ML16341B272

Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 7, Table 7.2-2, Interlock Circuits

ML16341B272
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: ML16341B272 (4)

Text

I I N N D D I I A A N N A A A A N N D D M M I I C C H H I I G G A A N N P P O O W W E E R R D D.. C C.. C C O O O O K K N N U U C C L L E E A A R R P P L L A A N N T T U U P P D D A A T T E E D D F F I I N N A A L L S S A A F F E E T T Y Y A A N N A A L L Y Y S S I I S S R R E E P P O O R R T T Revision: 21.2Table: 7.2-2 Page: 1 of 4 INTERLOCK CIRCUITS Note: Where applicable setpoints can be found in the T echnical Specifications for each unit, or in appropriate engineering documents. Designation Derivation Function P-4 1/2 Reactor trip breakers and its corresponding bypass breaker open Actuates main turbine trip.

Initiates feedwater isolation on T avg below setpoint. Actuates main feedwater pump trip.

Blocks re-actuation of safety injection after manual reset of safety injection actuation signal.

P-6 1/2 Intermediate range neutron flux above setpoint Allows manual block of source range reactor trip.

P-6 Reset 2/2 Intermediate range neutron flux below reset point Prevents or defeats the manual block of source range reactor trip.

P-7 Enabled by P-10 or P 2/4 Power range neutron flux channels above setpoint (P-10) or 1/2 turbine first stage pressure above setpoint (P-13) Permits reactor trip when any of the following conditions are sensed:

Greater than one loop reactor coolant flow low Greater than one reactor coolant pump breaker open Reactor coolant pump bus undervoltage or underfrequency Pressurizer low pressure Pressurizer high level P-7 Reset P-10 reset and P-13 reset Prevents or defeats th e reactor trip when any of the following conditions are sensed: Greater than one loop reactor coolant flow low Greater than one reactor coolant pump breaker open Reactor coolant pump bus undervoltage or underfrequency Pressurizer low pressure Pressurizer high level P-8 2/4 power range channels above setpoint Prevents or defeats the automatic block of reactor trip on low coolant flow condition in a single loop.

I I N N D D I I A A N N A A A A N N D D M M I I C C H H I I G G A A N N P P O O W W E E R R D D.. C C.. C C O O O O K K N N U U C C L L E E A A R R P P L L A A N N T T U U P P D D A A T T E E D D F F I I N N A A L L S S A A F F E E T T Y Y A A N N A A L L Y Y S S I I S S R R E E P P O O R R T T Revision: 21.2Table: 7.2-2 Page: 2 of 4 INTERLOCK CIRCUITS Note: Where applicable setpoints can be found in the T echnical Specifications for each unit, or in appropriate engineering documents. Designation Derivation Function Permits reactor trip wh en the Turbine Trip condition is sensed. P-8 Reset 3/4 NIS power range channels below reset point Permits the automatic block of reactor trip on low flow in a single loop.

Prevents or defeats th e reactor trip when the Turbine Trip condition is sensed.

P-10 2/4 power range neutron flux channels above setpoint Inputs to P-7 permissive.

Permits the manual block of reactor trip on: Intermediate range high neutron flux level.

Power range channel low setpoint high neutron flux level.

Permits manual block of intermediate range channel rod stop.

Permits automatic block of source range channel trip. P-10 Reset 3/4 power range channels below reset point Prevents or defeats the manual block of reactor trip on:

Intermediate range channel high neutron flux level.

Power range channel low setpoint high neutron flux level.

Prevents or defeats the manual block of intermediate range channel rod stop.

P-11 2/3 pressurizer pressure below setpoint Permits manual block of safety injection actuation on low pressurizer pressure. P-11 Reset 2/3 pressurizer pressure above reset point Prevents or defeats manual block of safety injection actuation on low

pressurizer pressure.

P-12 2/4 T avg channels below setpoint Permits manual block of safety injection on low steam line pressure.

Permits or causes steam line isolation on high steam line flow.

Blocks condenser steam dump. P-12 Reset 3/4 T avg channels above reset point Prevents or defeats manual block of safety injection on low steam line

pressure.

Prevents or defeats steam line isolation on high steam flow.

I I N N D D I I A A N N A A A A N N D D M M I I C C H H I I G G A A N N P P O O W W E E R R D D.. C C.. C C O O O O K K N N U U C C L L E E A A R R P P L L A A N N T T U U P P D D A A T T E E D D F F I I N N A A L L S S A A F F E E T T Y Y A A N N A A L L Y Y S S I I S S R R E E P P O O R R T T Revision: 21.2Table: 7.2-2 Page: 3 of 4 INTERLOCK CIRCUITS Note: Where applicable setpoints can be found in the T echnical Specifications for each unit, or in appropriate engineering documents. Designation Derivation Function Permits condenser steam dump.

P-13 1/2 turbine first stage pressure channel above setpoint Inputs to P-7. P-13 Reset 2/2 turbine first stage pressure below reset point Inputs to P-7.

P-14 2/3 hi-hi steam generator level (any steam generator) greater than or equal to setpoint Permits the initiation of:

Feedwater isolation Main feedwater pump trip.

Main turbine trip. P-14 Reset 2/3 hi-hi steam generator level (any steam generator) less than or equal to reset point Prevents or defeats initiation of:

Feedwater isolation.

Main feedwater pump trip.

Min turbine trip. C-1 1/2 Intermediate range neutron flux above setpoint Blocks automatic and manual control rod withdrawal.

May be manually blocked above P-10.

Automatically unblocked below P-10. C-2 1/4 Power range neutron flux above setpoint Blocks automatic and manual control rod withdrawal. C-3 2/4 Overtemperature Delta T above setpoint Blocks automatic and manual control rod withdrawal.

Actuates turbine runback via load reference. C-4 2/4 overpower Delta T channels above setpoint Blocks automatic and manual rod withdrawal and initiates turbine

runback C-5 Turbine impulse pressure equivalent below setpoint Blocks automatic rod withdrawal C-7A, C-B 1/1 Time Derivative (absolute value) of turbine First Stage pressure (decrease only) above setpoint Makes steam dump valves available for either tripping or modulation. C-8 2/3 Turbine Emergency Trip Fluid pressure below setpoint or 4/4 stop valves closed Blocks steam dump control via load rejection T avg controller.

I I N N D D I I A A N N A A A A N N D D M M I I C C H H I I G G A A N N P P O O W W E E R R D D.. C C.. C C O O O O K K N N U U C C L L E E A A R R P P L L A A N N T T U U P P D D A A T T E E D D F F I I N N A A L L S S A A F F E E T T Y Y A A N N A A L L Y Y S S I I S S R R E E P P O O R R T T Revision: 21.2Table: 7.2-2 Page: 4 of 4 INTERLOCK CIRCUITS Note: Where applicable setpoints can be found in the T echnical Specifications for each unit, or in appropriate engineering documents. Designation Derivation Function 2/3 Turbine emergency trip fluid pressure above setpoint or 4/4 stop valves not closed Blocks steam dump control via turbine trip T avg controller. C-9 Any condenser vacuum above setpoint or All circulation water pump breakers open or Loss of CRID II Power Blocks steam dump to condenser. C-11 Control Bank D demand signal above withdrawal limit setpoint Blocks automatic control rod withdrawal. C-20 2/2 Turbine first stage pressure high Defeats the block of AMSAC.