Text

Proposed Tech Spec 3.5.2, ECCS-Shutdown
	ML20043B234
Person / Time
Site:	River Bend
Issue date:	05/21/1990
From:	; GULF STATES UTILITIES CO.
To:	;
Shared Package
ML20043B231	List: ML20043B234; RBG-32865, Application for Amend to License NPF-47,revising Requirements for Tech Spec 3.5.2, ECCS-Shutdown;
References
	NUDOCS 9005250121
	Download: ML20043B234 (7)
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-,x-TABLE 3.3.2-1 (Continued).

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-ISOLATION ACTUATION INSTRUNENTATION -

i mvo MINIMUM' APPLICABLE j8 ' y _

_ VALVE GROUPS

.m

- te z-OPERATED BY DPERABLE CHANNELS-OPERATIONAL

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Nj 7 ' TRIP FUNCTION

~ ' SIGNAL ***a PER TRIP SYSTEM (a).

CONDITION ACTION' no 57,k 3.

SECONDARY CONTAfletENT ISOLATION' J'?

,e.g oo e a '.-

Reactor Vessel Water.

Level-Low Low..Levc1 2-

y$$

11, 12,.

2 1,2,3 25 13(b)(e)(h)(1) on

'. Ot3 G

. b.

Drywell Pressure - High 11, 12,

~2 1,2,3 25.

13(b)(c)(e)(h)(j) c al Building Ventflation 13(e)(h).

28 3

Exhaust Radiation - High w

d.

Reactor Building 12(b)(a)(1) e Annulus Ventilation Exhaust

, 1 1,2,3 29 Radiation -Thigh-4.

REACTOR WATER CLEANUP SYSTEN ISOLATION a.

A Flow - High 7, 15,-16'.

1 1,2,3 27 b.

5FiowTimer 7, 15, 16 1

1,2,3 27 c.

Equipment Area Temperature.- 7 15; 16 1

1.2,3 27 High d.

Equipment Area A Temperature High 7,.15, 16-1 1,.2, 3 27 e.

Reactor Vessel-Water Level - Low Low, Level 2 7, 15, 16' 2 (m) 1,- 2, 3 {m).

27 f

f.

Main Steam Line Tunnel' 7,.15, 16 l'

1, 2. 3 27 Ambient Temperature - High 8..,

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TABLE'3.3.2-l'(Continued)

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h ISOLATION ACTUATION' INSTRUNENTATION '

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--MINIMUM APPLICABLE VALVE GROUPS-m

-OPERATED BY-OPERABLE CHANNELS' OPERATIONAL

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TRIP FUNCTION SIGNAL *** PER TRIP SYSTEM (a)

-CONDITION

-ACTION.

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5.

REACTOR CORE ISOLATION Q

-f,00 LING SYSTEM ISOLATION (continued)-

68 1.

Main Steam Line Tunnel

-Temperature Timer 2

1 1, 2, 3 27 j.

Rild Equipment-Room Ambient Temperature - High 2

1 1, 2, 3 27 U

k.

RHH Equipment Room A Teorerature - High 2

l ',

1, 2, 3 -

-27 R

1.

RHR/RCIC Steam Line Finw -'

2 1

1,2,3 27' Y

High I8) 1 1, 2,13 27 m.

Drywell Pressure - High 3

I}

n.

Manual Initiation 2

}

1, 2,.3 26 6.

RHR SYSTEM ISOLATION a.

RHR Equipment Area Ambient Temperature - High

5, 14-

-2 1, 2, 3 30 b.

RHR Equipment Area a Temperature - High 5, 14 2

1, 2,=3 30 l-

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Reactcr Vessel Water 2 (m) 1,. 2, 3p(m) 30 c.

Level Low, Level 3'.

5, 14 d.

Reactor Vessel' Water Level -

Low Low tow, Leval 1

.10

.2

1. 2.-3 30

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'en T/PLE 3.3.2-1-(Continued).

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ISOLA [.ONACTUATIONINSTRUMENTATION

ACTION,

, s,,.,y V;.F NOTES

~Nhen handling irradiated fuel in the Fuel Building.

May be bypassed with reactor mode switch not in.Run and'all turbine -

stop. valves closed.-

- - J The valve groups. listed are designated in Tables-3.6.4-1 and 3.6.5.3-1.

(a): A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for

. required surveillance without placing the trip system in the tripped-condition provided.at least one other OPERABLE channel in the. same trip system is monitoring that parameter, (b) Also actuates the standby gas treatment system.

(c) ~Also actuates the main' control room air conditioning system in the emergency mode of operation.

'(d) Also trips and isolates the* air removal pumps.

. (e)

Table 3.6.5.3-1.Also actuates secondary containment ventilation isolation dampers per r

q-'

(f). Manual' initiation of SLCS pump C0018 closes 1G33*MOVF001, and manual

. ' initiation of SLCS pump C001A closes 1G33*MOVF004..

(g) _ Requires RCIC_ system steam supply pressure-low coincident with drywell pressure-high.

(h) Also starts-the Fue1LBuilding Exhaust Filter Trains A and B.-

(1): Also starts T.he Annulus Mixing System. '

' g '

(j)- Also' actuates the' containment hydrogen analyzer / monitor recorder.

(k) : Manual initiat. ion i'solates the outboard steam supply isolation" valve only -

Valve '1E22*MOVF023:does not isolat's on the manual initiation.a (1) m-v v

v (ra) Also wuen the associated: division-is required under

-specification.3.5.2 note A

A.

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' TABLE 4 3 A l-1 5-ISOLMION ACTUATION INSTRUENTATION SURVEILLANCE REQUIREENTS

' OPERATIONAL-9 CHAfglEL-CONDITIONS IN WICH m

CHANNEL!

FUNCTIONAL CHA000EL'-

SURYEILLANCE REQUIREO'-

' CHECK, TEST CALIBRATION

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@y TRIP FUNCTION E

1.

PRIMARY CONTAll8E98T ISOLATICN Reactor Vessel Water Level -

R(b) 1,2,3 a..

Low Low Level 2 5

M R(b) 1, 2, 3 -

5 M

b.

Drywell ivessure - High Containment Purge Isolation Radiation - High 5

M R

.1, 2, 3 c.

2.

~ MAIN STEAM LINE 150LATI001 Reactor Vessel Water Level -

R(b) 1,2,3 R

Low Low Low Level 1 S

M a.

b.

Main Steam Line Radiation -

b w

S M

R.

1, 2, 3 4

High R(b) 3 m

Main Steam Line Pressure -

c.

S-M R(b) 1, 2, 3' Low d.

Main Steam Line Flow - High S

M R(b) y, 2**, 3**

S~

M m

. Condenser Vacuum - Low fm e.

f.

Main Steam Line Tunnel R

1,2,3 w

S M

g y Temperature - High O

Main Steam Line funnel' a Temperature - High.

5 M

R 1, 2, 3

.$ 0 g.

R(b)

%, 2, 3 1

S M

Y h.

Main Steam Line' Area Temperature-High 8

7.

2

-(Turbine Building) y V,u c:

!b kI h

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15 20 a

c N$

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i. f 5 11 m */

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. TABLE 4.3.2.1-1(Continued)

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ISOLATION ACTUATION INSTRINENTATION SURVEILLANCE REQUIRDENTS

'E E=

CHANNEL OPERATIOM L

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CHANNEL.

FUNCTIONAL CHAMEL

~ CONDITIONS:IN WHICH-.~.

m L

[TRIPFUNCTI0r.

CHECK

' TEST CALIBRATION.

SURVEILLANCE REQUIRE 0' 5 3.

SECONDARY CONTADOENT ISOLATION -

]

w a.

Reactor Vessel Water-R$ g Level - Low Low Level 2-5 M

i c

b.

Drywell Pressure -' High S

M.

R 1, 2, 3 l

i c.

Fuel Building ventilation 1, 2, 3 Exhaust Radiation - High S

M R-

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Reactor Building Annulus Ventilation Exhaust I

Radiation - High S

M R

1, 2, 3 -

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> 4.

REACTOR WATER CLEANUP SYSTEM ISOLATION

,Y a.

A Flow - High S

M R-1,2,3 b.

A Flow Timer M

M Q

c.

Equipment Area Temperature -

1, 2.j 3 I

High.

S M-R 1

2 d.

Equipment Area 1, 2, 3 in p a Temperature - High S

M R

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O e.

Reactor Vessel Water 1,2,3 (c)-

q D

g g

Level - Lev Low Level 2 S

M R

%O f.

Main Steam Line Tunnel Aabient 1, 2, o

j g'

1, ' ((3 );f 3 k

f Temperature'- High S.

M R

.o g.

Main Steam Line Tunnel

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f a Temperature - High S

M R

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-a. - E 5

M ")

1,. $3 (( g 7 8

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SLCS Initiation M

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r-EMERGENCY 40RE' COOLING SYSTEMS S/4.5.2 ECCS - SHUTOOWN 6

i.IMITING CONDITION FOR-OPERATION 3.5.2 At least tw f the following shall be OPERA 8LE:-

b a.

. The low pressure core spray (LPCS) system with a flow path capable of taking suction-from the; suppression pool and transfeering tr e -.

water-through the spray sparger to the reactor vessel, b.

Low pressure coolant injection (LPCI) subsystem "A" of the RHR' ap system with a flow path capable of taking suction from the suppres-sion pool;and transferring the water to the reactor vessel.

c.

Low pressure coolant injaction (LPCI) subsystem "B" of the RHR.-

system with a flow path capable of taking suction from the suppres?

.sion pool'and transferring the water to the reactor ve n el.

d.

Low pressure coolant injection'(LPCI) subsystem "C"t of the RHR system with a flow path capable of taking suction from the suppres-sion pool and transferring the water to,the reactor vessel.

' The high-pressure core spray (HPCS) system with a flow path capatile

,Ab e.-

of.taking suction' from the condensate storage tank or suppression T

. pool,' as applicable,- when these sources of water are OPERABLE per.*

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. Specification 3.5.3.b, and transferring the wat'er through the spray sparger'to the: reactor vessel.

APPLICABILITY: OPERATI,0N L CONDITION 4 and 5*.

ACTION:

y With o' ne of the above required subsystems / systems inoperable, restore a.

at least two suesystems/ systems te OPERABLE status.within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or suspend #11 operations that have a potential for draining the reactor vessel.

t b.

With'both of the above required subsystems / systems inoperable, suspend CORE ALTERATIONS and all operations that have a poteptial for draining o

the~ reactor vessel.

Restore at least one subsystem / system-to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or establish PRIMARY CONTAINMENT INTEGRITY - FUEL HANDLING within the next S nours.

"The ECCS is not required to be OPERABLE provided that the reactor vessel head

' s removed, the cavity is flooded, the upper containment fuel pool gate.is i

opened, and water level is wintained within the limits of Specifications 3.9.8 and 3.9.9.

m provided'atleastonedivisionofthenecessaryRHRandRWUUlev\\

One LPCI subsystem may be aligned in the shutdown cooling mode el isolations are operable per Specification 3/4.3.2 j

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TABLE 4.3.2.1-3 (Continued) 2..

ISOLATION ACTUATION INSTRIS E TATION SURVEILLANCE REQUIREE NTS E

e CHA181EL OPERATIONAL

Q CHANNEL-..

FUNCTIONAL CHANNEL CONDITIONS IN WHICH i

TRIP FUNCTIOW CHECK

-TEST CALIBRATION SURVEILLANCE REQt!IREE l,:

6.

RHR SYSTEM ISOLATION e5 a.

RHR Equipment Area Ambient

'Tamperature - High S

M R

1, 2, 3 b.

RHR Equipment Area A Temperature - High.:

S M

R 1, 2, 3

c. L : Reactor Vessel 1 dater Level -

.. (b)-

t y t j.3

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.R

?I.: 2.13, (c)

J

.d.

Reactor Vessel Water Level -

~

R(b) [

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Low Low Low Level 1 S

M m

1, 2, 3 e.

Reactor Vessel'(RHR Cut-in Permissive) Pressure - High S

M R

1, 2, 3 f.

Bryuell Pressure - High 5

M R

1, 2, 3

l

.R, y

7.

. MANUAL INITIATION NA M

NA 1,2,3 U

When handling irradiated fuel in the Fuel Building.

- When the reactor mode switch is in Run a.4/or any turbine.stop valve is open.

(a) Each train or logic channel shall be tested at least every 6ther 31 days.

(b),Ca1Jheate trip > unit-1st'at-~1 east engeg31' days ~

c) Mb be exh rstTrefueT1 Coutage, s M ihd to beg n 9-15-87.\\-

d) May be extended to the completion of the first reftseling outage, scheduled begin 9-15-87.

5 A

r A is required-u pecification 3.5.2 (c) Also when the associated di ',

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ML20043B234

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