ML20055B679

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Proposed Tech Spec Changes Requiring Chlorine Detector Operability Similar to ANO-2,in Response to NUREG-0737,Item III.D.3.4, Control Room Habitability
ML20055B679
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 07/14/1982
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20055B678 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.3.4, TASK-TM NUDOCS 8207220621
Download: ML20055B679 (5)
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Text

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3.5.1.7 The Decay Heat Removal System isolation valve closure setpoints shall be equal to or less than 340 psig for one valve and equal to or less than 400 psig for the second valve in the suction line. The relief valve setting for the DHR system shall be equal to or less than 450 psig.

3.5.1.8 The degraded voltage monitoring relay settings shall be as follows:

a. The 4.16 KV emergency bus undervoltage relay setpoints shall be > 3115 VAC but < 3177 VAC.
b. The 460 V. emergency bus undervoltage relay setpoints shall be > 423 VAC but < 431 VAC with a time delay setpoint of 8 seconds il second.
3. 5.1. 9 The following Reactor Trip circuitry shall be operable as indicated:
1. Reactor trip upon loss of Main Feedwater shall be operable (as determined by Specification 4.1.a, items 2 and 36 of Table 4.1-2) at greater than 5% reactor power. (May be bypassed up to 10% reactor power.)
2. Reactor trip upon Turbine Trip shall be operable (as determined by Specification 4.1.a items 2 and 42) at greater than 5% reactor power. (May be bypassed up to 20%

reactor power.)

3. If the requirements of Specifications 3.5.1.9.1 or 3.5.1.9.2 cannot be met, restore the inoperable trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or bring the plant to a hot shutdown condition.

3.5.1.10 The control room ventilatin chlorine detection system instrumentation shall be operable & capable of actuating control room isolation and filtration systems, with alarm / trip setpoints adjusted to actuate at a chlorine concentration of <_

Sppm.

-4 a-8207220621 820714 PDR ADOCK 05000313 P PDR

Table 3.5.1-1 (Cont'd)

Notes Cont'd

13. Channels may be bypassed for not greater than 30 seconds during reactor coolant pump starts. If the automatic bypass circuit or its alarm circuit is inoperable, the undervoltage protection shall be restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, otherwise, Note 14 applies.
14. With the number of channels less than required, restore the inoperable channels to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
15. This trip function may be bypassed at up to 10% reactor power.
16. This trip function may be bypassed at up to 20% reactor power.
17. With the number of channels less than required, 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

, channels to operable status, or initiate and maintain operation of the control room

, g; emergency ventilation system in the recirculation mode of operation.

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Channel Descriotion Check Test Calibrate Remarks

47. EFW Actuation Control Logic NA M R
48. EFW Flow Indication R NA R

! 49. RCS-subcooling margin D NA R monitor

50. Electrom= tic relief valve D NA R flow mon- .r
51. Electromatic relief block D NA R valve position indicator
52. Pressurizer safety valve D NA R flow monitor

, 53. Pressurizer water level D NA R Rj indicator er

54. Control Room Chlorine D M R Detector Note: S-Each Shift T/W-Twice per Week R-Once every 18 months W-Weekly Q-Quarterly PC-Prior to going Critical if not M-Monthly P-Prior to each startup' Done within previous 31 days Not done previous week D-Daily B/M-Every 2 Months NA-Not: applicable

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The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during ,

and following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

The OPERABILITY of the chlorine detection system ensures that sufficient capability is available to promptly detect and intiate protective action in the event of an accidental chlorine release. This capability is required to protect control room personnel and is consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators against an Accidental Chlorine Release," February 1975.

REFERENCE FSAR, Section 7.1 ,

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7 Table 3.5.1-1 (Cont'd)

OTHER SAFETY RELATED SYSTEMS 1 2 3 4 5 No of Operation Action channels Min. Min if conditions of No. of for sys- operable degree of column 3 4. 4 Functional Unit Channels tem trip channels redundancy cannot be met

2. Steam line break instrumenta-ion control system (SLBIC).

(a) SLBIC Control & Logic Channels 2 1 2 1 Notes 9, 5

3. Pressurizer level channels 3 N/A 2 1 Note 10
4. Emergency reedwater flow channels 2/S.G. N/A 1 0 Note 10 e 5. RCS subcooling margin (j monitors 2 N/A 1 0 Note 10 8
6. Electromatic relief valve flow monitor 2 N/A 1 0 Note 11
7. Electromatic relief block valve flow monitors 1 N/A 1 0 Note 12
8. Pressurizer code safety valve flow monitors 2/ valve N/A 1/ valve 0 Note 10
9. Degraded Voltage Monitoring
a. 4.16 KV Emergency Bus Undervoltage 2/ Bus 1/ Bus 2/ Bus 0 Note 14
b. 460 V Emergency Bus Undervoltage *1/ Bus 1/ Bus 1/ Bus 0 Notes 13, 14
10. Chlorine Detection Systems 2 1 1 0 Note 17
  • Two undervoltage relays per bus are used with a coincident trip logic (2-out-of-2)

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