ML20212K825

Proposed Tech Spec Tables 3.2.6. & 4.2.6,incorporating Redundant post-accident Instrumentation & Associated Limiting Condition for Operations & Surveillance Requirements,Per NUREG-0737 & Reg Guide 1.97

ML20212K825
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	01/12/1987
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20212K270	List: ML20212K266 ML20212K825
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8701290213
Download: ML20212K825 (3)

Text

.

VYNPS TABLE 3.2.6 POST-ACCIDENT INSTRUMENTATION Minimum Number of Operable Instrument Instrument Channels Parameter Type of Indication Range 2

Drywell Atmospheric Temperature Recorder #16-19-45 0-3000F (Note 1)

Recorder #TR-1-149-1 0-3000F 2

Containment Pressure (Note 1)

Meter #PI-16-19-12A 0-275 psia Meter #PI-16-19-12B 0-275_ psia 2

Torus Pressure (Note 1)

Meter #PI-16-19-36A 0-80' psia Meter #PI-16-19-36B 0-80 psia 2

Torus Water Level (Note 3)

Meter #LI-16-19-12A 0-25 ft.

Meter #LI-16-19-12B 0-25 ft.

2 Torus Water Temperature (Note 1)

Meter #16-19-48 60-1800F 2

Reactor Pressure (Note 1)

Meter #PI-2-3-56A 0-1500 psig Meter #PI-2-3-56B 0-1500 psig 2

Reactor Vessel Water Level Meter #2-3-91A

(-200)-0-(+200)"H O 2

(Note 1)

Meter #2-3-91B

(-200)-0-(+200)"H O 2

1 Control Rod Position (Notes 1,2)

Meter 0-48" RPIS 1

Neutron Monitor (Notes 1,2)

Meter 0-125% Rated Flux 2

Torus Air Temperature (Note 1)

Recorder #TR-16-19-45 0-3000F Meter #TI-16-19-41 50-3000F 2/ valve Safety / Relief Valve Position Lights (SRV 2-71-A thru D) Closed - Open From Pressure Switches (Note 4)

A:nendment No. 63, 99, 96 8701290213 870112 49 PDR ADOCK 05000271 p

PDR

VEPS TABLE 4.2.6 CALIBRATION FREQUENCIES POST-ACCIDENT INSTRUMENTATION i

Parameter Calibration Instrument Check I

Drywell Atmosphere Temperature Every 6 Months Once Each Day Containment Pressure Once/ Operating Cycle Once Each Day Tcrus Pressure Once/ Operating Cycle Once Each Day Torus Water Level Once/ Operating Cycle Once each Shift r*

l Torus Water Temperature Every 6 Months Once Each Day

)

l l

Raactor Pressure Once/ Operating Cycle Once Each Day l

R2 actor Vessel Water Level Once/ Operating Cycle Once Each Day Control Rod Position (Note 5)

Once Each Day N:utron Monitor Same as Reactor Once Each Day Protection Systems Torus Air Temperature Every 6 Months Once Each Day Sdfety/ Relief Valve Position Every Refueling Outage Once Each Day (Note 9) (a Functional Test to be performed quarterly) i Sefety Valve Position Every Refcaling Outage Once Each Day l

(Note 9) (a Functional Test to be performed quarterly)

Amendment No. 83, 96 60 l

VYNPS, l

3.2 (Continued) standby gas treatment system operation so that none.of the activity released during the refueling accident 13bve 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 maximum release rate of 0.08/E Ci/sec given in Specification 3.8.C.I.a.

The. monitoring system in the plant stack represents a backup to this system to limit gross radioactitrity releases to.the environs.

The purpose of isolating the mechanical vacuum pump 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 amin condenser.. The fission product radioactivity would be sensed by the main steam line radiation.

monitors which initiate isolation.

Post-accident instrumentation parameters for Containment Pressure, Torus Water Level, Containment Hydrogen /0xygen 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 continuous on-scale indication of the following: containment pressure in the 0 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 and 0 to 25% oxygen); and containment radiation in the 1 R/hr to 107 R/hr gamma. The Control Room Toxic Cas Monitor assures that the Control Room operators, wherever required to be in the Control Room, will be adequately protected against the effects of an accidental release of toxic gases and that the plant can be safely operated-or shut down under design basis accident conditions.

4.2 PROTECTIVE INSTRUMENTnfION The protective instrumentation systems covered by this Specification are listed in Table 4.2.

Most of there protective systems are composed of two or more independent and redundant subsystems which are combined in a dual-channel arrangement. Each of these subsystems contains an arrangement of' electrical relays which operate to initiate the required system protective action.

The relays in a subsystem are actuated by a number of means, including manually-operated switches, process-operated switches (sensors), bistable devices operated by analog sensor signals, timers, limit switches, and other relays.

In most. cases, final subsystem relay actuation is obtained by. satisfying the logic conditions established by a number of these relay contacts in a logic array. When a subsystem is actuated, the final subsystem relay (s) can operate protective equipment, such as valves and pumps, and can perform other protective actions, such as tripping the main turbine generator unit.

Amendment No. 96 66'

_