ML20004D043

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Proposed Changes to Tech Specs 3.5.1.7,3.5.1.8 & Table 3.5.1-1 Re Degraded Grid Voltage & Anticipatory Reactor Trip Sys
ML20004D043
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 05/29/1981
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20004D042 List:
References
NUDOCS 8106080247
Download: ML20004D043 (5)
v • d • e


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,O 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.

3.6.1.8 The degraded voltage monitoring relay settings shall be as

. follows
a. The 4.16 KV emergency bus undervoltage relay setpoints shall be > 3115 VAC out < 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 +1 second.

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L Table 3.5.1-1 (Cont'd) i i REACTOR PROTECTION SYSTEM (Cont'd) 1 2 3 4 5 l

l No. of Operator action channels Min. Min. if conditions of No. of for sys- operable degree of column 3 or 4 '

Functional Unit channels tem trip channels redundancy cannot be met j 11. Reactor trip upon loss of Main Feedwater 4 2 2 1 Notes 1, 15 i

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12. Reactor trip upon turbine trip 4 2 2 1 Notes 1, 16 1 i

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I Table 3. Sol-1 (Cont'd)

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

2. Steam line break instrumenta-tion 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 1 4. Emergency Feedwater flow g channels 2/S.G. N/A 1 0 Note 10 0
5. RCS subcooling margin monitors 2 N/A 1 0 Note 10
6. Electromatic relief valve flow nionitor 2 N/A 1 0 Note 11
7. Electromatic relief block valve position indicator 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/' Jus 0 Note 14
b. 400 V Emergency Bus Undervoltage *1/ Bus 1/ Bus 1/ Bus 0 Notes 13, 14
  • Two undervoltage relays per bus are used with a coincident trip lugic (2-out-of-2)

4 Table 3.5.1-1 (Cont'd)

Notes: 1. Initiate a shutdown using normal operating instructions and place the reactor in the hot shutdown condition if the requirements of columns 3 and 4 are not met within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

2. When 2 of 4. power range instrument channels are greater than 10% rages power, hot shutdown is not required.
3. When 1 of 2 intermediate range instrument channels is greater than 10-10 amps, hot shutdown is not required.
4. For channel testing, calibration, or maintenance, the minimum number of operable channels may be two and a degree of redundancy of one for a maximum of four hours, after which Note 1 applies.
5. If the requirements of Columns 3 or 4 cannot be met within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, place the reactor in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
6. The minimum number of operable channels may be reduced to 2, provided that the system is

. reduced to 1 out of 2 coincidence by tripping the remaining channel. Otherwise, Specifica-

$; tion 3.3 shall apply.

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7. These channels initiate control rod withdrawal inhibits not reactor trips at 10% rated power. Above 10% rated power, those inhibits are bypassed.
8. If any one component of a digital subsystem is inoperable, the entire digital subsystem is considered inoperable. Hence, the associated safety features are inoperable and Specifica-tion 3.3 applies.

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9. The minimum number of operable channels may be reduced to one and th minimum degree of re-dundancy to zero for a maximum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, after which Note 1 applies.
10. With the number of operable channels less than required, either restore the inoperable channel to operable status within 30 days, or be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

! 11. With the number of operable channels less than required, isolate the electromatic relief valve within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise Note 9 applies.

12. With the number of operable channels less than required, either return the indicator to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or verify the block valve closed and power removed within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the block valve cannot be verified closed within the additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, de-energize the electromatic relief valve power supply within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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Table 3.5.1-1 (Cont'd)

J Notes Cont'd.

' 13. Channels may be bypassed for not greater than 30 seconds during reactor coolant pump i 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.

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