· Cm TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUHENTATION j UDW'O.. Ã0'3 0; D~,eo j o~ AMxc Gl0 OO'~ I %Oh) acyl~', Aoz TRIP FUNCTION l. I) Low, Level 3 2) Low Low, Level 2 3) Low

Cm

TABLE 3.3.2-1

ISOLAT ION ACTUATION INSTRUHENTATION

j UDW'O..

Ã0'3

0;D~,eoj o~

AMxc

Gl0OO'~

I

%Oh)acyl~',Aoz

TRIP FUNCTION

l.

I) Low, Level 3

2) Low Low, Level 2

3) Low Low Low, Level 1

b. Drywel 1 Pressure — High

c. Hanual Initiation

PR IHARY CONTAINHENT ISOLATION

a. Reactor Vessel Mater Level

HINIHUHI SOLAT ION( )

OPERABLE CHANNELS

Y,Z,X

APPLICABLEOPERAT IONAL

COND IT ION

1,2,3I, 2, 3

I, 2, 3

I, 2, 3

I, 2, 3

ACTION

20

20

20

20

24

d. SGTS Exhaust Radiation-High R 3 4AAA 5k*A 20

2.

e. Hain Steaa Line Radiation-High C

SECONDARY CONTAINHENT ISOLATION

I, 2, 3 20

B~ IS

m Q.

Cortco O

a.

b.

e.

Reactor Vessel Mater Level-Low Low, Level 2

Drywell Pressure - llighRefuel Floor High Exhaust DuctRadiation - High

Rai lroad Access Shaft ExhaustDuct Radiation - High

Refuel Floor Wall Exhaust DuctRadiation - High

Hanual Initiation

I, 2, 3 and "

I, 2, 3

1,2,3and"

25

25

25

25

25

24

TABLE 3.3.2-1 (Continued)

HINIHUH APPLICABLEISOLATION OPERABLE CHANNELS 'PERATIONALSIGNAL(s) PER TRIP SYSTEM (b) CONOITION

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1 2 3

ISOLATION ACTUATION INSTRUHENTAT ION

D

TRIP FUNCTION

3. HAIN STEAM LINE ISOLATION

a. Reactor Vessel Water Level - X 2Low, Low, Low, Level 1

b. Hain Steam Line Radiation - C 2High

c. Main Steam Line Pressure - Low P 2

d. Hain Steam Line Flow - High D 2/1 inc

e. Condenser Vacuum - Low UA 2

f. Reactor Building Hain Steam Line E 2Tunnel Temperature - High

ACTION

21

21

22

20

21

21porn

lO g ~gI~~

~ sueo O0 gg

Cg')~ ~

Hanual InitiationTurbine Building Hain SteamLine Tunnel Temperature-High

4. REACTOR WATER CLEANUP SYSTEM ISOLAI ION

a. RWCU 6 Flow - High

b. RWCU Area Temperature - High

HighC ~ SLCS Initiation

Reactor Vessel WaterLevel - Low Low, Level 2

RWCU Flow - High

Hanual initiation

NA

E

1 2 3

1 2 3

1,2,31 ~ 2. 3

1,2,3I, 2, 3

I, 2, 3

1,2,3

24

21

23

23

23

23

23

24

l

II

\

ADC:m

TRIP FUNCTION

5. REACTOR CORE ISOLATION

TABLE 3. 3. 2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION

HINIMUMISOLATION OPERABLE CHANNELS

COOLING SYSTEM ISOLATION

APPLICABLEOPERATIONAL

CONDITION ACTION

a. RCIC Steam Line 4 Pressure - High K

b.,RCIC Steam Supply Pressure - Low KB

c. RCIC Turbine Exhaust Diaphragm KPres'sure - High

d. RCIC Equipment RoomTemperature - High

1,2,31, 2, 3

1, 2, 3

1, 2, 3

23

23

23

23

P -A RCIC Emergency Area CoolerTemperature - High

1, 2, 3 23

CL

ee B

O Pl

0'ili ct

CMOEDw O~ rClDIQ) ~ ~

4O

RCIC Pipe Routine AreaTemperature - High

Manual Initiaaien

Drywall Pressure - iligh

NA

1, 2, 3

1,2,31, 2, 3

23

24

23

l


ISOLATION ACTUATION INSTRUHENTATION

H IN IHUH APPLICABLEISOLATION OPERABLE CHANNELS OPERATIONAL

TRIP FUNCTION SIGNAL(s) PER TRIP SYSTEH (b) CONDITION

6. HIGH PRESSURE COOLANT INJECTION SYSTEH ISOLATION

ACTION

a. 'PCI Steam Line 6 Pressure - Lgigh

1, 2, 3 23

~ b.

C.

HPCI Steam Supply Pressure-Low . LB

HPCI Turbine Exhaust Diaphragm LPressure - High

HPCI Equipment RoomTemperature - High

1, 2, 3

1, 2, 3

1, 2,'3

23

23

23

VO fR~ ~BA~Nc+W

~S'RO c+tQ $

~MOCI~v

O~ I f+MOaO (0 ~ ~

W lO

HPCI Emergency Area CoolerTemperature - High

HPCI Pipe Routing AreaTemperature - High

ttannat init.iat.ian

Drywe)1 Pressure - High

l

NA

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

23

23

24

23

I g1

A

h

l t

II

</>


ISOLATION ACTUATION IHSTRUMEHTATIOH

HINIHUHISOLATION OPERABLE CHANNELS

. TRIP FUNCTION T H

7. RHR SYSTEH SHUTDOWN COOLING/HEAD SPRAY HODE ISOLATION


CONDITION ACTION

a.

b.

Reactor Vessel WaterLevel - Low, Level 3

Reactor Vessel (RHR Cut-inPermissive) Pressure - High

1,2,3

l,2,3

26

RHR Equipment AreaTemperature -. High

RllR Flow - lligh

Hanual Initiation

Drywell Pressure - High

1, 2, 3

1, 2, 3

~ 1, 2,.3

1, 2, 3

26

26

24

26

ACTION 2Q

ACTION 21

ACTION 22ACTION 23

ACTION 24-

ACTION 25

ACTION 26



ACTION STATEMENTS

Be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTOQWN

within the next 24 hours.Be in at least STARTUP with the associated isolation valvesclosed within 6 hours or be in at least HOT SHUTDOWN within12 hours and in COLD SHUTDOWN within the next 24 hours.Be in at least STARTUP. within 6 hours.Close the affected system isolation valves within 1 hourand declare the affected system inoperable.Restore the manual initiation function to OPERABLE statuswithin 8 hours or close the affected system isolation valveswithin the next hour and declare the affected system inoperabieor be in at least HOT SHUTDOWN within the next 12 hours and inCOLD SHUTDOWN with'in the following 24 hours.

,Establish SECONDARY CONTAINMENT INTEGRITY with the standby gastreatment system operating within 1 hour. 2ILock the affected system isolation valves closed within 1 hour

'nddeclare the affected system inoperable.

NOTESh

When handling irradiated fuel in. the secondary containment and du~ingCORE ALTERATIONS and operations with a potential f'r draining the reactorvessel.Actuates dampers shown in Table 3.6.5.2-1.When VENTING or PURGING the drywell per Specification 3.L1.2.8.

(a) See Specification 3.6.3, Table 3.6.3-1 for valves which are actuated bythese isolation signals.

(b) A channel may be placed in an inoperable status for up to 2 hours forrequired surveillance without placing the channel or trip system in thetripped condition provided at least one other OPERABLE channel in thesame trip system is monitoring that parameter. In addition, for the HPCIsystem and RCIC system isolation, provided that the redundant isolationvalve, inboard or outboard, as applicable, in each line is OPERABLE andall required actuation instrumentation for that valve is OPERABLE, one .

channel may be placed in an inoperable status for up to 8 hours forrequired surveillance without placing'he channel or trip system inthe tripped condition.

SUS/UEHANNA - UNIT 1 3/4 3-16 Amendment No. 36

TRIP FUNCTION

TABLE 3.3.2-2

ISOLATION ACTUATION INSTRUHENTATION SETPOINTS

TRIP SETPOINTALLOMABLE

VALUE

1. PRIHARY CONTAINHENT ISOLATION

a.

b.C.d.e.

Reactor Vessel Mater Level .

1) Low, Level 32) Low Low, level 23) Low Low Low, level 1Orwell Pressure - HighHanual InitiationSGTS Exhaust Radiation - HighHain Steam Line Radiation - High

> 13.0 inches"> -38.0 inches"> -129 inches"< 1.72 psigNA<23.0 NLR/hr< 7.0 x full power background

> 11 5 inches> -45.0 inches> -136 inches< 1.88 psigNA<31.0 aR/Hrcb.e a fuli ponce background

2. SECONDARY CONTAINHENT ISOLATION

'a e

d.

e.

Reactor Vessel Mater Level-Low Low, Level 2

Orwell Pressure - High

Refuel Floor High Exhaust DuctRadiation — High

Railroad Access Shaft ExhaustDuct Radiation - High

Refuel Floor Mall Exhaust DuctRadiation - High

Hanual Initiation

> -38.0 inches"< 1.72 psig

< 2.5 aR/hr.

< 2.5 mR/hr.

< 2. 5 mR/hr.

NA

> -45.0 inches

< 1.88 psig

< 4.0 aR/hr.

< 4.0 NLR/hr.

< 4.0 mR/hr.

NA

3. HAIN STEAH LINE ISOLATION

a. Reactor Vessel WaterLevel - Low Low low, level 1

Hain Steam LineRadiation - High

Hain Steam LinePressure - low

Hain Steam LineF)ow - High

> -129 inches"< 7.0 X full powerbackground

> aS> pstg

107 psid

> -136 inches< 8.4 X full powerbackground

> 841 psig

110 psid

r

TABLE 3.3.2-2 (Continued)C:

r<> ~ ISOLATION ACTUATION INSTRUHENTATION SETPOI NTS

TRIP FUNCTION TRIP SETPOINT

HAIN STEAN LINE ISOLATION (Continued)

e. Condenser Vacuum - Low > 9.0 inches Hg vacuum

ALLOWABLEVANE

> 8.8 inches Hg vacuum

f. Reactor Building Hain Steam LineTunnel Temperature - High < 177'F

D

I

CXI

aa aiannal Initiation NA

Turbine Building Hain Steam Line <177'FTunnel Temperature-High

4. REACTOR WATER CLEANUP SYSTEH ISOLATION

NA

<184'F

a. RMCU 6 Flow - High


< 60 gpm

< 147'F or 118.3'Fg

< 80 gpm

154 F or 125.3 F8

go m

Aa gC

Cl+v Q0 gy

u 0

SLCS InitiationReactor Vessel Mater Level-

Low Low, Level 2

RWCU Flow - High

Hanual Initiation

NA

> -38 inches"< 426 gpm

NA

5. REACTOR CORE ISOLATION. COOLING SYSTEH ISOLATION

NA

> -45 inches

< 436 gpm

NA

b.

RCIC Steam Line hPressure - High

RCIC Steam Supply Pressure - tuw

RClC lu>bine Lxl>aust Uiapl» agmI'russo>u - lligh

< 177" II~0

60 psig

10. 0 ps ig

189" II~0

53 ps lg

'0.0 psig

I

I

v

}I

r,

ADCm



TRIP FUNCTION TRIP SETPOINT

REACTOR CORE ISOLATION COOLING SYSTEH ISOLATION Continued)

d. RCIC Equipment RoomTemperature - High ( 167oF**

ALLOWABLEVALUE

< 174'F""

RCIC Pipe Routing AreaTemperature - High 167QFN 04DF////

RCIC Emergency AreaCooler Temperature - High

Iiannai InitiationDrywell Pressure - High

< 147'F

NA

<1.72 psig

< 154 F

NA

<1.88 psig


z~o mIA M~ c+ la

C7 0O I+CD C+CD ~~su O-~O O0 CDv a+~MI

~ ~

CO

HPCI Steam Line Flow - High

HPCI Steam SupplyPressure - Low

HPCI Turbine ExhaustDiaphragm Pressure - High

HPCI Equipment RoomTemperature - High

HPCI Emergency AreaCoolel Tempelature - lliyhill'Cl l'll)l.'outing Al'l!aI ulllllurillure H lyll

< 350 inches H>0

> 104 psig

< 10 psig

167 F

14/ f

< 367 inches H20

90 psig

< 20 psig

(174 F

<154"F

I /4"l

A

A P

( ~

t

AD

m

TRIP FUNCTION

TABLE 3.3.2-2 (Continued}


TRIP SETPOINTALLOWABLE

VALUE

~paeatu~4g<I ~ iianual Initiation NA

Drywe)i Pressure - High <1.72 psig


NA

<1.88 psig

a. Reactor Vessel Water Level-Low, Level 3

Reactor Vessel.(RHR Cut-inPermissive} Pressure - High

> 13. 0 inches"

< 98 psig

> 11.5 inches

< 108 psig

>am>n ~Ag~I~~~

C~rueCI>v Q0

~ ~' < , v ~

tt> g) ~ ~D~

RHR Equipment Area Temperature-High

RHR F low - Hi gh

Manual InitiationDrywell Pressure - High

< 167F< 25,000 gpm

NA

<1.72 psig

ee Bases figure B 3/4 3-l.NLower setpoints for TSH-G33-1N600 E, f and TOSH-G33-1N602 E, F.

IIN15 minute time delay.

w

< 170.5 F

< 26,000 gpm

NA

<1.88 psig

I 4'

I(

jl

lp j

TABLE 3.3.2-3

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME

RESPONSE TIME Seconds)t

<1o(')

<1(m710~ ~

HA<1o(')<1o(')

<1o(')<1O(a)<1o(')

<1o(').<1o(')

(co<'><1 O~g<1O(a)~~

1.O>RZO(a)„*0.5"/<10(a)~

Q

- TRIP FUNCTION

I. PRIMARY COHTAINMENT ISOLATIOH

a. Reactor Vessel Water LevelI) Low, Level 32) Low Low, Level 23) Low Low Low, Level 1

b. Drywall Pressure - Highc. Manual Initiationd. SGTS Exhaust Radiation - Highe. Main Steam Line Radiation - High

2. SECONDARY CONTAINMEHT ISOLATION

a. Reacto~ Vessel'Mater Level-Low L'ow, Level 2b. Drywall Pressure - Highc. Refuel Floor High Exhaust Duct Radiation - High( )d. Railroad Access Shy@ Exhaust Duct,

Radiation " Highe. Refuel Floor Wall Exhaust Duct Radiation -High

- f. Manual Initiation3. MAIN STEAM LINE ISOLATION

a. Reactor Vessel Mater Level- Low gm Low, Level 1b. Main Steam Line Radiation -

High'"'.

Main Steam Line Pressure Lowd. Main Steam Line Flow-Highe. Condenser Vacuum - Lowf. Reacto~ Building Main Steam Line Tunne1

Temperature - High

Manual InitiationTurbine BuiIding Main Steam Line Tunnel

Temperature - High

4. REACTOR MATER CLEANUP SYSTEM ISOLATION

a. RMCU 4 Flow - Highb. RWCU Area Temperature - High

SLCS InitiationReactor Vessel Water Level - Low Low, Level 2

G. 4 RMCU Flow - HighManual Initiation

5. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

a. RCIC Steam Line h Pressure - Highb. RCIC Steam Supply Pressure - Lowc. RCIC Turbine Exhaust Giaphragm Pressure - Highd.- RCIC Equipment Room Temperature - High

1O(a)%Ra

1O( )PANA

( )AQ<1O(a)

NA

SUSQUEHANNA - UNIT 1 3(4 3-21 Amendment Ho. 38

\ II

7

C

TABLE 3.3.2-3 (Continued}

ISOLATION SYSTEM IHSTRUMEHTATIOH RESPOHSE TiME

TRIP FUNCTION RESPONSE TIME Seconds 0

3/4 3-22

-e —RCJ4-Kquiqoeee-Roue-e-Teoqeoeeuoe~igu —NA-RCIC Pipe Routing Area Temperature - High HA

RCIC Emergency Area Cooler Temperature - High HAManual Initiation ~ NOrywell Pressure - High cia~'>

6. HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION

a. HPCI Steam Flow - High o('}b. HPCI Steam Supply Pressure - Low <l0( )

c. HPCI Turbine Exhaust Ofaphragm Pressure - High HA.d. HPCI Equipment Room Temperature - High HA~RCLZq~

HPCI Emergency Area Cooler Temperature - High NHPCI Pipe Routing Area Temperature - High N

MICLII4pMI~I@IManual Initiation HAj-+ Drywell Pressure - High <gO(a)

r

7. RHR SYSTEM SHUTDSO COOLING/HEAO SPRAY MOOE ISOLATION

a. „Reactor Vessel Mater Level - Low, Level 3 <~o(')b. Reactor Vessel (RHR Cut-in Permissive)

Pressure - High Nw~RIGEquipme~ee~ampeeaium=~

RHR'Equipment Area Temperature - High . N ~

IRHR Flow - High NA

e.-A- Manual Initfatfon NOrywell Pressure - High g.o(')

y hrecorded as a part of .the ISOLATION SYSTEM RESPOHSE TIME.'solationsystem fnstrumentatfon response time specified includes the delay fordiesel generator starting assumed in the accident analysis.

(b) Radiation detectors are exempt from response time testing. Response timeshall be measured from detector output or the input of the firstelectronic component in the channel.

"Isolation system instrumentation response time for MSIVs only. Ho dieselgenerator delays assumed for MSIV Valves.

~Isolation system instrumentation response time for associated valvesexcept MSIVs.

SIsolatfon system instrumentation response time specified for the TripFunction actuating each valve group shall be added to isolation timeshown in Table 3.6.3-1 and 3.6.5.2-1 for valves in each valve group toobtain ISOLATION SYSTEM RESPONSE TIME for each valve.

AWth tfme delay of 45 seconds.

NANfth time delay of 3 seconds.

~fth time delay of 3 seconds.

SUS(UEHANN - UNIT 1 Amendment No. 36

4

J

)1

4

TABLE 4.3.2.1-1

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS

TRIP FUNCTION

I. PRIHARY CONTAINMENT ISOLAT ION

a. Reactor Vessel Water Level-

CHANNELCHECK

CHANNELFUNCT IONAL

TESTCHANNEL

CALIBRATION

OPERATIONALCOND IT IONS FOR WHICH

SURVEILLANCE RE UIRED

~ ~

ot. Manual Initiation NA

1) Low, Level 3

2) Low Low, Level 2 5

3) Low Low Low, Level 1 5

b. Drywell Pressure - High NA

c. Hanual Initiation NA

d. SGTS Exhaust Radiation - High 5e. Hain Steaa Line Radiation - High 5

2. SECONDARY CONTAINMENT ISOLAT IONa. Reactor Vesse Water Leve

Low Low, Level 2 5

b. Drywel I Pressure - High NA

c. Refuel Floor High Exhaust DuctRadiation - High

d. Railroad Access Shaft ExhaustDuct Radiation - High

e. Refuel Floor Wail Exhaust DuctRadiation - High

NAR

R

NA

1,2,3I, 2, 3

1, 2, 3

1, 2, 3

1,2,34AAA 5AAA

1, 2, 3

I, 2, 3 and "

1, 2, 3

], 2, 3 and "

AD

TRIP FUNCTION

3. MAIN STEAM LINE ISOLATION

a. Reactor Vessel Water Level-Low, Low Low, Level l

b. Hain Steam LineRadiation - High

c. Hain Steam LinePressure - Low

CHANNEL OPERATIONALFUNCTIONAL CHANNEL CONDITIONS FOR WHICH

TEST CALIBRATION SURVEILLANCE RE UIRED

CHANNELCHECK

l, 2, 3

1, 2, 3

1ABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS

d. Hain Steam LineFlow - High

e. Condenser Vacuum - LowS

NA1,2,3l 2a" 3"

f. Reactor Building Main Steam LineTunnel Temperature - High NA 1, 2, 3

Manual Initiation NA

} ~ Turbine Building Hain Steam Line NA

Tunnel Temperature - High

4. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. RWCU h Flow - High S

b. RWCU Area Temperature - High NA

NA 1, 2, 3

1, 2, 3

1,2,3l,2,3

~ MOZv Q0 Qs

I t+EO I

%O Q) ~ ~W lQ

SLCS InitiationReactor Vessel WaterLevel - Low Low, Level 2

RWCU Flow - llighMa»»al l»itiatio»

S

NA

NA 1,2,3

l,2,31, 2, 3

1,2,3

TABLE 4. 3. 2. l- l (Continued)ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREHENTS

CHANNELTRIP FUNCTION CHECK

5. RFACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

CHANNEL OPERATIONALFUNCTIONAL CHANNEL CONDITIONS FOR WHICH

TEST CALIBRATION SURVEILLANCE RE UIRED

d.

RCIC Turbine Exhaust DiaphragmPressure - High

RCIC Equipment RoomTemperature - High

a. RCIC Steam Line hPressure - High

b. RCIC Steam Supply Pressure-Low

NA

l, 2, 3

1,2,3

I, 2, 3

l, 2, 3

RCIC Pipe Ruul.ing AreaTemperatur e - High NA 1,2,3

g O Pl

~$7 gNN~

~:~MeO~v O

CCQj ~ ~

HPCI Steam Line hPressure - High


HPC1 Turbine ExhaustDiaphragm Pressure - High

NA

NA

NA

I+ 4: RCIC Emergency Area Cooler

=Temperature - High NA

g m Manual Initiation NA

Drywell Pressure - High NA

6. HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION

Q

NAR

1, 2, 3

1, 2, 3I, 2, 3

1, 2, 3

1, 2, 3

I, 2, 3

E C

NA

TABLE 4.3.2. l-l (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREHENTS

CHANNEL OPERATIONALCHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE RE UIRED

HIGH PRESSURE COOLANT INJECTION SYS1EH ISOLATION (Continued)

d. HPCI Equipment RoomTemperature - High H 1, 2, 3

HPCI Emergency AreaCooler Temperature - High NA H

HPCI Pipe Routing Areae r - h NA H

Hanual Initiation NA R

Drywell Pressure - High NA H

7. RHR SYSTEM SHUTDOWN COOLING/HEAD SPRAY MODE ISOLATION

NAR

1,2,3

1, 2, 3

1, 2, 31, 2, 3

C)Rv Q0 Ol'tEQ CQ ~ ~

W 4O

a. Reactor Vessel Water Level-Low, Level 3 S H R

b. Reactor Vessel (RHR Cut-inPermissive) Pressure - High NA H Q

c—.RHR-Eq&y=fempeeator~N:g

RHR Equipment Area Temperature-High NA H

RHR flow - High S H R

Manual Initiation NA R NA

Drywel 1 Pressure — High NA H R

When hand rng rrradiated fuel in the secondary co»tai»ment and during CORE

with a pote!rtial for drai»ing the reactor vessel."" Whe» reactor steam dome pressure > 1043 psig and/or any tur'bir!e stop valve

'""" Whe» VLN)ING ur PURGlNG the drywel I per Specification 3.11.2.0.

l, 2, 3

l, 2, 3

1,2,31,2,31,2,3I, 2, 3

ALTERATIONS and operat.ions

I s ope».

TABLE 3.3.2-1ISOLATION ACTUATION INSTRUHENTATION

m

I

TRIP FUNCTION

1. PRIHARY CONTAINNENT ISOLATION

a. Reactor Vessel Mater Level

1) Low, Level 3

2) Low Low, Level 2

3) Low Low Low, Level1'.


c. 'Hanual Initiation

ISOLAT IONSIGNAL S a

X

Y,Z

NA

NINIHUH APPLICABLEOPERABLE CHANNELS OPERATIONAL

1, 2, 3

I, 2, 3

1, 2, 3

1; 2, 3

I, 2, 3

ACTION

20

20

20

20

24

DCol e.

2. SE

d. . SGTS Exhaust Radiation-High

Hain Steaa Line Radiation-High

CONOARY CONTAINNENT ISOLATION

1 2.3 20

3 4AAA 54*A 20

IO

CD

O

a. Reactor Vessel Mater Level-Low Low, Level 2

b. Orywell Pressure - Highc.'efuel Floor High Exhaust

Duct Radiation - High

d. Railroad Access Shaft ExhaustOuct Radiation - High

e. Refuel Floor Wall ExhaustGuet Radiation - High

f. Hanual Initiation NA

1, 2, 3 and "

1, 2, 3

I, 2, 3 and "

25

25

25

25

25

24

ADCm

TRIP FUNCTION



HINIHUHISOLATION OPERABLE CHANNELSSIGNAL S)(a PER TRIP SYSTEH (b)


CONDITION ACT 1 ON

(oman

HATTnm

m g~~gRN~~~~ rue

OCI

O

~4DC

3. HAIN STEAH LINE ISOLATIONa. Reactor Vesse ater Level-

Low Low Low, Level 1

b. Hain Steam Line Radiation-High

c. Hain Steam Line Pressure - Low

d. Hain Steam Line Flow - IIighe. 'ondenser Vacuum - Low

P

0

UA

SLCS Initiat.ionReactor Vessel Wat,erLevel - Low Low, Level 2

RWCU flow - High

Halllld l ln I t l at I VII

f. Reactor Building Hain Steam E

Line Tunnel Temperature - High~—Reacto~uWding.Hain<teaml p

Hanual Initiation NA

Turbine Building Hain Steam Line E

Tunnel Temperature - High

4. REACTOR WATER CLEANUP SYSTEH ISOLATION

a. RWCU b, Flow - High


~~NQLA~entMatio

2

2/line2

2

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

I, 2, 3

I, 2, 3

21

21

22

20

21

21

24

21

23

23

23

23

23

24

I

TABLE 3. 3. 2-1 (Conti nued)


HINIHUH APPLICABLE0 OPERABLE CHANNELS OPERATIONAL

~(IS LATION

TRIP FUNCTION ~(( (

5.- REACTOR CORE ISOLATION COOLING SYSTEH ISOLATION

ACTION

a. RCIC Steam Line 4 Pressure -High K

b. RCIC Steam Supply KB

Pressure - Low

c. RCIC Turbine ExhaustDiaphragm Pressure - High


RCK=Equipment Room

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

23

23

23

23

Q 4: RCIC Pipe Routing Area. Temperature - High

~~RCIC-..Pipe-Rout.inure

1, 2, 3 23

+ 4: RCIC Emergency Area CoolerTemperature - HighDO PiBnm

% g~n(n~~ P+: Hannal Initiation

Drywe)l Pressure - HighW ft

ese-t-v-ii)-4tnc 44en~>eed-n~~KJNB

1, 2, 3

1,2,3l, 2, 3

23

24

23

TABLE 3.3. 2-1 (Cont inued)


HINIHUHISOLATION OPERABLE CHANNELS

TRIP FUNCTION SIGNAL(S)(a) PER TRIP SYSTEH (b)



CONDITION ACTION

a. HPCI Steam Line h Pressure - '

High

b. HPCI Steam Supply Pressure-Low LB

c. HPCI Turbine Exhaust Diaphragm LPressure - High

d. HPCI Equipment RoomTemperature - High

~HRCL'-Equip me neoT~mpesatu~Wgh

HPCI Emergency Area CoolerTemperature - High

HPCI Pipe Routing AreaTemperature - High

Ap—.NLCI=Nye=Routing=Ar

2

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1,2,3

1, 2, 3

23

23

23

23

23

23

Manual InitiationC

4 ~ Drywell Pressure - High

m " "R~H~Wunebiet t-need-n W<tobev—VJ—,19~Manu

1, 2, 3

1, 2, 3

24

23

~ ~t

TASLE 3.3.2-1 (Cont)nues)

ISOLATION ACTUATIOH IHSTRINL'NTATION

TRIP FUNCTION

HIMIHUHISOLATIOH OPERNLE CINNNELS

APPL ICASLEOPERATIONAL

CONDITION ACTION

7. RHR SYSTEH SHUTOOMN COOLINGIHEAD SPRAY HOOE ISOLATIOH

a.

b.

Reactor Vessel MaterLevel - Low, level 3

Reactor Vesse) {RHR Cut-inPeraissive) Pressure " High US.

1,2,3

1,2,3

26

26

~ltglg-ck RHR Equipment Area

Temperature " High

RHR f)ov - lligh

Hanual initiation

g. ~ Drywall Pressure - Iligh

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

26

~ ~ 0

4

v

~ %

ACTION 20

ACTION n-ACTION 22

ACTION 23

ACTION 24-

ACTION 25

ACTION 26

TABLE 3.3. 2"1 (Continued)


ACTION STATEMENTS

Be fn at least HOT SHUTDOWN within X2 hours and in COLO SHUTDOWN

within the next 24 hours.Be fn at least STARTUP with the associated isolation valvesclosed within 6 hours or be fn at least HOT SHUTDOWN withinI2 hours and in COLO SHUTDOWN within the next 24 hours.

Be fn .at least STARTUP within 6 hours.Close the affected system isolation valves within I hourand declare the affected system inoperable.Restore the manual fnftfatfon function to OPERABLE statuswithin 8 hours or close the affected system isolation valveswfthfn the next hour and declare the affected system inoperabl'eor be fn at least HOT SHUTDOWN within the next X2 hours and inCOLO SHlPiOOWN wfthfn the i'ollowing 24 hours.

Establfsh SECONDARY CONTAINMENT INTEGRITY with the s andby gastreatment system operatfng within 1 hour.

Lack the affec.ad system isolation valves closed within 1 hourand declare the affected system inoperable.

TABLES NOTATIONS

When handling irradiated fuel fn the secondary containment and duringCORE ALTERATIONS and operations with a potential for draining the reactorvesiel.Actuates damper s shown in Tab1e 3.6.5.2-1.When VENTING or PURGING the drywell per Specft'fcatfon 3.11.2.8.

(a) See Specfffcatfon 3.6.3, Table 3.6.3-1 f'r valves which are actuated bythese isolation sfgnals.

(b) A channel may be placed fn an fnoperable'status for up to 2 hourC-1'orrequfred surveillance without placing the channel or trip system in the

*

tripped condition provided at least one other OPERABLE-channel fn thesame trip system fs monitoring that par ameter. In addition, for the HPCI .

system and RCIC system isolation, provided that the redundant isolationvalve, inboard or outboard, as applicable, fn each line fs OPERABLE andall required actuatfon fnstrumentatfon f'r that valve is OPERABLE, onechannel may be placed fn an inoperable status for up to 8 hours forquired surveillance without placing the channel or trip system inthe tripped condition.

SUSQUEHANNA UNIT 2 3/4. 3-16

TABLE 3.3.2-2

ISOLATION ACTUATION INSTRUHENTATION SETPOINTSAD

CmTRIP FUNCTION

PRIHARY CONTAINHENT ISOLATION


VALUE

a.

b.C.d.e.

Reactor Vessel Water level1) Low, level 32) Low low, level 23) Low Low low, Level 1

Drywell Pressure - HighHanual InitiationSGTS Exhaust Radiation - HighHain Steam Line Radiation - High

>13.0 inches"> -38.0 inches"> -129 inches"< 1.72 psigNA< 23.0 mR/hr< 7.0 X full power background

> 11.5 inches> -45.0 inches> -136 inches< 1.88 psigNA< 31.0 mR/hr

8.4 X full power background

2. SECONDARY CONTAINHENT ISOLATION

a.

b.

C.

d.

e.

Reactor Vessel Water Level-Low low, Level 2 .


Refuel Floor High Exhaust. DuctRadiation " High

Railroad Access Shaft ExhaustDuct Radiation - High

Refuel Floor Wall Exhaust Duct.Radiation - High

Hanual Initiation

> -38.0 inches".< 1.72 psig

< 2,5 mR/hr

< 2.5 aR/hr

< 2.5 aR/hr

NA

> -45.0 inches

< 1.88 psig

< 4.0 aR/hr

< 4.0 aR/hr

< 4.0 aR/hr

NA

3. HAIN STEAM LINE ISOLATION

aID

a0

C>CO ~

CI

a. Reactor Vessel MaterLevel - Low low low, Level 1

Hain Steam Line Radiation - High

Hain Steam Line Pressure - Low

Hain Steam Line flow - High

> -136 inches

< 8.4 X full power background

> 841 psig< 110 psid

> -129 inches"< 7.0 X full power background> 861 psig< 107 psid

TRIP FUNCTION


ISOLATION ACTUATION INS1RUHENTATION SETPOINTS


VALUE

> 9.0 inches Hg vacuum

HAIN STEAH LINE ISOLATION (Continued)

e. Condenser vacuum - Low

f. Reactor Building Hain Steam LineTunnel Temperature-- High < 177'F

> 8.8 inches Hg Yacuum

< 184 F

ID

n~CL3CD

O

O foal

g ~CT 5

MOCIv QWgQ) ~ ~

RCIC Steam Line h Pressure - High < 153" H~O

RCIC Steam Supply Pressure - Low > 60 psigRCIC Turbine Exhaust DiaphragmPressure - High 10.0 psig

~nauru!Teapenatuae=-High~9'anual

Initiation NA

Turbine Building Hain Steam LineTunnel Temperature - High < 177 F

4. REACTOR MATER CLEANUP SYSTEH ISOLATION

a. RMCU h Flow - High < 60 gpm

b. RWCU Area Temperature - High < 147'F or 118. 3'Fg

lllll-4empeeatu

SLCS Ini tiation NA

Reagtor Vessel Mater Level-Low Low, Level 2 > -38 inches"

RWCU Flow - High 426 gpmf~ iianual Initiation NA

5. REACTOR CORE ISOLATION COOLING SYSTEH ISOLATION

NA

< 184'F

< 80 gpm

< 154 F or 125. 3 FN

o *

> -45 inches

436 gpm

NA

< 165" Hq0

> 53 psig

< 20.0 psig

~ ~

4~'I

TRIP FUNCTION




VALUE

REACTOR CORE ISOLATION COOLING SYS1EH ISOLATION (Continued)

~ omI g~D

too~Papi

„~C


Wl~mperatur.~4g

g, M RCIC Pipe Routing AreaTemperature - HighGlC-Ripe-Roui.ing Ace'~

temperature=HighRCIC Emergency AreaCooler Temperature - HighHanual InitiationOrywell Pressure - High

6. HIGH PRESSURE COOLANT INJECTION SYSTEH

a. HPCI Steam Line Flow - Highb. HPCI Steam Supply Pressure - Lowc. HPCI Turbine Exhaust Diaphragm

Pressure - Highd. HPCI Equipment Boom

Temperature — High~—H

~mperatu~hgHPCI Emergency Area CoolerTemperature - HighHPCI Pipe Routing AreaTemperature - High

mp~r~iiglHanual Initiat.ionDrywell Pressure - High

< 167 F

< 167 F88

~AN< 147'FNA< 1.72 psig

ISOLATION

< 275 inches H20> 104 psig

< 10 psig

< 167 F

< 147'F

< 167 FH

QF

NA< l. /2 psig

< 174'F

< 174'FIN

< 154 F

NA< 1.88 psig

< 292 inches H2090 psig

< 20 psig

<D4F

< 154'F

< 174'FH

NA< 1.88 psig

lABLE 3.3.2-2 (Continued)

ISOLAlION ACTUATION INSTRUNENTATION SETPOINTS

> 13.0 inches~

TRIP fUNCTION TRIP SElPOINT

7. RHR SYSTEH SHUTDMi GNLING/HEAD SPRAY NODE ISOLATION

a; Reactor messy) i/ster Lev'el-Low, Lyvel 0

b. Reactor Vessel (RHg Cut-inPeraissjve) Pressure - High < 98 psig

ALLOKASLEVALUE

> )I-5 inches

< 108 psig

NQ Equipaent Area Teeperature -. High

RHR Flow - High

Nanual InitiationQrywell Pressure - High

<16) F

< 25,000 gapa

NA

< 1.22 psig

< 170.5'F< 26,000 gpa

NA

< $ .88 psig

~See Bases figure 8 3/i 3-1.

NLower setpoints for TSH-G33-2N600 E, f and TOSH-G33-2N602 E, F.

NNI5 minute tiae delay.

o

~ s ~ 4

f

«(I

TABLE 3.3.2-3ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME

<10(.)<10(')i4<10(')<1.0*C<XO(')-<1'0~]<10( )~~<0'5~]<gp( )~~HA

NA

( )¹¹HA

TRIP FUNCTION RESPONSE TIME Seconds ¹NT I KNf !5 LOFTI

a. eactor esse ater Level1) Low, Level 3 <10(2) Low Low, Level 2 1.0"]'<XO(a)*"

3) Low Low Low, Level 1 <10(')b. Drywell Pressure - High <1p(a)c. Manual Initiation Ha,d. SGTS Exhaust Radiation - High <10( )e. Main Steam Line Radiation - High <10(')

2. SECONDARY CONTAINMENT ISOLATIONa. eactor esse Water eve -Low Low, Level 2 <10b. Drywell Pressure - High <,0(.)c. Refuel Floor High Exhaust Duct Radiation - High <10d. Railroad Access Shaft Exhaust Duct

Radiation - Highe. Refuel Floor Mall Exhaust Duct Radiation -Highf. Manual Initiation

3. MAIN STEAM LINE ISOLATIONa. eactor esse Water Level- Low Low Low, Level 1

b. Main:Steam Line Radiation - Highc. Main Steam Line Pressure » Lowd. Main Steam Line Flow-Highe. Condenser Vacuum - Lowf. Reactor Building Main Steam Line Tunnel

Temperature - High NAag nnal

Manual Initiation NATurbine Building Main Steam Line TunnelTemperature - High

4. REACTOR WATER CLEANUP SYSTEM ISOLATIONa. ow-Hgb. RWCU Area Temperature - HighIlk hid t4 p I - Ig~

SLCS Initiation NAReactor Vessel Mater Level - Low Low, Level 2 <10RWCU Flow - High HAManual Initiation NA

5. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATIONa. C team L ne 4 Pressure - H gh <10b. RCIC Steam Supply Pressure - Lowc. RCIC Turbine Exhaust Diaphragm Pressure - High HAd; RCIC Equipment Room Temperature - High NA

I hl8 -6 RCIC Pipe Routing Area Temperature - High NA

.g~CILPApe&o~g&rea~~pe stum=Ngh—NA-RCIC Emergency Area Cooler Temperature - High NAManual Initiation NA

( )Drywell Pressure - High <10

SUS(UEHANNA - UNIT 2 3/4 3-21 Amendment No. 25

~ ~

TRIP FUNCTION

TABLE 3.3.2-3 (Contf nued)

ISOLATION SYSTEM INSTRQKIITATION RESPONSE TIME

RESPONSE TIME Seconds ¹6. HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION

a. HPCI Steam Flow - Hfghb. HPCI Steam Supply Pressure - Lowc. HPCI Turbine Exhaust Dfaphraga Pressure - Hfghd. HPCI Equfpment Room Temperature - Hfgh

-e~fPCJ-Kqufpment-Room-h-Tesperatuee=HfgHPCI Emergency Area Cooler Temperature - HighHPCI Pfpe Routfng Area Temperature - HfghdM

9 -4 Manual InftfatfonDrywell Pressure - High

7, RHR SYSTEM SHUTDOMN COOLING/HEAD SPRAY MODE ISOLATION

a. Reactor Vessel Mater Level - Low, Level 3b. Reactor Vessel (RHR Cut-fn Permissive)

Pressure - Highc ~N~ufpment&re

RHR Equipment Area Temperature - HighRHR Flow - High

8 ~ Manual InitiationDrywell Pressure - High

<~O(a)¹¹¹¹<XO(')RaNA

NA<$O(a)

<$O(a)

NANANA<gp(a)

(a) The fsolatfon system instrumentation response time shall be measured andrecorded as a part of the ISOLATION SYSTEM RESPONSE TIME. Isolationsystem fnstrumentatfon response time specified includes the delay fordiesel generator starting assumed fn the accident analysis.

'(b) Radfatfon detectors are exempt from response'ime testing. Response timeshall be measured from detector output or the fnput of the firstelectronfc component fn the channel.

~Isolatfon system fnstruwentatfon response time for MSIVs only. No dieselgenerator delays assed for MSIV Valves.

~Isolation system instrumentatfon response time for associated valvesexcept MSIVs.

¹Isolatfon system fnstrumentatfon response tfie specified for the TripFunction actuating each valve group shall be added to isolation timeshown fn Table 3.6.3-1 and 3.6.5.2-1 for valves fn each valve group toobtain ISOLATION SYSTEM RESPONSE TIME for each valve.

¹¹Mfth time delay of 45 seconds.

¹HNth time delay of 3 seconds.

¹¹¹¹Mfth tfae delay of 3 seconds.

SUSQUEHANNA- UNIT 2 3/4 3-22

TABLE 4. 3.2. 1-1

ISOLATION ACTUATION INSTRUHENTATION SURVEILLANCE RE UIRENENTS

TRIP FUNCTION

1. PRINARY CONTAINNENT ISOLATION

a. Reactor Vessel Mater Level-1) Low, Level 32) Low Low, Leve) 23) . Low Low Low, Level 1

b. Drywell Pressure - High

c. Hanual Initiatior}d. SGTS Exhaust Radiation - High

e. Hain Steam Line Radiation-High

2. -SECONDARY CONTAINNENT ISOLATION

CHANNELCHECK

555

NA

NA

5

CHANNELFUNCT IONAL

TES'I

NllH

N

R

H

CHANNELCAL IBRAT ION

R

NA

1,2,31, 2, 3

1, 2, 3

1, 2, 3

1, 2,

1, 2,

3

3 4aAa 5A*a t

1, 2, 3

OPERAT IONALCONDIT lONS FOR MHICH


a. Reactor Vessel Mater Level-Low Low, Level 2

b. Drywell Pressure - High

c. Refuel Floor High Exhaust DuctRadiation - High

d. . Railroad Access Shaft ExhaustDuct. Radiation - High

e. Refuel Floor Mall Exhaust DuctRadiation - High

f. Hanual Initiation5

NA

R

NA

1,2,3and»1, 2, 3

1, 2, 3 and "

ZlC:m

DI TRIP FUNCTION

3. HAIN STEAH LINE ISOLATION

CHANNELCHECK

CHANNELFUNCTIONAL

TESTCHANNEL

CALIBRATION

OPERATIONALCONDITIONS FOR MHICH


TABLE 4.3.2.1-1 (Continued)

I SOLAT ION ACTUATION INSTRUHENIATION SURVEILLANCE RE UIREHENTS

a.

d.e.f.

Reactor Vessel Water Level-Low Low Low, Level 1Hain Steam Line Radiation-HighHain Steam Line Pressure-LowHain Steam Line Flow - HighCondenser Vacuum — LowReactor Building Hain SteamLine Tunnel Temperature - High

-Line-Tunnels-h-Temperatu~

NAS

NA

2. 3

1, 2, 3

1,2,32%A 3%A

1, 2, 3

Hanual Initiation NA-4 Turbine Building Hain SteamLine Tunnel Temperature - High NA

4. REACTOR MATER CLEANUP SYSTEH ISOLATION

1, 2, 3

1, 2, 3

a. RMCU h Flow - High S

RMCU Area Temperature - High NA1, 2, 3

1, 2, 3

e"i~Q A tR

NflMOCIv O

Ql~ g+M CDBl Q) ~ ~

~Tempeaater.~4gSLCS InitiationReactor Vessel Water LevelLow Low, Level 2RMCU Flow - HighHanual Initiation

NA

S

S

NA

NA

R

R

NA

1,2,31, 2, 31, 2, 31, 2, 3

ggC'>+ « >

CjlAD

Cm

TABLE 4. 3.2. 1-1 (Continued)

ISOLATION ACTUATION INSTRUHENTATION SURVEILLANCE RE UIREHENTS

CHANNELCHANNEL FUNCTIONAL

TRIP FUNCTION CHECK TEST

5. REACTOR CORE ISOLATION COOLING SYSTEH ISOLATION

OPERATIONALCHANNEL CONOI LIONS FOR IctHICH

f fitf

a. RCIC Steam Line hPressure - High NA

b. RCIC Steam Supply Pressure-Low NA

c. RCIC Turbine Exhaust OiaphragmPressure - High NA

d. RCIC Equipment RoomTemperature - High NA

~IemRCIC Pipe Routing AreaTemperature - High NA

RRE-Hpe-Rout-i'-Aeea-~~mper'~

4 W RCIC Emergency Area CoolerTemperature - High NA

Hannai initiation NA

Orywell Pressure - High NA


Q

NA

R

l. 2. 3

1, 2, 3

1, 2, 3

1, 2, 3

1,2,3

1, 2, 3

1, 2, 3

1, 2, 3

CCa g ~CL CTR9 CCl c+CCa $ ~

~'Al

CIZ v Q0 ~CClh CO ~ ~

HPCI Steam Line 0,

Pressure - High


IIPCI Iurbine Exhaust0 i ai)hragm Pressure - Iligh

NA

NA

1, 2, 3

1,2,3

I, 2, 3

lH~l~l-Cl&-4le-OP44AN4M~luW~

TABLE 4.3.2. l-l (Continued)

ISOLATION ACTUATION INSTRUHENTATION SURVEILLANCE RE UIREHENTS

TRIP FUNCTIONCHANNEL

CHECK

CHANNELFUNCTIONAL

TESTCHANNEL

CALIBRATION

OPERATIONALCONDITIONS FOR WHICH


NA

NANA


HIGH PRESSURE COOLANT INJECTION SYSTEH ISOLATION (Continued)d. HPCI Equipment Room

Temperature - High NA H

~L-.Temperature=High NA "—qHPCI Emergency AreaCooler Temperature - High HHPCI Pipe Routing AreaTemperature - High NA H-h~l

Q ~. Hanual Initiation R

f,-+ Orywell Pressure - High H

I, 2, 3

1, 2, 3

1, 2, 3

1, 2, 31, 2, 3

a. Reactor Vessel Water Level-Low, Level 3

b. Reactor Vessel (RHR Cut-inPermissive) Pressure - High

~emper.atu ~KgRHR Equipment AreaTemperature - HighRHR Flow - High

8 4 Hanual InitiationDrywell Pressure - High

NA

NAS

NANA

HHR

H

QR

R

1, 2, 3

1, 2, 3

1, 2, 31 2.31, 2, 31, 2, 3

hen lrand rng rrradiated fuel in the secondary containment and during CORE

witlr a potential for'raining the reactor vessel.""Wlren reactor steam dome pressure > 1043 psig and/or any turbine stop valve

"*"Wlrerr VLNI lNG ur PUHGlNG tire drywell lrer Specification 3.11.2.8.

ALlERATIONS and operations

is open.

e i+i;~

Documents

· Cm TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUHENTATION j UDW'O.. Ã0'3 0; D~,eo j o~ AMxc Gl0 OO'~ I %Oh) acyl~', Aoz TRIP FUNCTION l. I) Low, Level 3 2) Low Low, Level 2 3) Low