable Value. The methodology of this option utilizes the "as measured" deviation from the specified calibration point for rack and sensor components in conjunction with a statistical combination of the other' uncertainties of the instrumentation to measure the process variable and the-uncertainties in calibrating the instrumentation.

In Equation 2.2-1, Z + R + S s TA, the interactive effects of the errors in the rack-and the sensor, and the "as measured" values of tha errors are considered.

Z, as specified in Table 3.3 4, in percent span, is the statistical summation of errors assumed in the analysis excluding those associated with the sensor and rack drift and the accuracy of the measurement. TA or Total Allowance 4

- SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-1 March 16, 1994

%.w.,

,-r

.--y

INSTRUMENTATION BASES REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued) is the difference, in percent span, between the trip setpoint and the value used in the analysis for the actuation.

R or Rack Error is the "as measured" deviation, in the percent span, for the affected channel from the specified Trip Setpoint.

5 or Sensor Error is either the "as measured" deviation of the sensor from its calibration point or the value specified in Table 3.3-4, in percent span, from the analysis assumptions.

Use of Equation 2.2-1 allows for a sensor drift factor, an increased rack drift factor, and provides a threshold value for REPORTABLE EVENTS.

The cethodology to derive the Trip Setpoints is based upon combining all of the uncertainties in the channels.

Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties.

Sensor and rack instrumentation utilized in these channels are expected to be capable of operating within the allowances of these uncertainty magnitudes.

Rack drift in excess of the Allowable Value exhibits the behavict that the rack has not met its allowance.

Being that there is a small statistical chance that this will happen, an infrequent excessive drift is expected.

Rack or sensor drift, in excess of the allowance that is more than occasional, may be indicative of more serious problems and should warrant further investigation.

The measurement of response time at the specified frequencies provides assurance that the Reactor trip and the Engineered Safety Features actuation associated with each channel is completed within the time limit assumed ir. the safety analyses.

No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total channel response time as defined.

Sensor response time varification may be demonstrated by either:

(1) in place, onsite, or offsite test measurements, or (2) utilizing replacement sensors with certified response times.

The Engineered Safety Features Actuation System senses selected plant para-meters and determines whether or not predetermined limits are being exceeded.

If they are, the signals are combined into logic matrices sensitive to combina-tions indicative of various accidents, events, and transients.

Once the re-quired logic combination is completed, the system sends actuation signals to those Engineered Safety Features components whose aggregate function best serves the requirements of the condition.

As an example, the following actions may be initiated by the Engineered Safety Features Actuation System to mitigate the consequences of a steam live break or loss-of-coolant accident:

(1) Safety In-jection pumps start, (2) Reactor trip, (3) feedwater isolation, (4) startup of the standby diesel generators, (5) containment spray pumps start and automatic valves position, (6) containment isolation, (7) steam line isolation, (8) Tur-bine trip, (9) auxiliary feedwater pumps start and automatic valves position, (10) reactor containment fan coolers start, (11) essential cooling water pumps start and automatic valves position, (12) Control Room Ventilation Systems start, and (13) component cooling water pumps start and automatic valves position.

SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-2

INSTRUMENTATION BASES REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)

Radiation Monitoring Bases are discussed in Section 3/4.3.3.1 below.

i The Engineered Safety Features Actuation System interlocks perform the following functions:

P-4 Reactor tripped - Actuates Turbine trip via P-16, closes main feed-water valves on T below Setpoint, prevents the opening of the avg main feedwater valves which were closed by a Safety Injection or High Steam Generator Water Level and allows Safety Injection block so that components can be reset or tripped.

Reactor not tripped prevents manual block of Safety Injection.

P-11 On increasing pressurizer pressure, P-11 automatically reinstates Safety Injection actuation on low pressurizer pressure or low compen-sated steamline pressure signals, reinstates steamline isolation on low cog ensated steamline pressure signals, and opens the accumulator discharge isolation valves. On decreasing pressure, P-11 allows the manual block of Safety Injection actuation on low pressurizer pres-sure or low compensated steamline pressure signals, allows the manual block of steamline isolation on low compensated steamline pressure signals, and enables steam line isolation on high negative steam line pressure rate (when steamline pressure is manually blocked).

l P-12 On increasing reactor coolant loop temperature, P-12 automatically provides an arming signal to the Steam Dump System.

On decreasing reactor coolant loop temperature, P-12 automatically removes the arming signal from the Steam Dump System.

P-14 On increasing steam generator water level, P-14 automatically trips the turbine and the main feedwater pumps, and closes all feedwater isolation valves and feedwater control valves.

3/4. 3. 3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The OPERABILITY of the radiation monitoring instrumentation for plan' operations ensures that:

(1) the associated action will be initicted whei. the radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be out of service for testing or maintenance. The radiation monitors for plant operations sense radiation levels in selected plant systems and locations and determine whether or not predetermined limits are being exceeded.

If they are, the signals are combined into logic matrices sensitive to combinations iadicative of various accidents and abnormal conditions.

Once the required logic combination is completed, the system sendt actuation signals to initiate alarms or automatic isolation action and actuation of Emergency Exhaust or Ventilation Systems.

SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-3 Unit I - Amendment No. J,4

PLANT SYSTEMS BASES t

The limitations on minimum water level and maximum temperature are based on providing a 30-day cooling water supply to safety-related equipment without exceeding its design basis temperature and is consistent with the recommend-ations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants,"

Harch 1974.

3/4.7.6 (Not used) 3/4.7.7 CONTROL ROOM MAKEUP AND CLEANUP FILTRATION SYSTEM The OPERABILITY of the Control Room Makeup and Cleanup Filtration System

. ensures that: (1) the ambient air temperature does not exceed the allowable temperature for continuous-duty rating for the equipment and instrumentation cooled by this system, and (2) the control room will remain habitable for operations personnel during and following all credible accident conditions.

Operation of the system with.the heaters operating for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rems or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A,10 CFR Part 50. ANSI H510-1980 will be used as a procedural guide for surveillance testing. $ 1nster W 3/4.7.8 FUEL HANDLING BUILDING EXHAUST AIR SYSTEM Gnu,&

The OPERABILITY of the Fuel Handling Building Exhaust Air System ensures that radioactive materials leaking from the ECCS equipment within the FHB fol-lowing a LOCA are filtered prior to reaching the environment.

Operation of the system with the heaters operating for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. The operation of thir system and the resultant effect on offsite dosage calculations was assumed in the safety analyses.

ANSI N510-1980 will be used as a procedural guide for surveillance testing.

3/4.7.9 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant System and all other safety-related systems is main-tained during and fo11owin2 a seismic or other event initiating dynamic loads.

Snubbers are classified and grouped by design and manufacturer but not by size.

For example, mechanical snubbers utilizing the same design features of the 2-k'ip, 10-kip and 100-kip capacity manufactured by Company A" are of the same type. The same design mechanical snubbers manufactured by Company "B" for the purposes of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.

A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance

. SOUTH TEXAS -' UNITS 1 & 2 B 3/4 7-4 Unit 1 - Amendment No. 19 Unit 2 - Amendment No. 9

./

i Inserts to page B 3/4 7 - 4 Insert 6 The time limits associated with the ACTIONS to restore an inoperable train to i

i OPERABLE status are consistent with the redundancy and capability of the system and l

the low probability of a design basis accident while the affected train (s) is out of serv ce.

A limited allowed outage time is allowed for all three trains to be out of service simultaneously in recognition of the fact that there are common plenums and some j

maintenance or testing activities require opening or entry into these common plenums.

This is acceptable based on the low probability of a design basis event in that brief allowed outage time and because administrative controls are imposed on the activities that provide for compensatory action to restore integrity of the system.

Insert 7 The FHB exhaust air system is comprised of two independent exhaust air filter trains and three exhaust ventilation trains. Each of the three exhaust ventilation trains has a main exhaust fan, an exhaust booster fan, and associated dampers. The main exhaust fans share a common plenum and the exhaust booster fans share a common plenum. An OPERABLE ventilation exhaust train consists of any OPERABLE main exhaust fan, any OPERABLE exhaust booster fan, and appropriate OPERABLE dampers.

Insert 8 The time limits associated with the ACTIONS to restore an inoperable train to OPERABLE status are consistent with the redundancy and capability of the system and the low probability of a design basis accident while the affected train (s) is out of service.

A limited allowed outage time is allowed for both exhaust air filter trains or all three exhaust ventilation trains to be out of service in recognition of the fact that there are common plenums and some maintenance or testing activities that require opening or entry into these common plenums This is acceptable based on the low probability of a design basis event in that brief allowed outage time and because administrative controls are imposed on the activities that provide for compensatory action to restore integrity of the system.

i l

REFUELING OPERATI0ld BASES 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that:

(1) sufficient cooling capacity is available to 4

remove decay heat and maintain the water in the reactor vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.

1 i

The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal casability. With the reactor vessel head removad and at least 23 feet of water a)ove the reactor pressure vesal flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.

3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge and exhaust penetrations will be automatically isolated upon detection of high radiation levels in the purge exhaust. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

3/4.9.10 and 3/4.9.11 WATER LEVEL - REFUELING CAVITY AND STORAGE POOLS The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the safety analysis.

3/4.9.12 FUEL HANDLING BUILDING EXHAUST AIR SYSTEM @Meer 0 The limitations on the Fuel Handling Building Exhaust Air System ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. Operation of the system with the heaters operating for at least 10 continuous ho~urs in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses. ANSI N510-1980 will be used as a procedural guide for sureillance testing. This Specification has been modified by a note that states, at least one FHB exhaust air filter train, one FHB exhaust booster fan, and one FHB main exhaust fan are capable of being powered from an Onsite emergency power source. This notes ensures that required FHB exhaust train components will have an emergency power source available, even if the limiting conditions for operation can be satisfied.

SOUTH TEXAS - UNITS 1 1 2 8 3/4 3-3 Unit 1 - Amendment No. 49, 71 Unit 2 - Amendment No. 68, 60

Insert to page B 3/4 9 -3 Insert 9 The FHB exhaust air system is comprised of two independent exhaust air filter trains and three exhaust ventilation trains. Each of the three exhaust ventilation trains has a main exhaust fan, an exhaust booster fan, and associated dampers. The main exhaust fans share a common plenum and the exhaust booster fans share a common plenum. An-i OPERABLE ventilation exhaust train consists of any OPERABLE main exhaust fan, any OPERABLE exhaust booster fan, and appropriate OPERABLE dampers.

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ML20154A428

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