ML20091F204

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs 4.5.2.d & 4.4.9.3.2 Allowing Removal of RHR Sys Suction Valve Autoclosure Interlock
ML20091F204
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 11/20/1991
From:
GEORGIA POWER CO.
To:
Shared Package
ML20091F201 List:
References
NUDOCS 9112020033
Download: ML20091F204 (2)


Text

._ . - . . . - . - . . . .. . ~ . -. - - . - ,.

_ REACTOR COOLANT SYSTfM OVERPRESSURE PROTECTION SYSTEM

-SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a.

)

Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereafter when the PORV is required CPERABLE; b.

Performance least once perof18amonths; CHANNEL and CALIBRATION on the PORY actuation channel at

c. Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the PORV is being used for overpressure protection.

4.4.9.3.2 Each RHR suction relief valvc shall be demonstrated OPERABLE when the RHR suction relief valves are being used for cold overpressure protection as follows:

a.-

For RHR suction relief valve PSV-8708A by verifying at least once per gAhours that RHR RCS suction isolation valves HV-8701A and HV-8701B are open; .

5 b.

For RHR suction relief valve PSV-87088 by verifying at least once per 72.p hours that RHR RCS suction isolation valves HV-8702A and HV-87028 arc open; and c.. Testing pursuant to specification 4.0.5.

4.4.9.3.3 The RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

  • when the vent (s) is being used for overpressure protection.

h

  • Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise~ secured in the open position, then verify these valves open at least once per 31 days. I V0GTLE UN115. 1&2 3/4 4-36 9112O20033 911120 i PDR ADOCK 05000424

{ P PDR

-'~ ~~

4

, F.HERGENCY C0RE COOLING SYSTEMS SURVEILLANCE'REQUIREMENIS_ _

_ _ )

4 ; 2 Each ECCS subsystem shall be demonstrated OPERABLE: .

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 lockout switches in the lockout position:

Valve Number Valve Function

)

Valve Position HV-8835 51 tump Cold Leg Inf. OPEN HV 8840 RHR Pump Hot Leg In<. CLOSED HV-8823 51 Pump Mini Flow Isol. OPEN HV 8806 51 Puao Suction from RWST OPEN HV-8802A, B $1pumpHotlegInj.

- CLOSE0 HV-8809A, B RHRPumpColdLegInj. OPEN* '

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 discharge 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 Emergency Sump anel cause restriction )

of the pump suctions during LOCA conditions. This visual inspection shall be performed:

1) For all accessible areas of the containment prior to establish-ing CONTAINMENT INTEGRITY, and
2) Of the areas affected within containment at the completion of each containment entry when CONTAINHENT INTEGRITY is establishtt d .- At least once per 18 months by:
1) Verifying automatic isolation : .d ' '.: '::L action of the RHR system from the Reactor Coolant System by ensuring tha F

- *) )(ith a simulated or actual Reacto d oolant System pressure l signal greater than or equal to M p g the interlocks prevent the velves from being opene and u- us.t . 4 u .a ,__.....a n..... c. a .-. c . . . 2_

,i'" .i iZ,' 72 ::

11 z'~ i'. ' G '1 'i" H"' 'i' 1 _ "_ ' 'm ' .

'.'.l' . . ' . J ', ". E

... .... '..l ' 1'. :2 . .'L 1 T'. , T '", ' ' " " ' '

' ' ~

2) A visual inspection of the Containment Emergency Sump and verify-ing 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.
  • Either valve may be realigned in Mode 3 for testing pursuant to Specification 4.4.6.2.2.

i V0GTI.E UNITS - 1 & 2 , 3/4 5-4

.