ML18009A769

Retyped Tech Spec Pages Re RHR Autoclosure Interlock Deletion

ML18009A769
Person / Time
Site:	Harris
Issue date:	12/21/1990
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18009A768	List: ML18009A767 ML18009A769
References
NUDOCS 9101040025
Download: ML18009A769 (5)

Text

ATTACHMENT 1 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 RETYPED TECHNICAL SPECIFICATION PAGES RESIDUAL HEAT REMOVAL AUTOCLOSURE INTERLOCK DELETION 9101040025g 901221 pDR ADOCK 05000q00 p

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EMERGENCY CORE COOLING SYSTEMS

.2 ECCS SUBSYSTEMS - T GREATER THAN OR EQUAL TO 350'F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:

a ~ One OPERABLE Charging/safety injection pump,

b. One OPERABLE RHR heat exchanger,

c. One OPERABLE RHR pump, and

d. An OPERABLE flow path capable of taking suction from the refueling water storage tank on a Safety Injection signal and, upon being manually aligned, transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-ing 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.

SURVEILLANCE RE UIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a ~ At, least once per 12 hours by.'.

Verifying that the following valves are in the indicated positions with the control power disconnect switch in the "OFF" position, and the valve control switch in the "PULL TO LOCK" position:

SHEARON HARRIS - UNIT 1 3/4 5-3 Amendment No.

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)

CP6L EBASCO Valve No. Valve No.. Valve Function Valve Position 1SI-107 2SI-V500SA-1 High Head Safety Injection to Closed Reactor Coolant System Hot Legs 1S 1-86 2SI-V501SB-1 High Head Safety Injection to Closed Reactor Coolant System Hot Legs 1SI-52 2SI-V502SA-1 High Head Safety Injection to Closed Reactor Coolant System Cold Legs 1SI-340 2SI-V579SA-1 Low Head Safety Injection to Open Reactor Coolant System Cold Legs 1SI-341 2SI-V578SB-1 Low Head Safety Injection to Open Reactor Coolant System Cold Legs 1SI-359 2SI-V587SA-1 Low Head Safety Injection to Closed Reactor Coolant System Hot Legs

b. At least once per 31 days by:

1. Verifying that the ECCS piping is full of water by venting 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 sump and 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 CONTAINMENT INTEGRITY is established.

SHEARON HARRIS - UNIT 1 3/4 5-4 Amendment No.

~ g ~

'f EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)

d. At least once per 18 months by.'.

Veri fying automatic interlock action of the RHR system from the Reactor Coolant System by ensuring that with a simulated or actual Reactor Coolant System pressure signal greater than or equal to 425 psig the interlocks prevent the valves from being opened.

2. A visual inspection of each 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.

e. At least once per 18 months, during shutdown, by:

1. Verifying that each automatic valve in the flow path actuates to its correct position on safety injection actuation test signal and on safety injection switchover to containment sump from an RWST Lo-Lo level test signal, and

2. Verifying that each of the following pumps start automatically upon receipt of a safety injection actuation test signal:

a) Charging/safety injection pump, b) RHR pump.

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

1. Charging/safety injection pump (Refer to Specification 4.1.2.4)

2. RHR pump > 100 psid at a flow rate of at least 3663 gpm.

g ~ By verifying that the locking mechanism is in place and locked for the following High Head 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.

SHEARON HARRIS - UNIT 1 3/4 5-5 Amendment No.

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UI REMENTS (Con t i nued )

EBASCO Valve No. CP&L Valve No.

2SI-V440SA-1 1SI-5 2SI-V439SB-1 1SI"6 2SI-V438SA-1 1SI-7 2SI-V437SA"1 1SI-69 2SI-V436SB-1 1SI-70 2SI-V435SA-1 1SI"71 2SI-V434SA"1 1SI-101 2SI-V433SB"1 1SI-102 2SI-V432SA-1 1SI-103 2SI-V431SA-1 1SI-124 2SI-V430SB-1 1SI-125 2SI-V429SA-1 1SI"126

h. By performing a flow balance test, during shutdown, following com-pletion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:

1. For Charging/safety injection pump lines, with a single pump running.')

The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 379 gpm, and b) The total pump flow rate is less than or equal to 685 gpm.

2. For RHR pump lines, with a single pump running, the sum of the injection line fl.ow rates is greater than or equal to 3663 gpm.

SHEARON HARRIS UNIT 1 3/4 5-6 Amendment No.