ML19339C436
| ML19339C436 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 11/12/1980 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML19339C433 | List: |
| References | |
| NUDOCS 8011180371 | |
| Download: ML19339C436 (5) | |
Text
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VYNPS 00 f~A
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3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMENT CD CD 2.
From and after the date that one of the Core Spray 2.
When it is determined that one Core Spray sub-subsystems is made or found to be inoperable for system is inoperable both LPCI subsystems (Except any reason, reactor operation is permissible only the Recirculation System discharge valves) and the during the succeeding sevan days unless such sub-diesel generators required for operation of such system is sooner made operable, provided that components if no external source of power were during such seven days all active components of available shall be demonstrated to be operable the other. Core Spray subsystem, the LPCI sub-immediately.
systems, and the diesel generators required for operation of such components if no external source of power were available, shall be operable.
3 When it is determined that one of the LPCI pumps is inoperable, the remaining active components of i
3 From and after the date that one of the LPCI pumps the LPCI (except the Recirculation System dis-is made or found to be inoperable for any reason, charge valves) and the Containment Cooling sub-reactor operation is permissible only during the systems, both Core Spray subsystems, and the die-succeeding seven days unless such pump is sooner sel generators required for operation of such com-made operable, provided that during such seven ponents if no external source of power were avail-days the remaining active components of the LPCI able shall be demonstrated to be operable imme-Containment Cooling subsystem and all active com-diately and the operable LPCI pumps daily there-ponents of both Core Spray subsystems and the die-after.
sel generators required for operation of such com-ponents if no external source of power were avail-able, shall be operable.
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3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMFMT 4.
From and after the date that the LPCI sub-4.
When it is determined that a LPCI subsystem system is made or found to be inoperable for is inoperable, both Core Spray subsystems, any reason, reactor operation is permis-the remaining LPCI Pumps and Containment sible only during the succeeding seven days Cooling subsystems and the diesel generators unless it is sooner made operabler provided required for onericion of such components if that during such seven days all active com-no external scm ce of power were available ponents of the other LPCI and the Contain-shall be demonstrated to be operable imme-ment Cooling subsystem, the Core Spray sub-diately and daily thereafter.
systems and the diesel generators required for operation of such components if no ex-ternal source of power were available, shall be operable.
5.
All recirculation pump discharge valves and 5.
a.
All recirculation pump discharge and by-bypass valves shall be operable or closed pass valves shall be tested for oper-prior to reactor startup.
abilility during any period of reactor cold shutdown exceeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if op-6.
If the requirements of Specification 3 5. A erability tests have not been performed cannot be met, an orderly shutdown of the during the preceding 31 days.
reactor shall be initiated and the reactor shall be in a cold shutdown condition within b.
Operability testing of the Recirculation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Pump discharge valves shall be in ac-cordance with Specification 4.6.E.
B.
Containment Spray gooling Capability B.
Containment Spray Cooling Capability 1.
Both containment cooling spray loops are re-1.
Surveillance of the drywell spray loops quired to be operable when the reactor watar shall be performed as follows, during each temperature is greater than 212 F except five year period, an air test shall be per-that a Containment Cooling subsystem may be formed on the drywell spray headers and noz-inoperable for thiry days.
zles.
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e 4
VYNPS 4.5 CORE AND CONTAINMENT COOLING SYSTEMS A.
Core Spray and LPCI During normal plant operation, manual tests of operabls pumps and valves shall be conducted in accordance with specification 4.5. A to demonstrate operability with the exception se the Recirculation Pump Discharge valves.
The Recirculation System discharge valves are not tested during plant operation since to do so would create a severe plant transient.
During each refueling shutdown, tests (as summarized below) shall be conducted to demonstrate proper automatic operation and system performance.
Periodic testing at the intervals specified above will demonstrate that all components which do not operate during normal conditions will operate properly if required.
The automatic actuation test will be performed by simulation of high drywell pressure or low-low water level.
The starting of the pump and actuation of valves will be checked. The normal power supply will be used during the test. Testing of the sequencing of the pumps when the diesel generator is the source of power will be checked during the testing of the diesel. Following the automatic actuation test, the flow rate will be check-ed by recirculation to the suppression chamber. The pump and valve operability checks will be performed by manually starting the pump or activating the valve.
B. and C.
Containment Spray Cooling Capability and RHR Service Water Systems The periodic testing intervals specified in Spcetfications 4.5.B. and C. will demonstrate that all components will operate properly if required. Since this is a manually actuated system, no automatic actuation test is required. The system will be activated manually and the.' low checked by an indicator in the control ron 2 Once every five years air tests will be performed to assure that the containment spray header nozzles are oper-able.
D.,
E. and F.
Station Service Water and Alternate Cooling Tower Systems and High Pressure Coolant Injection and Automatic Depressurization System The testing intervals for the HPCI system will demonstrate that the system will operate if required. The auto-matic depressurization system will demonstrate that the system will operate if required. The automatic depres-surization system is tested during refueling outages to avoid an undesirable blowdown of th reactor coolant system.
The HPCI Automatic Actuation Test will be performed by simulation of the accider.! aignal. This test is nor-mally performed in conjunction with the Automatic Actuation of all core standby cooD ng systems-103
J:.hk A
VYNPS 4.5 (Continu:d)
A flow rate test of HPCIS is performed once/ operating cycle during normal station operation by pumping water flow at f rated conditions from the conden tate storage tank and back through the full flow test return line to the tank.
The pump operability check will be performed by starting the turbine manually, valves will also be stroked by manual actuation of the operators.
G.
Reactor Core Isolation Cooling System Frequency of testi., " ' the ECIC system is as specified in Section 4.5.G.
This demonstrates that the system is operable if needed.
H.
Minimum Core and Containment Cooling System Availability Immediate testing followed by daily testing of all low pressure core cooling subsystems and containment cooling subsystems including the operable standby diesel generator upon determir.ction of one inoperable diesel generator adequately demonstrates the availability of core and containment cooling subsystems. This testing frequency is reduced to monthly during a refueling outage to permit various surveillance inspections on equipment. However, at laast one diesel is maintained fully operable and tested weekly.
I.
Maintenance of Filled Discharge Pipe Observation of water flowing from the discharge line high point vent monthly assures that the core cooling subsystems will not experience water hammer damage when any of the pumps are started. Core spray subsy stems and LPCI subsystems will also be vented through the discharge line high point vent following a return from an ir. operable status to assure that the system is "sclid" and ready for operation.
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4.7.A (Continusd) drywell through a 1-inch orifice. In tha event tha rate of change excssds this valun thin tha sourca of leakage will be identified and eliminated before power operation is resumed.
The drywell-suppression chamber vacuum breakers are exercised in accordance with Specification 4.7.A.6 and Onmediately following termination of discharge of steam into the suppression chamber. This monitoring of valve operability is intended to assure that valve operability and position indication system performance does not degrade between refueling inspections. When a vacuum breaker valve is exercised through an opening-closing cycle, the position indicating lights are designed to function as follows:
Full Closed 2 White - On (Closed to 10.050" open)
Open 2 White - Off
(>0.050" open to full open)
During each refueling outage, two drywell-suppression chamber vacuum breskers will be inspected to assure sealing surfaces and components have not deteriorated. Since valve internals are designed for a 40-year lifetime, an inspection program which cycles through all valves in one-eighth of the design lifetime is extremely conservative.
Experience has shown.that a weekly measurement of the oxygen concentration in the primary containment assures adequate surveillance of the primary econtainment atmosphere.
B. and C.
Standby Gas Treatment System and Secondary Containment System Initiating reactor building isolation and operation of the standby gas treatment system to maintain at least a 0.15 inch of water vacuum within the secondary containment provides an adequate test of the operation of the reactor building isolation valves, leakage tightness of the reactor building, and performance of the standby gas treatment system. Functionally testing of initiating sensors and associated trip channels demonstrates the capability for automatic actuation.
Periodic testing gives sufficient confidence of reactor building integrity and standby gas treatment system performance capability.
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