ML20209E095

Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months

ML20209E095
Person / Time
Site:	Oyster Creek
Issue date:	07/07/1999
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20209E088	List: ML20209E082 ML20209E089 ML20209E095
References
NUDOCS 9907140145
Download: ML20209E095 (6)

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l Revised Technical Specification Pages 1

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4.4 Eh1ERGENCY COOL ING Apolicability: Applies to surveillance requirements for the emergency cooling systems.

Objective:

To verify the operability of the emergency cooling systems.

Specification: Surveillance of the emergency cooling systems shall be performed as foibws:

Item Freauency A. Core Sorav System

1. Pump Operability Once/3 months. Also afler major maintenance and prior to startup following a refueling outage.

2. Motor operated valve Once/3 months operability

3. Automatic actuation test Every three months

4. Pump ompartment water-Once/ week and after each entry tight wrs closed

5. Cere s, ay header 4P ins., nentation Check Once/ day Calibrate Once/3 months Test Once/3 months B. Automatic Depressurization

1. Valve operability Once every 24 months *

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2. Automatic actuation test Every refueling outage b

C. Containment Gooline Smtem

1. PumpOperability Once/3 months. Also after major maintenance and prior to startup following a refueling outage.

• Ve!"e operability shall be demonstrated at system operating pressure i

prior te exceeding 5 percent power, following a refueling outage.

OYSTER CREEK 4.4-1 Amendment No. 109,144,193 i

4 Item Freauency C. Containment Cooline System

2. Motor-operated valve operability Every 3 months

3. Pump compartment water-Once/ week and after each entry tight doors closed D. Emercency Service Water System

1. Pump Operability Once/3 months. Also after major maintenance and prior to startup following a refueling outage.

E. Control Rod Drive Hydraulic System

1. PumpOperability Once/ month. Also after major maintenance and prior to startup following a refueling outage.

F. Fire Protection System

1. Pump Operability Once/ month. Also after major maintenance and prior to startup following a refueling outage.

2. Isolation valve operability Once/3 months. Also after major maintenance and prior to startup following a refueling outage.

Bases:

It is during major maintenance or repair that a system's design intent may be violated accidentally.

Therefore, a functional test is required after every major maintenance operation. During an extended outage, such as a refueling outage, major repair and maintenance may be performed on many systems. To be sure that these repairs on other systems do not encroach unintentionally on critical standby cooling systems, they should be given a functional test prior to startup.

Motor operated pumps, valves and other active devices that are normally on standby should be exercised periodically to make sure that they are free to operate. Motors on pumps should operate long enough to approach equilibrium temperature to ensure there is no overheat problem.

Whenever practical, valves should be stroked full length to ensure that nothing impedes their motion. Testing of components per OC Inservice Testing Program in accordance with ASME i

Section XI once every 3 months provides assurances of the availability of the system. The Control Rod Ilydraulic pumps and Fire Protection System pumps are not part of the Inservice Test Program per ASME Section XI and will continue to be tested for operability once per month.

Engineeringjudgment based on experience and availability analyses of the type presented in Appendix L of the FDSAR indicates that testing these components more often than once a month over a long period of time does not significantly improve the system reliability. Also, at this frequency of testing wearout should not be a problem through the life of the plant.

OYSTER CREEK 4.4-2 Amendment No.: 109,160

I)uring tests of the electromatic relief valves, steam from the reactor vessel will be discharged directly to l

the absorption chamber pool. Scheduling the tests in conjunction with the refueling outage permits the tests to be run at low power, prior to 5 percent power, enhancing the safety of the plant by assuring EMRV operability before higher power levels are reached.

The control rod drive hydraulic system is normally in operation, thereby providing continuous indication of system operability. A check of flow rate and operability can be made during normal operation.

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OYSTER CREEK 4.4-3 1

r-l the valve or its associated actuator by cycling the valve through at least one complete cycle of full travel and verifying the isolation j

time limit is met. Following maintenance, repair or replacement work on the control or power circuit for tne valves, the affected component shall be tested to assure it will perform its intended function in the circuit.

3.

Quarterly, during periods of sustained POWER OPERATION, each main steam isolation valve shall be closed (one at a time) and its closure time verified to be within the limits of Specification 4.5.F.1 above. Such testing shall be conducted with reactor power not greater than 50% of rated power.

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Reactor Building to Suppression Chamber Vacuum Breakers j

The reactor building to suppression chamber vacuum breakers a.

and associated irstrumentation, including setpoint, shall bc checked for proper operation every three months.

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During each REFUELING OUTAGE, each vacuum breaker shall be tested to determine that the force required to open the vacuum breaker from closed to fully open does not exceed the f

force specified in Specification 3.5.A.4.a. The air-operated vacuum breaker instrumentation shall be calibrated during each REFUELING OUTAGE.

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Pressure Suppression Chamber-Drywell Vacuum Breakers a.

Periodic OPERABILITY Tests Once every 3 months and following any release of energy which would tend to increase pressure to the suppression chamber, each OPERABLE suppression chamber - drywell vacuum breaker shall l'e exercised. Operation of position switches, indicators and alarms shall be verified every 3 months by operation of each OPERABLE vacuum breaker.

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REFUELING OUTAGE Tests (1)

All suppression chamber - drywell va.:uum breakers shall be tested to determine the force required to open each valve from fully closed to fully open.

(2)

The suppression chamber - drywell vacuum breaker position indication and alarm systems shall be calibrated and functionally tested.

OYSTER CREEK 4.5-3 Amendment No.: 144,186,196 i

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i Surveillance of the suppression chamber-reactor building vacuum breakers consists of OPERABILITY checks and leakage tests (conducted as part of the containment leak-tightness tests). These vacuum breakers are normally in the closed position and open only during tests or an accident condition. As a result, a testing frequency of three months for OPERABILITY is considered justined for this equipment.

l Inspections and calibrations are performed during the REFUELING OUTAGES, this frequency being based on equipment quality, experience, and engineering judgement.

j The 14 suppression chamber-drywell vacuum relief valves are designed to open to the i

full open position (the position that curtain area is equivalent to valve bore) with a j

force equivalent to a 0.5 psi differential acting on the suppression chamber face of the valve disk. This opening specification assures that the design limit of 2.0 psid j

between the drywell and external environment is not exceeded. Once each REFUELING OUTAGE, each valve is tested to assure that it will open fully in response to a force less than that speciGed. Also, it is inspected to assure that it closes freely and operates properly.

The containment design has been examined to establish the allowable bypass area z

between the drywell and suppression chamber as 10.5 in (expressed as vacuum breaker open area). This is equivalent to one vacuum breaker disk offits seat 0.371 inch; this length corresponds to an angular displacement of 1.25. A conservative allowance of 0.10 inch has been selected as the maximum pennissible valve opening.

Valve closure within this limit may be determined by light indication from two independent position detection and indication systems. Either system provides a control room alarm for a non-seated valve.

At the end of each refueling cycle, a leak rate test shall be performed to verify that signiGcant leakage flow paths do not exist between the drywell and suppression chamber. The drywell pressure will be increased by at least 1 psi with respect to the suppression chamber pressure. The pressure transient (if any) will be monitored with 1

a sensitive pressure gauge. If the drywell pressure cannot be increased by 1 psi over the suppression chamber pressure it would be because a signincant leakage path exists; in this event, the leakage source will be identined and eliminated before POWER OPERATION is resumed. If the drywell pressure can be increased by 1 psi over the suppression chamber, the rate of change of the suppression chamber pressure must not exceed a rate equivalent to the rate of air How from the drywell to the suppression chamber through a 2-inch orifice. In the event the rate of change of pressure exceeds this value, then the source ofleakage will be identined and eliminated before POWER OPERATION is resumed.

The drywell suppression chamber vacuum breakers are exercised every 3 months and immediately following termination of discharge of steam into the suppression chamber. This monitoring OYSTER CREEK 4.5-12 Amendment No.: 128,186,196