ML16343A190

7 to Updated Final Safety Analysis Report, Chapter 14, Table 14.1-2 - Reactor Trip Points and Time Delays to Trip Assumed in Safety Analysis

ML16343A190
Person / Time
Site:	Cook
Issue date:	10/24/2016
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML16336A263	List: AEP-NRC-2016-42, Fire Protection Program Change Summary ML16336A225 ML16336A228 ML16336A238 ML16336A291 ML16336A292 ML16336A294 ML16336A295 ML16336A297 ML16336A298 ML16336A299 ML16336A300 ML16336A301 ML16336A302 ML16336A303 ML16336A304 ML16336A305 ML16336A306 ML16336A308 ML16336A309 ML16336A310 ML16336A311 ML16336A312 ML16336A313 ML16336A314 ML16336A315 ML16336A316 ML16336A317 ML16336A318 ML16336A319 ML16336A320 ML16336A322 ML16336A323 ML16336A324 ML16336A325 ML16336A327 ML16336A328 ML16336A329 ML16336A330 ML16336A332 ML16336A333 ML16336A334 ML16336A336 ML16336A337 ML16336A338 ML16336A339 ML16336A340 ML16336A341 ML16336A342 ML16336A345 ... further results
References
AEP-NRC-2016-42
Download: ML16343A190 (1)

Text

IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 22.1 Table:

14.1-2 Page:

1 of 1 UNIT 1 REACTOR TRIP POINTS AND TIME DELAYS TO TRIP ASSUMED IN SAFETY ANALYSES 1 REACTOR TRIP FUNCTION LIMITING REACTOR TRIP POINT ASSUMED IN ANALYSIS TIME DELAY (sec)

Power range high neutron flux, high setting 118 percent 0.5 Power range high neutron flux, low setting 35 percent 0.5 Overtemperature T Variable, see Figure 14.1-1, -2, -3 & -4 8.0 2 Overpower T Variable, see Figure 14.1-1, -2, -3 & -4 8.0 3 High pressurizer pressure 2420 psig 2.0 Low pressurizer pressure 1825 psig 4 2.0 High pressurizer water level 100% NRS 2.0 Low reactor coolant flow (from loop flow detectors) 87 percent loop flow 1.0 Undervoltage trip 5

1.5 Low-low steam generator level 0.0 percent of narrow range level span 2.0 High-High steam generator level 6:

82 percent of narrow range level span

- Turbine Trip 2.5

- Feedwater Isolation 11.0 1 The control rod scram time to dashpot is 2.4 seconds.

2 Total time delay (including RTD time response, and trip circuit, channel electronics delay) from the time the temperature difference in the coolant loops exceeds the trip setpoint until the rods are free to fall.

The time delay assumed in the analysis supports the response time of the RTD time response, trip circuit delays, and channel electronics delay presented in the UFSAR Table 14.1-2 (Unit 1) or Table 7.2-6 (Unit 2). An evaluation has been performed (Reference 11) that demonstrates that the analyses remains bounding, given that the total 8.0 second time delay in the above table is satisfied.

3 Overpower T reactor trip was assumed in the steamline break mass/energy release outside containment calculations.

4 A value of 1845 psig is used in LOCA analyses.

5 No explicit value assumed in the analysis. Undervoltage trip setpoint assumed reached at initiation of analysis.

6 Time delay between High-High steam generator level and Turbine Trip is 2.5 seconds. The Turbine Trip subsequently causes a Reactor Trip.