ADMIN PRACTICE QUIZ

Question 1

34SV-SUV-013-0, “Weekly Breaker Alignment Checks”, is used to confirm or verify offsite power sources are available and supplying the __________.
The MINIMUM qualification level of personnel performing this procedure is a __________.

A. Plant Startup Transformers;
NON LICENSED Plant Operator

B. Plant Startup Transformers;
LICENSED Nuclear Plant Operator

C. 4160 VAC Emergency Buses;
NON LICENSED Plant Operator

D. 4160 VAC Emergency Buses;
LICENSED Nuclear Plant Operator

Answer 1

A. Plant Startup Transformers;
NON LICENSED Plant Operator

4.3.1 2. Perform Attachment 3, indicating two closed circuits from an offsite transmission line to SAT 1C, SAT 1D and SAT 1E.

4.3.2 2. Perform Attachment 3,
indicating two closed circuits from an offsite transmission line to SAT 1C, SAT 1D, SAT 1E, SAT 2C, SAT 2D, and SAT 2E.

System operators will collect the majority of the data for this procedure during rounds.

Question 2

IAW 34SV-SUV-019-2, “Surveillance Checks”, and Tech Spec 3.4.4, RCS Operational LEAKAGE, which ONE of the choices below identifies the integrator used in determining UNIDENTIFIED leakage rate and its location?

A. Drywell Floor Drain Sump Integrator, 2G11-K601, located on panel 2H11-P602.

B. Drywell Floor Drain Sump Integrator, 2G11-K601, located on panel 2H11-P613.

C. Drywell Equipment Drain Sump Integrator, 2G11-K603, located on panel 2H11-P602.

D. Drywell Equipment Drain Sump Integrator, 2G11-K603, located on panel 2H11-P613.

Answer 2

B. Drywell Floor Drain Sump Integrator, 2G11-K601, located on panel 2H11-P613.

34SV-SUV-019-2
7.24.5 2H11-P613 - 2G11-K601, D/W Floor Drain Leakage

Question 3

Tech Spec. 3.5.1 requires 34SV-SUV-018-1/2, ECCS Status Checks (SR 3.5.1.2), to be performed __________.
The purpose of 34SV-SUV-018-1/2, ECCS Status Checks, is to verify, for each ECCS injection/spray subsystem that the __________.

A. once every shift;
valves in the flow path are in the correct position;

B. once every shift;
piping is filled with water from the pump discharge valve to the injection valve.

C. once every 31 days;
valves in the flow path are in the correct position;

D. once every 31 days;
piping is filled with water from the pump discharge valve to the injection valve.

Answer 3

C. once every 31 days;
valves in the flow path are in the correct position;

34SV-SUV-018-2
2.0 Applicability
It is required to be performed once every 31 days by Tech Specs.

This procedure is applicable to the valves in the flow paths of the following ECCS AND safe shutdown systems:
High Pressure Coolant Injection System, Reactor Core Isolation Cooling System, LPCI AND Suppression Pool Cooling and Spray Modes AND Drywell Spray Mode of the Residual Heat Removal System AND the Core Spray System.

Question 4

Procedure steps, series of steps, or actions that, if performed INCORRECTLY, will cause irreversible, intolerable harm to plant equipment, people, or significantly impact plant operation are _________ .
A statement that is contained within a box and appears within a procedure to make the reader or user aware that hazards may be present and personal injury may result if procedural steps
are NOT followed is a __________.

A. Critical Steps;
Warning

B. Critical Steps;
Note

C. Continuous Action Steps;
Warning

D. Continuous Action Steps;
Note

Answer 4

A. Critical Steps;
Warning

NMP-AP-003

2. 0 Definitions
3. Critical Step – A procedure step, series of steps, or action that, if performed incorrectly, will cause irreversible harm to plant equipment or people or will significantly impact plant operation.

NMP-AP-002

2. 0 Definitions
3. Warning - A statement placed immediately before applicable steps to warn users of potential for personnel injury, loss of life, or health hazards.

Question 5

A Unit 2 startup is in progress per 34GO-OPS-001-2, “Plant Startup”.
The shift team has decided to N/A the step in 34GO-OPS-001-2, requiring the Steam Packing
Exhauster to be started prior to placing sealing steam on the Main Turbine.
Per NMP-AP-003, “Procedure and Work Instruction Use and Adherence”:

A. This step can NOT be N/A’d.

B. The step can be marked N/A without explanation.

C. The step can be marked N/A but must be explained.

D. The step can be marked N/A but must be approved by the SM.

Answer 5

A. This step can NOT be N/A’d.

NMP-AP-003
4.2.7 c. Steps without conditional statements or specified conditions may be marked N/A, if ALL the following criteria are satisfied:
• The step is NOT needed for the current mode, condition, or configuration of the plant.
• The intent (method of operation or the results) of the steps or sections does NOT change.
• The initial conditions, precautions, or prerequisites sections are NOT violated.

Question 6

You are performing a Locked Valve Surveillance when you arrive at 2C41-F031. (Locked Closed Valve)
The MINIMUM procedurally required action(s) to confirm that 2C41-F031 is in the required
position while performing a Locked Valve Surveillance is to __________, and then initial
and date the Locked Valve Surveillance form.

A. verify that the valve remains locked; then
use all available indications and indicators to verify that the valve is in the required position, it is not necessary to attempt to turn the valve handwheel,

B. unlock the valve; then,
attempt to turn the handwheel in the OPEN direction, ensuring it turns < 1/4 turn; then, install the locking device

C. unlock the valve; then,
attempt to turn the handwheel in the CLOSE direction, ensuring it turns < 1/4 turn; then, install the locking device

D. unlock the valve; then,
attempt to turn the handwheel in the CLOSE direction, ensuring it turns < 1/4 turn; then,
turn the handwheel in the OPEN direction, ensure the valve is NOT on its back seat;
then, install the locking device

Answer 6

A. verify that the valve remains locked; then
use all available indications and indicators to verify that the valve is in the required position, it is not necessary to attempt to turn the valve handwheel,

34GO-OPS-001-0

7.1.5.2 IF the valve to be verified is locked,
the valve SHOULD remain locked and position indicators should be utilized to determine the valve position,
e.g. valve stem position or flow indication, are consistent with the required position.

7.1.5.3 IF the valve to be verified is locked, AND cannot be ensured by the use of a position indicator, e.g. valve stem position or flow indication,
check the position by performing the following:

7.1.5.3.1 IF the valve is required to be CLOSED,
unlock the valve and:
turn the handwheel in the “CLOSED” direction, using normal force or torque.
The handwheel will normally turn no more than one quarter turn to seat the valve.

7.1.5.3.2 IF the valve is required to be OPEN,
unlock the valve and:
turn the handwheel in the “CLOSE” direction,
UNTIL there is a small amount of stem movement,
THEN return the valve to the FULL OPEN position.

Question 7

Unit 1 has experienced a transient.
o HPCI has failed to start and RWL is DECREASING
IAW DI-OPS-59-0896, “Operations Management Expectations”, which ONE of the choices
below completes the following statements?
When reporting the HPCI failure to the Shift Supervisor, the operator __________ required
to use the Shift Supervisor’s name or title.
If the operator provides the exact value of RWL to the Shift Supervisor, then the operator
__________ required to provide the trend direction.

A. is;
is still

B. is;
is NOT

C. is NOT;
is still

D. is NOT;
is NOT

Answer 7

A. is;
is still

NMP-GM-005-002

4. 1.2 3. g. Use 3-Part Communication for all order/directions that involve operation of plant equipment, or exchange of critical information related to the plant or plant equipment, to promote a reliable transfer of information and understanding.
   (1) Sender Responsibilities (Direction)
   (a) Address intended receiver by name or title.

NMP-OS-007-001
4.19.2 5. All parameters are communicated with values, units, trends, and, where appropriate, rates

Question 8

IAW NMP-OS-007-001, “Conduct of Operations, Standards and Expectations”:
Procedure place-keeping __________ required for notes, cautions and warnings for
Reference Use procedures.
Place-keeping for steps containing “multiple actions” will be performed by __________.

A. is NOT;
initialing next to the completed step

B. is NOT;
utilizing the circle/slash method

C. is;
utilizing the circle/slash method

D. is;
initialing next to the completed step

Answer 8

B. is NOT;
utilizing the circle/slash method

NMP-OS-007-001
References NMP-AP-003

NMP-AP-003
4.4.1 Review and understand the document before performing any steps including the precautions, limitations, and prerequisites sections.

4. 7.5 a. (1) (a) IF the step contains multiple actions, circle each action verb within the step.
   b. PERFORM the step or specific action.
   c. ANNOTATE the procedure step as complete.
   (2) IF the step contains multiple actions, individually check or mark each action previously circled after each action is completed.

Question 9

IAW NMP-OS-007, “Conduct of Operations”, EXCLUDING shift turnover walkdowns:
The Operator at the Controls (OATC) is required to walkdown the front Control Room panels __________.
The walkdowns ______ required to be documented in the Unit Control Log.

A. at least once per shift;
are

B. at least once per shift;
are not

C. approximately every two hours during the shift;
are not

D. approximately every two hours during the shift;
are

Answer 9

B. at least once per shift;
are not

NMP-OS-007

3. 17 OATC
4. Walks down the applicable portions of the control boards and control room displays at turnover and at intervals throughout the shift (mid-shift, and after system manipulations are recommended).

Question 10

IAW NMP-OS-007, “Conduct of Operations”, EXCLUDING shift turnover walkdowns:
The Unit Shift Supervisor is required to walkdown the front Control Room panels __________.
The walkdowns ______ required to be documented in the Unit Control Log.

A. at least once per shift;
are

B. at least once per shift;
are not

C. approximately every two hours during the shift;
are not

D. approximately every two hours during the shift;
are

Answer 10

A. at least once per shift;
are

NMP-OS-007

3. 10 Shift Supervisor
4. (Farley, Hatch, Vogtle 1-2) Walks down the control boards and control room displays at turnover and at least once during the shift (preferably with the UO/OATC) to verify component position and system parameters. This walk-down should be recorded in the unit control log.

Question 11

Per NMP-GM-005-002, “Human Performance Tools Instruction”, which ONE of the choices below completes the following statements?
The verification practice used, when the consequences of an incorrect action would lead to
immediate and possibly irreversible harm to the plant or personnel, is __________ Verification.
The primary focus of a Peer Check is __________.

A. Independent;
the performers actions

B Independent;
status control of equipment

C. Concurrent;
the performers actions

D. Concurrent;
status control of equipment

Answer 11

C. Concurrent;
the performers actions

NMP-GM-005-002
4.2.3 2. b. WHEN to perform Concurrent Verification:
WHEN the consequences of an incorrect action would lead to immediate and possibly irreversible harm to the plant or personnel.

4.2.3 3. b. (1) (g) The peer witnesses the positioning (or check) of the component and physically verifies component position or condition, WHEN applicable.

Question 12

Unit 2 is performing a reactor startup. Reactor power is at 14% and there are six (6) control rods with substitute positions.
Subsequently the following occurs:
o At 10:00, control rod 22-11 is withdrawn to position 14 where a failed reed switch is encountered
o At 10:05, a substitute control rod position is inserted IAW 34GO-OPS-065-0, “Control Rod Movement”
o At 10:10, control rod 22-11 is withdrawn to position 16 where there is an operable reed switch. No other operator action has been taken.

At 10:07, a total of __________ more substitute control rod position(s) may be inserted.
At 10:11, there are __________ control rods on the substitute control rod list.

A. two (2);
seven (7)

B. two (2);
six (6)

C. one (1);
seven (7)

D. one (1);
six (6)

Answer 12

D. one (1);
six (6)

34GO-OPS-065-0
4.3.6

Notes:
• The RWM will NOT allow a substitute position to be entered IF there is a functional reed switch for that rod’s position OR IF there are already EIGHT control rods with substitute positions.
• The rod will automatically be removed from the substitute rod list IF it is moved to a position with an operating reed switch OR IF its reed switch is returned to service.

Question 13

A Unit 1 startup is in progress per 34GO-OPS-001-1, “Plant Startup”.
o Rx Engineering has determined that Control Rod 26-11 is a “fast rod”
IAW 34GO-OPS-065-0, “Control Rod Movement”:
__________ must review AND approve any planned control rod movements (other than routine CRD exercising).
Control rods that have been deemed as “fast rods”, are to be withdrawn in __________.

A. Shift Supervisor;
single notch mode (only)

B. Shift Supervisor;
single notch or continous withrawal mode

C. Shift Manager;
single notch mode (only)

D. Shift Manager;
single notch or continuous withdrawal mode

Answer 13

C. Shift Manager;
single notch mode (only)

34GO-OPS-065-0
3.3.2.1 The Shift Manager (SM) must review AND approve any planned control rod movements (other than routine CRD exercising).
Additionally, the Shift Supervisor must be made aware of all planned control rod movements PRIOR to their performance.

2. 1.8. Control Rods that have been deemed as “fast rods” are to be withdrawn in single notch mode only, EXCEPT while performing the following.
   a. Control Rod sequence exchanges
   b. Scram time testing
   c. Flux tilt testing
   d. Any rod movement performed under 34GO-OPS-066-0
   e. As approved by Reactor Engineering.

Question 14

IAW 10AC-MGR-001-0, “Plant Organization Staff Responsibilities & Authorities”:
The order to start up or shutdown the reactor for planned maintenance or refueling is issued
by the __________ or designated alternate.
In an emergency or when it is judged that continued operation would jeopardize plant or
personnel safety, ANY MEMBER of the Operations Department __________ have the
authority to order the reactor shutdown or to shut it down himself.

A. Vice President;
does NOT

B. Vice President;
does

C. Plant Manager;
does

D. Plant Manager;
does NOT

Answer 14

A. Vice President;
does NOT

10AC-MGR-001-0
3.3.1. The order to start up or to shut down the reactor for planned maintenance or refueling is issued by the VP or his designated alternate.

3.3.2. In an emergency or when it is judged that continued operation would jeopardize plant or personnel safety, any member of the plant staff holding an operator license has the authority to order the reactor shut down or to shut it down himself.

Question 15

The following data is from Attachment 8 of 34GO-OPS-001-2, “Plant Startup”.

Reading Time RPV Press(PSIG) RPV Coolant(°F) Metal Temp(°F)

1. 0700 95 334 330
2. 0715 105 341 339
3. 0730 115 347 345
4. 0745 205 390 388

Based on the provided data:

The heatup rate __________ violating Tech Specs; AND,
Action to decrease the heatup rate __________ procedurally REQUIRED.

A. is;
is

B. is NOT;
is

C. is;
is NOT

D. is NOT;
is NOT

Answer 15

B. is NOT;
is

34GO-OPS-001-2 Attachment 8
4. Check “RPV Coolant 15 min change” is < 25 °F.
IF it is NOT,
THEN take action to lower the heatup rate such that the heatup limit of 100 °F in any one hour period is NOT exceeded.

Question 16

A Unit 2 startup is in progress per 34GO-OPS-001-2, “Plant Startup”. The reactor has been
declared CRITICAL.

o All SRM & IRM detectors are FULLY inserted o All IRMs are on Range 1
The following SRM and IRM indications exist:
SRM Indication
A 1x10^5 cps
B 1x10^5 cps
C 3x10^5 cps
D 3x10^5 cps

IRM Indication IRM Indication
A 6/125 B 6/125
C 7/125 D 3/125
E 6/125 F 3/125
G 3/125 H 4/125

At this point in time during the startup, IAW 34GO-OPS-001-2, “Plant Startup”, acceptable overlap has been achieved on ALL IRMs associated with __________ ; AND, control rod withdrawal ___________.

A. 1 SRM channel ONLY;
must be halted

B. 3 SRM channels;
must be halted

C. 3 SRM channels;
can continue

D. 1 SRM channel ONLY;
can continue

Answer 16

A. 1 SRM channel ONLY;
must be halted

34GO-OPS-001-2
4.2.21
CAUTION
IF SRM/IRM OVERLAP IS NOT CHECKED, ROD WITHDRAWAL WILL BE HALTED. TECH SPECS WILL BE ADDRESSED TO DETERMINE IF ANY IRMS DECLARED INOPERABLE DUE TO FAILURE TO DEMONSTRATE OVERLAP WILL ALLOW STARTUP TO CONTINUE.

Question 17

A Unit 2 reactor startup is in progress. The following IRM readings have been observed while
switching up from range 6 to range 7:

IRM Channel Range 6 Range 7
———– ——- ———-
A 75 8.0 and slowly rising
B 80 0.0 and steady
C 75 8.0 and slowly rising
D 90 9.0 and slowly rising
E 90 10.0 and slowly rising
F 80 0.0 and steady
G 75 9.0 and slowly rising
H 80 8.5 and slowly rising

IAW 34GO-OPS-001-2, “Plant Startup”, which ONE of the choices below completes BOTH of the following statements?

Based on the above IRM data, acceptable overlap on ALL IRMs __________ confirmed.

The MINIMUM approval required to continue the reactor startup is the __________ .

A. is;
Shift Supervisor

B. is;
Shift Manager

C. is NOT;
Shift Supervisor

D. is NOT;
Shift Manager

Answer 17

C. is NOT;
Shift Supervisor

34GO-OPS-001-2

4.2.28. To continue power ascension with any inoperable IRMs,
obtain Shift Supervisor approval.

Question 18

Unit 2 is in MODE 2, preparing to go to MODE 1.

o It is determined that RCIC is INOPERABLE

Based on the above conditions:

IAW Tech Spec 3.5.3, RCIC System, the Reactor Mode switch __________ .

A. can be transferred to MODE 1 with no further actions

B. can be transferred to MODE 1 as long as HPCI is operable

C. can NOT be transferred to MODE 1 until RCIC is returned to operable status

D. can NOT be transferred to MODE 1 until performance of a risk assessment determines it is allowable

Answer 18

C. can NOT be transferred to MODE 1 until RCIC is returned to operable status

LCO 3.0.4
When an LCO is not met, entry into a mode or other specified condition
in the Applicability shall only be made:

a. When the associated ACTIONS to be entered permit continued
operation in the MODE or other specified condition in the
Applicability for an unlimited period of time,

b. After performance of a risk assessment addressing inoperable
systems and components, consideration of the results,
determination of the acceptability of entering the MODE or other
specified condition in the Applicability, and establishment of risk
management actions, if appropriate (exceptions to this specification
are stated in the individual Specifications);

3.5.3 LCO 3.0.4.b is not applicable to RCIC
Condition Required Action Comp Time
A. RCIC System INOP A.1 Verify HPCI Oper 1 hour
AND
A.2 Restore RCIC Oper 14 days

Question 19

The following Unit 1 data was collected for a Core Heat Balance and APRM Gain Adjustment:

o APRM A 68.0 %
o APRM B 74.0 %
o APRM C 72.0 %
o APRM D 70.0 %

The above APRM readings were recorded as the AS LEFT readings after performance of
34SV-SUV-021-0, “APRM Adjustment to Core Thermal Power”, for ALL of the APRMs.

Calculated reactor power prior to performance of the gain adjustments was 71.2 % RTP based on performance of 34SV-SUV-025-0, “Core Heat Balance”.

All of the requirements of 34SV-SUV-021-0 are being met by ___________ at this time.

A. only 1 APRM
B. only 2 APRMs
C. only 3 APRMs
D. All 4 APRMs

Answer 19

A. only 1 APRM

34SV-SUV-021-0
5.2.4 “AS LEFT” APRM readings shall NOT be less than the Heat Balance value AND shall NOT exceed the Heat Balance value by more than 2%.
For example, if the Heat Balance indicates that Reactor Power is 79%, the “AS LEFT” APRM reading must indicate between 79% and 81%.

Question 20

Per AG-ADM-30-1209, “Preconditioning Evaluation”:

On the same day following maintenance on HPCI, it __________ acceptable to perform
34SV-E41-002, “HPCI Pump Operability”, one time to serve as BOTH the post maintenance test AND to satisfy a scheduled TS surveillance; AND,

It _______ acceptable to perform TS required sections of 34SV-E11-002, “RHR Valve
Operability”.

A. is;
is

B. is;
is NOT

C. is NOT;
is

D. is NOT;
is NOT

Answer 20

D. is NOT;
is NOT

AG-ADM-30-1209
6.11 Do not routinely schedule TS surveillance interval tests after maintenance activities so the
surveillance test can also serve as the post maintenance test. The post maintenance test will be recorded for baseline performance or condition data but will not count as the surveillance interval test.

Question 21

Per 34GO-OPS-001-2, “Plant Startup”:

PRIOR to exceeding an indicated thermal power of ______ Rated Thermal Power, a MANUAL calculation of thermal power is required in accordance with 34SV-SUV-025-0, “Core Heat Balance”.

If RWCU return temperature to the vessel used in the calculation is LOWER than actual, then calculated power is ______ than actual.

A. 15%;
less

B. 15%;
greater

C. 24%;
less

D. 24%;
greater

Answer 21

D. 24%;
greater

34SV-SUV-025-0
This procedure is to be performed:
2.5 During any reactor startup, PRIOR to exceeding 225 MWE, OR PRIOR to exceeding an indicated thermal power of 24% Rated Thermal Power (RTP), in accordance with 34GO-OPS-001-1 (34GO-OPS-001-2).

CTP=Steam + Ambient + RWCU - FW - CRD - Recirc

RWCU = In - Out
If return was lower, then the RWCU calculated Q would be higher leading to a greater CTP value.

Question 22

Unit 1 is in a refueling outage making preparations for startup.

o The Reactor Mode switch is in SHUTDOWN
o Reactor Coolant temperature…………….155°F

At 10:00, only ten (10) reactor vessel head bolts have been FULLY tensioned
At 14:00, ALL reactor vessel head bolts are FULLY tensioned

Based on these conditions:
At 10:00 the reactor is considered to be in ______; AND, At 14:00 the reactor is considered to be in _______ .

A. Mode 4; Mode 4

B. Mode 4; Mode 5

C. Mode 5; Mode 4

D. Mode 5; Mode 5

Answer 22

C. Mode 5; Mode 4

Tech Specs
Table 1.1-1 Modes
MODE TITLE REACTOR MODE SWITCH POSITION COOLANT TEMPERATURE (°F)

1 Power Operation Run NA

2 Startup Refuel(a) or Startup/Hot NA Standby

3 Hot Shutdown(a) Shutdown > 212

4 Cold Shutdown(a) Shutdown ≤ 212

5 Refueling(b) Shutdown or Refuel NA

(a) All reactor vessel head closure bolts fully tensioned.
(b) One or more reactor vessel head closure bolts less than fully tensioned.

Question 23

Unit 2 is in MODE 4 with “2B” RHR pump in Shutdown Cooling (SDC). Preparations are in progress to warm the “B” Loop of Recirc and then start the “2B” Recirc Pump.

o Reactor Coolant temperature………………… 180°F
o “2B” Recirc Suction temperature…………… 135°F

IAW 34SO-B31-001-2, “Reactor Recirculation System”, with the above temperatures, which
ONE of the choices below completes the following statements?

The temperature difference between the reactor coolant inside the idle loop to be started and the coolant in the reactor pressure vessel ______ WITHIN limits.

“2B” Recirc loop Suction temperature will be monitored on panel _______ .

A. is NOT;
2H11-P602

B. is NOT;
2H11-P601

C. is;
2H11-P601

D. is;
2H11-P602

Answer 23

D. is;
2H11-P602

34SO-B31-001-2 Attachment 5
3.0 PRIOR to starting a Recirculation pump,
check the temperature differential between the reactor coolant WITHIN the idle loop to be started up AND
the coolant in the reactor pressure vessel are WITHIN 500°F of each other.

4.1.5 Notes
• UNLESS otherwise noted, all actions are performed at panel 2H11-P602.

Question 24

IAW Unit 2 Technical Specification 3.8.4, DC Sources Operating.

A Diesel Generator DC electrical power subsystem can be considered OPERABLE if you have ________ , ________ , and interconnecting cabling supplying power to the associated bus.

A. one 125 VDC battery;
two battery chargers

B. one 125 VDC battery;
one battery charger

C. two 125 VDC batteries in series;
two battery chargers

D. two 125 VDC batteries in series;
one battery charger

Answer 24

B. one 125 VDC battery;
one battery charger

3. 8.4 LCO Bases
   2) each DG DC subsystem consisting of one battery bank, one battery charger, and the corresponding control equipment and interconnecting cabling

Question 25

Unit 1 is at 60% rated power.

o 34SV-E41-002-1, “HPCI Pump Operability”, is in progress

IAW 34SV-E41-002-1:

The MINIMUM acceptable flowrate for HPCI to be considered OPERABLE is _________.

During the surveillance when the HPCI pump flowrate is at rated, the HPCI System will _________.

A. 4000 gpm;
NOT be operable because 1E41-F008, Test To CST Vlv, is throttled open

B. 4000 gpm;
still be operable because HPCI will automatically realign to the injection mode upon receipt of an initiation signal

C. 4250 gpm;
NOT be operable because 1E41-F008, Test To CST Vlv, is throttled open

D. 4250 gpm;
still be operable because HPCI will automatically realign to the injection mode upon receipt of an initiation signal

Answer 25

C. 4250 gpm;
NOT be operable because 1E41-F008, Test To CST Vlv, is throttled open

34SV-E41-002-1
4.2.8. Prior to positioning 1E41-F008, notify the Shift Supervisor to declare HPCI INOP AND place it under a RAS.

Question 26

Unit 1 is at 60% rated power with Control Rod 22-47 at position 10.

If it is discovered that Rod 22-47 is stuck at position 10, IAW 34AB-C11-003-1, “Inability To Move A Control Rod”, _______ approval is required prior to increasing drive water pressure above a MINIMUM of ________ for control rods which are not fully inserted.

A. Shift Manager;
350 psid

B. Shift Manager;
600 psid

C. Operations Management;
350 psid

D. Operations Management;
600 psid

Answer 26

A. Shift Manager;
350 psid

34AB-C11-003-1
CAUTION 1
SHIFT MANAGER APPROVAL IS REQUIRED PRIOR TO INCREASING DRIVE WATER PRESSURE ABOVE 350 PSID FOR CONTROL RODS WHICH ARE NOT FULLY INSERTED.

Question 27

Unit 1 is operating at 100 % power.

Which ONE of the following pump combination below would satisfy Unit 1 Tech Spec requirements for RHR Torus Cooling mode?

NOTE: ONLY the RHR & RHRSW pumps listed in each statement are operable AND all other system components are operable.

RHR Pumps RHRSW pumps
Operable Operable

A. “1A” and “1C” “1A”, “1C”, and “1D”

B. “1B” and “1D” “1A”, “1B”, “1C”, and “1D”

C. “1B” and “1C” “1A”, “1B”, and “1D”

D. “1A” and “1D” “1A”, “1B”, “1C”, and “1D”

Answer 27

RHR Pumps RHRSW pumps
Operable Operable

D. “1A” and “1D” “1A”, “1B”, “1C”, and “1D”

To ensure that these requirements are met, two RHR suppression pool cooling subsystems must be OPERABLE with power from two safety related independent power supplies. active failure. An RHR suppression pool cooling subsystem is OPERABLE when one of the pumps, the heat exchanger, and associated piping, valves, instrumentation, and controls are OPERABLE. Each RHR suppression pool cooling subsystem is supported by an independent subsystem of the Residual Heat Removal Service Water (RHRSW) System. Specifically, two OPERABLE RHRSW pumps and an OPERABLE flow path, as defined in the Bases for LCO 3.7.1,

Question 28

Unit 1 is at 100% RTP with the following conditions:

o The “1B” Control Rod Drive (CRD) pump is tagged out o All control rods are withdrawn

The following sequence of events occur:

o 10:00 the “1A” CRD pump trips.
o 10:05 an operator attempts to restart the “1A” CRD pump and is NOT successful.
o 10:10 a System Operator reports several CRD scram accumulators are less than 940 psig.

In accordance with Tech Specs 3.1.5, which ONE of the following is the LATEST time that the Reactor Mode Switch MUST be in the Shutdown position?

A. 10:05

B. 10:10

C. 10:25

D. 10:30

Answer 28

D. 10:30

TS 3.1.5
Condition
B Two or more control rod scram accumulators inoperable with reactor steam dome pressure ≥ 900 psig.

Required Action
B.1 Restore charging water header pressure to ≥ 940 psig.

Completion Time
20 minutes from discovery of Condition B concurrent with charging water header pressure < 940 psig

D. Required Action and associated Completion Time of Required Action B.1 or C.1 not met.

D.1 Place the reactor mode switch in the shutdown position. Immediately

Question 29

The control room has been evacuated and an operator has been sent to align the HPCI suction to the CST IAW 31RS-E41-001-2, “HPCI Operation From Outside Control Room”.

Links are to be opened and a jumper installed on the internal side of the terminal strip.

The jumper must be placed on the ________ side of the link the _________ possum tail identification tag is on.

A. same;
pink

B. same;
yellow

C. opposite;
pink

D. opposite;
yellow

Answer 29

B. same;
yellow

31RS-E41-001-2
4.2 Note
• WHEN the internal side of a link is specified for 2-part jumper installation,
the jumper must be placed on the side of the link the possum tail identification tag is on.

Pink - EOPs
Yellow - RSDP

Question 30

A Plant Operator (PO) is performing 34SV-R43-004-2, “Diesel Generator 2A Semi-Annual 24 Hour Run and Hot Restart Test.”

o At 13:00 the PO pre-lubes the “2A” EDG
o At 13:13 the PO is ready to start the “2A” EDG

DETERMINE the correct operator action:

A. The “2A” EDG must be pre-lubed again if the “2A” EDG is not started within the next 2 minutes.

B. The PO may start the “2A” EDG anytime within the next 17 minutes without pre-lubing the “2A” EDG.

C. The PO must NOT pre-lube the EDG again prior to starting the “2A” EDG.

D. Due to pump start limits on the pre-lube pump, the “2A” EDG must NOT be pre-lubed again until 14:00.

Answer 30

A. The “2A” EDG must be pre-lubed again if the “2A” EDG is not started within the next 2 minutes.

34SV-R43-004-2
4.2.2 h. NOTE
Prelube will be performed within 15 minutes of starting the diesel engine. Delays between prelube and engine starting will negate the effects of prelube due to system drain down. The Prelube Pump, WHEN started, will operate for approximately 3 minutes. Prelube can be accomplished in the Control Room OR locally.

Question 31

2 12

Unit 1 is operating at 100% power. I & C reports that a document review has revealed the
Turbine Stop Valve (TSV) closure scram setpoints are set according to the table below:

TSV                        Setpoint(% valve closure)
#1                                  9

IAW TS Bases 3.3.1.1, Reactor Protection System (RPS) Instrumentation, which ONE of the following describes the significance of these setpoints and their effects following a Turbine Trip?

(Reference: 3.3.1.1-1 Function 8 TSV Allowable value ≤ 10% Closed)

The setpoints for TSV ________ .

This will ________ following a Turbine Trip.

A. #2 & #4 are set too high;
narrow the margin to MCPR

B. #1 & #3 are set too low;
narrow the margin to MCPR

C. #2 & #4 are set too high;
result in an excessive RPV level transient

D. #1 & #3 are set too low;
result in an excessive RPV level transient

Answer 31

A. #2 & #4 are set too high;
narrow the margin to MCPR

3.3.1.1 Bases
The Turbine Stop Valve - Closure Allowable Value is selected to be high enough to detect imminent TSV closure, thereby reducing the severity of the subsequent pressure transient.

Question 32

Unit 2 is operating at 85% RTP (80% rated flow) after starting up following a refueling outage.
STA informs you that the recirc loop jet pump flow mismatch between the loops is as follows:

o “A” loop is 34.3 Mlbm/hr
o “B” loop is 27.3 Mlbm/hr

This flow mismatch ________ violating a limit.

The Shift Supervisor should direct the NPO to enter _______ .

A. is;
34GO-OPS-005-2, “Power Changes”

B. is;
34AB-B31-001-2, “Rx Recirc Pump(s) Trip, Loop Flow Mismatch”

C. is NOT;
34GO-OPS-005-2, “Power Changes”

D. is NOT;
34AB-B31-001-2, “Rx Recirc Pump(s) Trip, Loop Flow Mismatch”

Answer 32

B. is;
34AB-B31-001-2, “Rx Recirc Pump(s) Trip, Loop Flow Mismatch”

34AB-B31-001-2
4.0 Note
• IF recirculation loop jet pump flow mismatch with both recirc loops in operation is:
a. >10% (7.70 Mlbm/hr) of rated core flow,
WHEN operating at <70% (53.90 Mlbm/hr) of rated core flow;
OR
b. >5% (3.85 Mlbm/hr) of rated core flow,
WHEN operating at ≥70% (53.90 Mlbm/hr) of rated core flow;
THEN the loop with the lower flow must be considered NOT in operation.

Question 33

Which ONE of the choices below completes the following statements concerning the Unit 1 RWCU Group 5 isolation signal on low reactor water level (RWL)?

The HIGHEST listed RWL at which the RWCU system will have isolated is _________.

IAW TS Bases, the function associated with this RWCU isolation is NOT directly assumed in the FSAR safety analyses because the RWCU System line break _______ .

A. -36 inches;
alone will NOT result in fuel damage

B. -36 inches;
is bounded by breaks of larger systems

C. -61 inches;
alone will NOT result in fuel damage

D. -61 inches;
is bounded by breaks of larger systems

Answer 33

B. -36 inches;
is bounded by breaks of larger systems

Level 2 RWL = -35”

3.3.6.1 Function 5.d. Low Low Level 2 RWL
The Reactor Vessel Water Level - Low Low, Level 2 Function associated with RWCU isolation is not directly assumed in the FSAR safety analyses because the RWCU System line break is bounded by breaks of larger systems (recirculation and MSL breaks are more limiting).

Question 34

IAW B3.3.1.1, RPS Instrumentation, the RPV Water Level Low (Level 3) trip function ensures that ________ ; and,

IAW B3.3.5.1, ECCS Instrumentation, the RPV Water Level Low (Level 3) function ________ used to prevent a spurious initiation of ADS due to spurious RPV Water Level Low Low Low (Level 1) signals.

A. the heat energy generated in the fuel is substantially reduced before the fuel is uncovered;
is ALSO

B. the heat energy generated in the fuel is substantially reduced before the fuel is uncovered;
is NOT

C. enough time is available for the ECCS to start and reflood the reactor core before the Peak Cladding Temperature exceeds 2200°F;
is ALSO

D. enough time is available for the ECCS to start and reflood the reactor core before the Peak Cladding Temperature exceeds 2200°F;
is NOT

Answer 34

A. the heat energy generated in the fuel is substantially reduced before the fuel is uncovered;
is ALSO

Bases 3.3.1.1 Function 4 Low, Level 3 RWL
Therefore, a reactor scram is initiated at Level 3 to substantially reduce the heat generated in the fuel from fission.

Bases 3.3.5.1 ADS
One of the two strings in each trip system must also have a confirmed Reactor Vessel Water Level -
Low, Level 3.

Question 35

Unit 1 is operating at 90% RTP when Chemistry contacts the control room at the below times with the associated specific iodine activity:

TIME Specific Iodine Activity
0000 0.1 µCi/gm
0100 0.5 µCi/gm
0200 1.0 µCi/gm
0300 4.1 µCi/gm

Concerning the Required Action Statement (RAS) for LCO 3.4.6, RCS Specific Activity.

The EARLIEST time that a RAS is entered is ________ .

The TS Bases for LCO 3.4.6 is to ensure whole body doses at the site boundary are within 10CFR limits for up to ________ hours.

A. 0100;
2

B. 0100;
48

C. 0300;
2

D. 0300;
48

Answer 35

A. 0100;
2

LCO 3.4.6 The specific iodine activity is limited to ≤ 0.2 μCi/gm DOSE EQUIVALENT I-131. This limit ensures the source term assumed in the safety analysis for the MSLB is not exceeded, so any release of radioactivity to the environment during an MSLB is a small fraction of the 10 CFR 50.67 limits.

Accident analysis from the FSAR
Offsite and onsite doses are determined. 1) the dose to an individual located at any point on the boundary of the exclusion area (EAB) for any 2-h period following the onset of the postulated fission product release and 2) the dose to an individual located at

Question 36

Unit 2 is operating at 85% RTP when an event occurs requiring the Drywell to be vented using 2T48-F319 and 2T48-F320, Drywell Vent valves.

Drywell pressure is being maintained between 0.5 psig and 1.0 psig.

Concerning 2T48-F319 and 2T48-F320 and the 2D11-K621A & B, Drywell Radiation Monitors.

If 2D11-K621A & B, Drywell Radiation Monitors increase to 145 R/hr, 2T48-F319 and 2T48-F320 will _________ .

IAW TS Bases 3.3.6.1, the Drywell Radiation - High function, _________ .

A. close;
is NOT assumed in the U2 FSAR accident or transient analysis because the MSIV leakage path is MORE limiting.

B. close;
is assumed in the U2 FSAR accident or transient analysis because the MSIV leakage path is LESS limiting.

C. remain open;
is NOT assumed in the U2 FSAR accident or transient analysis because the MSIV leakage path is MORE limiting.

D. remain open;
is assumed in the U2 FSAR accident or transient analysis because the MSIV leakage path is LESS limiting.

Answer 36

A. close;
is NOT assumed in the U2 FSAR accident or transient analysis because the MSIV leakage path is MORE limiting.

TS 3.3.6.1-1 Function 2C Allowable value ≤138 R/hr
Isolates Drywell and Torus 18” Vent and Purge valves

Bases 3.3.6.1 2c Drywell Rad - High
However, this Function is not assumed in any accident or transient analysis in the FSAR because other leakage paths (e.g., MSIVs) are more limiting.

Question 37

Unit 2 is at 100% RTP performing 34SV-E41-002-2, “HPCI Pump Operability”, surveillance.

IAW Tech Spec, the HPCI surveillance must be stopped and HPCI shutdown before exceeding a MAXIMUM torus temperature of .

A. 100°F

B. 105°F

C. 110°F

D. 120°F

Answer 37

B. 105°F

TS 3.6.2.1 Cond C
Suppression pool average temperature > 105°F. THEN Suspend all testing that adds heat to the suppression pool, IMMEDIATELY.

Question 38

Concerning the Unit 2 Scram Discharge Volume (SDV) Vent and Drain Valves.

If 2R26-M066A AND 2R26-M066B, local Disconnect switches for 2C11-F040
System A & B, are placed in the OFF position, the SDV ________ will close.

IAW TS Bases 3.1.8, SDV Vent and Drain Valves Safety Analyses, the acceptance criteria for the SDV vent and drain valves are that they ______ .

NOTE: Outboard valves, 2C11-F035A, 2C11-F035B, & 2C11-F037
Inboard valves, 2C11-F010A, 2C11-F010B & 2C11-F011

A. Outboard valves ONLY;
close during a scram ONLY

B. Outboard valves ONLY;
close during a scram AND open on a scram reset

C. Inboard and Outboard valves;
close during a scram ONLY

D. Inboard and Outboard valves;
close during a scram AND open on a scram reset

Answer 38

B. Outboard valves ONLY;
close during a scram AND open on a scram reset

31RS-OPS-001-2
4.7 NOTE
The 2C11-F035A, 2C11-F035B, AND 2C11-F037, Outboard Valves for Scram Discharge Volume, can be closed by placing the following switches in the OFF position: 2R26-M066A AND 2R26-M066B which are located in the Control Building, North Wall, Unit 2 RPS MG Set room. These switches will de-energize 2C11-F040, Solenoid Valve, which vents air from the header, causing the outboard valves to close.

Bases 3.1.8
The OPERABILITY of all SDV vent and drain valves ensures that the SDV vent and drain valves will close during a scram to contain reactor water discharged to the SDV piping. Additionally, the valves are required to open on scram reset to ensure that a path is available for the SDV piping to drain freely at other times.

Question 39

Which ONE of the following identifies a plant personnel notification (including the specific procedure) that is first required when the reactor is made critical and is AGAIN required when the mode switch is transferred to RUN?

A. On-shift Lab foreman IAW 34GO-OPS-001-2, Plant Startup.

B. Northern/Southern Control Center IAW 34GO-OPS-001-2, Plant Startup.

C. Plant Manager IAW 40AC-ENG-016-0, Reactivity Management Program.

D. Reactor Engineer IAW 40AC-ENG-016-0, Reactivity Management Program.

Answer 39

A. On-shift Lab foreman IAW 34GO-OPS-001-2, Plant Startup.

34GO-OPS-001-2
4.2.20 d. Notify the on shift Lab Foreman of reactor criticality.

4.4 19. Notify the on-shift Lab Foreman that the Mode Switch is now in RUN.

Question 40

Unit 2 is in MODE 2 at 920 psig.
o PSW pump “2A” has been declared INOPERABLE Based on this information, a mode change to MODE 1 is:

A. NOT allowed by TS (no exceptions). No additional TS actions are required as long as the mode is not changed.

B. NOT allowed by TS (no exceptions). Restore PSW pump “2A” to operable within 30 days. If not returned in 30 days; be in Mode 3 in 12 hours and Mode 4 within 36 hours.

C. Allowed by TS without other admin actions required. If not returned within 30 days; be in Mode 3 in 12 hours.

D. Allowed by TS only if a Risk Assessment indicates that a low risk condition exists. If not returned within 30 days; be in Mode 3 in 12 hours.

Answer 40

D. Allowed by TS only if a Risk Assessment indicates that a low risk condition exists. If not returned within 30 days; be in Mode 3 in 12 hours and Mode 4 within 36 hours.

LCO 3.0.4 b Risk Analysis