The two seperate signals providing an OPEN signal to the Accumulator Discharge Valves.
What is when the RCS is > 1970 psig (P-11) and upon an SIS?
100
OSP-SE-00004 explains the expected NIS gain adjustments for a 20% power change.
What is 2-4%?
100
The Modes of applicability for OTO-BB-00010.
What is Modes 3 with Accumulators Isolated or Mode 4?
100
Reasons described in the Basis Document of E-1 for the RCP Trip Criteria during a Large Break LOCA and for a Small Break LOCA.
What is to protect the RCPs from damage during a LBLOCA and to maintain Core Cooling and RCS Inventory during a SBLOCA?
100
The C/D Rate Limit directed in FR-C.1 when ECCS Equipment can not be started.
What is MAXIMUM Rate?
200
The Hot Legs that the 'A' SI Pump inject to upon Hot Leg Recirc operation.
What is the Loop 2 and Loop 3 Hot Legs?
200
Succession of command of the Senior Director, Nuclear Operations during normal working hours per APA-ZZ-00001.
Who is the Director, Nuclear Operations or the Duty Manager?
200
OTO-GN-00002 CRDM Temperature Limit and the FSAR CRDM Temperature Limit.
What is 165 deg F and 172 deg F?
200
Procedure referenced for Cold Leg Recirc upon entry of ECA-0.2 when "RWST Lo Lo 1" annunciator is recieved.
What is ECA-0.2?
200
Ctmt Hydrogen Concentration described in FR-C.1 for starting a Hydrogen Recombiner.
What is 0.5% - 4.0%?
300
The requirements to OPEN EJHV8804 (A or B).
What is to CLOSE (BBPV)8701 or (EJHV)8702 AND (EMHV)8814s or (EMHV)8813?
300
APA-ZZ-00310 describes the time when WPA Restraints are primarily used AND the minimum equipment voltage requiring the use of Switching Orders.
What is when an Alternate Energy Source is being applied AND > or = 13.8 kV?
300
OTO-BB-00010 instructs to check RCS pressure is greater than this value for this reason PRIOR TO actuating CPIS.
What is > 360 psig in order to protect the RCP seals from damage?
300
ECA-0.0 step 17 direction provided during the cooldown of the RCS by depressurizing SGs if all SG levels are < 7% (3 things).
What is to stop the depressurization and maintain MAXIMUM feed flow until > 7% [25%] in at least one SG?
300
Caution in FR-C.1 directing this limited number of hours RHR should be allowed to run without CCW supplied to the RHR Heat Exchangers.
What is 2 hours?
400
List of the Tech Spec 3.0.3. Valves and their positions for the RHR System.
What is EJHV8809s (A+B) + EJHV8716s (A+B) + EJHV8840 + BNV8717?
400
The systems and the modes of those systems which are prohibited from using T.S. 3.0.4.b. per ODP-ZZ-00014.
What is COMS (Mode 4), ECCS CCP Subsystem (Mode 4), AFW System (Mode 1), Emergency Diesel Generators (Modes 1-1)?
400
OTO-ZZ-00008 Step 14 directs going to this procedure if Plant Parameters can NOT be maintained, the leak is isolable and Reator Power is < 50%.
What is OTO-AC-00001?
400
ES-1.1 order of securing ECCS Equipment.
What is to Stop all but one CCP, (isolate BIH and align Normal Charging), Stop BOTH SI Pumps, and Stop Both RHR Pumps?
400
FR-C.1 step 17 criteria for transition to E-1 step 11 (3 things).
What is CETC's < 1200 deg F, 2 T-Hots < 350 deg F, and RVLIS > 65%?
500
The signals (3) that will auto-close BGPCV115.
What is Waste Gas Suction of -0.5 psig, and Hydrogen Concentration at the Waste Gas Analyzer of > or = 9%, and VCT Pressure < or = 13 psig?
500
The times when Boron Dilution Flux Multiplication Signals may be Blocked in accordance with OTG-ZZ-00001A.
What is Subcritical Physics Testing, Mode 2
500
The attachment (or attachment title) directed to for an Aircraft Threat in OTO-SK-00002 for an Ultralight Aircraft headed is for the Reactor Building.
What is Attachment C of OTO-SK-00002 (Informational Threat)?
500
While reducing ECCS Injection flow during ES-1.2, RNO action is allowed to start an RHR Pump if these certain conditions are satisfied and the reason for these conditions to be met.
What is Hot Leg Temperature < 370 degrees F which is the saturation temperature corresponding to the RCS Pressure allowing the RHR Pump to pump forward and inject into the RCS?
500
This Procedure is mentioned in a note at the beginning of FR-C.3, Response to Saturated Core Cooling, which prevents the performance of FR-C.3 if This Procedure is in effect.
What is ECA-3.2 (SGTR with a Loss of Reactor Coolant)?