ML20081M737

Proposed Tech Spec 3.5.1 Re Eccs,Adding Action Statement to Specify Actions to Be Taken in Event of Inoperable Automatic Depressurization Sys Supply Header Low Pressure Alarm Sys

ML20081M737
Person / Time
Site:	Perry
Issue date:	06/28/1991
From:	CENTERIOR ENERGY
To:
Shared Package
ML20081M730	List: ML20081M737 PY-CEI-NRR-1350, Application for Amend to License NPF-58,changing Tech Spec 3.5.1 Re ECCS to Add Action Statement to Specify Actions to Be Taken in Event of Inoperable Automatic Depressurization Sys Supply Header Low Pressure Alarm Sys
References
NUDOCS 9107100096
Download: ML20081M737 (5)

Text

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Af6 6,uit A P)'-C EI/N M -lifd L EMERGENCY CORE COOLING SYSTEMS.

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LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued) d.

For ECCS divisions 1 and 2, provided that ECCS division 3 is OPERABLE:

1.

With LPCI subsystem " A" and either LPCI subsysten "B" or "C" inoperable, restore at least the inoperable LPCI subsystem "A" or inoperable LPCI subsysten "B" or "C" to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

2.

With the LPCS system inoperable and either LPCI subsystws "B" or "C" inoperable, restore at least the inoperable LPCS system or inoperable LPCI subsystem "B" or "C" to OPE 3ABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> *.

e.

For ECCS divisions 1 and 2, provided that ECCS division 3 is OPERABLE and divisions 1 and 2 are otnervise OPERABLE.

1.

With one of the above required ADS valves inoperable, restore the inoperable ADS valve to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce

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reactor steam dome pressure to 1100 psig within ti.e next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

With two or more of the abuve required ADS valves inoperable, be in at least HOT SHUTDOWN within 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-and reduce teactor LserE A steam dome pressure to 1100 psig within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

g.f.

With an ECCS discharge line " keep filled" pressure alare instrumenta-tion channel inoperable, perform surveillance 4.5.1.a.1 at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

h.g In-the event an ECCS system is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and sub-mitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to.date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

"Whenever two or more RHR subsystems are inoperable, if unable to attain l 3 COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.

i 9107100096 910628 POR ADOCK 05000440 P

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PtMKT - unit 1 3/4 5-3

PY-CEI(!RR-1350 L Page 2 of 4 Insert A f.

Vith an ADS safety related instrument air header (s) lov pressure alarm system instrumentation channel (s) inoperable, determine the associated ADS header pressure from alternative indication and verify that ADS header pressure-is greater than or equal to the alarm setpoint specified in Surveillance Requirement 4.5.1.e.2.c at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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A % Jimt,1 PY-C E.T)MFR - 1%So L EMERGENCY CORE C00LINC SYSTEMS g 3 of 9 (P

SURVEILLAMCE REQUIREMENTS (Continued) e.

For the ADS by:

1.

At least once per 31 dcyb, mrty ig a CHANNEL FUNCTIONAL TEST of the safety related intti #

, system low pressure alarm system.

2.

At least once per 18 mentns; a)

Perfor~

a system functional test which includes simulated autcma

.tuatiori of the system throughout its emergency operati..,, nequence, but excluding actual valve actuation, e)

Manually" opening each ADS valve when the reactor steam b

dome pressure is greater than or equal to 100 psig* and f '" g J observing that either:

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4 1)

The control valve or bypass valve position responds accordingly, or y Me,9

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• 2)

There is a corresponding change in the measured steam fe, -

flow, or t&

3 3)

The safety relief valve discharge pressure switch indicates the valve is open.

c)

Performing a CHANNEL CALIBRATION of the safety related instrument air system low pressure alarm system and verifying an alarm setpoint of > 155 psig with an allowable value of > 151.9 psig on decreasing pressure.

• The provisions of Specification 4.0.4 are not applicable previded the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> af ter reactor steam pressure is adequate to perform the test.

• • ADS solenoid energization shall be used alternating between ADS Division 1 and ADS Division 2.

i, PERRY - UNIT 1 3/4 5-5 Amendment No. 6

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P Y-c cI/N RR-J A5 0 L 3/4.5 EMERGENCY CORE COOLING SYS[EM tg e 4. d t E

BASES ECCS-OPERATING and SHUT 30VN (Continued)

With the HPCS system inoperable, adequate core cooling is assured by the OPERABILITY of the redundant and diversified automatic depressurization system and both the LPCS and LPCI systems.

In addition, the reactor core isolation cooling (RCIC) system, a system for which no credit is taken in the safety analysis, will automatically provide makeup at reactor operating pressures on a reactor low water level condition. The HPCS out-of-service period of 14 days is based on the demonstrated OPERABILITY of redundant and diversified low pressure core cooling systems.

The surveillance requirements provide adequate assurance that the HPCS system will be OPERABLE when required.

Flow and total developed head values for surveillance testing include system losses to ensure design requirements are met. Although all active components are testable and full flow can be demonstrated by recirculation through a test loop during reactor operation, a complete functional test with reactor vessel injection requires reactor shut-down. The pump discharge piping is maintained full to prevent water hammer damage and to provide cooling at the earliest moment.

Upon failure of the HPCS system to function properly after a snall break loss-of--coolant accident, the automatic depressurization system (A05 auto-matically causes selected safety relief valves to open, depressurd l the reactor so that flow from the low pressure core cooling systems can

,ter the core in time to limit fuel cladding temperature to less than 2MC"F.

A05 is conservatively required to be OPERABLE whenever reactor vesse: pressure exceeds 100 psig even though LPCS flow is 6110 gpm rated flow at 128 psid, and LPCI flow is 7100 gpm rated flow at 24 psid.

ADS automatically controls eight selected safety relief valves although the safety analysis only takes credit for seven valves.

It is therefore appropriate to permit one valve to be out-of-service for up to 14 days without materially reducing system reliability. Also, a lf e rn.te is Ak fan is p ro vid ed in %

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3/4.S.3 SUPPRESSION POOL aimpo.

The supression pool is required to be OPERABLE as part of the ECC5 to ensure that a sufficient supply of water is available to the HPCS, LPCS and LPCI systems in the event of a LOCA.

This limit on suppression pool minimum water volume ensures that sufficient water is available to permit recirculation cooling flow to the core.

The OPERABILITY of the suppression pool in OPERATIONAL CONDITIONS 1, 2 or 3 is required by Specification 3.6.3.1.

Repair work might require making the suppression pool inoperable. This specification will permit those repairs to be made and at the same time give assurance that the irradiated fuel has an adequate coolin0 water supply when the suppression pool must be made inoperable, including draining, in OPERATIONAL CONDITIONS 4 or 5.

In OPERATIONAL CONDITION 4 and 5 the suppression pool minimum required water volume is reduced because the reactor coolant is aaintained at or below 200*F.

Since pressure suppression is not required below 212 F, the minimum required water volume is based on NPSH, recirculation volume, and vortex prevention plus a safety margin for conservatism.

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