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Proposed TS SR for TS 4.5.1, ECCS - Operating
	ML20126E729
Person / Time
Site:	River Bend
Issue date:	12/22/1992
From:	; GULF STATES UTILITIES CO.
To:	;
Shared Package
ML20126E728	List: ML20126E729; RBG-37939, Application for Amend to License NPF-47,revising TS SR for TS 4.5.1, ECCS - Operating to Correct Minor Nonconservative Calculational Errors Discovered During Self Initiated Safety Sys Functional Insp;
References
	NUDOCS 9212290286
	Download: ML20126E729 (6)
	v • d • e

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ATTACIL%fENT 3 Proposed Technical Specification Changes 1

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3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ECCS - OPERATING LIMITING CON 0! TION FOR OPERATION 3.5.1 ECCS divisions I, II, and III shall be OPERABLE with:

ECCS division I ennsisting of:

a.

1.

The OPERABLE low pressure core spray (LPCS) system with a flow path capable of taking suction from the suppression pool and transferring the water through the spray sparger to the reactor vessel.

2.

The OPERABLE low pressure coolant injection (LPCI) subsystem A"

of the RHR system with a flow path capable of taking suction from the suppression pool and transferring the water to the reactor vessel.

3.

7 OPERABLE ADS valves.

b.

ECCS division II consisting of:

1.

The OPERABLE low pressure coolant injection (LPCI) subsystems "B" and "C" of the RHR system, each with a flow path capable of taking suction from the suppression pool and transferring the water to the reactor vessel.

2.

7 OPERA 8LE ADS valves.

ECCS division III consisting of the OPERABLE high pressure core spray c.

(HPCS) system with a flow path capable of taking suction from the suppression pool and transferring the water through the spray sparger to the reactor vessel.

APPLICABILITY:

OPERATIONAL CONDITION 1, 2*'# and 3*'

aihe A05 is not required to be OPERABLE when reactor steam dome pressure is less than or equal to 100 psig.

See Special Test Exception 3.10.5.

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N0ne LPCI subsystem of the RHR system may be aligned in the shutdown cooling mode'when reactor vessel pressure is less than the RHR Cut-in permissive setpoint.

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_ EMERGENCY CORE COOLING SYSTEMS 4

LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

For ECCS division I, provided that ECCS divisions II and III a.

OPERABLE:

are 1.

With the LPCS system inoperable, restore the inoperabl system to OPERABLE status within 7 days.

e LPCS 2.

With LPCI subsystem "A" inoperable, restore the inope subsystem "A" to OPERABLE status within 7 days.

rable LPCI 3.

With the LPCS system inoperable and LPCI subsystem "A"

i restore at least the inoperable LPCI subsystem "A" or thenoperable, inoperable LPCS system to OPERABLE status within 72 hou rs.

4 and in COLO SHUTOOWN within the followin ours b.

For ECCS division II, provided that ECCS divisions I a d III OPERABLE:

n are 1.

With either LPCI subsystem "B" or "C" inoperable inoperable LPCI subsystem "B" or "C" to OPERABLE status withi

, restore the 7 days.

n 2.

With both LPCI subsystems "B" and "C" inoperable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .least the inoperable LPCI subsystem or "C" to OPERA 8LE

, restore at 3.

and in COLD SHUTDOWN within the followin urs RCIC system are OPERABLE:For ECCS division III, provided t c.

and the 1.

With ECCS division III inoperable, declare th nope r-within 14 days.

2.

Otherwise, be in at least HOT SHUTDOWN within the next 12 ho and in COLD SHUTDOWN -within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

s "Whenever two or more RHR subsystems are inoperable, low as practical by use of alternate heat removal metho mperature as RIVER BEND - UNIT 1 3/4 5-2

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EM'ERGENCY CORE C00 LING SYSTEMS

LIMITING CONDITION FOR OPERATION (Continued) f ACTION:

(Continued) d.

For ECCS divisions I and II, provided that ECCS' division III is OPERA 8LE:

1.

With LPCI subsysten "A" and either LPCI subsystee _"8" or "C" inoperable, restore at least the Inoperable LPCI subsysten "A" or inoperable LPCI subsystes "8" or_"C" to OPERA 8LE status within' 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

2.

With the LPCS system inoperable and either LPCI subsystes "8" or "C" inoperable. ' restore at least the inoperable LPCS system or inoperable LPCI subsysten "8" or "C" to OPERA 8tE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .-

3.

Otherwise,.be in at least HOT SHUTDOWN w'ithin the next 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s-and in COLD SHUTDOWN within the-following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ".

For ECCS divisions-I and II, provided that ECC$ division III is e.

OPERA 8LE and divisions I and II are otherwise OPERA 8LE:-

1.

With one of the above required ADS valves inoperable, restore the inoperable ADS valve to 0PERA8LE status'within 14 days or be in'at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ~and reduce reactor steam dome pressure to f,100_ psig within the next -

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

-With two or more of the above required ADS-valves: inoperable',-

(

be in at least H0T SHUTDOWN!within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reduce reactor steam does pressure to e 100 psig within_the next:24 hours.

f.

With_an ECCS discharge line " keep' filled" pressure alars instrumentation-channel inoperable, perfore Surveillance Requirement 4.5.1.a.1 at lea,st once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

g.

In the event' an ECC5 systes is actuated and. injects water. into the Reacter Coolant Systee, a Special Report shall be prepared and sub-mitted within 90 days to the-Commission, purcuant to Specification c

8.9.2, describing the circumstances of the actuation and the t_otal accumulated actuation cycleszto.date.

The current value of the usage factor for each affected safety injection l nozzle shall be provided in this Special-Report whenever. its.value exceeds:0.70.

i "Whenever two or more RHR subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this' ACTION, maintain reactor coolant temperature as

low as practical by use of alternate heat removal methods.

RIVER 8END - UNIT 1 3/4 5 '

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l EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.1 ECCS division 1, II and III shall be demonstrated OPERABLE by:

a.

At least once per 31 days for the LPCS, LPCI and HPCS systems:

1.

Verifying by venting at the high point vents that the system piping from the pump discharge valve to the system isolation valvo is filled with water.

2.

Verifying that each valve (manual, power operated or automatic),

in the flow path, that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

Verifying that, when tested pursuant to Specification 4.0.5, each:

1.

LPCS pump develops a flow of at least 5010 gpm a pump differential pressure greater than or equal to sid.

2.

LPCI pump develops a flow of at least 5050 gpa a pump differential pressure greater than or equal to sid.

3.

HPCS pump develops a flow of at least 5010 gpa a pump differential pressure greater than or equal to sid.

A$

RR c.

At least once per 18 months, for the LPCS LPCI and HPCS systems, performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence and verifying that each automatic valve in the flow path actuates to its correct position.

Actual injec-tion of coolant into the reactor vessel say be excluded from this test.

d.

At least once per 18 months, for the HPCS system, verifying that the suction is automatically transferred from the condensate storage tank to the suppression pool on a condensate storage tank low water 1evel signal and on a suppression pool high water level signal, and verifying that the HPCS system will automatically re Reactor Vessel Water Level - Low Low Level 2.

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4ett r. P RRMay be extended to the completionof the first refueling outage, scheduled to begin 9-15-87.

RECEIVED I

RIVER BEND - UNIT 1 3/4 5-4 AUG 191987 Amendment No. 9-T, SDC

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EMERGENCY-CORE COOLING SYSTEMS-SURVEILLANCE REQUIREMENTS (Continued)

At least once per 18 months for-the ADS by:

e.

1.

' Performing a system functional test which includes-simulated:

automatic _ actuation of:the system throughout its emergency operating sequence, but excluding actual _ valve actuation.

2, Manually opening each ADS valve wh'en1the reactor steam dome

-pressure is greater than or equal to 100.psig* and observing that:

a)-

The control valve or' bypass valve position responds accordingly, or b)

There is.a corresponding change in'the measured steam flow, or c)

The: acoustic monitoring system indicates the valve"is '

open.

L l

1 i.

"The provisions of. Specification 4.0.4: are not applicable provided 'the

- surveillance is1 performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure -is -

adequate lto: perform the test.

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ML20126E729

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