ML051610371

Initial Submittal of the SRO Written Exam for the Quad Cities Initial Examination - May 2005

ML051610371
Person / Time
Site:	Quad Cities
Issue date:	05/31/2005
From:	Valos N NRC/RGN-III/DRS/OLB
To:	Exelon Nuclear
References
50-254/05-301, 50-265/05-301
Download: ML051610371 (25)

Text

QUESTION 001 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 295003 2.4.04 QUESTION Unit 1 is at 65% power, increasing to full load.

Unit 2 is at rated power.

Moments ago, a lightning strike in the switchyard caused transformer 345 KV BUS 4 to trip.

Assuming that all automatic actions occurred, which statement below describes the procedures that should be directed. (may not list ALL procedures required)

a. Unit 1 must enter QCGP 2-3, REACTOR SCRAM. Unit 2 must perform QCOS 0005-09, UNIT TWO ELECTRICAL DISTRIBUTION BREAKER AND VOLTAGE VERIFICATION within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b. Unit 1 must perform QOA 6100-01, LOSS OF TRANSFORMER 12(22) DURING POWER OPERATION. Unit 2 must perform QCOS 0005-09, UNIT TWO ELECTRICAL DISTRIBUTION BREAKER AND VOLTAGE VERIFICATION within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

c. Unit 1 must perform QCOS 0005-09, UNIT ONE ELECTRICAL DISTRIBUTION BREAKER AND VOLTAGE VERIFICATION within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Unit 2 must enter QCGP 2-3, REACTOR SCRAM.

d. Unit 1 must perform QCOS 0005-08, UNIT ONE ELECTRICAL DISTRIBUTION BREAKER AND VOLTAGE VERIFICATION within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Unit 2 must perform QOA 6100-01, LOSS OF TRANSFORMER 12(22) DURING POWER OPERATION.

ANSWER b.

REFERENCE QOA 912-2 B4 BUS 4 TRIP XFMR 12 TRIP QOA 6100-01 LOSS OF TRANSFORMER 12(22) DURING POWER OPERATION.

HIGHER NEW EXPLANATION: A trip of 345KV Bus 4 will cause circuit breakers 3-4 and 4-6 to open, which will cause a loss of Transformer 12. 4KV power will automatically transfer so a reactor scram will not occur or be required.

QUESTION 002 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 295004A204 QUESTION Unit 1 and Unit 2 were at rated power.

The 1/2 250VDC Battery Charger was Out Of Service for replacement.

902-8 A10, 250 V BATTERY CHARGER 2 TRIP was received.

An Operator reported that the charger feed breaker on MCC 29-2 is tripped and CANNOT be reset.

Subsequently, a LOCA occurs on Unit 2.

Regarding the loads connected to the Unit 2 250VDC battery:

(1) What action is REQUIRED to maintain voltage?

(2) The REASON for maintaining voltage, is because the Unit 2 250 VDC battery _____.

a. (1) TRIP the Emergency Hydrogen Seal Oil Pump within 30 minutes.

(2) IS REQUIRED to meet MINIMUM safety functions on Unit 2

b. (1) TRIP the Emergency Hydrogen Seal Oil Pump within 30 minutes.

(2) MAY BE required to support safe shutdown on Unit 1

c. (1) TRIP the Recirc MG Set Emergency Lube Oil Pumps within 30 minutes.

(2) MAY BE required to support safe shutdown on Unit 1

d. (1) TRIP the Recirc MG Set Emergency Lube Oil Pumps within 30 minutes.

(2) IS REQUIRED to meet MINIMUM safety functions on Unit 2 ANSWER c.

REFERENCE QCOA 6900-05 LOSS OF SAFETY RELATED 250VDC BATTERY CHARGERS CONCURRENT WITH A DESIGN BASIS ACCIDENT TS Bases B 3.8.4-2 and B3.8.4-4 MEMORY NEW EXPLANATION: Loss of the all 250VDC battery chargers concurrent with a DBA LOCA require load-shedding of MG-Set Emergency Lube Oil Pumps within 30 minutes in order to ensure that the 250VDC system is able to support safe shutdown of the opposite unit The procedure does not require the Emergency Hydrogen Seal Oil pump to be de-energized within 30 minutes.

QUESTION 003 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 295006 2.1.32 QUESTION Unit 2 is shutting down for a refueling outage. A manual reactor scram was inserted as planned, after the Main Turbine was taken off line.

Immediately following the scram, Reactor water level dropped to -3 inches before returning to 30 inches. All EXPECTED automatic actions occurred.

A log entry describing the expected plant response was NOT MADE prior to inserting the manual scram.

Which statement describes the reportability of this event?

a. A 1-hour ENS call IS REQUIRED, because NO LOG ENTRY was made prior to the event.

b. An ENS call is NOT required, because the plant performed as EXPECTED.

c. An ENS call is NOT required, because NO automatic actions occurred.

d. A 4-hour ENS call IS REQUIRED, because NO LOG ENTRY was made prior to the event.

ANSWER b.

REFERENCE QCGP 2-3 Precaution D.7 MEMORY NEW EXPLANATION: During a planned reactor scram, in the absence of any other cause for reaching a low water level trip setpoint, the Reactor low water level trip is expected and a 4 -hour ENS call is NOT required.

QUESTION 004 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 295028 2.4.06 QUESTION A Group 1 Isolation occurred with failure of the reactor to scram.

The following conditions are observed:

- RPV water level is being maintained -142 to -166 inches

- ADS Valves are being used to maintain RPV pressure 800-1000 psig

- Reactor power is 5%, LOWERING

- SBLC is injecting and tank level has dropped from 85 to 60%

- Drywell pressure is 17 psig, STEADY

- Torus pressure is 15 psig, STEADY

- Drywell temperature is 290°F, RISING

- Torus water level is 14.5 feet, RISING

- Torus water temperature is 160°F, RISING NO QGA 200 actions have been ordered.

WHICH of the following is the NEXT action to take per the QGAs?

a. Lower the RPV pressure band to stay within the Heat Capacity Limit.

b. Raise RPV level to ensure core cooling.

c. Blowdown the RPV to stay within the Pressure Suppression Pressure limit.

d. Spray the Drywell to lower Drywell temperature.

ANSWER d.

REFERENCE QGA 200, QGA 101, Strategies document, Rev 11 QGA Procedures with entry conditions blanked provided HIGHER MODIFIED EXPLANATION: - DW sprays are directed in the DW Temperature leg because Pressure

& Temp are WITHIN the Drywell Spray Initiation Limit. - Blowing down, (for PSP) without first attempting the sprays first is wrong because of direction in strategies document - Raising RWL is wrong because SBLC tank level has not dropped by 28% -LOWERING RPV pressure band is wrong because the HCL is not being threatened (torus temperature is lowering.)

QUESTION 005 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 295025A202 QUESTION In the Tech Spec Bases, the Reactor Vessel Steam Dome Pressure-High scram ________.

a. is assumed in the Reactor overpressurization analysis, to occur AFTER Reactor power reaches the APRM Fixed Neutron Flux-High scram setpoint

b. is assumed in the Reactor overpressurization analysis, to occur BEFORE Reactor power reaches the APRM Fixed Neutron Flux-High scram setpoint

c. is credited in the control rod drop accident analysis, for causing the Reactor scram.

d. is credited in the Reactor Recirc controller failure analysis, for causing the reactor scram.

ANSWER a.

REFERENCE TS B 3.3.1.1-11 B 3.3.1.1-13, B 3.3.1.1-14 MEMORY NEW EXPLANATION: The overpressurization analyses conservatively assume scram on the APRM High signal, not the Reactor Vessel Steam Dome Pressure High or MSIV closure signals.

QUESTION 006 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 295031 2.1.14 QUESTION Unit 2 was operating at 100% power when a transient occurred causing RPV water level to decrease.

Which of the following is the HIGHEST RPV water level that would REQUIRE a plant public address announcement?

a. 0"

b. -59"

c. -142"

d. -191" ANSWER c.

REFERENCE Emergency Action Level Wallboard EP-AA-1006 App. 3 Quad Cities Annex Emergency Action Level Wallboard EP-AA-1006 App. 3 Quad Cities Annex provided HIGHER NEW EXPLANATION: At -142" RPV water level there is a loss of the RCS and a potential loss of the fuel clad placing the plant in a Site Area Emergency. Entry into the E-plan requires a plant announcement.

QUESTION 007 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 600000A213 QUESTION Given:

- Unit 2 has experienced a reactor scram and a loss of off-site power.

- There is a fire 15 feet north of the 2A TBCCW pump.

- The Unit 2 Supervisor has determined that normal and emergency plant procedures are insufficient to control the event.

Using the information provided, DETERMINE which QCARP Procedure (if any) should be used?

a. 0030-02

b. 0030-03

c. 0030-04

d. NO QCARP procedure is required ANSWER c.

REFERENCE QCOA 0010-12 Attachment C QCOA 0010-12 Attachment C page 4 and 5 provided HIGHER MODIFIED EXPLANATION: The fire is near Bus 27 (north of TBCCW pumps) in area TB-II. QCARP 0030-04 is appropriate for Unit 2

QUESTION 008 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 295002 2.4.6 QUESTION Unit 2 was operating at 75% power when a leak developed on the Main Condenser Boot.

Five minutes ago, backpressure reached 6.5" Hg. and a manual Reactor scram was inserted.

Conditions are now:

- Reactor power is 15% and LOWERING slowly

- Reactor pressure is 930 psig and STEADY

- Four Turbine Bypass valves are OPEN

- Reactor Level is 0" and LOWERING

- Reactor Recirc Pumps are TRIPPED

- Drywell pressure is 1.3 psig and STEADY

- Reactor Relief Valves are ALL CLOSED

- Main Condenser Backpressure is 7.0" Hg and RISING

- MSIV's are ALL OPEN With regards to reactor pressure control, what are the INITIAL actions that should be directed?

a. DO NOT BYPASS the RPV low level isolations and control reactor pressure 800-1000 psig with Turbine Bypass valves.

b. BYPASS the RPV low level isolations and control reactor pressure 800-1000 psig with Turbine Bypass valves.

c. DO NOT BYPASS the RPV low level isolations and control reactor pressure 700-900 psig with Relief valves.

d. BYPASS the RPV low level isolations and control reactor pressure 700-900 psig with Relief valves.

ANSWER b.

REFERENCE Strategies for successful transient mitigation HIGHER BANK EXPLANATION: STRATEGIES FOR SUCCESSFUL TRANSIENT MITIGATION, Rev 11

3. Pressure Leg (ATWS) states: Direct initial band of 800 - 1000 psig.

The lower limit of 800 psig will not complicate level interpretation from the charts and will prevent unwanted cooldown. The upper limit of 1000 psig is a round number below 1040 psig. Do NOT allow the use of ADS valves to interfere with BPVs. The US is directed to bypass RPV low level isolations in the level leg and is not asked "is the condenser available",

only "are the MSIV's open."

QUESTION 009 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 295012A201 QUESTION Given the following conditions:

- It is 0900 on 5/9/05

- The unit is starting up following a refueling outage

- HPCI periodic flow-rate testing is in progress

- Reactor Power 16%

- Drywell Pressure 1.15 psig

- Torus Pressure 0.20 psig

- Torus Water Avg Temp 102°F

- Drywell Avg Temp 155°F Based upon the above conditions, what is the EARLIEST time that a Tech Spec required action must be completed?

a. 0900 on 5/9/05

b. 1000 on 5/9/05

c. 1700 on 5/9/05

d. <0900 on 5/10/05 ANSWER c.

REFERENCE TS 3.6.1.5 TS 3.6.1.5, TS 3.6.2.1, TS 3.6.2.5 provided HIGHER NEW EXPLANATION: DW temp does not meet its LCO and actions must be taken in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Misapplying TS 3.6.2.1 for torus temp the student may choose 0900 or 1000 on May 5th. DW to torus D/P does not meet its LCO and action must be taken in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

QUESTION 010 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 295017A204 QUESTION Which of the following unisolable leaks, with offsite radiation release rates approaching the General Emergency level, would require you to select QGA 500-01 as the appropriate procedure to protect the general public?

a. Fuel pool cooling discharging into Radwaste Valve-Alley

b. RWCU piping discharging into the RWCU demin room

c. HPCI steam inlet piping discharging into the Torus area

d. The Main Turbine Bypass Valves discharging into the Turbine Building ANSWER d.

REFERENCE QGA 400 QGA procedures with entry conditions blanked out provided.

MEMORY BANK EXPLANATION: The answer is the only choice in which the SOURCE of the leak meets the criteria for RPV blowdown in QGA 400. Main Steam leaking in the Turbine Building is a PRIMARY system discharging outside the primary AND secondary containment. FP cooling is not a primary system. The RWCU and HPCI leaks are INSIDE the secondary containment.

QUESTION 011 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 209001A205 QUESTION Unit 1 is at rated power. The 1B Core Spray Pump was taken OOS service earlier this shift for motor bearing repair. All appropriate Tech Spec action statements were entered.

At 15:30 the Unit NLO reports from the 2201-7 rack that the Core Spray Header High D/P switches indicate:

A - 1.3 psid B + 1.2 psid What is causing this indication and what Tech Spec actions are required?

a. The B Core Spray discharge line is broken inside the reactor. Be in MODE 3 by 0430 tomorrow.

b. The B Core Spray discharge line is broken inside the reactor. RESTORE B Core Spray loop to operable status within 7 days.

c. The A Core Spray discharge line is broken inside the reactor. RESTORE A Core Spray loop to operable status within 7 days.

d. The A Core Spray discharge line is broken inside the reactor. Be in MODE 3 by 0430 tomorrow.

ANSWER b.

REFERENCE QCAN 901(2)-3 F5, Core Spray Lesson Plan Tech Spec section 3.5.1 provided HIGHER NEW EXPLANATION: The D/P indication shows that the B loop discharge line inside the reactor is broken. Since B loop is ALREADY inoperable, the 7 day action statement continues.

QUESTION 012 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 261000 2.1.33 QUESTION Given:

- Unit 1 is in the process of off loading the reactor core

- Unit 2 is operating at 100% power

- The 1/2 A SBGT operability surveillance has just been completed with the following results - 4400 scfm flow - 6.13 inches of water pressure drop across the HEPA filters and charcoal adsorbers

- The 1/2 B SBGT train is now running for an upcoming RB vent OOS Five minutes later an electrical fault causes the 1/2-7504B, TURB BLDG CLG AIR DMPR, to OPEN.

What actions are required by Tech Specs?

a. Unit 1: Restore one SGT subsystem to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Unit 2: Restore one SGT subsystem to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b. Unit 1: Suspend movement of irradiated fuel in the secondary containment, suspend core alterations and initiate action to suspend OPDRVs immediately.

Unit 2: Restore one SGT subsystem to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

c. Unit 1: Restore SGT subsystem to operable status within 7 days.

Unit 2: Restore SGT subsystem to operable status within 7 days.

d. Unit 1: Place the operable SGT subsystem in operation immediately.

Unit 2: Restore SGT subsystem to operable status within 7 days.

ANSWER b.

REFERENCE Tech Spec 3.6.4.3 and its Bases. TS 5.5.7.d Tech Spec sections 3.6.4.3 and 5.5.7.d provided HIGHER BANK EXPLANATION: 6.13" of water D/P inops the A train of SBGT. Per TS Bases the TB cooling damper must be operable for the train to be operable. Therefore both trains are inoperable. During a core offload irradiated fuel is being moved so SBGT is required to be operable for both units. Unit 1 will be in condition F of TS 3.6.4.3 and Unit 1 will be in condition D.

Misinterpretation of the applicability or operability status of one of the SBGT trains would lead the students to choose one of the distractors.

QUESTION 013 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 264000 2.4.30 QUESTION Unit 1 was operating at rated power when the following scenario occurs.

0000 LOOP on Unit 1 0001 1/2 EDG fails to start, cause unknown 0003 U1 EDG output breaker trips on overload 0007 Bus 13-1 to Bus 23-1 crosstie breaker fails to close, cause unknown 0012 U1 SBO fails to start due to starting air failure 0020 1/2 EDG is manually started and loads to 13-1 0022 Busses 14-1 and 24-1 are crosstied 0035 Off-Site power is restored.

Which one of the following most correctly describes the reportability for this event?

a. This event IS reportable as an Unusual Event.

b. This event IS reportable as an ALERT.

c. This event IS reportable as a Site Area Emergency.

d. This event is NOT reportable since Busses 13-1 AND 14-1 are ENERGIZED.

ANSWER c.

REFERENCE EP-AA-1006r19e App 3. Quad Cities Annex EP-AA-1006r19e App 3. Quad Cities Annex provided HIGHER NEW EXPLANATION: Busses 13-1 and 14-1 are deenergized from 0003 to 0020 (17 min) so MS1 (Site Area Emergency) is applicable and reportable to outside agencies. UE and Alert are also applicable, but station procedures require reporting the HIGHEST classification that is met.

QUESTION 014 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 400000 2.1.33 QUESTION Unit 1 is operating at full power. At 0900 the ANSO notes no light indication for the MO 1-3702, U1 RBCCW SPLY VLV. Investigation reveals an electrical short has damaged breaker components and the breaker requires extensive repairs which will take 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Which of the following is correct regarding the situation?

a. No action is required because the MO 1- 3702 does NOT have a required stroke time.

b. RBCCW flow must be isolated to the drywell by 1300.

c. RBCCW flow must be isolated to the drywell by 1700.

d. No actions are required since the in-line check valve is operable.

ANSWER b.

REFERENCE TS 3.6.1.3 TRM Appendix A page A1-3 TS 3.6.1.3 TRM Appendix A pages A1-1 through A1-14 provided HIGHER NEW EXPLANATION: The MO-1-3702 is a PCIV in a flowpath with 2 PCIVs. As such it must be isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

QUESTION 015 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A A2.09 QUESTION Both Units are at rated power.

A Laborer reported that inside the SSMP room, he had "bumped" valve 1/2-2999-11, causing it to break off and spray water.

You dispatched the Field Supervisor and an NLO who CLOSED valves 1/2-2999-7 AND 1/2-2901-25 to STOP the leak (see below).

Assume NO additional equipment is damaged AND an IR has been generated, what is the IMPACT on the SSMP system, AND what should be done to correct it?

a. SSMP is INOPERABLE. Valve in the Fire Header to the SSMP suction.

b. SSMP is OPERABLE. No additional actions are required.

c. SSMP is INOPERABLE. Valve in Service Water to the room cooler.

d. SSMP is INOPERABLE. Valve in the Fire Header to the room cooler.

ANSWER d.

REFERENCE QCOP 2900-01 HIGHER NEW EXPLANATION: With service water isolated to the room cooler, the SSMP system is INOPERABLE. The Fire Header can be valved into the room cooler.

COMMENT: No KA exists for the SSMP system. System was added to random selection process, following discussion with lead examiner, in accordance with per ES 401-1, note 3. The KA for the HPCS System was used as a model:

206000.A2.12 Ability to (a) predict the impacts of the following (Loss of room cooler) on the SAFE SHUTDOWN MAKEUP PUMP SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations. Proposed worth:

(RO=3.4 / SRO=3.5)

QUESTION 016 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 230000A215 QUESTION A LOCA has occurred on Unit 2, concurrently with a LOOP.

Reactor Pressure is 400 psig and LOWERING.

RCIC and SBLC are the ONLY high pressure systems available AND injecting into the Reactor.

Reactor Water Level is -193" and LOWERING.

The RHR System is in operation per QCOP 1000-30.

- BOTH loops of Torus Sprays are in operation.

- BOTH loops of Torus Cooling are in operation.

- Drywell sprays are NOT in operation due to valve binding on both loops.

Drywell Pressure is 19 psig and RISING.

Torus Pressure is 17 psig and RISING.

Torus Level is 14 feet and STABLE.

Complete the following statements.

QGA 500-1, RPV BLOWDOWN is required based upon __(1)__.

The 901-3 Panel Operator should be directed to __(2)__.

a. (1) Reactor Water Level AND Torus Pressure (2) STOP Torus Cooling AND Torus Sprays

b. (1) Reactor Water Level ONLY (2) STOP Torus Cooling AND Torus Sprays

c. (1) Reactor Water Level AND Torus Pressure (2) CONTINUE to operate Torus Cooling AND Torus Sprays

d. (1) Torus Pressure ONLY (2) CONTINUE to operate Torus Cooling AND Torus Sprays ANSWER a.

REFERENCE QGA 100, QGA 200 QGAs with entry conditions blanked out provided.

HIGHER NEW EXPLANATION: QGA 100 at "3" requires that injection is MAXIMIZED, which requires the SRO to direct the ANSO to terminate Containment cooling / sprays and allow LPCI to inject at full capacity. Blowdown is required on RPV level AND torus pressure outside the PSP.

QUESTION 017 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 259001 2.2.25 QUESTION What is the TS bases for the high level RFP and Turbine trips?

a. To ensure that the fuel cladding integrity Safety Limit and the cladding 1% plastic strain limit are not violated during the feedwater controller failure, maximum demand event.

b. To ensure that the fuel design limits are not exceeded anywhere in the core during normal operation, including anticipated operational occurrences.

c. To ensure that the Safety Limit MCPR is not violated during a slow recirc flow increase event that does not terminate in a scram.

d. To prevent overflow into the Main Steam Lines.

ANSWER a.

REFERENCE TS B 3.3.2.2 MEMORY NEW EXPLANATION: Answer is direct from the bases. Two of the distractors were chosen due to wording similar to the correct answer. Those two are the bases for LHGR and MCPR. The last distractor is the bases for the HPCI high level trip which happens at the same RPV water level as the RFP trip

(+48").

QUESTION 018 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 290001A205 QUESTION Unit 1 has experienced a transient. The following lists the current conditions.

- RPV pressure 800 psig and LOWERING

- RPV water level 30" and STEADY, maintained with feedwater

- Torus area water level is 3" and RISING

- Second floor RB radiation reading is 3.5 R/hr and RISING

- B RWCU pump room temperature is 250°F and RISING

- RWCU heat exchanger room temperature is 210°F and RISING

- The breakers for the RWCU isolation valves have TRIPPED and will NOT reset Which of the following is the correct action to take and the basis for that action?

a. Blowdown the RPV per QGA 500-1. This will maintain HPCI and RCIC availability for core submergence.

b. Cooldown the RPV per QCGP 2-1. This will maintain habitability in accessible portions of the secondary containment.

c. Blowdown the RPV per QGA 500-1. This will maintain habitability in accessible portions of the secondary containment.

d. Cooldown the RPV per QCGP 2-1. This will maintain HPCI and RCIC availability for core submergence.

ANSWER c.

REFERENCE QGA 300 and EPG page B-8-12 QGA procedures with entry conditions blanked out provided HIGHER NEW EXPLANATION: With 2 area temperatures above max safe and a primary system discharging into the secondary containment, blowdown is required. Area temps are maintained for personnel access and equipment availability, however HPCI and RCIC will automatically isolate during the blowdown so the concern of their availability is moot.

QUESTION 019 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 2.1.5 QUESTION Both units are operating at full reactor power. On midnight shift the Unit 1 ANSO becomes very ill and at 0400 leaves the site to seek medical attention. The day shift ANSO is expected to be in at 0630.

As the US you locate the QAP binder in the control room and find that the Shift Manning procedure is missing. When you attempt to access EDMS you find it is down for server maintenance.

Where could you locate the most current revision of the procedure and what actions are required in this case?

a. In Passport OR In the WEC. Immediately take action to replace the missing ANSO.

b. In Passport ONLY. Immediately take action to replace the missing ANSO.

c. In Passport OR in the WEC. No action to INCREASE shift manning is required.

d. In the WEC ONLY. No action to INCREASE shift manning is required.

ANSWER a.

REFERENCE QAP 0300-03 MEMORY NEW EXPLANATION: Passport and The WEC both contain real time sets of procedures. Shift manning may drop below minimum for not more than two hours but immediate action must be taken to restore it.

QUESTION 020 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 2.1.9 QUESTION You are the Unit Supervisor. An activity that will cause the Shutdown Risk status change from GREEN to YELLOW requires a Heightened Level of Awareness (HLA) briefing on your shift.

Which of the following lists your responsibilities per HU-AA-1211, BRIEFINGS - PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY AND POST-JOB BRIEFINGS?

a. Acting as the Test Coordinator for the evolution and granting permission to begin the evolution.

b. Deciding who needs to monitor the brief and acting as Test Coordinator for the evolution.

c. Deciding who needs to monitor the brief and setting abort criteria for the evolution.

d. Granting permission to perform the evolution and setting abort criteria for the evolution.

ANSWER d.

REFERENCE From HU-AA-1211 MEMORY EXPLANATION: see technical reference.

QUESTION 021 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 2.2.29 QUESTION You have been assigned to SUPERVISE fuel moves on the refuel floor during a FULL-CORE OFFLOAD.

Which of the following activities is required EVERY SHIFT, before fuel moves can begin?

a. Sign on as a HOLDER of the Clearance Order that is place to prevent cavity draining.

b. INSPECT the refueling bridge and the area around the cavity for loose parts or foreign material.

c. ANNOUNCE over the Public Address system that fuel moves are ABOUT TO COMMENCE.

d. VERIFY with the QNE that Shutdown Margin is MET.

ANSWER b.

REFERENCE QCFHP 0100-01, QCFHP 0300-01 MEMORY NEW EXPLANATION: QCFHP 0300-01 is required to be performed EACH SHIFT when fuel movement is to occur. It contains the requirement to inspect for loose parts on bridge or around pools. QNE verification of SDM is required before core RELOAD. No PA announcement is required C&T procedure allows a supervisor to STAY signed on as a HOLDER if the job continues.

QUESTION 022 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 2.2.16 QUESTION Under which of the following circumstances would an INTERIM Procedure Change be appropriate as opposed to a TEMPORARY procedure change?

a. The proposed procedure change will NOT change the intent of the original procedure and will be used MANY TIMES over the upcoming refuel cycle.

b. The proposed procedure change will NOT change the intent of the original procedure and will be used only ONCE.

c. When the Shift Manager determines there is NOT sufficient time to perform reviews, REGARDLESS of change of intent status.

d. The proposed procedure change WILL change the intent of the original procedure and will be used only ONCE.

ANSWER d.

REFERENCE AD-AA-101 MEMORY BANK EXPLANATION: An interim change DOES change the intent. The procedure requires a full review for Interim changes.

QUESTION 023 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 2.3.1 QUESTION According to Tech Specs, what is the lowest level of authority responsible for the administrative control of keys to locked high radiation areas?

a. The Shift Manager on duty OR ANY Radiation Protection Technician

b. ANY LICENSED Operator on duty OR the Radiation Protection ALARA Coordinator

c. The Shift Manager on duty OR Radiation Protection Supervision

d. ANY Senior Reactor Operator on duty OR Radiation Protection Supervision ANSWER c.

REFERENCE TS 5.7.2.a MEMORY BANK EXPLANATION: See Ref.

COMMENT: The term Shift Engineer has been replaced with Shift Manager. The responsibilities are the same, only the name has been changed.

QUESTION 024 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 2.4.22 QUESTION Complete the following statement regarding EMERGENCY usage of safety systems included in Tech Specs during plant emergencies.

Tech Spec required safety systems...

a. can be disabled ONLY AFTER notifying the NRC of entry into 10 CFR 50.54(x).

b. are NEVER intentionally disabled.

c. are procedurally REQUIRED to be disabled, WHEN doing so will protect fission product barriers.

d. can be disabled ONLY AFTER receiving approval from the Site Emergency Director.

ANSWER c.

REFERENCE QGA Bases page I-3 MEMORY NEW EXPLANATION: QGA procedures sometimes REQUIRE safety systems to be disabled (CS in PTL, INHIBIT ADS et cetera) Actions taken, directed by approved procedures do not require declaration of 10CFR 50.54(x) or approval of Engineering.

QUESTION 025 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL S K/A 2.4.7 QUESTION Which of the following is NOT a proper action when a HOLD point is reached during QGA execution?

a. CONTINUE to review and complete subsequent step(s) PRIOR to meeting the conditions listed in the HOLD point.

b. CONTINUE to review and complete PARALLEL QGA LEGS step(s) PRIOR to meeting the conditions in the HOLD point.

c. CONTINUE to review and complete prior step(s) until the conditions in the HOLD point have been met.

d. CONTINUE to review and complete override(s) applicable to prior step(s) PRIOR to meeting the conditions in the HOLD point.

ANSWER a.

REFERENCE QGA Lesson Plan MEMORY BANK EXPLANATION: