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While performing reactor startup, the operator raises reactor power to the heating range (range B on IRMs) and observes a sharp rise in reactor level and coolant temperature, period becoming shorter and power continuing to rise.
These are indications of a:
A. positive temperature coefficient. This can occur anywhere between middle and end of cycle.
B. negative temperature coefficient. This can occur anywhere between middle and end of cycle.
C. positive temperature coefficient. This can occur anywhere between beginning and middle of cycle.
D. negative temperature coefficient. This can occur anywhere between beginning and middle of cycle.
A. positive temperature coefficient. This can occur anywhere between middle and end of cycle.
With a positive coefficient, rising temperature adds positive reactivity and makes power continue to rise at the point of adding heat. This can occur anywhere from middle to end of cycle at low temperatures due to the core being over moderated.
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Unit Two (2) is conducting a reactor startup in accordance with GP-02, Approach to Criticality and Pressurization of the Reactor. The reactor has just been declared critical the Control Operator observes that it takes 15 seconds for reactor power to rise from 20 to 40 on IRM range 4.
Based on these plant conditions, which one of the following is the desired action?
A. Immediately scram the reactor.
B. Insert control rods until a stable positive period of greater than 100 seconds is obtained.
C. Fully insert at least 10 control rods beyond the rod that the reactor achieved criticality on.
D. As reactor power increases, reposition the IRM range switches to mainatain IRM recorder indication between 15 and 50 on the 0 to 125 scale.
B. Insert control rods until a stable positive period of greater than 100 seconds is obtained.
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Reactor pressurization is in progress per 0GP-02, Approach to Criticality and Pressurization of the Reactor.
The feedwater system is aligned as follows:
RFP A is in Service
RFP A Recirc Valve (FW-FV-V46) is open
Reactor Pressure is 400 psig
SULCV (FW-LV-3269) in Auto
Feedwater Heater 4A and 48 inlet isolation valves are closed
FW-FV-177, Feedwater Recirc Valve, throttled open with 0.5 Mlbm/hr.
Which one of the following choices predicts the automatic response of the SULCV and also completes the caution statement in accordance with GP-02?
If the operator throttles FW-FV-177 in the open direction, the SULCV will automatically throttle in the _________ direction. Opening the FW-FV-177 more than the _______ may cause feedwater line depressurization and loss of flow to the reactor vessel.
A. open;
RFP A Recirc Valve
B. closed;
RFP A Recirc Valve
C. open;
SULCV
D. closed;
SULCV
Throttling open the FW-V177 will divert flow from the reactor back to the condenser. This will require the SULCV to open further to provide the needed flow to maintain set reactor water level. A Caution in GP-02 warns against opening FW-V117 more than the SULCV. This may cause depressurization of the feedwater line and loss of flow to the reactor vessel.
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Unit Two is in Mode 2 and preparing to place the Mode Switch to Run per GP-03.
Reactor Coolant System specific activity is 0.4 ~Ci/gm.
Can Unit Two place the Mode Switch to Run?
A. No, this is prohibited by LCO 3.0.4.
B. Yes, this is allowed by LCO 3.04.a.
C. Yes, this is allowed by LCO 3.04.b.
D. Yes, this is allowed by LCO 3.0.4.c.
D. Yes, this is allowed by LCO 3.0.4.c.
Specific activity of 0.2 to 4.0 requires entry into LCO 3.4.6, Condition A. This condition specifically allows mode change per LCO 3.0.4.c. If activity were >4, Condition B does not have the allowance for LCO 3.0A.c, and would prohibit mode change without a risk assessment per LCO 3.0A.b since operation in Mode 1 is limited.
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What the purpose for performing Alternate Power Verification per Attachment 1 of 0GP-03?
A. Allow calibration of the LPRMs.
B. Increase balance of plant efficiency.
C. Verify proper indication of core thermal limits.
D. Verify actual core power is not more than indicated core power.
D. Verify actual core power is not more than indicated core power.
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Unit Two (2) is conducting a reactor startup. Using 0GP-03 Attachment 1, “Verification of Reactor Power Using Alternate Indications,” the reactor operator has collected the following data?
APRMs 18% Power
Bypass Valve 22% Equivalent Power
Steam Flow 21% Equivalent Power
LPRM 22% Power
Heat Balance 15% Power
Based on the above data what is the recommendation regarding the power ascension?
A. continue without APRM adjustments.
B. continue only if APRMs are adjusted to at least 21% power.
C. continue only if APRMs are adjusted to at least 22% power.
D. not continue, contact Reactor Engineering to account for dirrerences in agreement.
B. continue only if APRMs are adjusted to at least 21% power.
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According to the Brunswick General Plant Operating Procedures (GPs), the IRMs are withdrawn from the core:
A. Immediately after IRM/APRM overlap is verified.
B. After the MODE switch is placed in RUN.
C. Two at a time to provide continuous period monitoring during detector withdrawl.
D. As required to keep indicated power on each IRM between 15 and 50 on the 0-125 scale.
B. After the MODE switch is placed in RUN.
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Unit One (1) is performing a shutdown per GP-05. The following conditions existed at the times listed:
..............1400 Hours - 1430 Hours - 1500 Hours
Reactor Pressure: 5 psig - 0 psig - 0 psig
Recirc Loop A Temp: 225°F - 212°F - 201°F
Recirc Loop B Temp: 200°F - 188°F - 180°F
Rx Vessel Shell Temp: 237°F - 226°F - 215°F
Rx Vessel Flange Temp: 244°F - 232°F - 224°F
Bottom Head Drain Temp: 202°F - 190°F - 183°F
Recirc Loop A Status: in service - in service - in service
Recirc Loop B Status: shutdown - shutdown - shutdown
RWCU System Status: in service - in service - in service
Shutdown Cooling: shutdown - shutdown - shutdown
Given these plant conditions, calculate dooldown rate.
A. 23 °F/hr
B. 24 °F/hr
C. 27°F/hr
D. 30 °F/hr
C. 27°F/hr
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Unit One has shutdown for an outage and is in the process of transitioning from Cold Shutdown to Refueling. Actions are in progress to realign level indicating loops B21-L1-R605NB from transmitters B21·LT·N027NB to B21-LT-7468NB in preparation for cavity flood up. Why are level transmitters N027NB taken out of service for refueling operation?
A. N027NB variable leg piping is to be disconnected.
B. N027NB are calibrated for post accident conditions.
C. N027NB reference leg piping is to be disconnected.
D. N027NB are calibrated for normal operating conditions.
C. N027NB reference leg piping is to be disconnected.
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