ML17284A582

Proposed Tech Specs Modifying Section 3/4.7.3,Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation to Reflect Mods in Sys Configuration & Operation

ML17284A582
Person / Time
Site:	Columbia
Issue date:	10/24/1988
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17284A581	List: ML17284A580 ML17284A582
References
NUDOCS 8811040306
Download: ML17284A582 (9)

Text

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3.3.7.1 The radiation monitoring instrumentation channels shown in Table 3.3.7.1-1 shall be OPERABLE with their ala / p setpoints within the specified limits.

I APPLICABILITY: As shown in Table 3.3.7.1-1.

ACTION:

as With a radiation monitoring instrumentation channel ala >W set" point exceeding the value shown in Table 3.3. 7. 1-1, adjust e set-point to within the limit within S h+s or declare the channel inoperable.

b. with one or more radiation monitggng channels inoperable, take the ACTION required by Table,3.3. 1. 4

c. The provisions of Specifica s 3.0.3 and 3. 0.4 are not applicable. ~s SURVEILLANCE RE UIREMENTS 4.3. 7. 1 Each of the above required r'adiation monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL

. CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the

. conditions and 'at the frequencies shown in Table 4.3.7.1-1.

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MASHINGTON NUCLEAR - UHIT 2 3/4 3-58'TTACHMENT 1

(Page 1 of 3)

TABLE 3.3.7.1-1 RADIATION HONITORING INSTRUHENTATION HINIHUH CHANNELS ALARM/

IN STRUHENTATION 2/intake'PPLICABLE OPERABLE CONDITIONS SETPOINT ACTION

1. Hain Control Room 1,2,3,5 and " < 5000 cpm 70 Ventilation Radiation Honitor

2. Area Monitors

a. Criticality Honitors

1) New Fuel < 5 R/h(a) 71 Storage Vault

2) Spent Fuel < 20 mR/h Storage Pool TABLE NOTATIONS "Mhen the main condenser air evacuation system is, in operation.

AMith fuel in the new fuel storage vault.

8With fuel in the spent fuel storage pool.

(a) Alarm setpoint set IAM 10 CFR 70.24. a.1.

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. 6 ACTION STATEHENTS ACTION 70

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a~ Mith one of the required monitors inoperable, y4ace-the-inoperaMe-chann&~4e-h4pped-

/k -cen4WAea within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the inoperable channel to OPERABLE status within %days, or, within the nextl'x hours, initiate and maintain operation of the control room emergency filtration system in/the pressurization mode of operation.

b. Mith both of the required monitors inoperable, initiate and maintain operation of the control room emergency filtration system in the pressurization mode of operation within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 71 Mith the required monitor inoperable, assure a portable continuous monitor with the same alarm setpoint is OPERABLE in the vicinity of the installed monitor during any fuel movement. If no fuel movement is being made, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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INSTRUMENTATION CONTROLLED COPY BASES 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any .of the emergency core cooling equipment.

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.

3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION The control rod block functions are provided consistent with the require-ments of Specifications 3/4.1.4, Control Rod Program Controls,"3/4.2, Power Distribution Limits and 3/4.3.1 Reactor Protection System Instrumentation.

The trip logic is arranged so that a trip in any one of the inputs will result in a control rod block.

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.

3/4. 3. 7 MONITORING INSTRUMENTATION

. 3/4. 3.7. 1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring instrumentation ensures that; (1) the radiation levels are continually measured in the areas served by the individual channels; (2) the alarm ~u4emrbi~cHon. is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with 10 CFR Part 50, Appendix A, General Design Criteria 19, 41, 60, 61, 63, and 64.

The criticality monitor alarm setpoints were calculated using the criteria from 10 CFR 70.24.a.1 that requires detecting a dose;rate of 20 Rads per minute of combined neutron and gamma radiation at 2 meters. The alarm setpoint was determined by calculational methods using the gamma to gamma plus neutron ratios from ANSI/ANS 8.3-1979, Criticality Accident Alarm System, Appendix B and assuming a critical mass was formed from a seismic event, with a volume of 6'

'he 6' 6't a distance of 27.7 feet from the two detectors.

calculated dose rate using the methodology is 5.05 R/hr. The allowable value for the alarm setpoint was, therefore, established at 5R/hr.

3.4. 3.7. 2 SEISMEC MONITORING INSTRUMENTATION The OPERABILITY of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison of the measured response to that used 'in the design basis for the unit. This instrumentation is consistent with the recommendations of Regulatory Guide 1.12, "Instrumentation for Earthquakes," April 1974.

WASHINGTON NUCLEAR " UNIT 2 B 3/4 3"4 Amendment No. 51

~ ATTACHMENT 1 (Page 3 of 3)

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