ML17277B660

Proposed Tech Specs,Changing Tables 3.3.2-1,3.3.2-2,3.3.2-3 & 4.3.2.1-1 Re Isolation Actuation Instrumentation Trip Setpoints & Allowable Values

ML17277B660
Person / Time
Site:	Columbia
Issue date:	03/13/1985
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17277B659	List: GO2-85-133, Application for Amend to License NPF-21,changing Tech Spec Tables 3.3.2-1,3.3.2-2,3.3.2-3 & 4.3.2.1-1 Re Isolation Actuation Instrumentation Trip Setpoints & Allowable Values. Fee Paid ML17277B660
References
TAC-57260, NUDOCS 8503200386
Download: ML17277B660 (14)

Text

lH TRIP I

fUHCTIOH REACTOR WATER CLEANUP SYSTEN ISOLATION a.

A Flow - Nigh 1, 2, 3

TABLE 3.3.2-1 (Continued)

ISOLATIOH ACTUATIOH IHSTAUNENTATION VALVE GROUPS HIHIHUH APPLICABLE OPERATEO BY OPERABLE CllAHHELS OPERATIONAL ACT10N 22 b.

lleat Exchanger Area Temperature - lligh 7

c.

lleat Exchanger Area Ventilation 6 Temp.-

lligh 7

d.

Pump Area Terrrperature - lligh I)

Pump Room A 2)

Pump Room B

e.

Pump Area Ventilation h Temp. - Nigh 1)

Pump Room A 2)

Pump Room B

1 1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

22 22 22 22 22 22 0'rr "PJHA wO0 mo OO IAlA mo mo HD OQ

,OC Gl

,m

~ Ofc rA@

m0.0 f.

SLCS Initiation 7(f) g.

Reactor Vessel Mater Level - Low Low, Level 2 7

h.

AMCU/ACIC Line Routing Area Temperature - lligh 7

i.

AMCU Line Routing Area Temperature - lligh j.

Hanual Initiation Veom 50 l goon Kl l i go~ 405 Roo~ 40q H. A.

1/group l

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

>g 2)E 22 22 22 24

'K2.

221 2K 22

I J.

N

TRIP FUNCTION TABLE 3. 3. 2-1 (Continued)

ISOLATION ACTUATIOtl INSTRUHENTATION VALVE GROUPS Hltill'IUH OPERATED BY OPERABLE CHANNELS APPLICABLE OPERATIONAL CONDITION ACTION 4.

REACTOR CORE ISOLATION CODLING SYSTEH ISOLATIOtl ae b.

C.

d.

e.

RCIC Steam Line Flow - High RCIC/RHR Steam Line Flow - High RCIC Steam Supply Pressure

- Low RCIC Turbine Exhaust Diaphragm

.Pressure

- High RCIC Equipment Room Temperature

- High RCIC Equipment Room d Temperature - High RWCU/RCIC Steam Line Routing Area Temperature - High Drywell Pressure - High Hanual Initiation(h) 8, 9

0 +P 1

8 f

1 1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1,2,3 1, 2, 3

22 22 22 22 22 22 22 22 24 5.

RIIR SYSTEH SHUTDOMtl COOLING RODE ISOLATIOtl a.

Reactor Vessel Water Level - Low, Level 3 6

b.

Reactor Vessel (RHR Cut-in

. Permissive)

Pressure

- High 6

c.

Equipment brea Temperature - High 6

d.

Equipment brea Ventilation d Temp. - High 6

e.

Shutdown Cooling Suction Flow Rate - tligh 6

f.

RHII I!eat Exchanger brea 6~X Teepere lure - Ill<ye 1, 2, 3

ls 2e 3

1, 2, 3

1, 2, 3

1, 2, 3

26 26 26 26 26 g.,

llanual Initiation Reeeee (o O (a Roe' aq Roem boS Roou SG5 6

Co 1/group I

I le 2, 3

I) 2)$

I) R)5 I)E 3 24 2(o 2'Q

PA ap

TRIP FUNCTION TABLE 3. 3. 2-2 ISOLATION AC1UATIOtl IHSTRUHENTATIOH SETPOIHTS TRIP SETPOINT ALLOMABLE VALUE 1.

PRIHARY COHTAItlMEHT ISOLATION b.

C.

e.

Reactor Vessel Mater Level 1)

Low, Level 3

2)

Low Low, Level 2

Drywell Pressure

- lligh Main Steam Line 1)

Radiation - lligh 2)

Pressure

- Low 3)

Flow - lllgh Hain Steam Line Tunnel Temperature - lligh Hain Steam Line Tunnel 6 Temperature - lligh Condenser Vacuum - Low g.

Hanual Initiation 2.

SECONDARY CONTAltNENT ISOLATION

> 13.0 inches*

> -50 inches*

< 1.68 psig

< 3.0 x full power background sig sid DELC~

< 150 F

N. A.

> 11.0 inches

> -57 inches

< 1.88 psig

< 3.6 x full power background

> 811 psig

< 108 psid

<+eeoIp 170 F

< ee p

lO'F

> 24.5 inches Ilg absolute pressure N.A.

b.

C.

Reactor Building Vent Exhaust Plenum Radiation lligh Drywell Pressure

- Nigh Reactor Vessel Mater Level - Low Low, Level 2

Manual Initiation 1%.0 w 'R/h

< 1.68 psig

> -50 inches" N.A.

.)Q.O ~RJ+

< 1.88 psig

> -57 inches N.A.

0r gJ

~

Zoo+ ~0'I g0nhn, Sll goo~ 409 Room 40$

0 P

~>toF

< lt O'

~ lI,DF f/'

c lPOoF

~ )QDF w +4g,, ~Q

<illF TRIP FUtlCTIOtI TAOI.E 3.3.2-2 (Contio<ied)

ISOLATION ACTUATION INSTRUMEtITATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUE 3.

REACTOR MATER CLEAtIUP SYSTN ISOLATION

'a ~

C.

d.

h Flow - High lleat Exchanger Area Temperature - High Ileat Exchanger Area Ventilation A Temp. - High Pump Area Temperature

" High Pump Room A Pump Room 0 Puaip Area Ventilation I Temp.-

High Pump Room A Pump Room B

SLCS Initiation g.

Reactor Vessel Mater Level-Low Low, Level 2

h.

RMCU/RCIC Line Routing Area Temperature - tligh i.

AMCU Line Routing Area Temperature - High j.

Hanua Initiation

< 50.5 gpm

< ~~&0 F'(o0

+

< +3fPF M l60 F QO F g< <8<+

'70~ F Q

N.A.

< 65.5 gpm

< +88~ Ito0 F

<~~ao'F

< ~~ISD F

<~a~ ISO'F F

IOO tl.A.

4.

REACTOR CORE ISOLATION COOLING SYSTEH a.

ACIC Steam Line Flow - lllgh b.

AIIR/ACIC Steam Line Flow - High c.

RCIC Steam Supply Pressure

- Low d.

ACIC Turbine Exhaust Oiapt>ragm Pressure

- lligh e.

ACIC Equipment Room

~ ITemperature - High I y i,)

> -50 inches"

~140 I

N.A.

ISOI.ATION

< 290K of rated flow

< 101.5 inches He0

> 62 psig

< 10.0 psig ll o F

> -57 inches

<~ I Qo'F N.A.

< 300X of rated flow

< 107.5 inches Il>0

> 58 psig

< 20.0 psig lSG F I

P 1

/p'I

/~)

lg

'i l a

-I C3 I

C M

4J C

3W CO TABLE 3.3.2-2 (Continued)

.ISOLATIOH ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION TRIP SETPOIHT 4.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Continued) f.

RCIC Equipment Room A Temperature-lligh g.

RMCU/RCIC Steam Line Routing Area Temperature - High h.

Drywell Pressure

- High i.

Manual Initiation

< ~petteh ~ F

< 174 inches H 0~~><~'~~< ~

TABLE HOTATIOHS "See Bases Figure 0 3/4 3-1.

< ~~ltoo F

< 1<65 psig N.A.

5.

RHR SYSTEM SIIUTDOMH COOLING MODE ISOLATION a.

Reactor Vessel Mater Level-Low, Level 3

> l~tgches" b.

Reactor Vessel (RIIR Cut-in Permissive)

Pressure - High

< 125 psig~

c.

Equipment Area Temperature - High Pump Room A

< +38'9 Pump Room 0

< 33gstp l40'l=

p d.

Equipment Area Ventilat.ion h Temp. - Iligh

~~6 p Pump Room A Pump Room B

<~~~

I=

e.

Shutdown Cool ing Return Flow Rate-High f.

RHR Heat Exchanger Area

~ at'emperature

- Iligh g.

Manual Initiation H.A.

7 t

ALLOMABLE VALUE

< ~"40 ~

< ~~l~oF

< 1.85 psig N.A.

> 11.0 inches

< 135 psig

<+e~lSo F

< ~~ ISOF gtgl6 4k

< 183 inches lingu N.A.

ROOM 60(c3 QOOMt So'7 ROO bh ho~

Roose SOB 4%0 F

~ 15o'F m l40oF 30op

V t

J 1N

TRIP FUNCTION TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME

RESPONSE

TIME Seconds 8

4.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.

b.

C.

d.

e.f.

g.

h.

1 ~

RCIC Steam Line Flow - High RHR/RCIC Steam Line Flow - High RCIC Steam Supply Pressure Low RCIC Turbine Exhaust Diaphragm Pressure - High RCIC Equipment Room Temperature - High RCIC Equipment Room h Temperature - High RHCU/RCIC Steam Line Routing Area Temperature - High Drywell Pressure

" High Manual Initiation

< 13(a)

< 13(a)

< 13(a)

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

5.

ae b.

C.

d.

e.f.

g.

RHR SYSTEM SHUTDOlrlN COOLING MODE ISOLATION Reactor Vessel Hater Level - Low, 3

Reactor Vessel (RHR Cut-in Permissi Pressure

- High Equipment Area Temperature-Equipment Area Ventilation I

. " High Shutdown Coolin'g Return Fl te - High RHR Heat Exchanger Area erature - High Manual Initiation zeu*T~ > q%'

13(a)

N.A.

N.A.

N. A.

N.A.

N.A N.A.

'WASHINGTON NUCLEAR - UNIT 2 3/4 3-20

~

4 S

)

f

.V>

~,g I

TABLE 4. 3. 2. 1-1 (Continued)

ISOLATION 'ACTUATIOtl INSTRUMENTATIOtl SURVEILLANCE RE UIREHEtlTS TRIP FUNCTION OIANHEL CIIECK CHAIINEL F UNCTIOtlAL TEST CIIANHEL CALIBRATION OPERATIONAL CONDITIONS FOR MIIICH SURVEILLANCE RE UIRED n

Im 4.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Continued) g h.

RMCU/RCIC Steam Line Routing Area Temperature - High Drywell Pressure - High Manual Initiation N.A.

H.A.

H.A.

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

5.

RIIR SYSTEH SHUTOOMH COOLING MODE ISOLATI a.

Reactor Vessel Mater Level-Low Level 3

b.

Reactor Vessel (RHR Cut-in Permissive)

Pressure

- High N.A.

1 2.3 1, 2, 3

c.

Equipment Area Temperature-High d.

Equipment Area Ventilation h Temp. - High e.

Shutdown Cooling Return Flow Rate - High f.

RIIR Heat Exchanger Area

+~XTemperature - iiihh g.

Hanua I Initiat ion tl.A.

N.A.

TABLE NOTATIONS g

R N.A.

le2p 3

1, 2, 3

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

Mhen reactor steam pressure

> 1037 psig and/or any. turbine stop valve is open.

When handling irradiated fuel in the secondary containment and during CORE ALTERATIOHS and operations with a potential for draining the reactor vessel.

N During CORE ALTERATIOH and operations with a potential for draining the reactor vessel.

C

~

~

t4 J,

'I