ML20095D578

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Proposed Tech Spec 4.7.1.2.2.b.1,deleting Words During Shutdown
ML20095D578
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 08/17/1984
From:
ALABAMA POWER CO.
To:
Shared Package
ML20095D575 List:
References
NUDOCS 8408230399
Download: ML20095D578 (2)


Text

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PLA'4T SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

~ 2. Verifying that each automatic vald in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10% RATED THERMAL POWER.

3. Verifying that the stop check valves 3350A, 3350B, and 3350C are in the open position with the breaker to the valve operators locked open.
b. At least once per 18 months by: .

Verifying that each automatic valve in the flow path actuates to its correct position on an auto pump start signal.

c. At least once per 18 months during shutdown by:
1. Verifying that each motor driven pump starts automatically upon receipt of each of the following test signals:

a) Safety injection, b) Steam generator water level low-low in any steam generator, and c) Loss of Site Power (LOSP).

2. Verifying that the steam turbine driven pump starts automatically upon receipt of each of the following test signals:

a) Undervoltage on 2 out of 3 reactor coolant pump buses, and b) Steam generator water level low-low in two steam generators.

3. Verifying that,the turbine-driven auxiliary feedwater pump l steam admission valves Q1N12V001A-A and Q1N12V0018-B will open when air is supplied from their respective air accumulators.
d. The auxiliary feedwater system shall be demonstrated OPERABLE prior to entry into MODE 2 following each COLD SHUTDOWH by performing a flow test to verify the nonnal flow path from the emergency condensate storage tank through each auxiliary pump to its associated steam generator. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

FARLEY-UNIT 1 3/47-5 AMENDMENT NO.

B400230399 840817 PDR ADOCK 05000348 p PDR

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2. Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10% RATED THERMAL POWER.
3. Verifying that the stop check valves 3350A, 3350B, and 3359C are in the open position with the breaker to the valve operators locked open.
b. At least once per 18 months by:

Verifying that each automatic valve in the flow path actuates to its correct position on an auto pump start signal.

c. At least once per 18 months during shutdown by:
1. Verifying that each motor driven pump starts automatically upon receipt of each of the following test signals:

a) Safety injection, b) Steam generator water level low-low in any steam generator, and c) Loss of Site Power (LOSP).

2. Verifying that the steam turbine driven pump starts automatically upon receipt of each of the following test signals:

a) Undervoltage on 2 out of 3 reactor coolant pump buses, and b) Steam generator water level low-low in two steam generators.

3. Verifying that the turbine-driven auxiliary feedwater pump j steam admission valves Q2N12V001A-A and Q2N12V001B-B will open when air is supplied from their respective air accunulators.
d. The auxiliary feedwater system shall be demonstrated OPERABLE prior to entry into MODE 2 following each COLD SHUTDOWN by l performing a flow test to verify the normal flow path from the emergency condensate storage tank through each auxiliary pump to its associated steam generator. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

FARLEY-UNIT 2 3/47-5 AMENDMENT N0.

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