ML20150A981

Proposed Tech Spec Tables 3.5.1-1 & 4.1-1 Re Reactor Trip Breaker Design Mods

ML20150A981
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/30/1988
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20150A968	List: 1CAN068809, Application for Amend to License DPR-51,changing Tech Specs Re Reactor Trip Breaker Design Mods,Per Generic Ltrs 83-28 & 85-10.Fee Paid ML20150A981
References
NUDOCS 8807110194
Download: ML20150A981 (4)

Text

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@@ Table 3.5.1-1 (Cont'd) .

b~ E m 82 R REACTOR PROTECTION SYSTEM (Cont'd) 1 2 3 4 5 E$ 5 No. of Operator action 8@== 5 channels Min. Min. if conditions of S&g ? No. of for sys- operable degree of colur.in 3 or 4

,05o a= Functional Unit channels tem trig channels redundancy cannot be met

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11. Reactor trip upon loss of Main Feedwater 4 2 2 1 Notes 1, 15

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

13. Electronic (SCR) Trip Relay 2 2 2 0 Note 22

14. Control Rod Drive Trip Breakers A. AC Breakers 2 2 2 0 Notes 23, 24 2

• B. DC Breakers (Note 25) 2 2 2 0 Notes 23, 24 E

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Table 3.5.1-1 Cont' d) ..

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!I 22. With the number of operable Electronic (SCR) Trip relays one less than the total number of Electronic F. (SCR) Trip relays in a channel, restore the inoperable Electronic (SCR) Trip relay to operable status in at 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the SCRs associated with the inoperable Electronic (SCR) Trip relay in trip in the next P hour. With two or more Electronic (SCR) Trip relays inoperable,' place all Electronic (SCR) Trip relays:

associated with that channel in trip in the next' hour. This requirement does not apply to the Electronic Trip channels associated with Group 8 Regulating Power Supply.

23. With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP.and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. Within 'I hour:

1. Place the inoperable channel in the tripped condition, c?

2. Remove power supplied to the control rod-trip device associated with the inoperable channel.

da b. One additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing and the inoperable

" channel above may be bypassed.for up to 30 minutes in any 24-hour period when necessary to test the trip breaker associated with the logic of the channel being tested. The inoperable channel above shall not be bypassed to test the logic of a channel of the trip system associated with the inoperable channel.

24. With one of the Control Rod Drive Trip Breaker diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE stetus in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the breaker in trip in the next hour.

25. Interrupts motor power to the Safety Groups of control rods only.

Table'4.1-1 Instrument Surveillance Requirements ',,.

Channel Descriptian Check Test Calibrate- -Remarks. .

y 1. Protective Channal NA M NA g Coincidence Logic k 2. Control Rod Drive NA- M(1) NA (1) To include independent testing

1 Trip Breaker of the shunt and undervoltage 2 trip attachments.

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3. Power Range Amplifier NA NA T/W(1) (1) Heat balance calibration twice weekly under steady state operating conditions, daily under non-steady state opera-ting conditions.

4. Power Range Channel S M M(1)(2) (1) Using incore instrumentation.

M(1) (2) Axial offset. upper and lower chambers monthly and after-each startup if not done previous week.

8 5. Intermediate Range Channel S P/M NA

6. Source Range Channel S(1) P NA (1) When in service.

7. Reactor Coolant Temperature S M R Chan1el

8. High Reactor Coolant S M R Pressure Channel

9. Low Reactor Coolant S M R-Pressure Channel

10. Flux-Reactor Coolant Flow S M R Comparator

11. Reactor Coolant Pressure S M- R Temperature Comparator

12. Pump Flux Comparator S M R

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Tab 1e 4.1-l'(Cont.) .,

y Channel Description Check Test Calibrate- ' Remarks

..g i a P. ' d. SG A high range level S M R 5 high-high z

P e. SG B high range level S M R high-high

= 57. Containment High Range D M R j- . Radiation Monitors

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• 58. Containment Pressure-High -M NA R l

,- 59. Containment Water Level-Wide M_ NA R E Range

60. Low Temperature Overpressure NA R R Protection Alarm Logic

61. Electronic (SCR) Trip Relays NA M NA a

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 done within previous 31 days 0 - Daily startup if not done NA --Not Applicable-previous week B/M - Every 2 months s

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