ML20057E649

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Proposed Tech Specs 4.5.2d Re RHR Sys Autoclosure Interlock Removal
ML20057E649
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 09/28/1993
From:
DUKE POWER CO.
To:
Shared Package
ML20057E647 List:
References
NUDOCS 9310120436
Download: ML20057E649 (2)


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ATTACIDIENT 4 PROPOSED TECllNICAL SPECIFICATION AAIENDMENTS FOR CATAWIIA i

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1 9310120436 930928 DR ADOCK 05000413 k PDR

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EMERGENCY CORE COOLING SYSTEMS I

SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators j

removed:

Valve Number Valve Function Valve Position NI-162A Cold Leg Recire.

Open j

NI-121A Hot Leg Recirc.

Closed NI-152B Hot Leg Recirc.

Closed i

NI-183B Hot Leg Recire.

Closed NI-173A Residual Heat Open j

Removal Pump Disch.

NI-178B Residual Heat Open Removal Pump Disch.

NI-100B Safety Injection Open Pump Suction from Refueling Water Storage Tank NI-147B Safety Injection Open Pump Mini-flow i

b.

At least once per 31 days by:

)

1)

Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible distnarge piping high points, and 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.

c.

By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment wmo and cause restriction of the pump suctions during LOCA conuttions.

This visual inspection shall be performed:

1)

For all accessible areas of the containment prior to establisn-ing CONTAINMENT INTEGRITY, and 2)

Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is establishe:

d.

At least once per 18 months by:

1)

Verifying automatic #::12ti r and interlock action of the resicual heat removal system f rom the Reactor Coolant System by ensuring that/f et w eith a simulated or actual Reactor Coolant System pressure signal greater than or ecual to 425 psig the interlocks

)

prevent the valves from being opened, efte-1%%d uc.

(un'.t i)

CATAWBA - UNITS 1 & 2 3/4 5-6 gyggen9 ffg, (un g y 1

r EMERGENCY CORE COOLING SYSTEMS i

SURVEILLANCE REOUIREMENTS (Continued) b)

U!th a timulated er actual "cacter Ceelent System presauce tign:1 lett than er cqual to CCO psis the lniciivui> wiii

th: ;;?v;; t; ;;t;;; tic;;'y cle m.

2)

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens,'etc.) show no evidence of structural distress or abnormal corrosion.

At least once per 18 months, during shutdown, byf**~

l e.

1)

Verifying that each automatic valve in the flow path actuates to its correct position on Safety Injection and Containment Sump Recirculation test signals, and 2)

Verifying that each of the following pumps start automatically upon receipt of a Safety Injection test signal:

a)

Centrifugal charging pump, b)

Safety Injection pump, and c)

Residual heat removal pump.

f.

By verifying that each of the following pumps develops the indicated differential pressure when tested pursuant to Specification 4.0.5:

1)

Centrifugal charging pump 1 2223 psid, 2)

Safety Injection pump 2 1341 psid, and 3)

Residual heat removal pump 1 165 psid.

g.

By verifying the correct position of each electrical and/or mechanical stop for the following ECCS throttle valves:

1)

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and 2)

At least once per 18 months.

Centrifugal Charging Pump Injection Throttle Safety Injection Throttle Valve Number Valve Number NI-14 NI-164 NI-16 NI-166 NI-18 NI-168 NI-20 NI-170 a w_ w_w _.

    • Thi: tur/ci' lance need not 50 acrfor::d cnti' p-icr te enter #ng HOT EMUT00P" 4

-4011cu eg the Unit One #4 rst rek:%er-CATAWBA - UNITS 1 & 2 3/4 5-7 Amendment No.1 (Unit 1)

Amendment No.

(Unit 2)