ML20066E151

Proposed Tech Specs,Consisting of Proposed Change 162 Re Toxic Gas Monitoring Sys

ML20066E151
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	01/15/1991
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20066E147	List: ML20066E146 ML20066E151 ML20066E157
References
NUDOCS 9101180103
Download: ML20066E151 (5)

Text

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ATTACl! MENT 1 Proposed Change No. 162 to Vermont Yankee Technical Specifications-i i

Pages Deleted Pages Inserted 34a 34a <

49c 49c 60b 60b 66 66 l

ATTAcilMENT 2 Analysis to Support Removal of the Vermont Yankee Toxic Cas Monitoring Syst g (YAEC-1759. Revision 1)-

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9101100103 910115

-PDR ADOCK 05000271 P POR

VYNPS 3.2 LIMITING CONDITIONS FOR OPERATION 4.2 SURVEILLANCE REQUIREMENTS 3.2 Protective Instrument Systems Specification 4.2 PROTECTIVE INSTRUMENT SYSTEMS (cont'd) .!

Specification (cont'd)

I. Recirculation Pump Trip Instrumentation I. Recirculation Fusp Trip Instrumentation During reactor power operation, the The Recirculation Pump Trip Instrumentation Recirculation' Pump Trip Instrumentation shall shall be functionally tested and calibrated be operative in accordance with Table 3.2.1. in accordance with Table 4.2.1.

J. Deleted J. Deleted i K. Degraded Grid Protective System K. Degraded Grid Protective System During reactor power operation,'the emergency The emergency bus undervoltage bus undervoltage instrumentation shall be instrumentation shall be functionally tested-operativa in accordance with Table 3.2.8. and calibrated in accordance with Table 4.2.8.'

L. Reactor Core Isolation Cooling System- L. Reacter Core Isolation Cooling System Actuation Actuation When the Reactor Core Isolation Cooling Instrumentation and Logic Systems shall be System is required in accordance with functionally tested and calibrated as Specification 3.5.G, the instrumentation indicated in Table 4.2.9.

which initiates actuation'of this system shall be operable in accordance with Table 3.2.9.

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Araendment No. 58, 96, 98, M / 34a-

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VYNPS 3.2 (Continued) standby gas treatment system operation so that none of the activity released during the refueling accident leave the Reactor Building via the normal ventilation stack but that all activity is processed by the standby gas treatment system. Trip settings for the monitors in the ventilation duct are based upon initiation of the normal ventilation isolation and standby gas treatment system operation at a radiation level equivalent to the e ximum site boundary dose rate of 500 mrem / year as given in Specification 3.8.E.1.a. The monitoring system in the plant stack represents a backup to this system to limit gross radioactivity releases to the environs.

The purpose of isolating the mechanical vacuum pun.p line is to limit release of radioactivity from the main condenser. During an accident, fission products would be transported from the reactor through the main steam line to the main condenser. The fission prodcct radioactivity would be sensed by the main steam line radiation anonitors which initiate isolation.

Post-accident instrumentation parameters for Containment Pressure, Torus Water Level, Containment Hydrogen / Oxygen Monitor, and Containment High-Range Radiation Monitor, are redundant, environmentally and .

seismically qualified instruments provided to enhance the operators' ability to follow the course of an event.

The purpose.of each of these instruments is to provide detection and measurement capability during and following an accident as required by NUREG-0737 by ensuring coatinuous on-scale indication of the following: containment -

pressure in the O to 275 psia range; torus water level in the O to 25 foot range (i.e., the bottom to 5 feet above the normal water level of the torus pool); containment hydrogen / oxygen concentrations (0 to 30% hydrogen 7

and 0 to 25% oxygen); and containment radiation in the 1 R/hr to 10 R/hr gamma.

i The Degraded Grid Protective System has been installed to assure that safety-related electrical equipment will not be subjected to sustained degraded voltage. This system incorporates voltage relays on 4160 Volt Emergancy Buses 3 an4 ' 4 which are set to actuate at the minimum voltage required to prevent damage of safety-related equipment.

If Degraded Grid conditions exist for 10 seconds, either relay will actuate an als.rm to alert operators of this condition. Based upon an assessment of these conditions the operator may choose to manually disconnect the off-site power. In addition, if an ESF signal is initiated in conjunction with low voltage below the relay setpoint for 10 seconds, the off-site power will be automatically disconnected.

4 Amendment No. 96, 98, 103, //7 66 c --

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