ML20076F016

Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for RCS Leakage Monitoring Sys

ML20076F016
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	05/26/1983
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20076F003	List: ML20076F000 ML20076F016
References
NUDOCS 8306010383
Download: ML20076F016 (4)

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3.6 LIMITING CONDITIONS FOR OPERATION 4.6 SURVEILLANCE REQUIREMENTS C. COOLANT LEAKAGE C. COOLANT LEAKAGE

1. During power operation, the reactor coolant Reactor coolant system leakage shall be system leakage into the primary containment demonstrated to be within the limits of 2@@ shall be limited to: Specifications 3.6.C.1 and 2 by checking and 20 logging the leakage collected in the primary Do a. No known pressure boundary leakage; containment floor and equipment sumps at least

@E3 once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. In addition, the primary gyj b. 5 gpm unidentified leakage when averaged containment atmosphere activity shall be checked u over a predetermined 24-hour period; and logged at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, usCD Cyj c. 20 gpm identified leakage when averaged om over a predetermined 24-hour period.

mun 04th 2" 2. Any time the reactor is in the run mode, reactor coolant system leakage into the primary containment from unidentified sources shall be limited to:

a. 2 gpm increase in unidentified leakage within a predetermined 24-hour period.

( See Note 1. )

3. If the requirements of specification 3.6.C.1 cannot be met, initiate action as follows:

a. With any known pressure boundary leakage, be in at least hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

o Note 1: During the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the run mode following startup, the limits of Specification 3.6.C.2 may be waived provided the requirements of Specification 3.6.C.1 are met. 108

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b. With any reactor coolant system leakage greater than any one of the limits specified in 3.6.C.1 b or c, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4. If the requirements _of Specification 3.6.C.2 cannot be met, initiate action as follows:

a. With any increase in unidentified leakage of greater than or equal to 2 gpm within a predetermined 24-hour period, identify the source of leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least cold shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

5. Both the sump and air sampling systems shall be operable during power operation. From and after the date that one of these systems is made or found inoperable for any reason, reactor operation is permissible only during the succeeding 7 days.

6. If the requirements of Specification 3.6.C.5 cannot be met, an orderly shutdown shall be initiated and the reactor brought to a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. SAFETY AND RELIEF VALVES D. SAFETY AND RELIEF VALVES

1. During reactor power operating conditions and 1. A minimum of 1/2 of all safety valves shall whenever the reactor coolant pressure is be bench-checked or replaced with a greater than 120 psig and temperature greater bench-checked valve each refueling outage.

than 3500F, both safety valves shall be Both valves shall be checked or replaced operable. The relief valves shall be every two refueling outages. The lift point operable, except that if one relief valve is of the safety valves shall be set as inoperable, reactor power shall be specified in Specification 2.2.B.

immediately reduced to and maintained at or below 95% of rated power. 108a

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2. If Specification 3.6.D.1 is not met, initiate 2. A minimum of 1/2 of all relief valves shall

! an orderly shutdown and the reactor coolant be bench-checked or replaced with a

! pressure shall be below 120 psig and 3500F bench-checked valve each refueling outage.

l within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. All four valves shall be checked or replaced

, every two refueling outages. The set

! pressures shall be as specified in

! Specification 2.2.B.

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3.6 and 4.6 (Continued) ,, ,

greater than the limit specified for unidentified leakage, the probability is .snall that imperf ections or cracks associated with such leakage would grow rapidly. Leakage less than the limit specified can be detected within a few hours utilizing the available leakage detection systems. If the limit is exceeded and the origin cannot be determined in a reasonably short time the plant should be shut down to allow further investigation and corrective action. The limits are consistent with those provided in NUREC-0313, Revision 1.

The removal capacity f rom the drywell floor drain sump and the equipment drain sump is 50 gpm each. Removal of 50 gpm f rom either of these sumps can be accomplished with considerable margin.

D. Safety and Relief Valves Parametric evaluations have shown that only three of the four relief valves are required to provide a pressure margin grearnr than the recommended 25 psi below the safety valve actuation settings as well as a MCFR greater than 1.06 f c the limiting overpressure transient below 98% power. Consequently, 95% power has been selected as a limiting power level for three valve operation. For the purposes of this limiting condition, a relief valve that is unable to actuate within tolerance of its set pressure is considered to be as inoperable as a mechanically malfunctioning valve.

Experience in safety valve operation shows that a testing of 50% of the safety valves per refueling outage is

' adequate to detect failure or deterioration. - The~ tolerance value is specified in Section III of the ASME Boiler and Pressure Vessel Code as + 1% of design pressure. An analysis has been performed which shows that with all safety valves set 1% higher the reactor coolant pressure safety limit of 1375 psig is not exceeded.

E. Structural Integrity A pre-service inspection of the components listed in Table 4.2-4 of the FSAR will be conducted af ter site erection to assure freedom from defects greater than code allowance; in addition, this will serve as a reference base for further inspections. Prior to operation, the reactor primary system will be free of gross defects. In addition, the facility has been designed such that gross defects should not occur throughout plant lif e. The inspection program given in Table 4.2-4 was based on the proposed ASME code for in-service inspection which was followed except where accessibility for inspection was not provided. This inspection provides further assurance that gross defects are not occurring after the system is in service. This inspection will reveal problem areas should they occur before a leak develops.

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